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Oconee 2015-302 Exam Draft Items for ADAMS 2A - Delay 2 Years Release
	ML17174B288
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Site:	Oconee
Issue date:	06/23/2017
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
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ES-301 Administrative Topics Outline Form ES-301-1 ILT48 Facility: Oconee Date of Examination: 12/02/2015 Examination Level: RO X SRO Operating Test Number: 1 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations [KA: GEN 2.1.37 (4.3/4.6)] (20 min) M, R Admin-106, Calculate Run Time For Deborating Demineralizer (Both) Conduct of Operations [KA: GEN 2.1.4 (3.3/3.8)] (15 min) D, R ADMIN-107, Determine If RO License Requirements Are Met (RO Only) Equipment Control [KA: GEN 2.2.12 (3.7/4.1)] (10 min) D, R Admin-203, Perform NI Surveillance And Determine Any Required Actions (RO Only) Radiological Control [KA: GEN 2.3.4 (3.2/3.7)] (20 min) N, R Admin-303, Calculate Maximum Permissible Stay Time (Both) Emergency Plan N/A NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from ES-301 Administrative Topics Outline Form ES-301-1 ILT48 Facility: Oconee Date of Examination: 12/02/2015 Examination Level: RO SRO X Operating Test Number: 1 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations [KA: GEN 2.1.37 (4.3/4.6)] (20 min) M, R Admin-106, Calculate Run Time For Deborating Demineralizer (Both) Conduct of Operations [KA: GEN 2.1.13 (2.5/3.2)] (15 min) D, R Admin-S106, Evaluate Items For Entry Into Containment (SRO Only) Equipment Control [KA GEN 2.2.12 (3.7/4.1)] (20 min) D, R Admin-S202, Complete a Surveillance Evaluation (SRO Only) Radiological Control [KA: GEN 2.3.4 (3.2/3.7)] (20 min) N, R Admin-303, Calculate Maximum Permissible Stay Time (Both) Emergency Plan [KA GEN 2.4.38 (2.4/4.4)] (30 min) N, R Admin-S403, Determine Emergency Classification And Complete The Initial Emergency Notification Form (SRO Only) NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 12/02/15 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. RO-102 Respond to a Boron Dilution Event AP/1/A/1700/003 (Boron Dilution) [KA: APE 024 AA1.04 (3.6*/3.7)] (15 min) N, S 1 b. RO-202 Remove 1A Letdown Cooler From Service OP/1/A/1104/002 HPI System Encl. 4.5 (Operation of Letdown Coolers) [KA: 004 G 2.2.2 (4.6/4.1)] (15 min) D, S 2 c. RO-304a Perform Rule 2 Following a LOSCM EP/1/A/1800/001 EOP Rule 2 (Loss of SCM) [KA: E/APE 011 EA2.11 (3.9/4.3)] (10 min) A, EN, N, S 3 d. RO-P402a Start a Fourth Reactor Coolant Pump OP/1/A/1103/006 Encl 4.4 (Starting 1B2 RCP) [KA: 003 A4.03 (2.8/2.5)] (10 min) A, D, L, S 4P e. RO-503, Pump the Quench Tank OP/1/A/1104/017 Encl 4.1 (Pumping QT) [KA: 007 A1.01 (2.9/3.1)] (10 min) D, L, S 5 f. RO-602, Restore Secondary Loads After Loss of Offsite Power AP/1/A/1700/011 (Recovery from Loss of Power) [KA: 062 A4.01 (3.3/3.1)] (15 min) N, S 6 g. RO-803a, Align Intake Canal For Recirc on Dam Failure AP/1/A/1700/013 Dam Failure [KA: 075 G2.1.23 (4.3/4.4)] (20 min) A, D, S 8 h. RO-901a Release GWD Tank OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release) [KA: 071 A4.26 (3.1/3.9)] (30 min) A, D, S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. AO-602 Startup a Vital Bus Inverter OP/2/A/1107/004 (Operation of Vital Bus, Computer, ICS, and Auxiliary Inverters) Encl 4.2 (Startup of Vital Bus Inverters) [KA: 062 A3.04 (2.7/2.9)] (12 min) D 6 j. AO-101 Swap CRD Filters OP/1/A/1104/008 (Component Cooling System) Encl 4.19 (Placing 1A or 1B CRD Filter in Service) [KA: 001 G2.3.13 (3.4/3.8)] (20 min) D, R 1 k. AO-802a Isolate HPSW and LPSW During an AB Flood AP/3/A/1700/030 (Auxiliary Building Flooding) Encl 5.1 (HPSW AB Flood Isolation) and 5.2 (LPSW AB Flood Isolation) [KA: BW/A07 AA2.2 (3.3/3.7)] (16 min) A, D, E 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 - / - (control room system)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 12/02/15 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. N/A b. N/A c. RO-304a Perform Rule 2 Following a LOSCM EP/1/A/1800/001 EOP Rule 2 (Loss of SCM) [KA: E/APE011 EA2.11 (3.9/4.3)] (10 min) A, EN, N, S 3 d. RO-P402a Start a Fourth Reactor Coolant Pump OP/1/A/1103/006 Encl 4.4 (Starting 1B2 RCP) [KA: 003 A4.03 (2.8/2.5)] (10 min) A, D, L, S 4P e. N/A f. RO-602, Restore Secondary Loads After Loss of Offsite Power AP/1/A/1700/011 (Recovery from Loss of Power) [KA: 062 A4.01 (3.3/3.1)] (15 min) N, S 6 g. N/A h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. N/A j. AO-101 Swap CRD Filters OP/1/A/1104/008 (Component Cooling System) Encl 4.19 (Placing 1A or 1B CRD Filter in Service) [KA: 001 G2.3.13 (3.4/3.8)] (20 min) D, R 1 k. AO-802a Isolate HPSW and LPSW During an AB Flood AP/3/A/1700/030 (Auxiliary Building Flooding) Encl 5.1 (HPSW AB Flood Isolation) and 5.2 (LPSW AB Flood Isolation) [KA: BWA07 AA2.2 (3.3/3.7)] (16 min) A, D, E 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 - / -

FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION1B1 Which ONE of the following combinations of statalarms, if actuated, would illuminate the Trip Confirm Lamp on the Diamond? A. 1SA-1/E-2 (CRD BKR A TRIP) 1SA-1/E-4 (CRD BKR C TRIP) B. 1SA-1/E-2 (CRD BKR A TRIP) 1SA-1/E-5 (CRD BKR D TRIP) C. 1SA-1/E-2 (CRD BKR A TRIP) 1SA-1/E-6 (CRD ELECTRONIC TRIP E) D. 1SA-1/E-3 (CRD BKR B TRIP) 1SA-1/E-7 (CRD ELECTRONIC TRIP F) EPE007 EK2.03 - Reactor TripKnowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45.7)Reactor trip status panel ..........................................Tuesday, October 06, 2015Page 1 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION1B1General DiscussionAnswer A DiscussionIncorrect. CRD Breaker trip combinations are: A and B, A and D, B and C, C and D, A and Electronic Trip F, B and Electronic Trip E. Plausible in that two CRD breakers indicate tripped and if either B or D were tripped in the place of C, it would be correct.Answer B DiscussionCORRECT. CRD Breakers A and D tripped will de-energize the CRDs and initiate a Trip Confirm, which will cause the Trip Confirm Lamp on the Diamond to illuminate.Answer C DiscussionIncorrect. CRD Breaker trip combinations are: A and B, A and D, B and C, C and D, A and Electronic Trip F, B and Electronic Trip E. Plausible since CRD BKR A and CRD ELECTRONIC TRIP F would be correct.Answer D DiscussionIncorrect. CRD Breaker trip combinations are: A and B, A and D, B and C, C and D, A and Electronic Trip F, B and Electronic Trip E. Plausible since CRD BKR B and CRD ELECTRONIC TRIP E would be correct.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesIC-CRI Obj. 05 and 14ARG401-9 Comments:Remarks/StatusBasis for meeting the KAThe Reactor Trip Status at Oconee is indicated by the CRD Breaker statalarms on 1SA-1 and the Trip Confirm Lamp on the Diamond. The question requires knowledge of the interrelations between a reactor trip and the CRD Breaker statalarms and Trip Confirm Lamp on the Diamond.Basis for Hi CogBasis for SRO onlyEPE007 EK2.03 - Reactor TripKnowledge of the interrelations between a reactor trip and the following: (CFR 41.7 / 45.7)Reactor trip status panel ..........................................Tuesday, October 06, 2015Page 2 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION2D2 Given the following Unit 1 conditions: Reactor power = 100% 1RC-66 fails OPEN 1) The initial Reactor Protective System trip function setpoint reached will be RCS __(1)__ pressure. 2) Following the Reactor trip, with actual SG Outlet pressure = 985 psig, the Turbine Bypass valves will be __(2)__. Which ONE of the following completes the statements above? ASSUME NO OPERATOR ACTIONS A. 1. Low 2. throttled open B. 1. Variable Low 2. throttled open C. 1. Low 2. closed D. 1. Variable Low 2. closed APE008 AA2.24 - Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CFR: 43.5 / 45.13)Value at which turbine bypass valve maintains header pressure after a reactor trip ........................................Tuesday, October 06, 2015Page 3 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION2D2General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since RCS pressure will decrease during this event to the point that the reactor will trip. Second part is incorrect. Plausible since it would be correct prior to the reactor trip. Normal Turbine Header Pressure setpoint = 885 psig. The Turbine Bypass Valves (TBVs) provide overpressure relief when the turbine is on-line at setpoint + 50 psig. So prior to the reactor trip, the TBVs would throttle open at 935 psig. Trip confirm inputs a + 125 psig bias. 885 + 125 = 1010 psig setpoint for TBVs following the reactor trip, so at 985 psig, the TBVs would be closed.Answer B DiscussionIncorrect. First part is correct. 1RC-66 open at 100% is essentially a SBLOCA and will cause RCS pressure to decrease with little/no temperature decrease. This will cause a trip on Variable Low Pressure. Second part is incorrect. Plausible since it would be correct prior to the reactor trip. Normal Turbine Header Pressure setpoint = 885 psig. The Turbine Bypass Valves (TBVs) provide overpressure relief when the turbine is on-line at setpoint + 50 psig. So prior to the reactor trip, the TBVs would throttle open at 935 psig. Trip confirm inputs a + 125 psig bias. 885 + 125 = 1010 psig setpoint for TBVs following the reactor trip, so at 985 psig, the TBVs would be closed.Answer C DiscussionIncorrect. First part is incorrect. Plausible since RCS pressure will decrease during this event to the point that the reactor will trip. Second part is correct.Answer D DiscussionCorrect. First part: 1RC-66 open at 100% is essentially a SBLOCA and will cause RCS pressure to decrease with little/no temperature decrease. This will cause a trip on Variable Low Pressure. Second part: Normal Turbine Header Pressure setpoint = 885 psig. Trip confirm inputs a + 125 psig bias. 885 + 125 = 1010 psig setpoint for TBVs following the reactor trip, so at 985 psig, the TBVs would be closed.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT45 Q1Student References ProvidedDevelopment ReferencesILT45 Q1ICS-02 Obj. 04401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of value at which turbine bypass valves maintain header pressure following a reactor trip due to a PZR vapor space accident.Basis for Hi CogBasis for SRO onlyAPE008 AA2.24 - Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CFR: 43.5 / 45.13)Value at which turbine bypass valve maintains header pressure after a reactor trip ........................................Tuesday, October 06, 2015Page 4 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION3A3 Given the following Unit 1 conditions:

Time = 1700 Reactor trip from 100%

Time = 1705 All SCMs = 0oF stable HPI header A flow = 578 gpm stable 1A and 1B HPI pumps operating 1C HPI pump breaker failed open

1) The valve that must be opened in accordance with Rule 2 (Loss of SCM) is __(1)__. 2) In accordance with Rule 6 (HPI), once the above valve is opened the MAXIMUM total HPI flow is __(2)__ gpm.

Which ONE of the following completes the statements above? A. 1. 1HP-409 2. 950 B. 1. 1HP-409 2. 750 C. 1. 1HP-410 2. 950 D. 1. 1HP-410 2. 750 EPE009 2.1.20 - Small Break LOCAEPE009 GENERICAbility to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 5 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION3A3General DiscussionAnswer A DiscussionCorrect, Rule 2 provides guidance if no flow in the "B" HPI header to open 1HP-409. In addition, if 1A & 1B HPI pumps operating with 1HP-409 open, do not exceed 950 gpm total.Answer B DiscussionIncorrect, first part is correct. Second part is incorrect. Plausible because this is the limit on HPI flow if ONLY one LPI to HPI flow path exists while in piggy back operation.Answer C DiscussionIncorrect, first part is incorrect. Plausible because the higher number valve would normally go to the "B" header. Second part is correct.Answer D DiscussionIncorrect, first part is incorrect. Plausible because the higher number valve would normally go to the "B" header. Second part is incorrect.Plausible because this is the limit on HPI flow if ONLY one LPI to HPI flow path exists while in piggy back operation.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT45 Q2Student References ProvidedDevelopment ReferencesILT 45 Q2 EAP-LOSCM Obj. 24Rule 2Rule 6401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires evaluating the plant following a SBLOCA and determining how to adjust HPI flow (Rules 2 & 6).Basis for Hi CogBasis for SRO onlyEPE009 2.1.20 - Small Break LOCAEPE009 GENERICAbility to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 6 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION4D4 Given the following Unit 1 conditions: Time = 1200 Power escalation in progress Reactor power = 38% slowly increasing A Switchyard Isolation occurs Time = 1215 RCS pressure = 2125 psig Pressurizer temperature = 640°F Pressurizer level is stable All Pressurizer heaters are energized 1) At Time = 1200, an AUTOMATIC Reactor trip __(1)__ occur. 2) At Time = 1215, the pressurizer is __(2)__ . Which ONE of the following completes the statements above?

A. 1. will 2. saturated B. 1. will 2. subcooled C. 1. will NOT 2. saturated D. 1. will NOT 2. subcooled APE056 AK1.03 - Loss of Offsite PowerKnowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: CFR 41.8 / 41.10 / 45.3)Definition of subcooling: use of steam tables to determine it ...........Tuesday, October 06, 2015Page 7 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION4D4General DiscussionAnswer A DiscussionIncorrect. First part is plausible since it could be true if Reactor power were > 40%. Second part is plausible since RCS presssure is below the normal pressure of 2155 psig and Pzr temperature is below normal saturated temp of 648 degrees..Answer B DiscussionIncorrect. First part is plausible since it could be true if Reactor power were > 40%. Second part is correctAnswer C DiscussionIncorrect. First part is correct. Second part is plausible since RCS presssure is below the normal pressure of 2155 psig and Pzr temperature is below normal saturated temp of 648 degrees..Answer D DiscussionCorrect. For load rejections <40% power the reactor will not automatically trip. Saturation temperature for 2125 psig is 645.5 degrees therefore the Pzr is subcooled.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesSAE-L020 Obj R2,3,4401-9 Comments:Remarks/StatusBasis for meeting the KAKA is met since a Loss of offsite power resulted in a plant runback which has resulted in a subcooled Pzr and the candidate has to be able to determine from the steam tables if the Pzr is subcooled as well as have a grasp on the thermodynamic properties of the Pzr and RCS pressure as a result of the Pzr being subcooled.Basis for Hi CogBasis for SRO onlyAPE056 AK1.03 - Loss of Offsite PowerKnowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: CFR 41.8 / 41.10 / 45.3)Definition of subcooling: use of steam tables to determine it ...........Tuesday, October 06, 2015Page 8 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION5D5 Given the following Unit 2 conditions: Initial conditions: Reactor power = 78% stable Current conditions: 2A2 Reactor Coolant Pump trips

1) Controlling Tave signal will AUTOMATICALLY switch to Loop __(1)__ Tave. 2) The reason that the Controlling Tave signal is switched is due to __(2)__.

Which ONE of the following completes the statements above?

A. 1. A 2. RCP 2A2 breaker position B. 1. B 2. RCP 2A2 breaker position C. 1. A 2. Loop RCS flow indication D. 1. B 2. Loop RCS flow indication APE015/017 AK3.05 - Reactor Coolant Pump (RCP) MalfunctionsKnowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : (CFR 41.5,41.10 / 45.6 / 45.13)Shift of T-ave. sensors to the loop with the highest flow ................Tuesday, October 06, 2015Page 9 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION5D5General DiscussionThe stated increase in the idle loop Tc was verified on the simulator.Answer A Discussion1st part is is incorrect but plausible since it is one of the A loop RCP's that trip therefore it would be plausible to believe that the temperature circuit swaps to look at the affected loop. 2nd part is plausible because the input swap to Controlling Tave is based on RCS flow in the A Loop decreasing below 6.2 E6 lbm/hr. It is plausible because some RPS inputs for RC flow is based on RCP breaker position.Answer B Discussion1st part is correct2nd part is plausible because the input swap to Controlling Tave is based on RCS flow in the A Loop decreasing below 6.2 E6 lbm/hr. It is plausible because some RPS inputs for RC flow is based on RCP breaker position.Answer C Discussion1st part is is incorrect but plausible since it is one of the A loop RCP's that trip therefore it would be plausible to believe that the temperature circuit swaps to look at the affected loop.2nd part is correctAnswer D DiscussionCorrect. The Tave circuit would monitor RCS flow and when the A Loop decreasing below 6.2 E6 lbm/hr the ciruit would swap to the other loop (Loop B).Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesIC-RCI Obj. 07 ICS-04 Obj. 01 ARG401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the response of the ICS Tave signal and the reason the signal swaps to the unaffected loop.Basis for Hi CogBasis for SRO onlyAPE015/017 AK3.05 - Reactor Coolant Pump (RCP) MalfunctionsKnowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : (CFR 41.5,41.10 / 45.6 / 45.13)Shift of T-ave. sensors to the loop with the highest flow ................Tuesday, October 06, 2015Page 10 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION6A6 Given the following Unit 1 conditions: Reactor power = 100% All HPI pumps fail AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated 1) Reactor Coolant Pump thermal barrier cooling will initially be provided by __(1)__. 2) The reason thermal barrier cooling is provided is to limit __(2)__ .

Which ONE of the following completes the statements above? A. 1. Component Cooling 2. damage to RCP seals B. 1. Component Cooling 2. temperature rise in LDST C. 1. Low Pressure Service Water 2. damage to RCP seals D. 1. Low Pressure Service Water 2. temperature rise in LDST APE022 AK3.06 - Loss of Reactor Coolant MakeupKnowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: (CFR 41.5, 41.10 / 45.6 / 45.13)RCP thermal barrier cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Tuesday, October 06, 2015Page 11 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION6A6General DiscussionAnswer A DiscussionCORRECT. Thermal barrier cooling is provided by Component Cooling on a loss of HPI to prevent seal damage from the hot RCS flowing up through the seals.Answer B DiscussionIncorrect. First part is correct. Second part is incorrect but plausible since seal return goes to the LDST. Therefore, on a loss of seal injection, the RCS flows up through the seal packages and goes to the LDST and the LDST has a maximum temperature limit. However, this is not the reason for thermal barrier cooling.Answer C DiscussionIncorrect. First part is incorrect but plausible since Low Pressure Service Water provides cooling to the Reactor Coolant Pump motors. Second part is correct.Answer D DiscussionIncorrect. First part is incorrect but plausible since Low Pressure Service Water provides cooling to the Reactor Coolant Pump motors. Second part is incorrect but plausible since seal return goes to the LDST. Therefore, on a loss of seal injection, the RCS flows up through the seal packages and goes to the LDST and the LDST has a maximum temperature limit. However, this is not the reason for thermal barrier cooling.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesPNS-CPS Obj. 3AP/14EAP-APG Obj. R9401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of how RCP thermal barrier cooling is provided on a loss of Reactor Coolant Makeup (all HPI Pumps).Basis for Hi CogBasis for SRO onlyAPE022 AK3.06 - Loss of Reactor Coolant MakeupKnowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: (CFR 41.5, 41.10 / 45.6 / 45.13)RCP thermal barrier cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Tuesday, October 06, 2015Page 12 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION7B7 Given the following Unit 1 conditions: Time = 1200 LPI aligned in the Normal Decay Heat Removal mode 1A LPI pump operating Time = 1201 Loss of offsite power results in Switchyard Isolation Time = 1202 Power restored via CT-4 1) Assuming NO operator actions, at Time = 1205 __(1)__ LPI pump(s) will be operating.

2) If NEITHER the 1A NOR the 1B LPI pumps were available at Time = 1202, manual reset of Load Shed is __(2)__ prior to starting the 1C LPI pump.

Which ONE of the following completes the statements above?

A. 1. the 1A 2. required B. 1. the 1A 2. NOT required C. 1. NO 2. required D. 1. NO 2. NOT required APE025 AK2.02 - Loss of Residual Heat Removal System (RHRS)Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: (CFR 41.7 / 45.7)LPI or Decay Heat Removal/RHR pumps ............................ Tuesday, October 06, 2015Page 13 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION7B7General DiscussionAnswer A DiscussionFirst part is correct. Second part is plausbile since the 1C LPI pump is not an ES component and therefore it is plausible it would respond as most other non-ES componnents and not be available until after the load shed signal had been reset.Answer B DiscussionCorrectSince the 1A LPI pump was operating its breaker will remain closed and therefore the pump will restart once power is restored. Pushing the Control Room MFB monitor RESET pushbuttons is not required because the signal for the 1C LPI Pump is removed 5 seconds after the Load Shed actuated if either the 1A or 1B LPI Pump is off.Answer C DiscussionIncorrect: First part is incorrect but plausible since it would be correct if the 1C pump were operating. Additionally plausible since this is below any ECCS requirments and there are no auto start requirments for LPI pumps as it relates for DHR. Second part is plausbile since the 1C LPI pump is not an ES component and therefore it is plausible it would respond as most other non-ES componnents and not be available until after the load shed signal had been reset.Answer D DiscussionIncorrect: First part is incorrect but plausible since it would be correct if the 1C pump were operating. Additionally plausible since this is below any ECCS requirments and there are no auto start requirments for LPI pumps as it relates for DHR. Second part is plausbile since the 1C LPI pump is not an ES component and therefore it is plausible it would respond as most other non-ES componnents and not be available until after the load shed signal had been reset.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT44 Q6Student References ProvidedDevelopment ReferencesILT44 Q6EL-PSL Obj 03401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the relationship between a loss of DHR due to loss of power and actions or inactions required in order to restore DHR cooling following restoration of power.Basis for Hi CogBasis for SRO onlyAPE025 AK2.02 - Loss of Residual Heat Removal System (RHRS)Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: (CFR 41.7 / 45.7)LPI or Decay Heat Removal/RHR pumps ............................ Tuesday, October 06, 2015Page 14 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION8B8 Given the following Unit 1 conditions:

Time = 1200 Reactor in MODE 3 RCS temperature = 450°F Various Breakers supplying Pzr heaters trip OPEN FIN24 reports 420 KW of Pressurizer heater capacity remain available Time = 1400 RCS temperature = 335°F stable

1) At Time = 1200, LCO 3.4.9 (Pressurizer) requirements __(1)__ met. 2) At Time = 1400, the requirements of Tech Spec 3.4.9 __(2)__ apply.

Which ONE of the following completes the statements above?

A. 1. are 2. do NOT B. 1. are 2. do C. 1. are NOT 2. do NOT D. 1. are NOT 2. do APE027 2.2.42 - Pressurizer Pressure Control System (PZR PCS) MalfunctionAPE027 GENERICAbility to recognize system parameters that are entry-level conditions for Technical Specifications. (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)Tuesday, October 06, 2015Page 15 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION8B8General DiscussionAnswer A Discussion1st part is correct2nd part is incorrect but plausible since the HPI spec applicability threshold is 350 degrees..Answer B DiscussionCorrect. The LCO of TS 3.4.9 requires 400 KW of heater capacity and the spec becomes applicable at 325 degreesAnswer C DiscussionIncoxrrect. First part is plausible since 400 KW is the required number and 420 is realtively close to that number. Also, total heater capacity is over 1600 kw therefore only having 420 kw represents a significant loss in capability.2nd part is incorrect but plausible since the HPI spec applicability threshold is 350 degrees.Answer D DiscussionIncoxrrect. First part is plausible since 400 KW is the required number and 420 is realtively close to that number. Also, total heater capacity is over 1600 kw therefore only having 420 kw represents a significant loss in capability.2nd part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesADM-ITS Obj. 7TS 3.4.9COLR PNS-PZR Obj: 12401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of TS entry requirements due to Pzr Heater malfunction.Basis for Hi CogBasis for SRO onlyAPE027 2.2.42 - Pressurizer Pressure Control System (PZR PCS) MalfunctionAPE027 GENERICAbility to recognize system parameters that are entry-level conditions for Technical Specifications. (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)Tuesday, October 06, 2015Page 16 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION9B9 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% 1A HPI pump operating 1HP-27 closed Current conditions: Both Main FDW pumps trip Reactor power 52% decreasing Rule 1 (ATWS/Unanticipated Nuclear Power Production) in progress 1) In accordance with Rule 1, 1B HPI pump will be started if 1HP-27 will NOT open in order to __(1)__. 2) In accordance with Rule 6 (HPI), CRS concurrence __(2)__ be required to throttle HPI. Which ONE of the following completes the statements above? A. 1. maximize flow in 1A HPI header 2. will B. 1. utilize the HPI Cross-over header 2. will C. 1. maximize flow in 1A HPI header 2. will NOT D. 1. utilize the HPI Cross-over header 2. will NOT EPE029 EK3.02 - Anticipated Transient Without Scram (ATWS)Knowledge of the reasons for the following responses as the apply to the ATWS: (CFR 41.5 / 41.10 / 45.6 / 45.13)Starting a specific charging pump ................................... Tuesday, October 06, 2015Page 17 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION9B9General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since HPI flow is inadequate with 1HP-27 closed and maximizing flow in 1A HPI header would increase the boration. However, the intent of the EOP is to provide flow in both headers. Second part is correct.Answer B DiscussionCORRECT. The Standby HPI Pump (1B in this case) will be started per Rule 1 if 1HP-27 will not open and 1HP-409 (HPI cross-over) will be opened to provide flow in both headers.. CRS concurrence is required to throttle HPI when emergency boration is in effect.Answer C DiscussionIncorrect. First part is incorrect. Plausible since HPI flow is inadequate with 1HP-27 closed and maximizing flow in 1A HPI header would increase the boration. However, the intent of the EOP is to provide flow in both headers.. Second part is incorrect. Plausible since it would be correct if not in emergency boration.Answer D DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since it would be correct if not in emergency boration.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-UNPP Obj. R12EAP-UNPP (Rule 1)Rule 1401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of a reason the Standby HPI Pump is started during an ATWS.Basis for Hi CogBasis for SRO onlyEPE029 EK3.02 - Anticipated Transient Without Scram (ATWS)Knowledge of the reasons for the following responses as the apply to the ATWS: (CFR 41.5 / 41.10 / 45.6 / 45.13)Starting a specific charging pump ................................... Tuesday, October 06, 2015Page 18 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION10A10 Given the following Unit 1 conditions: Steam Generator Tube Rupture in 1B SG Tcold = 490°F slowly decreasing RB pressure = 3.1 psig slowly decreasing RB temperature = 203°F slowly decreasing 1B SG pressure = 606 psig slowly decreasing 1B SG Full Range level = 54% slowly increasing

1) 1B SG level __(1)__ reached the level at which water can enter the Main Steam lines.

2) Assuming 1B SG has reached the level of water in the Main Steam line, __(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. has 2. discontinue steaming the affected SG B. 1. has NOT 2. discontinue steaming the affected SG C. 1. has 2. maximize steaming of the unaffected SG even if TS cooldown rates are exceeded D. 1. has NOT 2. maximize steaming of the unaffected SG even if TS cooldown rates are exceeded EPE038 EA2.16 - Steam Generator Tube Rupture (SGTR)Ability to determine or interpret the following as they apply to a SGTR : (CFR 43.5 / 45.13)Actions to be taken if S/G goes solid and water enters steam line ........ Tuesday, October 06, 2015Page 19 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION10A10General DiscussionAnswer A DiscussionCORRECT. First part is correct. Per EOP Encl. 5.21 (reference provided), the level at which water can enter the steam line is 52.7% Full Range. 1B SG level = 54% Full Range, therefore water has reached the level of water in the steam line. Second part is correct. Once the water in MS line level is reached, steaming is discontinued per the SGTR tab.Answer B DiscussionIncorrect. First part is incorrect. Plausible since the candidate has to determine level from Encl. 5.21 using RB temperature, pressure, and SG pressure. An error on any of the three parameters can cause the candidate to determine an incorrect level, which could indicate water has reached the level to enter the main steam lines. Second part is correct.Answer C DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since steaming the SG even if cooldown rates are exceeded is guidance provided in the SGTR Tab if the SG is approaching overfill conditions and maximizing steaming of the unaffected SG would decrease RCS temp and pressure, which would decrease the leak size in the 1B SG.Answer D DiscussionIncorrect. First part is incorrect. Plausible since the candidate has the determine level from Encl. 5.21 using RB temperature, pressure, and SG pressure. An error on any of the three parameters can cause the candidate to determine an incorrect level, which could indicate water has reached the level to enter the main steam lines. Second part is incorrect. Plausible since steaming the SG even if cooldown rates are exceeded is guidance provided in the SGTR Tab if the SG is approaching overfill conditions and maximizing steaming of the unaffected SG would decrease RCS temp and pressure, which would decrease the leak size in the 1B SG.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedEOP Encl. 5.21Development ReferencesEAP-SGTR Obj. R 15 & 17 SGTREOP Encl. 5.21401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of actions to be taken in accordance with the SGTR Tab when SG level reaches the point at which water can enter the MS line.Basis for Hi CogBasis for SRO onlyEPE038 EA2.16 - Steam Generator Tube Rupture (SGTR)Ability to determine or interpret the following as they apply to a SGTR : (CFR 43.5 / 45.13)Actions to be taken if S/G goes solid and water enters steam line ........ Tuesday, October 06, 2015Page 20 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION11A11 Given the following Unit 2 conditions: Loss of Heat Transfer has occurred Unit 2 TDEFWP is now available to feed the Steam Generators 2A SG level = 8" XSUR slowly decreasing 2A SG pressure = 412 psig slowly decreasing 2B SG level = 5" XSUR slowly decreasing 2B SG pressure = 385 psig slowly decreasing In accordance with Rule 7 (Steam Generator Feed Control), the MAXIMUM initial feed rate allowed to EACH Steam Generator is limited to __(1)__ gpm in order to prevent excessive __(2)__ to the Steam Generator tubes. Which ONE of the following completes the statement above?

A. 1. 100 2. excessive stresses B. 1. 100 2. flow induced vibration damage C. 1. 50 2. excessive stresses D. 1. 50 2. flow induced vibration damage APE054 AK1.02 - Loss of Main Feedwater (MFW)Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): (CFR 41.8 / 41.10 / 45.3)Effects of feedwater introduction on dry S/G ......................... Tuesday, October 06, 2015Page 21 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION11A11General DiscussionAnswer A DiscussionCorrect. Rule 7 limits flow to each affected Steam Generator to 100 gpm if the SG is dry. Level below 12" along with low and decreasing SG pressure indicates that the SG is dry, The EOP TBD explains that the 100 gpm flow limit is based on protecting the SG tubes from excessive stresses.Answer B DiscussionIncorrect. First part is correct. Second part is plausible since it would be correct if the SG already had Heat Trasfer established since that is the basis for flow limits for a SG 'with heat transfer.Answer C DiscussionIncorrect. First part is plausible under the misconception that the 100 gpm is a total flow limit instead of a limit to each SG. 100 gpm total flow is correct if feeding with SSF ASWP.Second part is correct.Answer D DiscussionIncorrect. First part is plausible under the misconception that the 100 gpm is a total flow limit instead of a limit to each SG. 100 gpm total flow is correct if feeding with SSF ASWP.Second part is plausible since it would be correct if the SG already had Heat Trasfer established since that is the basis for flow limits for a SG 'with heat transfer.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT46 Q10Student References ProvidedDevelopment ReferencesILT46 Q10 EAP-LOHT Obj R27Rule 7Rule 7 lesson plan401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the operational implications of not adhering to the flow limits established when introducing feed to a dry SG with no heat transfer.Basis for Hi CogBasis for SRO onlyAPE054 AK1.02 - Loss of Main Feedwater (MFW)Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): (CFR 41.8 / 41.10 / 45.3)Effects of feedwater introduction on dry S/G ......................... Tuesday, October 06, 2015Page 22 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION12A12 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% ACB-4 closed A Switchyard Isolation occurs Current conditions: Keowee Unit 2 Emergency lockout 230 KV Yellow Bus Differential lockout Main Feeder buses will be energized __(1)__ from __(2)__. Which ONE of the following completes the statement above?

A. 1. manually 2. CT-4 B. 1. automatically 2. CT-4 C. 1. manually 2. CT-5 D. 1. automatically 2. CT-5 EPE055 EA1.07 - Loss of Offsite and Onsite Power (Station Blackout)Ability to operate and monitor the following as they apply to a Station Blackout: (CFR 41.7 / 45.5 / 45.6)Restoration of power from offsite ..................................Tuesday, October 06, 2015Page 23 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION12A12General DiscussionAnswer A DiscussionCorrect. Since ACB-4 is closed, KHU-2 is tied to the underground (CT-4) and KHU-1 is tied to the Overhead. When the event occurs, KHU-1 is not capable of going through the overhead due to the Yellow Bus Differential lockout. KHU-2 is not available due to the emergency lockout. Encl 5.38 will direct lining up the available KHU unit (KHU-1) to the MFBs through CT-4.Answer B DiscussionIncorrect because there are no automatic means to line up the KHU aligned to the Overhead path (KHU-1) to power the Main Feeder Busses via CT-4 under the given conditions. It is plausible because if ACB 3 were closed instead of ACB-4, it would be correct.Answer C DiscussionIncorrect because Encl 5.38 will direct powering the Main Feeder Busses from KHU-1 through CT-4. It is plausible because if neither KHU were available, it would be correct.Answer D DiscussionIncorrect because Encl 5.38 will direct powering the Main Feeder Busses from KHU-1 through CT-4. It is plausible because if the Standby Busses were energized from CT-5 at the time of the event, it would be correct.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT39 Q11Student References ProvidedDevelopment ReferencesILT39 Q11 EL-PSL Obj. 07 ARG SA-3/C3401-9 Comments:Remarks/StatusBasis for meeting the KAThe applicant must be able to operate and monitor equipment associated with the restoration of power from off-site following a blackout.Basis for Hi CogBasis for SRO onlyEPE055 EA1.07 - Loss of Offsite and Onsite Power (Station Blackout)Ability to operate and monitor the following as they apply to a Station Blackout: (CFR 41.7 / 45.5 / 45.6)Restoration of power from offsite ..................................Tuesday, October 06, 2015Page 24 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION13A13 Given the following Unit 1 conditions: Station Blackout has occurred Concerning the TDEFWP-1) Oil cooling water will be supplied by __(1)__.

2) the MINIMUM steam pressure that will ensure proper operation of the pump is __(2)__ psig. Which ONE of the following completes the statements above?

A. 1. HPSW 2. 250 B. 1. HPSW 2. 300 C. 1. LPSW 2. 250 D. 1. LPSW 2. 300 APE056 2.4.20 - Loss of Offsite PowerAPE056 GENERICKnowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 25 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION13A13General DiscussionAnswer A DiscussionCorrect. The TDEFDWP Oil Cooler is normally supplied by CCW by an AC powered oil cooling water pump that starts when MS-93 (Steam Admission Valve) opens. HPSW provides backup cooling. Since the unit has experienced a blackout, the CCW supply will not be available and HPSW will supply the oil cooler.The minimum steam pressure that will ensure proper operation of the TDEFDW Pump is 250 psig.Answer B DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since this is the normal pressure for the Auxiliary Steam Header which is one of the steam supplies for the TDEFDW Pump. The other is Main Steam.Answer C DiscussionIncorrect. First part is incorrect. Plausible since LPSW supplies cooling water to the MDEFDW Pumps. Second part is correct.Answer D DiscussionIncorrect. First part is incorrect. Plausible since LPSW supplies cooling water to the MDEFDW Pumps. Second part is incorrect. Plausible since this is the normal pressure for the Auxiliary Steam Header which is one of the steam supplies for the TDEFDW Pump. The other is Main Steam.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesCF-EF Obj. 22 & 55EOP BO Tab401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of the EOP Caution related to minimum steam pressure required for proper TDEFDW Pump operation.Basis for Hi CogBasis for SRO onlyAPE056 2.4.20 - Loss of Offsite PowerAPE056 GENERICKnowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 26 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION14C14 Given the following Unit 1 conditions:

Initial conditions: Reactor power = 100% SASS in Manual while SPOC repairs Pressurizer Level 3 transmitter 1HP-120 in AUTO selected to Pressurizer Level 1 Current conditions: Vital power to ICCM Train A fails Which ONE of the following describes Pressurizer level control with 1HP-120? A. Selecting Pressurizer Level 2 and depressing the AUTO pushbutton on 1HP-120 are required to restore automatic control at setpoint B. Selecting Pressurizer Level 2 ONLY will restore automatic control at setpoint C. Manual control using 1HP-120 Bailey controller is all that is available D. Additional actions are NOT required since Automatic control at setpoint is retained APE057 AA1.06 - Loss of Vital AC Electrical Instrument BusAbility to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: (CFR 41.7 / 45.5 / 45.6)Manual control of components for which automatic control is lost ....... Tuesday, October 06, 2015Page 27 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION14C14General DiscussionAnswer A DiscussionIncorrect. ICCM Train A feeds both Pzr level 1 & 2. ICCM Train B feeds Pzr level 3. It is plausible to believe that since ICCM Train A feeds Pzr level 1 then ICCM Train B feeds Pzr level 2. Under this misconception it is plausible to believe that 1HP-120 would trip to Hand when power is lost to Pzr level 1 since there are multiple bailey control stations that trip to hand under various conditions.Answer B DiscussionIncorrect. ICCM Train A feeds both Pzr level 1 & 2. ICCM Train B feeds Pzr level 3. It is plausible to believe that since ICCM Train A feeds Pzr level 1 then ICCM Train B feeds Pzr level 2 which would lead choosing this as the correct answerAnswer C DiscussionCorrect. ICCM Train A feeds both Pzr level 1 & 2. ICCM Train B feeds Pzr level 3. With Pzr level 3 unavailable, if ICCM Train A fails, all auto control is lost, therefore only using 1HP-120 in hand would be correct.Answer D DiscussionIncorrect. Plausible since this would be correct if SASS were in Auto.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT44 Q14Student References ProvidedDevelopment ReferencesILT44 Q14PNS-PZR Obj. 20 & 21OP/1/A/1105/012401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to both manually operate and monitor manual control of 1fHP-120 following a loss of Vital Power to ICCM Train A.Basis for Hi CogBasis for SRO onlyAPE057 AA1.06 - Loss of Vital AC Electrical Instrument BusAbility to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: (CFR 41.7 / 45.5 / 45.6)Manual control of components for which automatic control is lost ....... Tuesday, October 06, 2015Page 28 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION15C15 Given the following Unit 1 conditions: Time = 0800: Reactor power = 100% Instrument Air pressure decreasing AP/22 (Loss of Instrument Air) initiated Time = 0810: 1B Main Steam Line Break in containment Reactor Building pressure 3.2 psig slowly increasing Instrument Air and Auxiliary Instrument Air pressure lost At Time = 0810-1) In accordance with Rule 7 (SG Feed Control), 1A SG will be controlled at __(1)__ inches XSUR level.

2) 1FDW-315 __(2)__ be operated from the Control Room. Which ONE of the following completes the statements above? A. 1. 30 2. can B. 1. 30 2. can NOT C. 1. 60 2. can D. 1. 60 2. can NOT APE065 AA1.01 - Loss of Instrument AirAbility to operate and / or monitor the following as they apply to the Loss of Instrument Air: (CFR 41.7 / 45.5 / 45.6)Remote manual loaders ...........................................Tuesday, October 06, 2015Page 29 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION15C15General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if RB pressure were < 3 psig. Second part is correct. 1FDW-315/316 have a nitrogen backup that will allow normal operation from the controllers in the Control Room for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following a loss of IA and AIA.Answer B DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if RB pressure were < 3 psig. Second part is incorrect. Plausible since it would be correct without the nitrogen backup, or once the nitrogen supply is depleted.Answer C DiscussionCORRECT. With degraded containment (RB pressure >/= 3 psig), abnormal containment (acc) levels apply and 30 inches is added to the SG level setpoints when on EFDW. Therefore, the SG acc level setpoint when on EFDW with RCPs operating is 60" XSUR. The operator must maintain the acc level with 1FDW-315/316 in manual since no auto control is available. Second part is correct.Answer D DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since it would be correct without the nitrogen backup, or once the nitrogen supply is depleted.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesCF-EF Obj. 41EAP-LOHT Rule 7 Obj. R27Rule 7401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of the ability to manually operate 1FDW-315/316 controllers during a loss of Instrument Air.Basis for Hi CogBasis for SRO onlyAPE065 AA1.01 - Loss of Instrument AirAbility to operate and / or monitor the following as they apply to the Loss of Instrument Air: (CFR 41.7 / 45.5 / 45.6)Remote manual loaders ...........................................Tuesday, October 06, 2015Page 30 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION16A16 Given the following Unit 1 conditions: Reactor power = 55% stable AP/34 (Generator Grid Disturbance) in progress Generator Frequency = 57 Hz Generator Output = 850 MWe and (+) 450 MVARs Generator Hydrogen Pressure = 60 psig Generator Output Voltage = 18.2 KV 1) In accordance with AP/34 the Generator output __(1)__ within the limits of the Generator Capability Curve. 2) Manually tripping the Main Turbine__(2)__ required.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. is 2. is B. 1. is NOT 2. is C. 1. is 2. is NOT D. 1. is NOT 2. is NOT APE077 AA2.06 - Generator Voltage and Electric Grid DisturbancesAbility to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)Generator frequency limitations..................................................Tuesday, October 06, 2015Page 31 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION16A16General DiscussionAnswer A Discussion1st part is correct. The generator output is within the limits of the Generator Capability Curve (AP/34 Encl. 5.1). 2nd part is correct. An automatic main turbine trip on low frequence should have occurred at 57.6 hz and since it did not occur (based on stem conditions) it should be manually tripped.Answer B Discussion1st part is incorrect. It is plausible since it would be correct if power factor were leading or if Gen H2 pressure were lower. 2nd part is correct. A Reactor trip is required by AP/34 due to frequency being < 57.6 HZ and reactor power > 50%.Answer C Discussion1st part is correct. The generator output is within the limits of the Generator Capability Curve (AP/34 Encl. 5.1).2nd part is incorrect because a reactor trip is required due to frequency being low. It is plausible since it would be correct if reactor power were </= 50%.Answer D Discussion1st part is incorrect. It is plausible since it would be correct if power factor were leading or if Gen H2 pressure were lower.2nd part is incorrect because a reactor trip is required due to frequency being low. It is plausible since it would be correct if reactor power were </= 50%.It is plausible to not be within the generator capability curve and not require a reactor trip because if parameters were such that you were not within the capability curve but were < 50% power, it would be correct.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT44 Q16Student References ProvidedAP/34 Encl. 5.1Development ReferencesILT44 Q16EAP-APG (AP/34) Obj. R4 and R7AP/1/A/1700/034401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires the ability to determine if a Generator frequency limit has been exceeded during an electric grid disturbance and whehter a reactor trip is warranted.Basis for Hi CogBasis for SRO onlyAPE077 AA2.06 - Generator Voltage and Electric Grid DisturbancesAbility to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)Generator frequency limitations..................................................Tuesday, October 06, 2015Page 32 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION16A16Tuesday, October 06, 2015Page 33 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION17D17 Given the following Unit 1 conditions: Loss of Heat Transfer exists due to the loss of ALL FDW sources HPI Forced Cooling in progress RCS pressure = 2210 psig slowly decreasing Pzr Level = 380 inches increasing Core SCM = 56°F increasing In accordance with Rule 6 (HPI), HPI flow __(1)__ be throttled because __(2)__.

Which ONE of the following completes the statement above? A. 1. may NOT 2. RCS pressure is decreasing B. 1. may NOT 2. CETCs are increasing C. 1. may 2. Pzr Level is increasing D. 1. may 2. CETCs are decreasing BWE04 EK2.2 - Inadequate Heat TransferKnowledge of the interrelations between the (Inadequate HeatTransfer) and the following:(CFR: 41.7 / 45.7)Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the properoperation of these systems to the operation of the facility.Tuesday, October 06, 2015Page 34 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION17D17General DiscussionAnswer A DiscussionIncorrect: First part is incorrect. Criteria for throttling HPI during HPI cooling is basedon Core SCM >0 and CETC decreasing. Plausible since decreasing RCS pressure can be an indication of overcooling.Answer B DiscussionIncorrect: First part is incorrect. Criteria for throttling HPI during HPI cooling is basedon Core SCM >0 and CETC decreasing. Plausible if correlation between increasingCore SCM and slowly decreasing pressure is not recognized as indication thatCETC temperatures are decreasing.Answer C DiscussionIncorrect: First part is correct. Second part is incorrect but plausible in that Pzr levelincreasing is part of the HPI throttling criteria if NOT in HPI F/C.Answer D DiscussionCorrect: Criteria for throttling HPI during HPI cooling is based on Core SCM >0and CETC decreasing. Core SCM increasing with RCS pressure slowlydecreasing indicates that CETC temperatures are decreasing.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion Source2009 Q18Student References ProvidedDevelopment References2009 Q18EAP-HPICD Obj. R3Rule 6401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of heat removal systems (HPI FC) and their operation during a loss of heat transfer event.Basis for Hi CogBasis for SRO onlyBWE04 EK2.2 - Inadequate Heat TransferKnowledge of the interrelations between the (Inadequate HeatTransfer) and the following:(CFR: 41.7 / 45.7)Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the properoperation of these systems to the operation of the facility.Tuesday, October 06, 2015Page 35 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION18C18 Given the following Unit 1 conditions:

Initial conditions: Reactor power = 100% 1A Main Steam Line Break occurs Current conditions: Reactor has tripped RCS Tave = 544°F slowly increasing 1A SG pressure = 0 psig 1B SG pressure = 990 psig slowly increasing 1) The Turbine Driven Emergency Feedwater Pump (TDEFDWP) is __(1)__.

2) The TDEFDWP can be __(2)__ AFIS is reset. Which ONE of the following completes the statements above?

A. 1. operating 2. secured before B. 1. operating 2. secured ONLY after C. 1. NOT operating 2. started before D. 1. NOT operating 2. started ONLY after BWE05 EK1.1 - Excessive Heat TransferKnowledge of the operational implications of the following concepts asthey apply to the (Excessive Heat Transfer)(CFR: 41.8 / 41.10 / 45.3)Components, capacity, and function of emergency systems.Tuesday, October 06, 2015Page 36 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION18C18General DiscussionAnswer A DiscussionIncorrect: Plausible since 1FDW-315 is closed in first step of Rule 5. This makes itplausible that AFIS would not secure the TDEFDWP so that it would be available tofeed the B SG if needed.Answer B DiscussionIncorrect: Plausible since 1FDW-315 is closed in first step of Rule 5. This makes itplausible that AFIS would not secure the TDEFDWP so that it would be available tofeed the B SG if needed. Second part is plausible since many components requiremanual action other than just turning switch to re-position following a safety systemactuation (ex: ES components).Answer C DiscussionCORRECT: The TDEFDWP control switch will override the AFIS interlock toclose TO-145. TO-145 blocks the hydraulic oil supply to MS-95 therefore stopping steam supply to the TDEFDWP. The TDEFDWP switch overrides theAFIS signal and allows the operator to restart the TDEFDWP as necessary tofeed Steam Generators without resetting the AFIS signal.Answer D DiscussionIncorrect: TDEFDWP would be off. Second part is plausible since many componentsrequire manual action other than just turning switch to re-position following a safetysystem actuation (ex: ES components).Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion Source2010A Q18Student References ProvidedDevelopment References2010A Q18 CF-EF Obj. 30401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of the operational implications of an AFIS actuation (emergency system) on the operation of the TDEFDWP (component) during an Excessive Heat Transfer event.Basis for Hi CogBasis for SRO onlyBWE05 EK1.1 - Excessive Heat TransferKnowledge of the operational implications of the following concepts as they apply to the (Excessive Heat Transfer)(CFR: 41.8 / 41.10 / 45.3)Components, capacity, and function of emergency systems.Tuesday, October 06, 2015Page 37 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION19C19 Given the following Unit 1 conditions: Reactor power = 75% stable Instrument failure results in rod withdrawal ICS is taken to hand during Plant Transient Response In accordance with OMP 1-18 (Implementation Standard During Abnormal and Emergency Events)-

1) In order to declare the plant stable, __(1)__ power must be less than or equal to the pre-transient level. 2) When inserting control rods during PTR, the criteria to stop the initial control rod insertion is when RCS pressure and Tave __(2)__. Which ONE of the following completes the statements above?

A. 1. NI 2. stop increasing B. 1. NI 2. return to the pre-transient values C. 1. Core Thermal 2. stop increasing D. 1. Core Thermal 2. return to the pre-transient values APE001 AK3.01 - Continuous Rod WithdrawalKnowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal : (CFR 41.5,41.10 / 45.6 / 45.13)Manually driving rods into position that existed before start of casualty ...Tuesday, October 06, 2015Page 38 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION19C19General DiscussionAnswer A DiscussionIncorrect. First part is plausible since NI's are what provide all reactor protection. Second part is correct.Answer B DiscussionIncorrect. First part is plausible since NI's are what provide all reactor protection. Second part is plausible since Core thermal power is reduced to less than or equal to the pre-transient value during PTR.Answer C DiscussionCorrect. During Plant Transient Response (PTR), OMP 1-18 direction is to reduce Core Thermal Power to a value less than or equal to the pre-transient value and insert control rods when RCS pressure and Tave are increasing due to the heat balance mismatch.Answer D DiscussionIncorrect. First part is correct. Second part is plausible since Core thermal power is reduced to less than or equal to the pre-transient value during PTR.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesADM-OMP Obj R10 OMP 1-18 Att J401-9 Comments:Remarks/StatusPreviewNew KABasis for meeting the KAThis question requires knowledge of the reason control rods would be inserted during the casualty. The reason rods would be inserted at this power level would be to gain control of increasing RCS pressure (generally associated with increasing temperature).. At ONS, the focus is not returning rods to the pre-transient position but it is placing control rods in a position that match FDW flow and that is determined by RCS pressure/temperature response.Basis for Hi CogBasis for SRO onlyAPE001 AK3.01 - Continuous Rod WithdrawalKnowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal : (CFR 41.5,41.10 / 45.6 / 45.13)Manually driving rods into position that existed before start of casualty ...Tuesday, October 06, 2015Page 39 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION20A20 Given the following Unit 1 conditions: Initial conditions: Reactor power = 68% increasing Current conditions: Control Rod group 6 Rod 6 = 0% withdrawn 1) An ICS Asymmetric Rod Runback will reduce power to __(1)__ .

2) If occurring, depressing the HOLD pushbutton on the LCP __(2)__ stop an ICS Asymmetric Rod Runback.

Which ONE of the following completes the statements above?

A. 1. 55% 2. will B. 1. 55% 2. will NOT C. 1. 60% 2. will D. 1. 60% 2. will NOT APE003 AA1.05 - Dropped Control RodAbility to operate and / or monitor the following as they apply to the Dropped Control Rod: (CFR 41.7 / 45.5 / 45.6)Reactor power - turbine power ..................................... Tuesday, October 06, 2015Page 40 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION20A20General DiscussionAnswer A DiscussionCorrect:1st part is correct. ICS is set to reduce reactor power to 55% upon receiving an Asymmetric Rod Runback.2nd part is correct. Depressing the HOLD button will stop an Asymmetric Rod Runback.Answer B Discussion1st part is correct. ICS is set to reduce reactor power to 55% upon receiving an Asymmetric Rod Runback.2nd part is incorrect because depressing HOLD will stop an Asymmetric Rod Runback. It is plausible since depressing the HOLD pushbutton will NOT stop any other runback.Answer C Discussion1st part is incorrect because power will be reduced to 55% upon receiving an Asymmetric Rod Runback. It is plausible because the TS setpoint for the Asymmetric Rod Runback is <=60%.2nd part is correct. Depressing the HOLD button will stop an Asymmetric Rod Runback.Answer D Discussion1st part is incorrect because power will be reduced to 55% upon receiving an Asymmetric Rod Runback. It is plausible because the TS setpoint for the Asymmetric Rod Runback is <=60%.2nd part is incorrect because depressing HOLD will stop an Asymmetric Rod Runback. It is plausible since depressing the HOLD pushbutton will NOT stop any other runback.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT39 Q20Student References ProvidedDevelopment ReferencesILT39 Q20 IC-CRI Obj. 11401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of if/how power changes due to a dropped control rod.Basis for Hi CogBasis for SRO onlyAPE003 AA1.05 - Dropped Control RodAbility to operate and / or monitor the following as they apply to the Dropped Control Rod: (CFR 41.7 / 45.5 / 45.6)Reactor power - turbine power ..................................... Tuesday, October 06, 2015Page 41 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION21A21 Given the following Unit 1 conditions: Initial conditions: Reactor shutdown in progress Reactor power = 58% decreasing Control Rod 3 in Group 7 mechanically bound Current conditions: 1SA-2/B-10 (CRD Asymmetric Rod Position Error) actuates Power decrease stopped Reactor power = 50% stable 1) Over the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , Control Rod 3 in Group 7 __(1)__ become closer to the Group 7 average position. 2) If a Reactor trip occurs, Group 7 in limit __(2)__ be indicated. Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. will 2. will B. 1. will NOT 2. will C. 1. will 2. will NOT D. 1. will NOT 2. will NOT APE005 AK1.03 - Inoperable/Stuck Control RodKnowledge of the operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: (CFR 41.8 / 41.10 / 45.3)Xenon transient .................................................. Tuesday, October 06, 2015Page 42 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION21A21General DiscussionAnswer A DiscussionCORRECT. With the power decrease stopped, Xenon will build in from the downpower causing Group 7 control rods to withdraw and become closer to the Rod 3 position. The Group in limit is received when any rod in that group reaches the limit switch.Answer B DiscussionIncorrect. First part is incorrect. Plausible since it is a common error to confuse control rod movement with changes in Xenon and boron. Second part is correct. The Group in limit is received when any rod in that group reaches the limit switch.Answer C DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible to believe the Group in limit indication would require each rod in the group to be at the in limit.Answer D DiscussionIncorrect. First part is incorrect. Plausible since it is a common error to confuse control rod movement with changes in Xenon and boron.Second part is incorrect. Plausible to believe the Group in limit indication would require each rod in the group to be at the in limit.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesIC-CRI Obj. 07RT-RBC Obj. 03401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires understanding the operational implications of long term operation with a misaligned control rod.Basis for Hi CogBasis for SRO onlyAPE005 AK1.03 - Inoperable/Stuck Control RodKnowledge of the operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: (CFR 41.8 / 41.10 / 45.3)Xenon transient .................................................. Tuesday, October 06, 2015Page 43 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION22A22 Given the following Unit 1 conditions: Reactor power = 100% Pressurizer level = 210" slowly decreasing 1HP-120 (RC VOLUME CONTROL) failed CLOSED AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection) initiated In accordance with AP/14...

1) RCS makeup is initially provided by throttling __(1)__. 2) pressurizer level is maintained at a MINIMUM of __(2)__ inches.

Which ONE of the following completes the statements above? A. 1. 1HP-26 2. 200 B. 1. 1HP-26 2. 80 C. 1. 1HP-122 (RC VOLUME CONTROL BYPASS) 2. 200 D. 1. 1HP-122 (RC VOLUME CONTROL BYPASS) 2. 80 APE028 2.4.11 - Pressurizer (PZR) Level Control MalfunctionAPE028 GENERICKnowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 44 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION22A22General DiscussionAnswer A DiscussionCORRECT: AP/14 directs throttling makeup through HP-26 to maintain PZR>200". If HP-26 fails, AO will locally open HP-122 (HP-120 bypass).Answer B DiscussionIncorrect: First part is correct. Second part is plausible since 80" is the pressurizerlevel required to maintain pressurizer heater operability. Rule 6 allows throttlingprovided pressurizer level is increasing and with the 80" heater cutoff it could be areasonable misconception that 80" is the low level limit.Answer C DiscussionIncorrect: First part is incorrect. First part is plausible since 1HP-122 would becorrect if 1HP-26 would not open. Second part is correct.Answer D DiscussionIncorrect: Both parts are incorrect. First part is plausible since 1HP-122 would becorrect if 1HP-26 would not open. Second part is plausible since 80" is thepressurizer level required to maintain pressurizer heater operability. Rule 6 allowsthrottling provided pressurizer level is increasing and with the 80" heater cutoff itcould be a reasonable misconception that 80" is the low level limit.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion Source2010A Q19Student References ProvidedDevelopment References2010A Q19 EAP-APG Obj. R9 AP/14401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of Abnormal Procedure (AP/14) pertaining to a Pzr level control malfunction.Basis for Hi CogBasis for SRO onlyAPE028 2.4.11 - Pressurizer (PZR) Level Control MalfunctionAPE028 GENERICKnowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 45 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION23D23 Given the following Unit 1 conditions: SGTR in the 1A SG SGTR tab in progress RCS temperature = 540°F decreasing 1TA and 1TB are de-energized In accordance with the SGTR tab- 1) Core SCM is decreased during cooldown to __(1)__.

2) The method that will be used to reduce SCM is cycling __(2)__. Which ONE of the following completes the statements above? A. 1. minimize tensile stress on the 1A SG 2. Pzr spray B. 1. minimize tensile stress on the 1A SG 2. the PORV C. 1. reduce the primary to secondary leak rate 2. Pzr spray D. 1. reduce the primary to secondary leak rate 2. the PORV APE037 AK1.02 - Steam Generator (S/G) Tube LeakKnowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: CFR 41.8 / 41.10 / 45.3)Leak rate vs. pressure drop ........................................ Tuesday, October 06, 2015Page 46 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION23D23General DiscussionAnswer A DiscussionIncorrect: First part is incorrect but plausible since SCM is reduced when a SG is isolated in the EHT tab to reduce tensile stress. It is not the reason in this case. Second part is incorrect but plausible since it would be correct if the RCP that provides PZR spray was operating.Answer B DiscussionIncorrect: First part is incorrect but plausible since SCM is reduced when a SG is isolated in the EHT tab to reduce tensile stress. It is not the reason in this case. Second part is correct.Answer C DiscussionIncorrect. First part is correct. Second part is incorrect but plausible since it would be correct if the RCP that provides PZR spray was operating.Answer D DiscussionCorrect. The purpose of reducing SCM during a SGTR is to reduce RCS pressure as much as possible while still maintaining SCM and RCPNPSH. This minimizes the differential pressure between the RCS and the affected SG(s), thus minimizing the tube leak flowUsing the PORV is a strategy used in the SGTR tab to reduce SCM in this case because the RCPs are not operating since 1TA and 1TB are de-energized.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT41 Q8Student References ProvidedDevelopment ReferencesQ23 ILT41 Q8 EAP-SGTR Obj. R1 and 4EOP SGTR401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowing that SCM is reduced when a SG has a tube rupture in order to decrease RCS pressure which in turn decreases the leak rate.Basis for Hi CogBasis for SRO onlyAPE037 AK1.02 - Steam Generator (S/G) Tube LeakKnowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: CFR 41.8 / 41.10 / 45.3)Leak rate vs. pressure drop ........................................ Tuesday, October 06, 2015Page 47 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION24B24 Given the following Unit 1 conditions: AP/31 (Primary to Secondary Leakage) in progress

1) As a result of Primary to Secondary leakage, the Unit 1/2 Turbine Building Sump (TBS) pump breakers are opened __(1)__. 2) A sustained loss of power to 1RIA-54 will trip BOTH Turbine Building Sump Pumps __(2)__. Which ONE of the following completes the statements above? A. 1. ONLY when RIA-54 is in alarm or inoperable 2. after a 2 minute timer B. 1. ONLY when RIA-54 is in alarm or inoperable 2. immediately C. 1. ANYTIME AP/31 (Primary to Secondary Leakage) has been initiated 2. after a 2 minute timer D. 1. ANYTIME AP/31 (Primary to Secondary Leakage) has been initiated 2. immediately APE059 AA1.01 - Accidental Liquid Radioactive-Waste ReleaseAbility to operate and / or monitor the following as they apply to the Accidental Liquid Radwaste Release: (CFR 41.7 / 45.5 / 45.6)Radioactive-liquid monitor ........................................Tuesday, October 06, 2015Page 48 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION24B24General DiscussionAnswer A Discussion1st part is correct. AP/31 directs opening the TB sump pump breakers if either 1RIA-54 is in alarm OR inoperable.2nd part is plausible because there is a 2 minute timer associated with low sample pump flow that provides for an automatic backwash of thestrainer on high strainer DP. It is plausible to believe it applies here since most SLC requirements for RIA's have a provision to allow in progressreleases to continue on loss of the associated RIA's which makes a 2 minute timer to allow power to be restored additionally plausible.Answer B Discussion1st part is correct. AP/31 directs opening the TB sump pump breakers if either 1RIA-54 is in alarm OR inoperable.2nd part is correct,Answer C Discussion1st part is incorrect because AP/31 does not direct opening TB Sump Pump breakers unless 1RIA-54 is in High Alarm or inoperable. It is plausible because the contaminated water from the secondary will eventually make it into the TB Sump so it would be conservative to open the breakers before the alarm is received.2nd part is incorrect because the sump pumps will trip immediately. It is plausible because there is a 2 minute timer associated with low sample pump flow that provides for an automatic backwash of the strainer on high strainer DP. It is plausible to believe it applies here since most SLC requirements for RIA's have a provision to allow in progressAnswer D Discussion1st part is incorrect because AP/31 does not direct opening TB Sump Pump breakers unless 1RIA-54 is in High Alarm or inoperable. It is plausible because the contaminated water from the secondary will eventually make it into the TB Sump so it would be conservative to open the breakers before the alarm is received.2nd part is correct. A loss of power to RIA=54 will automatically trip both TBS pump breakers.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT44 Q50Student References ProvidedDevelopment ReferencesILT44 Q50RAD-RIA Obj R2, Pg 25AP/31401-9 Comments:Remarks/StatusNew KABasis for meeting the KARequires the ability to monitor proper operation of the Radioactive Liquid Monitor (RIA-54) to prevent an accidental release.Basis for Hi CogBasis for SRO onlyAPE059 AA1.01 - Accidental Liquid Radioactive-Waste ReleaseAbility to operate and / or monitor the following as they apply to the Accidental Liquid Radwaste Release: (CFR 41.7 / 45.5 / 45.6)Radioactive-liquid monitor ........................................Tuesday, October 06, 2015Page 49 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION24B24Tuesday, October 06, 2015Page 50 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION25D25 Given the following plant conditions: B GWD Tank rupture occurs 1RIA-32 (Aux Bldg Gas) in HIGH alarm 1RIA-39 (Cntl Rm Gas) in HIGH alarm Unit 1 AP/18 (Abnormal Release of Radioactivity) has been entered 1) AP/18 directs starting __(1)__Outside Air Booster Fan(s).

2) The Outside Air Booster Fan(s) __(2)__ utilize Unit 2 Main Purge Filters. Which ONE of the following completes the statements above? A. 1. ONLY one 2. will B. 1. two 2. will C. 1. ONLY one 2. will NOT D. 1. two 2. will NOT APE060 AK3.03 - Accidental Gaseous-Waste ReleaseKnowledge of the reasons for the following responses as they apply to the Accidental Gaseous Radwaste: (CFR 41.5,41.10 / 45.6 / 45.13)Actions contained in EOP for accidental gaseous-waste release .........Tuesday, October 06, 2015Page 51 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION25D25General DiscussionAnswer A DiscussionIncorrect.1st part is incorrect. Plausible since following a radiological accident in the Spent Fuel Pool, only one of the two Spent Fuel Filtered Exhaust Fans are started in accordance with AP/9 (Spent Fuel Damage). Also plausible to believe that only one fan would be started since the design basis is for the Outside Air Booster Fans is the most limiting LOCA fission product release and not a GWD Tank rupture.2nd part is incorrect because the Booster Fans have their own intake ductwork including filters. It is plausible because other equipment, such as Spent Fuel Filtered Exhaust does utilize the RB Main Purge filters.Answer B DiscussionIncorrect.1st part is correct. With 1RIA-39 in alarm, AP/18 directs starting both Outside Air Booster Fans.2nd part is incorrect because the Booster Fans have their own intake ductwork including filters. It is plausible because other equipment, such as Spent Fuel Filtered Exhaust does utilize the RB Main Purge filters.Answer C DiscussionIncorrect.1st part is incorrect. Plausible since following a radiological accident in the Spent Fuel Pool, only one of the two Spent Fuel Filtered Exhaust Fans are started in accordance with AP/9 (Spent Fuel Damage). Also plausible to believe that only one fan would be started since the design basis is for the Outside Air Booster Fans is the most limiting LOCA fission product release.Second part is correct.Answer D Discussion1st part is correct. With 1RIA-39 in alarm, AP/18 directs starting both Outside Air Booster Fans.2nd part is correct. The Outside Air Booster fans have their own intake duct work and filter setup.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesRAD-RIA Obj R16AP/18 1SA8 B-9401-9 Comments:Remarks/StatusPreviewBasis for meeting the KAThe question matches the KA by requiring knowledge of the actions contained in the AP for an accidental gas release..Basis for Hi CogBasis for SRO onlyAPE060 AK3.03 - Accidental Gaseous-Waste ReleaseKnowledge of the reasons for the following responses as they apply to the Accidental Gaseous Radwaste: (CFR 41.5,41.10 / 45.6 / 45.13)Actions contained in EOP for accidental gaseous-waste release .........Tuesday, October 06, 2015Page 52 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION26D26 Given the following Unit 1 conditions:

Time = 0800: Reactor power = 25% 1A Main Feedwater Pump is operating 1SA-2/B-11 (ICS AUTO POWER FAILURE) actuated AP/23 (Loss of ICS Power) initiated Time = 0805: Reactor trips AP/23 (Loss of ICS Power)...

1) __(1)__ require tripping the 1A Main Feedwater Pump. 2) directs using __(2)__ to control decay heat removal.

Which ONE of the following completes the statements above?

A. 1. does NOT 2. ADVs B. 1. does 2. ADVs C. 1. does NOT 2. TBVs D. 1. does 2. TBVs BWA03 AA2.2 - Loss of NNI-YAbility to determine and interpret the following as they apply tothe (Loss of NNI-Y)(CFR: 43.5 / 45.13)Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.Tuesday, October 06, 2015Page 53 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION26D26General DiscussionAnswer A Discussion1st part is incorrect because AP/23 has an IAAT step that directs tripping all MFW pumps if the reactor trips. It is plausible because the MFW pump will trip on its own if a loss of ICS AUTO AND HAND power occurs but in this case, it doesn't automatically trip.2nd part is incorrect because the TBVs will be available for hea removal. It is plausible because if it were a loss of ICS AUTO AND HAND power, it would be correct.Answer B Discussion1st part is correct. In AP/23, section 4B (Loss of ICS AUTO Power Only) step 2, IAAT a Rx trip occurs and ICS AUTO power is unavailable, THEN trip both MFDWPs. 2nd part is incorrect because the TBVs will be available for hea removal. It is plausible because if it were a loss of ICS AUTO AND HAND power, it would be correct.Answer C Discussion1st part is incorrect because AP/23 has an IAAT step that directs tripping all MFW pumps if the reactor trips. It is plausible because the MFW pump will trip on its own if a loss of ICS AUTO AND HAND power occurs but in this case, it doesn't automatically trip.2nd part is correct. With ICS HAND power available, the TBVs are available for decay heat removal.Answer D Discussion1st part is correct. In AP/23, section 4B (Loss of ICS AUTO Power Only) step 2, IAAT a Rx trip occurs and ICS AUTO power is unavailable, THEN trip both MFDWPs.2nd part is correct. With ICS HAND power available, the TBVs are available for decay heat removal.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT44 Q24Student References ProvidedDevelopment ReferencesILT44 Q24EAP-APG Obj R9AP23401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of guidance provided in AP/23 on operating equipment with a loss of ICS power (NNI-Y).Basis for Hi CogBasis for SRO onlyBWA03 AA2.2 - Loss of NNI-YAbility to determine and interpret the following as they apply tothe (Loss of NNI-Y)(CFR: 43.5 / 45.13)Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.Tuesday, October 06, 2015Page 54 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION26D26Tuesday, October 06, 2015Page 55 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION27B27 Given the following Unit 1 conditions:

Time = 0800 Reactor trip SBLOCA ES 1-6 actuate CT-1 Lockout 1) At Time = 0801, Main FDW Pumps __(1)__ automatically tripped.

2) In accordance with Rule 2 (Loss of SCM), an initial EFDW flow rate of __(2)__ gpm per SG is established to remove decay heat. A. 1. have 2. 300 B. 1. have NOT 2. 300 C. 1. have 2. 450 D. 1. have NOT 2. 450 BWA05 AK2.2 - Emergency Diesel ActuationKnowledge of the interrelations between the (Emergency DieselActuation) and the following:(CFR: 41.7 / 45.7)Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the properoperation of these systems to the operation of the facility.Tuesday, October 06, 2015Page 56 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION27B27General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. At Time = 0800 the hotwell and condensate booster pumps, which provide suction to the Main FDW Pumps, trip with the loss of power. When the Main FDW Pump suction pressure is </= 235 psig, a 90 second timer starts. If the condition persists for 90 seconds, then the associated FDW Pump will trip. With ES actuated, power is restored through the Keowee Underground powerpath in approx. 15 seconds (12 - 18 sec). When ES actuates, the Keowee Units receive an emergency start signal. One second later a Load Shed signal is generated, which starts a 10 second timer for Transfer to Standby for a total of 11 seconds. At the 15 second mark, the Keowee unit will be up to speed and power will be restored, although the hotwell and condensate booster pumps do not auto restart.Second part is correct. Rule 2 initially establishes 300 gpm EFDW flow per SG.Answer B DiscussionCorrect:At Time = 0800 the hotwell and condensate booster pumps, which provide suction to the Main FDW Pumps, trip with the loss of power. When the Main FDW Pump suction pressure is </= 235 psig, a 90 second timer starts. If the condition persists for 90 seconds, then the associated FDW Pump will trip. The time given is at the 60 second mark and therefore, the Main FDW Pumps have not tripped. Rule 2 initially establishes 300 gpm EFDW flow per SG. If flow can only be established to 1 SG, then 450 gpm is established to that SG.Answer C DiscussionIncorrect. First part is incorrect. At Time = 0800 the hotwell and condensate booster pumps, which provide suction to the Main FDW Pumps, trip with the loss of power. When the Main FDW Pump suction pressure is </= 235 psig, a 90 second timer starts. If the condition persists for 90 seconds, then the associated FDW Pump will trip.Second part is incorrect. Plausible since Rule 2 directs the operator to establish 450 gpm EFDW flow to the intact SG (if both SGs are not intact) when feeding to the LOSCM setpoint.Answer D DiscussionIncorrect. First part is correct.

Second part is incorrect. Plausible since Rule 2 directs the operator to establish 450 gpm EFDW flow to the intact SG (if both SGs are not intact) when feeding to the LOSCM setpointCognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEL-PSL Obj. 11CF-FDW Obj. 06 EAP LOSCM Obj. 19Rule 2Basis for meeting the KAOconee's Emergency Diesel is the Keowee Hydro Units. The question requires knowledge of the interrelations between Keowee and the Motor Driven EFDW Pumps and the required EFDW flow for the SBLOCA event.Basis for Hi CogBasis for SRO onlyBWA05 AK2.2 - Emergency Diesel ActuationKnowledge of the interrelations between the (Emergency DieselActuation) and the following:(CFR: 41.7 / 45.7)Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the properoperation of these systems to the operation of the facility.Tuesday, October 06, 2015Page 57 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION27B27401-9 Comments:Remarks/StatusTuesday, October 06, 2015Page 58 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION28A28 1) The normal power supply to the 1A CC pump is __(1)__. 2) If MFBMP circuitry is activated (power to the Main Feeder Busses is lost) and then power is restored, CC pumps with their control switches in AUTO will start __(2)__.

Which ONE of the following completes the statements above? A. 1. 1XL 2. immediately B. 1. 1XL 2. after a 20 second time delay C. 1. 1XS1 2. immediately D. 1. 1XS1 2. after a 20 second time delay SYS003 K2.02 - Reactor Coolant Pump System (RCPS)Knowledge of bus power supplies to the following: (CFR: 41.7)CCW pumps ....................................................Tuesday, October 06, 2015Page 59 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION28A28General DiscussionAnswer A Discussion1st part is correct. 1XL is the normal power supply for the 1A CC pump. 2nd part is correct. With its switch in AUTO, after a MFBMP activation occurs, the CC pumps will receive a start signal. When power is restored, the pump will start.Answer B Discussion1st part is correct. 1XL is the normal power supply for the 1A CC pump.2nd part is incorrect because the CC pump will start as soon as power is restored. It is plausible because there a 20 second time delay associated with the MFBMP logic. The MFBs have to be de-energized for 20 seconds before the MFBMP actuates.Answer C Discussion1st part is incorrect because the power supply is 1XL. It is plausible since 1XS1 is a motor control center that does supply major components including component cooling valve 1CC-7 however it does not supply power to the CC pumps. Second part is correct.2nd part is correct. With its switch in AUTO, after a MFBMP activation occurs, the CC pumps will receive a start signal. When power is restored, the pump will start.Answer D Discussion1st part is incorrect because the power supply is 1XL. It is plausible since 1XS1 is a motor control center that does supply major components including component cooling valve 1CC-7 however it does not supply power to the CC pumps. Second part is correct.2nd part is incorrect because the CC pump will start as soon as power is restored. It is plausible because there a 20 second time delay associated with the MFBMP logic. The MFBs have to be de-energized for 20 seconds before the MFBMP actuates.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion Source2010A Q35Student References ProvidedDevelopment References2010A Q35IC-ES Obj. 28PNS-CC Obj R15401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the 1A CC pump normal and emergency backup powersupplies.Basis for Hi CogBasis for SRO onlySYS003 K2.02 - Reactor Coolant Pump System (RCPS)Knowledge of bus power supplies to the following: (CFR: 41.7)CCW pumps ....................................................Tuesday, October 06, 2015Page 60 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION28A28Tuesday, October 06, 2015Page 61 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION29C29 Given the following Unit 1 conditions:

0800: Reactor power = 100% MSLB inside containment occurs RCS pressure = 1575 psig 0805: RCS pressure = 1800 psig increasing The BOP is performing Encl 5.1 (ES Actuation)

1) At 0800, Diverse HPI __(1)__ actuated. 2) ES Channels 1 & 2 MANUAL Pushbuttons __(2)__ have to be depressed prior to throttling HPI.

Which ONE of the following completes the statements above? A. 1) has 2) do B. 1) has 2) do NOT C. 1) has NOT 2) do D. 1) has NOT 2) do NOT SYS004 K4.04 - Chemical and Volume Control SystemKnowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)Manual/automatic transfers of control ............................... Tuesday, October 06, 2015Page 62 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION29C29General DiscussionAnswer A DiscussionIncorrect.1st part is incorrect because the setpoint for Diverse HPI = 1550 psig. It is plausible because if pressure had decreased to below 1550 psig, it would be correct.2nd part is correct.Answer B DiscussionIncorrect.1st part is incorrect because the setpoint for Diverse HPI = 1550 psig. It is plausible because if pressure had decreased to below 1550 psig, it would be correct.2nd part is incorrect. Plausible because if it were the RESET P/Bs, it would be correct.Answer C DiscussionCorrect.Diverse HPI setpoint = 1550 psig.ES Channels 1 and 2 have to be placed in manual (manual P/Bs depressed) in order to throttle HPI.Answer D DiscussionIncorrect.1st part is correct. Diverse HPI setpoint = 1550 psig.2nd part is incorrect. Plausible because if it were the RESET P/Bs, it would be correct.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesIC-ES Obj 21Encl 5.1Encl 5.41401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of the ES design features that allow for transfering from automatic to manual control.Basis for Hi CogBasis for SRO onlySYS004 K4.04 - Chemical and Volume Control SystemKnowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)Manual/automatic transfers of control ............................... Tuesday, October 06, 2015Page 63 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION30B30 Given the following Unit 3 conditions: Reactor Power = 100% 3A Purification IX in service Letdown temperature increases by 5°F

1) RCS boron concentration will __(1)__ .

2) With control rods responding, assuming no other operator actions, taking ONLY the ICS Reactor Bailey station to HAND __(2)__ stop the rod motion. Which ONE of the following completes the statements above? A. 1. increase 2. will B. 1. increase 2. will NOT C. 1. decrease 2. will D. 1. decrease 2. will NOT SYS004 K6.20 - Chemical and Volume Control SystemKnowledge of the effect of a loss or malfunction on the following CVCS components: (CFR: 41.7 / 45.7)Function of demineralizer, including boron loading and temperature limitsTuesday, October 06, 2015Page 64 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION30B30General DiscussionAnswer A DiscussionIncorrect.First part is correct. Changing letdown temperature affects reactivity management due to the temperature effect on demineralizer resin. Increasing letdown temperature increases RCS boron and decreasing letdown temperature decreases RCS boron.2nd part is plausible since the name itself implies that it controls signals to the reactor. Additionally, it does block changes in demand from getting the control rods so it would be plausible to believe that neutron error would also be blocked.Answer B DiscussionCORRECT.Changing letdown temperature affects reactivity management due to the temperature effect on demineralizer resin. Increasing letdown temperature increases RCS boron and decreasing letdown temperature decreases RCS boron.Since neutron error drives control rod motion and neutron error is generated downstream of the Reactor Bailey, taking only the Rx bailey to hand will not stop the rod motion. It would freeze Rx demand but the boron would still impact neutron production therefore neutron error would still react and Control Rods would still respond.Answer C DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if letdown temperature decreased.Second part is incorrect. Plausible since the name itself implies that it controls signals to the reactor. Additionally, it does block changes in demand from getting the control rods so it would be plausible to believe that neutron error would also be blocked.Answer D DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if letdown temperature decreased.Second part is correct. Since neutron error drives control rod motion and neutron error is generated downstream of the Reactor Bailey, taking only the Rx bailey to hand will not stop the rod motion. It would freeze Rx demand but the boron would still impact neutron production therefore neutron error would still react and Control Rods would still respond.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q30Student References ProvidedDevelopment ReferencesILT46 Q30PNS-HPI Obj 07ICS picture401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of how a malfunction of a demineralizer (boron loading) will affect the rest of the plant. In this case the "malfunction" would be that procedurally the demineralizer should have been saturated to current RCS boron before being placed in service. An incorrectly boron saturated demineralizer being placed in service is effectively a malfunction.Basis for Hi CogBasis for SRO onlySYS004 K6.20 - Chemical and Volume Control SystemKnowledge of the effect of a loss or malfunction on the following CVCS components: (CFR: 41.7 / 45.7)Function of demineralizer, including boron loading and temperature limitsTuesday, October 06, 2015Page 65 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION31C31 Given the following Unit 1 conditions: Reactor Power = 100% 1TE bus lockout occurs Which ONE of the following contains ONLY pumps that are still being powered from 4160V switchgear. A. 1B HPIP, 1B LPIP B. 1B HPIP, 1C LPIP C. 1C HPIP, 1B LPIP D. 1C HPIP, 1C LPIP SYS005 K2.01 - Residual Heat Removal System (RHRS)Knowledge of bus power supplies to the following: (CFR: 41.7)RHR pumps .....................................................Tuesday, October 06, 2015Page 66 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION31C31General DiscussionAnswer A DiscussionIncorrect. Plausible since both pumps are from the "B" trains.Answer B DiscussionIncorrect. Plausible since one pump is from "B" train and the other from "C" trainAnswer C DiscussionCorrect. Neither 1C HPIP nor 1B LPIP are powered from 1TE.Answer D DiscussionIncorrect. Plausible since ONS component power does not strictly adhere to the "train" principle of alignment.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q31Student References ProvidedDevelopment ReferencesILT46 Q31IC-ES Obj R20Power Supply chart401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of power supplies to LPI pumpsBasis for Hi CogBasis for SRO onlySYS005 K2.01 - Residual Heat Removal System (RHRS)Knowledge of bus power supplies to the following: (CFR: 41.7)

RHR pumps .....................................................Tuesday, October 06, 2015Page 67 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION32C32 Given the following Unit 1 conditions: Time = 0400 Reactor power = 100% Time = 0405 RCS pressure = 550 psig decreasing Time = 0445 RCS pressure = 200 psig decreasing Time = 0450 RCS pressure = 100 psig decreasing 1LP-17 is failed CLOSED 1) In accordance with OMP 1-18 Attachment A (Licensed Operator Memory Items) at Time = 0405, the LATEST time the LPI pumps are required to be secured is __(1)__.

2) At Time = 0450, LPI flow __(2)__ entering the core through BOTH LPI injection nozzles. Which ONE of the following completes the statements above? A. 1. 0425 2. is B. 1. 0425

2. is NOT C. 1. 0435 2. is D. 1. 0435

2. is NOT SYS006 K6.10 - Emergency Core Cooling System (ECCS)Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: (CFR: 41.7 / 45.7)Valves .........................................................Tuesday, October 06, 2015Page 68 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION32C32General DiscussionAnswer A DiscussionIncorrect. First part is plausible in the candidate has the misconception that the time allowed is 20 minutes. 20 minutes is the time for several time critical tasks including "starting the SSF RCMUP during a HELB" and "transferring MDEFDWP suction to the hotwell" . Second part is correct.Answer B DiscussionIncorrect. First part is plausible if the candidate has the misconception that the time allowed is 20 minutes. 20 minutes is the time for several time critical tasks including "starting the SSF RCMUP during a HELB" and "transferring MDEFDWP suction to the hotwell" . Second part is plausible because the main injection valve for the "A" header (1LP-17) is closed therefore without knowledge of the LPI crossover alignment downstream of 1LP-17 and 1LP-18 the candidate would make this choice.Answer C DiscussionCorrect. Per OMP 1-18 Attachment A, the LPI pumps must not operate against a shutoff head greater than 30 minutes. The LPI pumps would be manually restarted as RCS pressure decreases below 200 psig. Due to the crossover mod LPI flow will enter the core through both nozzles even with 1LP-17 closed since the LPI crossover mod connected the two LPI headers downstream of LP=17 and LP-18.Answer D DiscussionIncorrect. First part is correct.. Second part is plausible because the main injection valve for the "A" header (1LP-17) is closed therefore without knowledge of the LPI crossover alighnment downstream of 1LP-17 and 1LP-18 the candidate would make this choice.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT41 Q32Student References ProvidedDevelopment ReferencesILT41 Q32EAP-ESA Obj R12, R17 OMP 1-18401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledege of ECCS response when a valve is failed closed. 1LP-17 is an ECCS valve in the 1A LPI header.Basis for Hi CogBasis for SRO onlySYS006 K6.10 - Emergency Core Cooling System (ECCS)Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: (CFR: 41.7 / 45.7)Valves .........................................................Tuesday, October 06, 2015Page 69 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION33A33 Given the following Unit 2 conditions: Reactor power = 100% Quench Tank is being pumped to 2A BHUT using the Quench Tank Pump AND the Component Drain Pump 1) In accordance with OP/2/A/1104/017 (Quench Tank Operations), Quench Tank Level shall be maintained at a MAXIMUM of __(1)__ inches. 2) If ES -1/2 actuates, this flow path __(2)__ automatically isolate. Which ONE of the following completes the statements above? A. 1. 90 2. will B. 1. 90 2. will NOT C. 1. 100 2. will D. 1. 100 2. will NOT SYS007 A1.01 - Pressurizer Relief Tank/Quench Tank System (PRTS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: (CFR: 41.5 / 45.5)Maintaining quench tank water level within limits ..........................................................Tuesday, October 06, 2015Page 70 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION33A33General DiscussionAnswer A Discussion1st part is correct. IAW OP/1104/017 limits and precautions, QT level shall be maintained between 80 and 90 inches.2nd part is correct. Upon receiving an ES signal, 2CS-5 (ES-1) and 2CS-6 (ES-2) will close and isolate the flow path.Answer B Discussion1st part is correct. IAW OP/1104/017 limits and precautions, QT level shall be maintained between 80 and 90 inches.2nd part is incorrect because if you are pumping the QT to the 2A BHUT (OP/2/A/1104/017 Encl 4.1) 2CS-5 and 2CS-6 will close upon receiving an ES 1 & 2 signal. It is plausible because if you were pumping from the 2A BHUT TO the Quench Tank (OP/2/A/1104/017 Encl 4.2), it would be correct because this flow path is performed with manual valves that will not isolate upon receiving an ES 1/2 signal.Answer C Discussion1st part is incorrect because Unit 2 upper limit is 90 inches. It is plausible because if it were Unit 1, it would be correct. 2nd part is correct. Upon receiving an ES signal, 2CS-5 (ES-1) and 2CS-6 (ES-2) will close and isolate the flow path.Answer D Discussion1st part is incorrect because Unit 2 upper limit is 90 inches. It is plausible because if it were Unit 1, it would be correct.2nd part is incorrect because if you are pumping the QT to the 2A BHUT (OP/2/A/1104/017 Encl 4.1) 2CS-5 and 2CS-6 will close upon receiving an ES 1 & 2 signal. It is plausible because if you were pumping from the 2A BHUT TO the Quench Tank (OP/2/A/1104/017 Encl 4.2), it would be correct because this flow path is performed with manual valves that will not isolate upon receiving an ES 1/2 signal.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q34Student References ProvidedDevelopment ReferencesILT46 Q34PNS-CS Obj 101104/17401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of Quench Tank level limits associated with the system.Basis for Hi CogBasis for SRO onlySYS007 A1.01 - Pressurizer Relief Tank/Quench Tank System (PRTS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: (CFR: 41.5 / 45.5)Maintaining quench tank water level within limits ..........................................................Tuesday, October 06, 2015Page 71 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION33A33Tuesday, October 06, 2015Page 72 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION34A34 Given the following Unit 1 conditions:

Time = 0400: Reactor power = 100% Component Cooling Return Flow = 563 gpm decreasing 1SA-09/C-1 (Component Cooling Return Flow Low) actuates Time = 0402 Component Cooling Return Flow = 103 gpm decreasing The Standby CC pump has NOT started CC Surge Tank level = 18 inches stable 1) At Time = 0400, Statalarm 1SA-09/C-1 __(1)__ valid. 2) At Time = 0402, in accordance with 1SA-09/C-1 ARG, the Standby CC pump __(2)__ be manually started. Which ONE of the following completes the statements above? A. 1. is 2. will B. 1. is 2. will NOT C. 1. is NOT 2. will D. 1. is NOT 2. will NOT SYS008 A4.01 - Component Cooling Water System (CCWS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5)CCW indications and controls .....................................Tuesday, October 06, 2015Page 73 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION34A34General DiscussionAnswer A DiscussionCorrect. 1SA-09/C-1 set point is 575 gpm. The Standby CC pump did not start and should be started after verifying that CC surge tank level is > 12 inches.Answer B DiscussionIncorrect. First part is correct. Second part is plausible because it would be correct if CC level were less than 12 inches.Answer C DiscussionIncorrect. First part is plasuible because it is above the setpoint for Statalarm 1SA-09/B-1 (CRD Return Flow Low) of 138 gpm. Second part is correct.Answer D DiscussionIncorrect. First part is plasuible because it is above the setpoint for Statalarm 1SA-09/B-1 (CRD Return Flow Low) of 138 gpm. Second part is plausible because it would be correct if CC level were less than 12 inches.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT42 Q7Student References ProvidedDevelopment ReferencesILT42 Q7 PNS-CC Obj 08ARG401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of Component Cooling related indications and controls it the control room.Basis for Hi CogBasis for SRO onlySYS008 A4.01 - Component Cooling Water System (CCWS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5)CCW indications and controls .....................................Tuesday, October 06, 2015Page 74 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION35B35 Given the following Unit 1 conditions:

Initial conditions: Reactor power = 100% 1RC-1 failed OPEN RCS pressure = 2150 psig decreasing AP/44 (Abnormal Pressurizer Pressure Control) initiated Current conditions: 1RC-3 failed OPEN

1) Pressurizer heaters __(1)__ be able to maintain RCS pressure above the RPS trip setpoint.

2) AP/44 will initially direct stopping the __(2)__ to help mitigate the failure.

Which ONE of the following completes the statements above? A. 1. will NOT 2. 1A1 RCP ONLY B. 1. will NOT 2. 1A1 and 1A2 RCPs C. 1. will 2. 1A1 RCP ONLY D. 1. will 2. 1A1 and 1A2 RCPs SYS010 K3.01 - Pressurizer Pressure Control System (PZR PCS)Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: (CFR: 41.7 / 45.6)RCS ...........................................................Tuesday, October 06, 2015Page 75 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION35B35General DiscussionAnswer A DiscussionIncorrect. First part is correct. Second part is plausible because the 1A1 RCP is the "spray" pump.Answer B DiscussionCorrect. Heaters will not maintain pressure with the Spray valve open. Pressure will continue to decrease. AP/44 will initially stop the 1A1 and 1A2 RCPs.Answer C DiscussionIncorrect. First part is plausible because the candidate may have the misconception that Pzr heaters could overcome Pzr spray. Second part is plausible because the 1A1 RCP is the "spray" pump.Answer D DiscussionIncorrect. First part is plausible because the candidate may have the misconception that Pzr heaters could overcome Pzr spray. Second part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT45 Q37Student References ProvidedDevelopment ReferencesILT45 Q37 PNS-PZR Obj. 11EAP-APG Obj. R9AP/44401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of how a failure of Pressurizer pressure control system (PZR spray) would affect RCS pressure.Basis for Hi CogBasis for SRO onlySYS010 K3.01 - Pressurizer Pressure Control System (PZR PCS)Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: (CFR: 41.7 / 45.6)RCS ...........................................................Tuesday, October 06, 2015Page 76 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION36C36 The DNBR Safety Limit is applicable in MODE(s) __(1)__ and the High flux RPS trip setpoint __(2)__ designed to prevent exceeding that limit. Which ONE of the following completes the statement above? A. 1. one ONLY 2. is B. 1. one ONLY 2. is NOT C. 1. one AND two 2. is D. 1. one AND two 2. is NOT SYS012 K5.01 - Reactor Protection System (RPS)Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5 / 45.7)DNB ...........................................................Tuesday, October 06, 2015Page 77 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION36C36General DiscussionAnswer A DiscussionIncorrect. First part is incorrect but plausible since the Safety Limits do apply in MODE 1. Also it would be plausible to question the logic of a DNBR limit being in place in MODE 2 since power is limited to 5% in that MODE.Second part is correct.Answer B DiscussionIncorrect. First part is incorrect but plausible since the Safety Limits do apply in MODE 1. Also it would be plausible to question the logic of a DNBR limit being in place in MODE 2 since power is limited to 5% in that MODE.Second part is plausible since the High Flux trip is also designed to protect the fuel centerline temperature Safety Limit therefore under the misconception that a trip only protects against one safety limit it would be more logical to choose the High Temperature trip as the DNBR protection and high flux as the fuel centerline melt protection.Answer C DiscussionCorrect. The DNBR and fuel centerline temperature Safety Limits are applicable in both Mode 1 and 2. The High flux RPS trip is designed to protect against exceeding both the DNBR and Fuel Centerline temperature Safety Limits.Answer D DiscussionIncorrect. First part is correct. Second part is plausible since the High Flux trip is also designed to protect the fuel centerline temperature Safety Limit therefore under the misconception that a trip only protects against one safety limit it would be more logical to choose the High Temperature trip as the DNBR protection and high flux as the fuel centerline melt protection.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT42 Q38Student References ProvidedDevelopment ReferencesILT42 Q38IC-RPS Obj R4401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of the operational implications of exceeding RPS trip setpoints as they relate to DNBR.Basis for Hi CogBasis for SRO onlySYS012 K5.01 - Reactor Protection System (RPS)Knowledge of the operational implications of the following concepts as the apply to the RPS: (CFR: 41.5 / 45.7)DNB ...........................................................Tuesday, October 06, 2015Page 78 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION37C37 Given the following Unit 1 conditions: RCS cooldown in progress RCS pressure = 1730 psig slowly decreasing 1) 1SA-7/D-6 (ES HPI Bypass Permit) __(1)__ actuated.

2) Once bypassed, HPI ES __(2)__ AUTOMATICALLY reinstate when RCS pressure is returned to normal operating pressure.

Which ONE of the following completes the statements above?

A. 1. is 2. does B. 1. is 2. does NOT C. 1. is NOT 2. does D. 1. is NOT 2. does NOT SYS013 K4.12 - Engineered Safety Features Actuation System (ESFAS)Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following : (CFR: 41.7)Safety injection block ............................................ Tuesday, October 06, 2015Page 79 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION37C37General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since pressure is below 1740 psig which is the pressure where it is reinstated. Second part is correct.Answer B DiscussionIncorrect. First part is incorrect. Plausible since pressure is below 1740 psig which is the pressure where it is reinstated. Second part is incorrect. Plausible since other safety systems like AFIS do not auto reinstate once actuated.Answer C DiscussionCORRECT. 1SA-7/D6 (ES HPI Bypass Permit) actuates at 1715 psig decreasing RCS pressure. Once actuated, it will reset at 1740 psig RCS pressure increasing. Therefore with RCS pressure 1730 psig decreasing , the alarm is not actuated.If HPI ES is bypassed, it will auto reinstate when RCS pressure increases above 1740 psig.Answer D DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since other safety systems like AFIS do not auto reinstate once actuated.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT45 Q32Student References ProvidedDevelopment ReferencesILT45 Q32EC-ES Obj 05401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of design features and interlock operation of the HPI portion of ES as it relates to blocking actuation.Basis for Hi CogBasis for SRO onlySYS013 K4.12 - Engineered Safety Features Actuation System (ESFAS)Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following : (CFR: 41.7)Safety injection block ............................................ Tuesday, October 06, 2015Page 80 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION38D38 Given the following Unit 1 Conditions: Time = 0500: Reactor power = 25% stable 1A and 1C RBCUs operating in HIGH speed 1B RBCU is operable and OFF Time = 0501: A LOCA occurs ES channels 1-5 actuate ES channel 6 fails to actuate A LOOP occurs Time = 0505: Offsite power is restored to Unit 1 At Time = 0506, 1C RBCU is __(1)__ and 1B RBCU is __(2)__. Which ONE of the following completes the statement above? A. 1. operating in LOW speed 2. operating in LOW speed B. 1. operating in LOW speed 2. OFF C. 1. OFF 2. operating in LOW speed D. 1. OFF 2. OFF SYS022 A3.01 - Containment Cooling System (CCS)Ability to monitor automatic operation of the CCS, including: (CFR: 41.7 / 45.5)Initiation of safeguards mode of operation ...........................Tuesday, October 06, 2015Page 81 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION38D38General DiscussionAnswer A DiscussionINCORRECT. First part is plausible if the applicant misapplies the 3-minute time delay AND confuses which RBCU restarts from ES-5. (A RBCU restarts from ES-5 and C RBCU restarts from ES-6). Second part is plausible if the applicant misapplies the 3-minute time delay and starts the clock at ES actuation rather than restoration of power.Answer B DiscussionINCORRECT. First part is plausible if the applicant misapplies the 3-minute time delay AND confuses which RBCU restarts from ES-5. (A RBCU restarts from ES-5 and C RBCU restarts from ES-6). Second part is correct.Answer C DiscussionINCORRECT. First part is correct. Second part is plausible if the applicant misapplies the 3-minute time delay and starts the clock at ES actuation rather than restoration of power.Answer D DiscussionCORRECT. In the case of a simultaneous LOCA and LOOP, the 3-minute time delay starts when power is restored (rather than when ES actuates). Therefore only 1 minute has passed since power was restored.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT43 Q39Student References ProvidedDevelopment ReferencesILT43 Q39PNS-RBC Obj. 01401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires the applicant to know that ES-5/6 actuate on high containment pressure, and then determine the RBCU configuration as a result of the actuation, including the 3 minute time delay. The mixed speed circuit stops all running RBCUs on receipt of ES Ch-5/6 actuation, and after a 3-minute time delay, restarts them in LOW. In the case of a simultaneous LOCA and LOOP, the 3-minute time delay starts whenpower is restored (rather than when ES actuates).Basis for Hi CogBasis for SRO onlySYS022 A3.01 - Containment Cooling System (CCS)Ability to monitor automatic operation of the CCS, including: (CFR: 41.7 / 45.5)Initiation of safeguards mode of operation ...........................Tuesday, October 06, 2015Page 82 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION39D39 Following a LBLOCA, __(1)__ is added to the Reactor Building Emergency Sump to __(2)__.

Which ONE of the following completes the statement above? A. 1. LIOH (Lithium Hydroxide) 2. minimize Hydrogen production from the Boric Acid reaction with Zircoloy B. 1. LIOH (Lithium Hydroxide) 2. aid in keeping Iodine in solution, ultimately reducing offsite dose C. 1. TSP (Trisodium Phosphate Dodecahydrate) 2. minimize Hydrogen production from the Boric Acid reaction with Zircoloy D. 1. TSP (Trisodium Phosphate Dodecahydrate) 2. aid in keeping Iodine in solution, ultimately reducing offsite dose SYS026 A1.05 - Containment Spray System (CSS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 / 45.5)Chemical additive tank level and concentration ........................Tuesday, October 06, 2015Page 83 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION39D39General DiscussionAnswer A DiscussionIncorrect. First part is plausible because TSP is added to the Emergency sump to control PH and LIOH is added to RCS to control PH. Second part is plausible since it does inhibit H2 production due to the boric acid reaction with Zinc and Aluminum.Answer B DiscussionIncorrect. First part is plausible because TSP is added to the Emergency sump to control PH and LIOH is added to RCS to control PH. Second part is correct.Answer C DiscussionFirst part is correct. Second part is plausible since it does inhibit H2 production due to the boric acid reaction with Zinc and Aluminum.Answer D DiscussionCorrect. TSP is added to the Emergency Sump by way of TSP baskets as containment water level increases following a LOCA. The TSP is added to control PH which controls the amount of Iodine that comes out of solution which reduces offsite doses.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT43 Q40Student References ProvidedDevelopment ReferencesILT43 Q40PNS-RBS Obj 1401-9 Comments:Remarks/StatusBasis for meeting the KACE stated that asking question regarding the TSP baskets could be used to match this KA. Requires the ability to monitor changes in parameters (offsite doses) based on addition of TSP. The TSP is added to containment water which is utilized by the RBS system.Basis for Hi CogBasis for SRO onlySYS026 A1.05 - Containment Spray System (CSS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 / 45.5)Chemical additive tank level and concentration ........................Tuesday, October 06, 2015Page 84 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION40B40 1) The actual SETPOINT for Reactor Building Spray actuation is __(1)__ psig. 2) The 1BS-2 position if ES Channel 8 fails to actuate is __(2)__.

Which ONE of the following completes the statements above? A. 1. 10 2. Open B. 1. 10 2. Closed C. 1. 15 2. Open D. 1. 15 2. Closed SYS026 K1.01 - Containment Spray System (CSS)Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)ECCS ..........................................................Tuesday, October 06, 2015Page 85 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION40B40General DiscussionAnswer A DiscussionIncorrect: First part is correct. Second part is plausbile since there are mulitiple ESvalve components that are normally in their ES position. (Ex. HP-27 is C HPI pumpdisch valve and is normally open). Also plausble since the pump suction valves areMOV's and are normally open. Also plausble since we leave BS-15 (BS header drainvalve located in RB) open to ensure we do not spray down containment at power.Answer B DiscussionCorrect: ES-7&8 actual setpoint is 10 psig and the RB Spray pump dischargevalves (BS-1&2) are normally closed and are required to open on ES signal.Answer C DiscussionIncorrect: First part is plausible since <15 psig is the TS required setpoint. Secondpart is plausbile since there are mulitiple ES valve components that are normally intheir ES position. (Ex. HP-27 is C HPI pump disch valve and is normally open). Alsoplausble since the pump suction valves are MOV's and are normally open. Also plausble since we leave BS-15 (BS header drain valve located in RB) open toensure we do not spray down containment at power.Answer D DiscussionIncorrect: First part is plausible since <15 psig is the TS required setpoint. Secondpart is correct.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT40 Q43Student References ProvidedDevelopment ReferencesILT40 Q43 PNS-BS Obj. 03 & 06401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the relationship between CSS (building spray) and ECCS (initiation).Basis for Hi CogBasis for SRO onlySYS026 K1.01 - Containment Spray System (CSS)Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)ECCS ..........................................................Tuesday, October 06, 2015Page 86 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION41A41 Given the following plant conditions: Time = 1200 Unit 2 Reactor power = 75% Reactor Diamond, BOTH FDW masters, and the Main and Startup FDW valves are in HAND Time = 1215 Reactor trip occurs 1) At Time = 1200, the Unit 2 Main Feedwater Pump Turbines are being controlled by their associated __(1)__. 2) At Time = 1215, runback of Main Feedwater flow __(2)__ occur AUTOMATICALLY. Which ONE of the following completes the statements above? A. 1. Motor Gear Unit 2. will B. 1. Motor Gear Unit 2. will NOT C. 1. Motor Speed Changer 2. will D. 1. Motor Speed Changer 2. will NOT SYS039 A4.03 - Main and Reheat Steam System (MRSS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)MFW pump turbines ..............................................Tuesday, October 06, 2015Page 87 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION41A41General DiscussionAnswer A DiscussionCorrect.1st part is correct because the Motor Gear Unit (MGU) is the normal speed control for the Main FDW Pumps. At 75% power, both Main FDW Pumps are operating and since there is no mention of the Hand Jack switch, the FDWPs are being controlled by the MGU. In order for the FDWP to be controlled by the Motor Speed Changer (MSC), the FDWP would have to be on the Hand Jack. The Hand Jack switch is used when it is necessary to remove the MGU from service for maintenance, etc. while the FDWP is operating. Placing the FDWP on Hand Jack simulates the MGU on the high speed stop. FDWP control is the lowest speed signal called for, which when on the Hand Jack, would be the MSC.2nd part is correct because upon receiving a reactor trip signal, the MFWPTs, Main & Startup FDW valves will transfer to AUTO and process the runback signal.Answer B DiscussionIncorrect.1st part is correct.2nd part is incorrect because the upon receiving a reactor trip signal, the MFWPTs, Main & Startup FDW valves will transfer to AUTO and process the runback signal. It is plausible becasuse if they did not receive a separate signal on a reactor trip, the runback signal from the ICS "Integrated Master" would not pass through the Loop Masters to runback feedwater and this answer would be correct.Answer C DiscussionIncorrect.1st part is incorrect. Plausible since it would be correct if the FDWPTs were on the Hand Jack.2nd part is correct because upon receiving a reactor trip signal, the MFWPTs, Main & Startup FDW valves will transfer to AUTO and process the runback signal.Answer D DiscussionIncorrect.1st part is incorrect. Plausible since it would be correct if the FDWPTs were on the Hand Jack.2nd part is incorrect because the upon receiving a reactor trip signal, the MFWPTs, Main & Startup FDW valves will transfer to AUTO and process the runback signal. It is plausible because if they did not receive a separate signal on a reactor trip, the runback signal from the ICS "Integrated Master" would not pass through the Loop Masters to runback feedwater and this answer would be correct.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesCF-FPT obj 02STG-ICS401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to monitor for proper steam supply to the main feedwater pumps. Reheat Steam is consistent with D bleed.Basis for Hi CogBasis for SRO onlySYS039 A4.03 - Main and Reheat Steam System (MRSS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)MFW pump turbines ..............................................Tuesday, October 06, 2015Page 88 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION41A41Tuesday, October 06, 2015Page 89 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION42B42 In accordance with Limits and Precautions of OP/1/A/1106/014 (Moisture Separator Reheater), the MAXIMUM allowed side to side delta Temperature across the Low Pressure Turbines during normal operation is __(1)__ degrees F and we ensure this limit is not exceeded by throttling valves controlling the steam supply to the __(2)__ as power level changes. Which ONE of the following completes the statement above?

A. 1. 50 2. First Stage Reheaters B. 1. 50 2. Second Stage Reheaters C. 1. 100 2. First Stage Reheaters D. 1. 100 2. Second Stage Reheaters SYS039 2.1.32 - Main and Reheat Steam System (MRSS)SYS039 GENERICAbility to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)Tuesday, October 06, 2015Page 90 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION42B42General DiscussionAnswer A DiscussionIncorrect, First part is correct. Second part is plausible since this method would control side to side delta T's on the LP turbine however the this is not how it is controlledAnswer B DiscussionCorrect. Per L&P's 50 degrees is the maximum side to side delta T allowed and this is controlled by throttling MS-112 and 173 with power level. These valves control the steam being supplied to the SSRH's and therefore the steam temperature being admitted to the LP turbines.Answer C DiscussionIncorrect. First part is plausible since 100 degrees/hr is the maximum SSRH tube HUR allowed by L&P's.Second part is plausible since this method would control side to side delta T's on the LP turbine however the this is not how it is controlledAnswer D DiscussionIncorrect. First part is plausible since 100 degrees/hr is the maximum SSRH tube HUR allowed by L&P's.Second part is correct..Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesSTG-MSR obj 08 1106/14401-9 Comments:Remarks/StatusBasis for meeting the KARequires the knowledge of a system L&P in the MSR procedure and how we apply that limit during power maneuvering (how we control the temperature below the limit).Basis for Hi CogBasis for SRO onlySYS039 2.1.32 - Main and Reheat Steam System (MRSS)SYS039 GENERICAbility to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)Tuesday, October 06, 2015Page 91 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION43C43 Given the following Unit 1 conditions: Reactor power = 80% stable Reactor Diamond and both Feedwater masters are in HAND Feedwater Transient occurs which results in one of the Main Feedwater Pumps tripping on High Discharge Pressure

1) The Main Feedwater Pump with the LOWER Discharge Pressure trip setpoint is the __(1)__ Main Feedwater Pump. 2) In accordance with AP/1 (Unit Runback), a Manual power reduction to a MINIMUM of __(2)__ % power will be performed. Which ONE of the following completes the statements above?

A. 1. 1A 2. 65 B. 1. 1A 2. 74 C. 1. 1B 2. 65 D. 1. 1B 2. 74 SYS059 A2.07 - Main Feedwater (MFW) SystemAbility to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Tripping of MFW pump turbine ....................................Tuesday, October 06, 2015Page 92 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION43C43General DiscussionAnswer A DiscussionIncorrect. First part is plausible since there are only 2 MFDWP's and since 1A is first alphabetically it would be logical to assume it would be the one you want to trip first if you did not know the specific setpoints.Second part is correct.Answer B DiscussionIncorrect. First part is plausible since there are only 2 MFDWP's and since 1A is first alphabetically it would be logical to assume it would be the one you want to trip first if you did not know the specific setpoints.Second part is plausible since it would be correct for a RCP trip.Answer C DiscussionCorrect. The 1B MFDWP disch pressure setpoint is 1240 psig and the 1A MFDWP disch pressure trip setpoint is 1275 psig.Answer D DiscussionIncorrect. First part is correct.Second part is plausible since it would be correct for a RCP trip.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesCF-FPT Obj 14 AP/1401-9 Comments:Remarks/StatusNEW KABasis for meeting the KAQuestion requires the candidate to predict which FDW pump will trip first during a malfucntion that impacts FDWP discharge pressure and then use procedures to mitigate the consequences.Basis for Hi CogBasis for SRO onlySYS059 A2.07 - Main Feedwater (MFW) SystemAbility to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Tripping of MFW pump turbine ....................................Tuesday, October 06, 2015Page 93 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION44B44 Given the following Unit 1 conditions:

Initial Conditions: Reactor power = 100% Two AFIS pressure transmitters on 1A SG fail high Current Conditions: 1A Main Steam Line break occurs 1A SG pressure = 480 psig rapidly decreasing 1) AFIS __(1)__ actuated.

2) Rule 5 (Main Steam Line Break) will direct the operator to __(2)__. Which ONE of the following completes the statements above? A. 1. is 2. open 1AS-40 while closing 1MS-47 B. 1. is 2. select OFF for 1A MD EFDW Pump C. 1. is NOT 2. open 1AS-40 while closing 1MS-47 D. 1. is NOT 2. select OFF for 1A MD EFDW Pump SYS059 A3.06 - Main Feedwater (MFW) SystemAbility to monitor automatic operation of the MFW, including: (CFR: 41.7 / 45.5)Feedwater isolation ..............................................Tuesday, October 06, 2015Page 94 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION44B44General DiscussionAnswer A DiscussionIncorrect. First part is correct. Second part is plausible since it would be correct if the MSLB were in the B SG. With the leak in the A SG, Rule 5 will not direct transfer of the CSAE steam supply.Answer B DiscussionCorrect: AFIS uses 4 transmitters. Any two of the 4 decreasing to 550 psig will result in an AFIS actuation therefore AFIS will still automatically initiate as long as there are two PTs available. Rule 5 will direct placing the switch for the 1A MD EFDWP in OFF.Answer C DiscussionIncorrect: AFIS will auto initiate. Plausible if AFIS Logic is assumed to be disabled with 2 pressure switches failed which is the case for numerous instrument strings (2/3 logic to mitigate a single failure). Second part is plausible since it would be correct if the MSLB were in the B SG. With the leak in the A SG, Rule 5 will not direct transfer of the CSAE steam supply.Answer D DiscussionIncorrect: AFIS will auto initiate. Plausible if AFIS Logic is assumed to be disabled with 2 pressure switches failed which is the case for numerous instrument strings (2/3 logic to mitigate a single failure). Second part is correct. Additionally, second part is plausible if you believe that AFIS has not actuated since the MDEFWP is placed in OFF anytime there is a MSLB on its associated SG. This means that even if pressure does notdecrease to the AFIS setpoint you would still place the MDEFWP in OFF.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion Source2009B NRC Exam Q43Student References ProvidedDevelopment References2009B NRC Exam Q43CF-FDW Obj. 19 EAP-EHT Obj. R14EOP Rule 5401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of design features and automatic operation of the Main Feedwater system as it relates to the Automatic Feedwater Isolation System.Basis for Hi CogBasis for SRO onlySYS059 A3.06 - Main Feedwater (MFW) SystemAbility to monitor automatic operation of the MFW, including: (CFR: 41.7 / 45.5)Feedwater isolation ..............................................Tuesday, October 06, 2015Page 95 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION45A45 Given the following Unit 1 conditions: Reactor power = 100% Confirmed flooding of the Turbine Building is in progress 1) The EOP TBF tab __(1)__ state that AP/10 (Turbine Building Flood) will be performed in parallel with the tab. 2) Actions taken in accordance with AP/10 will require that __(2)__ Feedwater be used for a long term source of water to the Steam Generators. Which ONE of the following completes the statements above? A. 1. does 2. Emergency B. 1. does 2. Main C. 1. does NOT 2. Emergency D. 1. does NOT 2. Main SYS061 2.4.8 - Auxiliary / Emergency Feedwater (AFW) SystemSYS061 GENERICKnowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 96 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION45A45General DiscussionAnswer A DiscussionCORRECT. A note at the beginning of AP/10 and the EOP TBF tab states that the AP will be used in parallel with the EOP. The AP attempts to identify and stop the source of the water while the EOP focuses on core protection. AP/10 directs securing the CCW pumps in order to stop or reduce the in leakage. A note in the AP explains that this will cause a loss of vacuum and therefore a loss of the Main Feedwater pumps.Answer B DiscussionIncorrect. First part is correct. In the case of AP/10, both the AP and the EOP TBF tab state that AP/10 is to be performed in parallel with the EOP TBF tab. Second part is plausible since without considering the loss of Vacuum caused by the securing of CCW pumps directed in AP/10, Main FDW would be available for long term DHR as needed.Answer C DiscussionIncorrect. First part is incorrect. Plausible since it would be correct for other Aps, which are not performed in parallel with the EOP.Second part is correct.Answer D DiscussionIncorrect. First part is incorrect. Plausible since it would be correct for other APs, which are not performed in parallel with the EOP.Second part is plausible since without considering the loss of Vacuum caused by the securing of CCW pumps directed in AP/10, Main FDW would be available for long term DHR as needed.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-APG R9AP/10401-9 Comments:Remarks/StatusBasis for meeting the KARequired knowledge of how the EOP and AP/10 are used in conjunction with each other with consequences being EFDW being used as long term SG feedwater source.Basis for Hi CogBasis for SRO onlySYS061 2.4.8 - Auxiliary / Emergency Feedwater (AFW) SystemSYS061 GENERICKnowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 97 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION46D46 1) Automatic control circuits will close the associated feeder breakers of 1X7, 2X4 & 3X4 after a load shed has occurred and a __(1)__ second timer has timed out. 2) The reason 1X7, 2X4 & 3X4 load shed is to __(2)__.

Which ONE of the following completes the statements above? A. 1. 30 2. ensure the integrity of the RCP seals B. 1. 30 2. prevent overloading the CT-4 or CT-5 transformers C. 1. 60 2. ensure the integrity of the RCP seals D. 1. 60 2. prevent overloading the CT-4 or CT-5 transformers SYS062 K1.04 - AC Electrical Distribution SystemKnowledge of the physical connections and/or cause-effect relationships between the ac distribution sys- tem and the following systems : (CFR: 41.2 to 41.9)Off-site power sources ...........................................Tuesday, October 06, 2015Page 98 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION46D46General DiscussionAnswer A DiscussionINCORRECT. First part is plausible because X5 & X6 load centers are load shed under certain conditions and the auto reclose time delay for these is 30 seconds. Second part is plausible because this is one of the purposes of the Main Feeder Bus Monitor Panels. MFBMP's assure the integrity of the RCP seals by insuring that seal injection and component cooling flows are regained following a loss of power.Answer B DiscussionINCORRECT. First part is plausible because X5 & X6 load centers are load shed under certain conditions and the auto reclose time delay for these is 30 seconds. Second part is correct, the purpose of the load shed system is the shedding non-essential loadsreducing the load on the Main Feeder Bus to within the capacity of the standby transformers (CT4 and CT5).Answer C DiscussionINCORRECT. First part is correct; the time delay for 1X7, 2X4 & 3X4 after a load shed is 60 seconds to reenergize. Second part is plausible because this is one of the purposes of the Main Feeder Bus Monitor Panels. MFBMP's assure the integrity of the RCP seals by insuring that seal injection and component cooling flows are regained following a loss of powerAnswer D DiscussionCORRECT. The time delay for 1X7, 2X4 & 3X4 after a load shed is 60 seconds to reenergize. The purpose of the load shed system is the shedding non-essential loads reducing the load on the Main Feeder Bus to within the capacity of the standby transformers (CT4 and CT5).Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT43 Q15Student References ProvidedDevelopment ReferencesILT43 Q15EL-PSL Obj. 03401-9 Comments:Remarks/StatusNobody missed it on 43Basis for meeting the KARequires knowledge of the relationship between a portion of the AC Distribution System (1X7, 2X4, 3X4) and Offsite Power source CT-5.Basis for Hi CogBasis for SRO onlySYS062 K1.04 - AC Electrical Distribution SystemKnowledge of the physical connections and/or cause-effect relationships between the ac distribution sys- tem and the following systems : (CFR: 41.2 to 41.9)Off-site power sources ...........................................Tuesday, October 06, 2015Page 99 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION47D47 Given the following station conditions: Initial conditions: All three units Reactor power = 100% Current conditions: All Unit's 4160v Main Feeder Busses are de-energized Unit 1, 2, and 3 EOP Blackout tabs in progress Which ONE of the following describes the required status of Unit 1 Essential Inverters per EOP Enclosure 5.38 (Restoration of Power) and why?

Unit 1's Essential Inverters _______. A. remain energized to provide power to ES channels B. remain energized to provide control power to 4160v C. are de-energized to prevent inverter damage D. are de-energized to extend the life of available batteries SYS063 2.1.23 - DC Electrical Distribution SystemSYS063 GENERICAbility to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)Tuesday, October 06, 2015Page 100 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION47D47General DiscussionAnswer A DiscussionIncorrect.: Plausible if ES Channels (are vital loads from KVIA,B,C,D) are confused with essential loads (from KI, KU, KX); vital loads must be differentiated from essential loads.Answer B DiscussionIncorrect: Plausible if control power (ex. for breakers, switches, etc) are incorrectly assumed to be essential inverter loadsAnswer C DiscussionIncorrect: Incorrect but plausible in that inverters could be damaged due to high current as input voltages start to decrease.Answer D DiscussionCorrect: Essential Inverters KI, KU, & KX DC input breakers are opened to extend battery life per direction given from the EOP SBO tab and Encl. 5.38.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT45 Q49Student References ProvidedDevelopment ReferencesILT45 Q49 EAP-BO Obj. R8EOP Encl. 5.38401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of required actions within procedures and the correlation of the impact of high battery load on available battery capacity as the bases for actions directed in the EOPBasis for Hi CogBasis for SRO onlySYS063 2.1.23 - DC Electrical Distribution SystemSYS063 GENERICAbility to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)Tuesday, October 06, 2015Page 101 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION48B48 Given the following plant conditions: 3CA Battery Charger fails - output voltage = 0 VDC 3CA Battery voltage = 120 VDC 3DCB Bus voltage = 123 VDC Unit 1 DCA/DCB Bus voltage = 125 VDC Unit 2 DCA/DCB Bus voltage = 127 VDC Which ONE of the following will automatically supply power to 3DIA panelboard? A. 3CA Battery B. Unit 1 DC Bus C. 3DCB Bus D. Unit 2 DC Bus SYS063 K1.03 - DC Electrical Distribution SystemKnowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)Battery charger and battery ........................................ Tuesday, October 06, 2015Page 102 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION48B48General DiscussionAnswer A DiscussionIncorrect. Plausible because the 3CA battery will supply power to the bus if its voltage is higher than the backup source. In this case it is not. Unit 1's voltage is higher.Answer B DiscussionCorrect, The voltage from Unit 1 is higher than the 3CA battery voltage since Unit 1 is being supplied from the charger, so Unit 1 will supply power.Answer C DiscussionIncorrect. For the Vital DC system, the 3DCB bus is not aligned to the 3DCA bus. Plausible because 3DCB Bus is aligned to backup the essential invertersAnswer D DiscussionIncorrect. Unit 2's DC Bus is not connected to Unit 3. Plausible because Unit 2 is adjacent to Unit 3 and supplies backup power to Unit 3 for other equipment such as the Unit 3 Control Rod Drive System.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT44 Q75Student References ProvidedDevelopment ReferencesILT44 Q75EL-DCD Obj. 06401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of relationships between the control battery, battery charger, and DC Electrical System.Basis for Hi CogBasis for SRO onlySYS063 K1.03 - DC Electrical Distribution SystemKnowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)Battery charger and battery ........................................ Tuesday, October 06, 2015Page 103 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION49A49 Given the following plant conditions:

Time = 1200 All three units at 50% power ACB-3 is closed Time = 1245 LOCA occurs on Unit 1 ES channels 1 and 2 actuate on Unit 1 CT-1 lockout occurs At Time = 1250, KHU 1 control power is supplied by ________. Which ONE of the following completes the statement above?

A. CX Transformer from Keowee Unit 1 B. 1X Transformer from Keowee Unit 1 C. CX Transformer from Keowee Unit 2 D. 1X Transformer from 230 KV Switchyard SYS064 K2.03 - Emergency Diesel Generator (ED/G) SystemKnowledge of bus power supplies to the following: (CFR: 41.7)Control power ................................................... Tuesday, October 06, 2015Page 104 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION49A49General DiscussionAnswer A DiscussionCorrect. 3 sources of power are normally available to the 1X Load Center, which in turn supplies control power to the Keowee unit. The power supplies are: 1) 1X Transformer from the 230KV switchyard; 2) 1X Transformer from KHU 1 through ACB-1; 3) CX Transformer from 1TC Switchgear. For the Underground unit, CX Transformer is the normal supply and 1X Transformer is the alternate supply. If the normal supply is lost for 36 seconds and the alternate supply is available, the alternate supply will close in. If the normal source returns during the 36 seconds, the logic returns to the normal source. In this question, KHU 1 is the underground unit. With the reactor trip and CT-1 lockout, power is lost to Unit 1 and thus 1TC (CX Transformer), but returns from KHU 1 in less than 36 seconds.Answer B DiscussionIncorrect. . Plausible because it would be true if this was the overhead unit and a Switchyard Isolation occurred (KHU 1 running with ACB-1 closed).Answer C DiscussionIncorrect. Plausible because it would be correct if KHU 2 were supplying power to Unit 1.Answer D DiscussionIncorrect. Plausible because it would be correct if power were lost to 1TC (CX Transformer) for > 36 seconds.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEL-KHU Obj. 01401-9 Comments:Remarks/StatusPreviewBasis for meeting the KAThe question requires knowledge of the bus power supply to control power for the Keowee Hydro Units, which is Oconee's equivalent of Emergency Diesel Generator (ED/G) System, during various plant conditions.Basis for Hi CogBasis for SRO onlySYS064 K2.03 - Emergency Diesel Generator (ED/G) SystemKnowledge of bus power supplies to the following: (CFR: 41.7)Control power ................................................... Tuesday, October 06, 2015Page 105 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION50A50 Given the following Unit 1 conditions: Time = 1200 Reactor power = 100% ACB-4 Closed Large Break LOCA occurs coincident with a total loss of offsite power Time = 1205 Keowee Hydro Unit (KHU)-2 Emergency Lockout occurs At Time = 1210 the __(1)__ power path is being used to supply Unit 1 ECCS systems and __(2)__ LPI pumps are operating. Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. Overhead 2. ONLY 2 B. 1. Overhead 2. ALL 3 C. 1. Underground 2. ONLY 2 D. 1. Underground 2. ALL 3 SYS064 K3.03 - Emergency Diesel Generator (ED/G) SystemKnowledge of the effect that a loss or malfunction of the ED/G system will have on the following: (CFR: 41.7 / 45.6)ED/G (manual loads) ............................................. Tuesday, October 06, 2015Page 106 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION50A50General DiscussionAnswer A DiscussionCorrect. ACB-4 closed indicates that KHU-2 is aligned to the underground power path. Following the LOCA/LOOP, MFB would be energized by KHU-2 through the underground power path. With a subsequent loss of KHU-2, retransfer to startup logic would transfer power to the overhead power path which would be supplied by KHU-1.Although there are 3 LPI pumps, only the A and B are ECCS pumps therefore only 2 would be operating.Answer B DiscussionIncorrect. First part is correct. Second part is plausible since there are 3 LPI pumps and other ECCS systems with 3 major components require all 3 (HPI, LPSW, RBCU's).Answer C DiscussionIncorrect. ACB-4 closed indicates that KHU-2 is aligned to the underground power path. Following the LOCA/LOOP, MFB would be energized by KHU-2 through the underground power path. With a subsequent loss of KHU-2, retransfer to startup logic would transfer power to the overhead power path which would be supplied by KHU-1. However, if the Startup source were not available KHU-1 would be aligned to the Underground Powerpath by closing ACB-3.Second part is correctAnswer D DiscussionIncorrect. ACB-4 closed indicates that KHU-2 is aligned to the underground power path. Following the LOCA/LOOP, MFB would be energized by KHU-2 through the underground power path. With a subsequent loss of KHU-2, retransfer to startup logic would transfer power to the overhead power path which would be supplied by KHU-1. However, if the Startup source were not available KHU-1 would be aligned to the Underground Powerpath by closing ACB-3.

Second part is plausible since there are 3 LPI pumps and other ECCS systems with 3 major components require all 3 (HPI, LPSW, RBCU's).Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q49Student References ProvidedDevelopment ReferencesILT46 Q49EL-PSL Obj 07PNS-LPI401-9 Comments:Remarks/StatusBasis for meeting the KAOur "EDG system" is our Keowee Hydro Units. This question requires knowledge of the effect that a loss of one of the KHU's will have on ONS plant loads and the other KHU. You have to know that when KHU is supplying emergency power to CT-4 following a loca/loop and that KHU is lost, the retransfer to startup will align the other KHU through the overhead power path to the units Main Feeder Buses which are supplying ECCS loads.Basis for Hi CogBasis for SRO onlySYS064 K3.03 - Emergency Diesel Generator (ED/G) SystemKnowledge of the effect that a loss or malfunction of the ED/G system will have on the following: (CFR: 41.7 / 45.6)ED/G (manual loads) ............................................. Tuesday, October 06, 2015Page 107 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION51A51 Given the following Unit 1 conditions: Unit 1 startup in progress RB Purge in progress 1RIA-45 (Norm Vent Gas) determined to be inoperable 1) Automatic termination of RB Purge operation due to increasing activity __(1)__ available.

2) If automatic termination of RB Purge occurs, __(2)__ will close. Which ONE of the following completes the statements above? A. 1. is 2. 1PR-2 through 1PR-5 ONLY B. 1. is 2. 1PR-1 through 1PR-6 C. 1. is NOT 2. 1PR-2 through 1PR-5 ONLY D. 1. is NOT 2. 1PR-1 through 1PR-6 SYS073 K4.01 - Process Radiation Monitoring (PRM) SystemKnowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)Release termination when radiation exceeds setpoint ..................Tuesday, October 06, 2015Page 108 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION51A51General DiscussionAnswer A DiscussionCorrect In case of a failure of RIA-45 HIGH alarm, RIA-46 HIGH alarm (via the switchover function) will actuate the required interlock functions which will trip the RB Purge Fan and close 1PR-2 through 1PR-5.Answer B DiscussionIncorrect, First part is correct. In case of a failure of RIA-45 HIGH alarm, RIA-46 HIGH alarm (via the switchover function) will actuate the required interlock functions.Second part is incorrect. Plausible since 1PR-1 and 1PR-6 are containment isolation valves and are closed by an ES actuation.Answer C DiscussionIncorrect. First part is plausible since 1RIA-45 provides the normal means of automatic isolation of RB purge based on increasing activity therefore it would be plausible to assume that if 1RIA-45 did not auto terminate RB Purge then manual termination would be required.Second part is correct.Answer D DiscussionIncorrect. First part is plausible since 1RIA-45 provides the normal means of automatic isolation of RB purge based on increasing activity therefore it would be plausible to assume that if 1RIA-45 did not auto terminate RB Purge then manual termination would be required.Second part is incorrect. Plausible since 1PR-1 and 1PR-6 are containment isolation valves and are closed by an ES actuation.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT44 Q41Student References ProvidedDevelopment ReferencesILT44 Q41RAD-RIA obj 08ARG 1SA-8/B9401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the effect that a loss of RIA-45 will have on the availability of automatic termination if RIA setpoint is exceeded.Basis for Hi CogBasis for SRO onlySYS073 K4.01 - Process Radiation Monitoring (PRM) SystemKnowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)Release termination when radiation exceeds setpoint ..................Tuesday, October 06, 2015Page 109 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION52C52 Given the following plant conditions: Time = 1200 Spent Fuel Pool level = 0.1 foot stable Time = 1215 Spent Fuel Pool level = -3.4 feet decreasing 1RIA-6 (Spent Fuel Pool Area Monitor) in HIGH alarm 1RIA-41 (Spent Fuel Pool Building Gas) in HIGH alarm An AO is being dispatched to the SFP area to investigate the cause. The AO's dose for this year is 525 mrem The AO has NOT received a dose extension for this year Which ONE of the following is the MAXIMUM TEDE dose (mrem) allowed for the AO while performing the assigned task?

A. 1475 B. 4475 C. 5,000 D. 10,000 SYS073 K5.03 - Process Radiation Monitoring (PRM) SystemKnowledge of the operational implications as they apply to concepts as they apply to the PRM system: (CFR: 41.5 / 45.7)Relationship between radiation intensity and exposure limits ............ Tuesday, October 06, 2015Page 110 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION52C52General DiscussionAnswer A DiscussionIncorrect. Plausible since this would be correct if EDL's were not in effect.Answer B DiscussionIncorrect. Plausible since this would be correct under the misconception that the 5 rem EDL limit included normal occupational exposure for the associated year.Answer C DiscussionCorrect. 5 rem is the EDL limit for individual exposureAnswer D DiscussionIncorrect. Plausible since this is the limit for all activities during an EDL event and could be correct if the Shift Manager were consulted to allow exceeding the 5 Rem or if the actions were specifically to protect valuable property.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-TCA obj R6AP/35401-9 Comments:Remarks/StatusBasis for meeting the KAMeets the KA because a process monitor is being used to determine the operational implications of exposure limits. RIA-41 is a process monitor which is indicating an increase in radiation intensity and that increase in intensity is (in part) a determining factor for what exposure limits apply. Since there is no direct relationship between radiation exposure limits and radiation intensity (e.g. dose limits are not variable based on radiation intensity), making the connection between an accident that causes increased radiation intensity which also impacts exposure limits is used to match the KA.Basis for Hi CogBasis for SRO onlySYS073 K5.03 - Process Radiation Monitoring (PRM) SystemKnowledge of the operational implications as they apply to concepts as they apply to the PRM system: (CFR: 41.5 / 45.7)Relationship between radiation intensity and exposure limits ............ Tuesday, October 06, 2015Page 111 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION53B53 Given the following Unit 3 conditions: Time = 1200 Reactor power = 100% 3A Letdown cooler tube leak rate = 0.1 gpm Time = 1230 3A Letdown cooler tube leak rate = 5.0 gpm 1) LPSW flow to the Component Coolers would be required to__(1)__ in order to maintain 3A Letdown Cooler Component Cooling outlet temperature constant from 1200 - 1230. 2) The MINIMUM RCS letdown temperature that will result in an AUTOMATIC isolation of letdown is __(2)__°F. Which ONE of the following completes the statements above?

A. 1. increase 2. 130 B. 1. increase 2. 135 C. 1. remain approximately the same 2. 130 D. 1. remain approximately the same 2. 135 SYS076 A1.02 - Service Water System (SWS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: (CFR: 41.5 / 45.5)Reactor and turbine building closed cooling water temperatures. ......... Tuesday, October 06, 2015Page 112 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION53B53General DiscussionAnswer A DiscussionFirst part is correct. Second part is plausible since this is the high letdown temperature alarm setpoint.Answer B DiscussionCorrect. Since RCS is at a higher temperature and pressure than Component Cooling and the Letdown Coolers are located before the RCS pressure breakdown orifice in the letdown line the tube leakage would be RCS leaking into the CC system (CC pump disch pressure approx. 150 psig), That means that CC temperature would be increasing requiring LPSW flow to increase in order to maintain CC temp constant. If letdown temperature reaches 135 degrees, 1HP-5 will automatically close isolating letdown.Answer C DiscussionFirst part is plausible for two reasons. If the candidate confuses the other closed loop cooling system (RCW) as the Letdown cooler cooling medium then they would pick LPSW flow to remain unchanged. However the more likely plausibility comes from the location of the Letdown coolers in the letdown line. If the coolers were downstream of the letdown orifice then leakage would be by way of CC leaking into the RCS which would make LPSW flow remaining approximately unchanged the correct choice.Second part is plausible since this is the high letdown temperature alarm setpoint.Answer D DiscussionFirst part is plausible for two reasons. If the candidate confuses the other closed loop cooling system (RCW) as the Letdown cooler cooling medium then they would pick LPSW flow to remain unchanged. However the more likely plausibility comes from the location of the Letdown coolers in the letdown line. If the coolers were downstream of the letdown orifice then leakage would be by way of CC leaking into the RCS which would make LPSW flow remaining approximately unchanged the correct choice.Second part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesPNS-CC Obj 03, 04, 06PNS-HPI401-9 Comments:Remarks/StatusBasis for meeting the KAThe SWS is our LPSW system. This question requires the ability to predict a parameters response (3A Letdown Cooler CC outlet temp) associated with operating the LPSW controls since LPSW is the cooling medium for the CC system. CC (Component Cooling) is the Reactor closed loop cooling water system at Oconee,Basis for Hi CogBasis for SRO onlySYS076 A1.02 - Service Water System (SWS)Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: (CFR: 41.5 / 45.5)Reactor and turbine building closed cooling water temperatures. ......... Tuesday, October 06, 2015Page 113 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION54C54 Given the following plant conditions: Initial conditions: Time = 0400 Primary IA compressor tripped Current conditions: Time = 0405 Instrument Air pressure = 91 psig decreasing At Time = 0405-

1) Auxiliary IA Compressors are __(1)__. 2) Backup IA compressors are __(2)__.

Which ONE of the following completes the statements above? A. 1. OFF 2. OFF B. 1. Operating 2. OFF C. 1. OFF 2. Operating D. 1. Operating 2. Operating SYS078 A3.01 - Instrument Air System (IAS)Ability to monitor automatic operation of the IAS, including: (CFR: 41.7 / 45.5)Air pressure .....................................................Tuesday, October 06, 2015Page 114 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION54C54General DiscussionBackup IA Compressors switches are maintained in STBY 1 during normal operation.Backup IA Compressors in STBY 1 start at 93 psig.Unit 1 Aux IA Compressor starts at 88 psig.Sullair Service Air Compressors start at 95 psig.SA-141 (SA to IA Controller) automatically regulates IA header pressure to 85 psig.Diesel Air Compressors in Auto start at 90 psig.Answer A DiscussionIncorrect:. First part is correct. Second part is incorrect. The Backup IA Compressors are normally in STBY 1 and auto start at 93 psig decreasing. Plausible because it would be correct if the Backup IA Compressor switches were in STBY 2. In STBY 2 the auto start setpoint is 90 psig decreasing.Answer B DiscussionIncorrect:. First part is incorrect. Plausible because it would be correct for the Sullair Service Air Compressors, which auto start at 95 psig decreasing SA pressure. Second part is incorrect. The Backup IA Compressors are normally in STBY 1 and auto start at 93 psig decreasing. Plausible because it would be correct if the Backup IA Compressor switches were in STBY 2. In STBY 2 the auto start setpoint is 90 psig decreasing.Answer C DiscussionCorrect:. Backup IA compressors started at 93 psig and the AIA compressors are still off because they start at 88 psig.Answer D DiscussionIncorrect.First part is incorrect. Plausible because it would be correct for the Sullair Service Air Compressors, which auto start at 95 psig decreasing SA pressure. Second part is correct.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT41 Q52Student References ProvidedDevelopment ReferencesILT41 Q52 SSS-IA Obj. 16 & 25 AP/22401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of how Instrument Air System components respond to changes in instrument air pressure.Basis for Hi CogBasis for SRO onlySYS078 A3.01 - Instrument Air System (IAS)Ability to monitor automatic operation of the IAS, including: (CFR: 41.7 / 45.5)Air pressure .....................................................Tuesday, October 06, 2015Page 115 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION55B55 Given the following Unit 1 conditions: Time = 1200 Reactor in MODE 5 RCS Loops dropped Pressurizer level = 340" stable RB Purge in progress Reactor Building Normal Sump is being pumped Time = 1205 1RIA-48 (Reactor Building Iodine) in HIGH alarm 1RIA-49 (Reactor Building Gas) in HIGH alarm 1) The Containment Evacuation alarm __(1)__ AUTOMATICALLY actuate.

2) __(2)__ will provide guidance to complete the system isolation initiated by 1RIA-49.

Which ONE of the following completes the statements above?

A. 1. will 2. OP/1/A/1102/014 (RB Purge) B. 1. will 2. OP/1/A/1104/007 (LWD System) C. 1. will NOT 2. OP/1/A/1102/014 (RB Purge) D. 1. will NOT 2. OP/1/A/1104/007 (LWD System) SYS103 A2 04 - Containment SystemAbility to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations (CFR: 41.5 / 43.5 / 45.3 / 45.13)Containment evacuation (including recognition of the alarm) ............ Tuesday, October 06, 2015Page 116 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION55B55General DiscussionAnswer A DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since it would be correct on a 1RIA-45 high alarm.Answer B DiscussionCORRECT. 1RIA-49 HIGH alarm does actuate the RB Evacuation alarm. 1RIA-49 HIGH alarm also closes 1LWD-2 to isolate the RBNS. The procedure used to pump the RBNS is OP/1/A/1104/007 (LWD System) and provides guidance to ensure the RBNS Pumps are off and 1LWD-1 is closed.Answer C DiscussionIncorrect. First part is incorrect. Plausible since some other RIA's in the RB do NOT actuate the Containment Evacuation alarm (Ex. RIA-3, 57, 58). Second part is incorrect. Plausible since it would be correct on a 1RIA-45 high alarm.Answer D DiscussionIncorrect. First part is incorrect. Plausible since some other RIA's in the RB do NOT actuate the Containment Evacuation alarm (Ex. RIA-3, 57, 58). Second part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q54Student References ProvidedDevelopment ReferencesILT46 Q54 RAD-RIA Obj. 08OP/1/A/1104/007401-9 Comments:Remarks/StatusPREVIEWBasis for meeting the KAQuestion requires predicting actuation of the Containment Evacuation alarm and using procedures to complete the isolation of the RBNS.Basis for Hi CogBasis for SRO onlySYS103 A2 04 - Containment SystemAbility to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations (CFR: 41.5 / 43.5 / 45.3 / 45.13)Containment evacuation (including recognition of the alarm) ............ Tuesday, October 06, 2015Page 117 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION56A56 Which ONE of the following describes ALL of the MCCs which supply power to Unit 1's Control Rod Drive System? A. 1X9 and 2X1 B. 1X9 and 2X2 C. 1X1 and 2X9 D. 1X1 and 3X9 SYS001 K2.03 - Control Rod Drive SystemKnowledge of bus power supplies to the following: (CFR: 41.7)One-line diagram of power supplies to logic circuits ...................Tuesday, October 06, 2015Page 118 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION56A56General DiscussionAnswer A DiscussionCorrect. Normal CRD supply is 1X9. Alternate supply is 2X1.Answer B DiscussionIncorrect. Plausible because 1X9 is correct and 2X2 is plausible because 2X2 is Unit 3s Alternate supply.Answer C DiscussionIncorrect. Plausible because would be correct for Unit 2.Answer D DiscussionIncorrect. Plausible if the candidate had the misconception that Unit 3 backed up Unit 1. That misconception is plausible since the Unit 3 DC system does back up Unit 1s DC system.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT41 Q56Student References ProvidedDevelopment ReferencesILT41 Q56 IC-RPS obj R27401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of the normal and alternate power supplies for the CRD system which includes the logic circuits used to ensure power to CRD's is available or removed as required.Basis for Hi CogBasis for SRO onlySYS001 K2.03 - Control Rod Drive SystemKnowledge of bus power supplies to the following: (CFR: 41.7)One-line diagram of power supplies to logic circuits ...................Tuesday, October 06, 2015Page 119 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION57C57 Given the following Unit 1 conditions: Reactor in MODE 5 Reactor Vessel level = 80" stable Reactor Vessel Cold Leg Ultrasonic level NOT available 1) In accordance with SD 1.3.5 (Shutdown Protection Plan), reducing the reactor vessel level to 40" __(1)__ allowed.

2) Improper venting of the RCS results in RCS pressure greater than Containment pressure and LT-5 readings that are __(2)__ than actual.

Which ONE of the following completes the statements above? A. 1. is 2. greater B. 1. is 2. less C. 1. is NOT 2. greater D. 1. is NOT 2. less SYS002 K6.03 - Reactor Coolant System (RCS)Knowledge of the effect or a loss or malfunction on the following RCS components: (CFR: 41.7 / 45.7)Reactor vessel level indication .....................................Tuesday, October 06, 2015Page 120 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION57C57General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if level were not going below 50 inches. Second part is correct. LT-5 contains a dp transmitter filled reference leg that is open to the containment atmosphere. If RCS pressure is greater than containment pressure, LT-5 will indicate greater than actual level.Answer B DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if level were not going below 50 inches. Second part is incorrect. LT-5 contains a dp transmitter filled reference leg that is open to the containment atmosphere. If RCS pressure is greater than containment pressure, LT-5 will indicate greater than actual level. It would be correct if containment pressure were greater than RCS pressure.Answer C DiscussionCorrect. First part is correct. SD 1.3.5 requires that all 4 RV level indications be operable prior to going below 50" RV level. Second part is correct. LT-5 contains a dp transmitter filled reference leg that is open to the containment atmosphere. If RCS pressure is greater than containment pressure, LT-5 will indicate greater than actual level.Answer D DiscussionIncorrect. First part is correct. SD 1.3.5 requires that all 4 RV level indications be operable prior to going below 50" RV level. Second part is incorrect. LT-5 contains a dp transmitter filled reference leg that is open to the containment atmosphere. If RCS pressure is greater than containment pressure, LT-5 will indicate greater than actual level. It would be correct if containment pressure were greater than RCS pressure.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesADM-SPP Obj 10 SD 1.3.5CP-RCD Obj 10401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of RV level restrictions as a result of a loss of one of the RV level indications. With the loss of the Reactor Vessel cold leg Ultrasonic level, the RCS drain procedure will not allow reducing the reactor vessel level < 50".Basis for Hi CogBasis for SRO onlySYS002 K6.03 - Reactor Coolant System (RCS)Knowledge of the effect or a loss or malfunction on the following RCS components: (CFR: 41.7 / 45.7)Reactor vessel level indication .....................................Tuesday, October 06, 2015Page 121 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION58D58 Given the following Unit 1 conditions: Time = 1200 Plant is stable following a Reactor trip Pressurizer (Pzr) level = 100" stable Time = 1230 1HP-120 fails closed Pressurizer level decreasing at 1" per minute 1) Assuming no operator actions, the EARLIEST time that Pzr heaters will become unavailable is __(1)__. 2) Based on the conditions above, AP/14 (Loss of Normal HPI Makeup And/Or RCP Seal Injection) __(2)__ direct closing 1HP-5 while 1HP-120 is being repaired.

A. 1. 1245 2. will B. 1. 1245 2. will NOT C. 1. 1250 2. will D. 1. 1250 2. will NOT SYS011 K3.03 - Pressurizer Level Control System (PZR LCS)Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following: (CFR: 41.7 / 45.6)PZR PCS .......................................................Tuesday, October 06, 2015Page 122 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION58D58General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since this time equates to 85" which would be correct if asking about SSF Pzr heaters. Second part is incorrect. Plausible since AP/14 does direct closing 1HP-5 when suction is lost to the HPI Pumps.Answer B DiscussionIncorrect. First part is incorrect. Plausible since this time equates to 85" which would be correct if asking about SSF Pzr heaters. Second part is correctAnswer C DiscussionIncorrect. First part is correct.Second part is incorrect. Plausible since AP/14 does direct closing 1HP-5 when suction is lost to the HPI Pumps.Answer D DiscussionCorrect. This time equates to 80" Pzr level which is the low level cutoff for the Pzr heaters. AP/14 will not direct closing 1HP-5 under the given conditions.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-APG R9 PNS-Pzr obj R7 AP/14401-9 Comments:Remarks/StatusBasis for meeting the KARequired knowledge of the effect that 1HP-120 failing closed will have on Pressurizer heaters.Basis for Hi CogBasis for SRO onlySYS011 K3.03 - Pressurizer Level Control System (PZR LCS)Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following: (CFR: 41.7 / 45.6)PZR PCS .......................................................Tuesday, October 06, 2015Page 123 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION59B59 Given the following Unit 1 conditions: Main Steam Line Break on the 1A Steam Generator Reactor Building pressure = 6.3 psig very slowly decreasing Indicated 1B SG XSUR level = 75" decreasing ALL Subcooling Margins = 65°F stable 1) Actual 1B SG level is __(1)__ indicated XSUR level. 2) 1B SG level __(2)__ AUTOMATICALLY be controlled at the desired level in accordance with Rule 7 (SG Feed Control). Which ONE of the following completes the statements above? A. 1. lower than 2. will B. 1. lower than 2. will NOT C. 1. approximately the same as 2. will D. 1. approximately the same as 2. will NOT SYS016 A3.02 - Non-Nuclear Instrumentation System (NNIS)Ability to monitor automatic operation of the NNIS, including: (CFR: 41.7 / 45.5) Relationship between meter readings and actual parameter value .........Tuesday, October 06, 2015Page 124 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION59B59General DiscussionAnswer A DiscussionIncorrect: First part is correct. Second part is plausible for three reasons. 1. If SG pressure did not exceed 3 psig it would be correct. 2. It would be plausible to believe that the SG level control system setpoint would change when ACC conditions exist and therefore control at the level designated in Rule 7. 3. SG level will be automatcially controlled in this case, only it will be controlled at 30" instead of 60" as required by Rule 7.Answer B Discussion Correct. Since XSUR is not temperature compensated, as RB temperatures increase, actual level becomes lower than indicated level. As RB pressure exceeds 3 psig, ACC conditions are determined to exist and Rule 7 will direct controlling available steam generators at 60" XSUR. This requires manually controlling level since auto level control will attempt to control at 30" XSUR.Answer C DiscussionIncorrect: First part is plausible since it would be correct if asking about SG Operating Range level since it is temperature compensated.Second part is plausible for three reasons. 1. If SG pressure did not exceed 3 psig it would be correct. 2. It would be plausible to believe that the SG level control system setpoint would change when ACC conditions exist and therefore control at the level designated in Rule 7. 3. SG level will be automatcially controlled in this case, only it will be controlled at 30" instead of 60" as required by Rule 7Answer D DiscussionIncorrect: First part is plausible since it would be correct if asking about SG Operating Range level since it is temperature compensated.Second part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-EHT obj R13Rule 7401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to determine the relationship between actual SG level and indicated SG level following a MSLB inside containment. Also requires the ability to monitor automatic operation of SG level control system and determine if it is controlling at the desired level following a MSLB.Basis for Hi CogBasis for SRO onlySYS016 A3.02 - Non-Nuclear Instrumentation System (NNIS)Ability to monitor automatic operation of the NNIS, including: (CFR: 41.7 / 45.5) Relationship between meter readings and actual parameter value .........Tuesday, October 06, 2015Page 125 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION60B60 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% Current conditions: Condenser vacuum = 18.5 inches Hg stable 1TB de-energized Which ONE of the following is the Steam Generator level that will be automatically maintained?

A. 25 inches Startup Range B. 30 inches XSUR C. 50% Operating Range D. 240 inches XSUR SYS035 K4.01 - Steam Generator System (S/GS)Knowledge of S/GS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)S/G level control ................................................Tuesday, October 06, 2015Page 126 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION60B60General DiscussionAnswer A DiscussionIncorrect. Plausible since it would be correct if Main Feedwater were still availableAnswer B DiscussionCorrect. With Vacuum at 18.5 inches, Main Feedwater pumps have already tripped on low vacuum. Since there are still 2 RCP's operating EFDW will control level at 30" on XSUR.Answer C DiscussionIncorrect. Plausible since this would be correct if Main Feedwater were still available and all 4 RCP's were tripped.Answer D DiscussionIncorrect. Plausible since it would be correct if both 1TA and 1TB had been de-energized.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q45Student References ProvidedDevelopment ReferencesILT46 Q45CF-EF Obj 31CF-FW Obj 11401-9 Comments:Remarks/StatusNew K/ABasis for meeting the KARequires knowledge of automatic Steam Generator level control design.Basis for Hi CogBasis for SRO onlySYS035 K4.01 - Steam Generator System (S/GS)Knowledge of S/GS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)S/G level control ................................................Tuesday, October 06, 2015Page 127 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION61D61 Given the following Unit 1 conditions: Power escalation in progress Reactor power = 25% slowly increasing Main Condenser vacuum 27" Hg and degrading 1) The Main Turbine low vacuum trip setpoint is __(1)__ inches Hg.

2) After restoring vacuum to normal and stabilizing from the transient, Tave will be approximately __(2)__ degrees F. Which ONE of the following completes the statements above?

A. 1. 19 2. 555 B. 1. 19 2. 579 C. 1. 21.75 2. 555 D. 1. 21.75 2. 579 SYS045 A1.05 - Main Turbine Generator (MT/G) SystemAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: (CFR: 41.5 / 45.5)Expected response of primary plant parameters (temperature and pressure) following T/G trip ................................Tuesday, October 06, 2015Page 128 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION61D61General DiscussionAnswer A DiscussionIncorrect. First part is plausible since that is the low vacuum trip setpoint for the Main Feedwater pumps. Second part is plausible since it would be correct for Turbine Trips that occur with Rx Power >29.75% power.Answer B DiscussionIncorrect. First part is plausible since that is the low vacuum trip setpoint for the Main Feedwater pumps. Second part is correct.Answer C DiscussionIncorrect. First part is correct.Second part is plausible since it would be correct for Turbine Trips that occur with Rx Power >29.75% power.Answer D DiscussionCorrect. The low vacuum trip setpoint for the Main Turbine is 21.75" Hg. Since the Turb/Rx trip is not yet armed the Rx will not trip as a result of the Main Turbine trip therefore the resulting Tave would remain approximately 579 degrees once the plant stabilized.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesSTG-MT Obj 16CF-FWPTIC-RPS401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to predict changes in Tave following a Main Turbine trip a low in the power range.Basis for Hi CogBasis for SRO onlySYS045 A1.05 - Main Turbine Generator (MT/G) SystemAbility to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: (CFR: 41.5 / 45.5)Expected response of primary plant parameters (temperature and pressure) following T/G trip ................................Tuesday, October 06, 2015Page 129 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION62B62 Given the following Unit 1 conditions: Reactor power = 35% stable Air Ejector off-gas activity increasing Local RP survey indicates significant increase in 1B Main Steam Line activity 1) 1RIA-40 (Air Ejector Off Gas) __(1)__ be used to determine Primary to Secondary leak rate. 2) In accordance with the SGTR tab, the MAXIMUM RCS temperature allowed when isolating the 1B SG is __(2)__ degrees F. Which ONE of the following completes the statements above? A. 1. can 2. 525 B. 1. can 2. 532 C. 1. can NOT 2. 525 D. 1. can NOT 2. 532 SYS055 K1.06 - Condenser Air Removal System (CARS)Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)PRM system .................................................... Tuesday, October 06, 2015Page 130 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION62B62General DiscussionAnswer A DiscussionIncorrect. First part is correct. 1RIA-40 can be used to determine Primary to Secondary leak rate. Second part is incorrect. Plausible since the band to isolate the SG is 525 to 532 degrees as directed by the SGTR tab.Answer B DiscussionCorrect.First part is correct. 1RIA-40 can be used to determine Primary to Secondary leak rate. Second part is correct. The SGTR tab directs cooling the RCS to a band of 525 to 532 degrees prior to isolating the SG.Answer C DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if asking about RIA-59/60. Per the SGTR tab, RIA-59/60 cannot be used to determine leak rate with Reactor power is < 40%.Second part is incorrect. Plausible since the band to isolate the SG is 525 to 532 degrees as directed by the SGTR tab.Answer D DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if asking about RIA-59/60. Per the SGTR tab, RIA-59/60 cannot be used to determine leak rate with Reactor power is < 40%. Second part is correct.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion Source2009B Q9Student References ProvidedDevelopment ReferencesEAP-AP31 Obj R1, R9EAP-SGTR Obj 28,29,30 2009B Q9401-9 Comments:Remarks/StatusBasis for meeting the KAThis question requires knowledge of the cause-effect relationship between increasing activity in the air ejector off gas system and Process Radiation Monitor system use by the operators.Basis for Hi CogBasis for SRO onlySYS055 K1.06 - Condenser Air Removal System (CARS)Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)PRM system .................................................... Tuesday, October 06, 2015Page 131 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION63B63 In accordance with OP/1-2/A/1104/018 (GWD System)- 1) A newly isolated GWD tank must be sampled for Hydrogen within __(1)__ hours. 2) If Hydrogen concentration in a GWD tank is 3.5%, the Hydrogen concentration must be reduced to < 3% within __(2)__ hours.

Which ONE of the following completes the statements above?

A. 1. 24 2. 24 B. 1. 24 2. 48 C. 1. 48 2. 24 D. 1. 48 2. 48 SYS071 A4.10 - Waste Gas Disposal System (WGDS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)WGDS sampling ................................................. Tuesday, October 06, 2015Page 132 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION63B63General DiscussionAnswer A DiscussionIncorrect. First part is correct. Second part is incorrect but plausible since it would be correct if hydrogen concentration were greater than 4%.Answer B DiscussionCorrect. IAW limits and precautions of 1104/18, an isolated GWD tank must be sampled for Hydrogen within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of being isolated. If H2 concentration in a tank exceeds 3% but is less than or equal to 4% volume, the concentration must be reduced to less than or equal to 3% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .Answer C DiscussionIncorrect. First part is plausible since 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is the time allowed to reduce Hydrogen pressure to less than or equal to 3% when hydrogen is > 3% but less than or equal to 4%. Second part is incorrect but plausible since it would be correct if hydrogen concentration were greater than 4%.Answer D DiscussionIncorrect. First part is plausible since 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is the time allowed to reduce Hydrogen pressure to less than or equal to 3% when hydrogen is > 3% but less than or equal to 4%. Second part is correct.Cognitive LevelComprehensionJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesWE-GWD obj 111104/18401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to monitor H2 concentration and perform actions related to operation of the GWD tanks and sampling of the tanks. Actions for tank sampling, isloations ,and additions are initiated from the Control Room.Basis for Hi CogBasis for SRO onlySYS071 A4.10 - Waste Gas Disposal System (WGDS)Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)WGDS sampling ................................................. Tuesday, October 06, 2015Page 133 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION64D64 Given the following Unit 1 conditions: Reactor power = 100% Instrument Air (IA) header pressure = 90 psig decreasing 1) Unit __(1)__ AP/22 (Loss of Instrument Air) will dispatch an operator to ensure Diesel Air Compressors are operating.

2) IF IA header pressure reaches 85 psig the Service Air compressors will __(2)__ the instrument air header. A. 1. one 2. manually be aligned to B. 1. two 2. manually be aligned to C. 1. one 2. automatically begin to supply D. 1. two 2. automatically begin to supply SYS079 A2.01 - Station Air System (SAS)Ability to (a) predict the impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Cross-connection with IAS ........................................Tuesday, October 06, 2015Page 134 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION64D64General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since there are definitely actions that need to be taken outside of the Control Room during a loss of IA on Unit 1, however it is the Unit 2 AP/22 that directs those actions. Second part is incorrect. Plausible since other system cross connects directed by AP's are performed manually (example: cross connecting LPSW systems on loss of LPSW).Answer B DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since other system cross connects directed by AP's are performed manually (example: cross connecting LPSW systems on loss of LPSW).Answer C DiscussionIncorrect. First part is incorrect. Plausible since there are definitely actions that need to be taken outside of the Control Room during a loss of IA on Unit 1, however it is the Unit 2 AP/22 that directs those actions. Second part is correct.Answer D DiscussionCorrect. The Unit 2 AP/22 directs actions outside the control room on a loss of IA. The setpoint for SA-141 is 85 psig. When that pressure is reached, SA-141 begins to regulate IA pressure using the Service Air System.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT46 Q65Student References ProvidedDevelopment ReferencesILT46 Q65EAP-APG R9AP/22401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to predict the impact of decreasing IA pressure on SA system more specifically the impact of reaching the cross connect setpoint. It also requires using procedures to mitigate the consequences of decreasing IA pressure when operation of SA-141 will occur. Some of these actions are specifically associated with the fact that the IA and SAS have cross connected (ex. Ensuring DAC is operating and start if necessary).Basis for Hi CogBasis for SRO onlySYS079 A2.01 - Station Air System (SAS)Ability to (a) predict the impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Cross-connection with IAS ........................................Tuesday, October 06, 2015Page 135 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION65C65 Given the following Unit 1 conditions: Reactor power = 100% An Active fire has been reported in 1TA switchgear

1) De-energizing 1TA switchgear will result in a loss of the 1A1 and the __(1)__ Reactor Coolant Pumps. 2) In accordance with the "Fire Plan", a water fog __(2)__ be used on the switchgear to fight the fire. Which ONE of the following completes the statements above?

A. 1. 1A2 2. can B. 1. 1A2 2. can NOT C. 1. 1B1 2. can D. 1. 1B1 2. can NOT SYS086 K5.03 - Fire Protection System (FPS)Knowledge of the operational implication of the following concepts as they apply to the Fire Protection System: (CFR: 41.5 / 45.7)Effect of water spray on electrical components .......................Tuesday, October 06, 2015Page 136 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION65C65General DiscussionAnswer A DiscussionIncorrect. First part is plausible since it would be logical to assume that the two "A" loop RCP's were powered from 1TA switchgear. Second part is correct.Answer B DiscussionIncorrect. First part is plausible since it would be logical to assume that the two "A" loop RCP's were powered from 1TA switchgear. Second part is plausible since water conducts electricity and therefore there would be a concern of electrical shock. Also since water on metal promotes oxidation it would also be plausible to believe it is prohibited in order to not cause further damage to the switchgear. And lastly it is plausible because a water stream cannot be used.Answer C DiscussionCorrect. The 1A1 and 1B1 RCP's are powered from the 1TA switchgear. A water fog is allowed to be used on electrical switchgear fires.Answer D DiscussionIncorrect. First part is correct. Second part is plausible since water conducts electricity and therefore there would be a concern of electrical shock. Also since water on metal promotes oxidation it would also be plausible to believe it is prohibited in order to not cause further damage to the switchgear. And lastly it is plausible because a water stream cannot be used.Cognitive LevelMemoryJob LevelROQuestionTypeMODIFIEDQuestion SourceILT42 Q99Student References ProvidedDevelopment ReferencesILT42 Q99RCP pwr supplyFire PlanTA-OE Obj R2401-9 Comments:Remarks/StatusBasis for meeting the KAPer CE, OK to ask about use of fog pattern with water on electrical equip. This question requires knowledge of the use of water fog on electrical equipment and the effect of de-energizing switchgear when using a water fog to extinguish a fire.Basis for Hi CogBasis for SRO onlySYS086 K5.03 - Fire Protection System (FPS)Knowledge of the operational implication of the following concepts as they apply to the Fire Protection System: (CFR: 41.5 / 45.7)Effect of water spray on electrical components .......................Tuesday, October 06, 2015Page 137 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION66B66 1) The MAXIMUM number of visitors you can escort into a Vital Area is __(1)__. 2) If a Site Assembly were to occur while you were in a Vital Area with visitors you should report to your assembly location __(2)__. Which ONE of the following completes the statements above?

A. 1. 5 2. once you have returned the visitors to Security at the PAP B. 1. 5 2. immediately taking the visitors with you C. 1. 10 2. once you have returned the visitors to Security at the PAP D. 1. 10 2. immediately taking the visitors with you GEN2.1 2.1.13 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of facility requirements for controlling vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10)Tuesday, October 06, 2015Page 138 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION66B66General DiscussionAnswer A DiscussionFirst part is correct. Second part is plausible since that is where visitors are returned to once they have finished with being inside the protected area.Answer B DiscussionCorrect. You can only escort 5 visitors into Oconee Vital areas and if a site assembly were to occur while you were escorting visitors you would take the visitors to your assembly location with you.Answer C DiscussionIncorrect. First part is plausible since it is correct for other areas inside the Protected Area. Second part is plausible since that is where visitors are returned to once they have finished with being inside the protected area.Answer D DiscussionIncorrect. First part is plausible since it is correct for other areas inside the Protected Area. Second part is correct.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEOP-SEP R10,11,12Annual Update RP/1000/009401-9 Comments:Remarks/StatusBasis for meeting the KACE allowed asking "initial training" information since there are not items specific to license duties related to this KA. Question requires knowledge of facility requirements for limits on personnel you can escort into a vital area.Basis for Hi CogBasis for SRO onlyGEN2.1 2.1.13 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of facility requirements for controlling vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10)Tuesday, October 06, 2015Page 139 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION67D67 Given the following Unit 3 conditions: Reactor in MODE 6 Refueling in progress Which ONE of the following describes the source range NI requirements while refueling the reactor in accordance with OP/3/A/1502/007 (Operations Defueling/Refueling Responsibilities)? A. Reactor Operator can use any one source range NI B. Reactor Operator can use any two source range NI's C. Reactor Engineering will specify the one required source range NI D. Reactor Engineering will specify the two required source range NI's GEN2.1 2.1.41 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of the refueling process. (CFR: 41.2 / 41.10 / 43.6 / 45.13)Tuesday, October 06, 2015Page 140 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION67D67General DiscussionAnswer A DiscussionIncorrect: Plausible since it would be correct if fuel handling was not in progress. Only 1 SR NI is required to be operable while shutdown when fuel handling is not in progress.Answer B DiscussionIncorrect: Plausible since the limits and precautions section of 1502/007 (Operations Defueling/Refueling Responsibilities) states "Any combination of two Source Range NI's may be used for defueling." However the two must be selected by Reactor Engineering per the body of the procedure (Encl 4.1 Step 4.3). So it is reasonable to conclude the RO can select any two Nis for refueling.Answer C DiscussionIncorrect: Plausible since only 1 SR NI is required to be operable while shutdown when fuel handling is not in progress. It would be reasonable to conclude that one is required any time while shutdown.Answer D DiscussionCORRECT. Two Source Range Nis are required and they are selected by Reactor Engineering in accordance with OP/3/A/1502/007.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT39 Q66Student References ProvidedDevelopment ReferencesILT39 Q66FH-FHS Obj. 17OP/3/A/1502/007401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the refueling process procedures.Basis for Hi CogBasis for SRO onlyGEN2.1 2.1.41 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of the refueling process. (CFR: 41.2 / 41.10 / 43.6 / 45.13)Tuesday, October 06, 2015Page 141 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION68B68 Given the following Unit 1 condition: Reactor in MODE 1 Which ONE of the following is the MINIMUM Pressurizer level (inches) that would require declaring Tech Spec 3.4.9 (Pressurizer) LCO NOT met in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance)?

A. 240 B. 260 C. 285 D. 340 GEN2.2 2.2.22 - GENERIC - Equipment ControlEquipment ControlKnowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)Tuesday, October 06, 2015Page 142 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION68B68General DiscussionAnswer A DiscussionIncorrect. Plausible since this value is below the TS required value of 285 therefore it is plausible to believe it to be an instrument corrected value. Also, 240 inches is the hi level alarm setpoint for the OAC alarm. Additional plausibility from the fact that this is a fairly common level value however it is the SG level required for natural circ when on EFDW.Answer B DiscussionCorrect. PT.600/01 corrects the TS required 285" for allowable instrument error and uses 260" as the threshold value.Answer C DiscussionIncorrect. Plausible since this is the analytical value provided in Tech Spec 3.4.9 for maximum level.Answer D DiscussionIncorrect. Plausible since this is a value associated with the pressurizer however this is the maximum Pzr level allowed for RCP restart with abnormal containment conditions.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT44 Q59Student References ProvidedDevelopment ReferencesAdm-ITS Obj R8TS 3.4.9PT/600/01401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the conditions that would require the LCO requirments of TS 3.4.9 NOT met.Basis for Hi CogBasis for SRO onlyGEN2.2 2.2.22 - GENERIC - Equipment ControlEquipment ControlKnowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)Tuesday, October 06, 2015Page 143 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION69C69 Given the following Unit 1 conditions:

Initial conditions: Reactor power = 100% Current conditions: Keowee Emergency Start channels 1 and 2 inoperable In accordance with Tech Spec 3.3.21 (EPSL Keowee Emergency Start Function) - 1) The MAXIMUM time allowed to declare both KHU's inoperable is __(1)__.

2) The Required Action associated with this inoperability is to energize __(2)__ Standby Bus(es) from a Lee Combustion Turbine via an isolated power path.

Which ONE of the following completes the statements above? A. 1. immediately 2. at least ONE B. 1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 2. at least ONE C. 1. immediately 2. BOTH D. 1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 2. BOTH GEN2.2 2.2.39 - GENERIC - Equipment ControlEquipment ControlKnowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13)Tuesday, October 06, 2015Page 144 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION69C69General DiscussionAnswer A DiscussionIncorrect, First part is correct. Second part is incorrect. Plausible since it would be correct if only the KHU Underground powerpath were inoperable per TS 3.8.1 Condition D.Answer B DiscussionIncorrect, First part is incorrect but plausible since 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is a common completion time for significant inoperabilities. Additionally, allowing 1 hr to declare components inoperable is allowed in other TS's (Ex. 3.3.7) which adds to plausibility of the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months completion time for declaring KHU's not operable. Also, when one KHU is declared inoperable, 1 hr is allowed to operability test the other KHU to determine if it is operable.Second part is incorrect. Plausible since it would be correct if only the KHU Underground powerpath were inoperable per TS 3.8.1 Condition D.Answer C DiscussionCorrect. Both Keowee units are required to be declared inoperable immediately per TS 3.3.21 Condition C. TS 3.8.1 Condition I requires energizing BOTH standby buses within 1 hr with both KHU's inoperable.Answer D DiscussionIncorrect, First part is incorrect but plausible since 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is a common completion time for significant inoperabilities. Additionally, allowing 1 hr to declare components inoperable is allowed in other TS's (Ex. 3.3.7) which adds to plausibility of the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months completion time for declaring KHU's not operable. Also, when one KHU is declared inoperable, 1 hr is allowed to operability test the other KHU to determine if it is operable. Second part is correct.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion Source2009B NRC Exam Q70Student References ProvidedDevelopment References2009B NRC Exam Q70 ADM-TSS Obj. R4 TS 3.3.21TS 3.8.1401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of 1 hr or less actions required by TS 3.3.21 and 3.8.1.Basis for Hi CogBasis for SRO onlyGEN2.2 2.2.39 - GENERIC - Equipment ControlEquipment ControlKnowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13)Tuesday, October 06, 2015Page 145 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION70B70 Given the following Unit 3 conditions: 3A GWD gas tank release in progress Release is at 2/3 Station Limit 1) 3RIA-45 High and Alert setpoints will be set at __(1)__ the normal 1/3 Station Limit setpoint in accordance with PT/0/A/0230/001 (Radiation Monitor Check). 2) If 3RIA-45 High alarm setpoint is reached, the 3A GWD gas tank release __(2)__ automatically terminate. Which ONE of the following completes the statements above? A. 1. double 2. will B. 1. double 2. will NOT C. 1. half 2. will D. 1. half 2. will NOT GEN2.3 2.3.11 - GENERIC - Radiation ControlRadiation ControlAbility to control radiation releases. (CFR: 41.11 / 43.4 / 45.10)Tuesday, October 06, 2015Page 146 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION70B70General DiscussionAnswer A DiscussionIncorrect.First part is correct. Per PT/0/A/230/001, when performing a 2/3 station limit release, the releasing unit's RIA-45 setpoint is double the normal setpoint for 1/3 Station Limit.Second part is incorrect. Plausible since RIA-45 high alarm will automatically terminate a RB Purge release on the respective unit.Answer B DiscussionCorrect.First part is correct Per PT/0/A/230/001, the releasing unit's RIA-45 setpoint is double the normal setpoint for 1/3 Station Limit when performing a 2/3 station limit release.Second part is correct. RIA-45 will not terminate the release. RIA-37/38 are the process monitors that are interlocked to terminate the release.Answer C DiscussionIncorrect.First part is incorrect. Plausible since PT/0/A/230/001 (Radiation Monitor Check) directs the setpoint for RIA-45 on the non-releasing unit to be set at half the 1/3 Station Limit value when release is at 2/3 station limit.Second part is incorrect. Plausible since RIA-45 high alarm will automatically terminate a RB Purge release on the respective unit.Answer D DiscussionIncorrect.First part is incorrect. Plausible since PT/0/A/230/001 (Radiation Monitor Check) directs the setpoint for RIA-45 on the non-releasing unit to be set at half the 1/3 Station Limit value when release is at 2/3 station limit..Second part is correct. RIA-45 will not terminate the release. RIA-37/38 are the process monitors that are interlocked to terminate the release.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT39 Q70Student References ProvidedDevelopment ReferencesILT39 Q70WE-GWD Obj. 07OP/3/A/1104/018PT/0/A/0230/001401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of the process for releasing at 2/3 the station limit.Basis for Hi CogBasis for SRO onlyGEN2.3 2.3.11 - GENERIC - Radiation ControlRadiation ControlAbility to control radiation releases. (CFR: 41.11 / 43.4 / 45.10)Tuesday, October 06, 2015Page 147 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION71A71 Given the following Unit 1 conditions: 36 gpm primary to secondary leak in 1A SG RCS cooldown in progress RCS temperature = 395°F decreasing The SRO has determined that current method of maintaining SCM is inadequate

1) The reason that the SGTR tab makes every effort to prevent a Reactor trip during shutdown is to minimize the chance of __(1)__ . 2) If an operator is dispatched to align Auxiliary Pressurizer Spray during the subsequent RCS cooldown and receives a dose alarm while performing this task he will __(2)__. Which ONE of the following completes the statements above? A. 1. lifting the MSRVs and causing a radiation release to the environment 2. complete the task while monitoring his dose B. 1. lifting the MSRVs and causing a radiation release to the environment 2. immediately stop and leave the area C. 1. RCS pressure transients and causing the Primary to Secondary leak rate to increase 2. complete the task while monitoring his dose D. 1. RCS pressure transients and causing the Primary to Secondary leak rate to increase 2. immediately stop and leave the area GEN2.3 2.3.14 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10)Tuesday, October 06, 2015Page 148 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION71A71General DiscussionAnswer A DiscussionCorrect. The SGTR tab directs shutting down the plant as long as all available HPI can maintain Pzr level in order to prevent lifting the MSRV's would release to environment. Since emergency dose limits (EDLs) are in effect, the AO is expected to complete the task while monitoring his dose.Answer B DiscussionIncorrect, First part is correct. The SGTR tab directs maintaining SCM low in order to reduce the dp between RCS and SG pressure, which in turn reduces the leak rate and contamination of the secondary plant. Second part is incorrect but plausible since it would be correct if EDLs were not in affect.Answer C DiscussionIncorrect: First part is incorrect. Plausible since an RCS pressure transient could cause an increase in Primary to Secondary leakage however this is not the reason for guidance in the EOP for a controlled shutdown.Second part is correct.Answer D DiscussionIncorrect: First part is incorrect. Plausible since an RCS pressure transient could cause an increase in Primary to Secondary leakage however this is not the reason for guidance in the EOP for a controlled shutdown. Second part is incorrect but plausible since it would be correct if EDLs were not in affect.Cognitive LevelComprehensionJob LevelROQuestionTypeMODIFIEDQuestion SourceILT42 Q70Student References ProvidedDevelopment ReferencesILT42 Q70EAP-TCA Obj. R6SGTR Tab Obj R1EAP-SGTR401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires knowledge of radation hazards due to a SGTR in that it requires an understanding of the impact of lifting the MSRV's during a SGTR..Basis for Hi CogBasis for SRO onlyGEN2.3 2.3.14 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10)Tuesday, October 06, 2015Page 149 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION72A72 In accordance with PD-RP-ALL-0001 (Radiation Worker Responsibilities), which ONE of the following states- 1) the MAXIMUM annual Dose Limit (REM) allowed by the NRC? 2) the MAXIMUM lifetime Planned Special Exposure limit (REM) allowed by the NRC?

A. 1. 5 2. 25 B. 1. 5 2. 50 C. 1. 2 2. 25 D. 1. 2 2. 50 GEN2.3 2.3.4 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10)Tuesday, October 06, 2015Page 150 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION72A72General DiscussionAnswer A DiscussionCorrect. The maximum annual dose limit allowed by the NRC is 5 REM. The maximum lifetime planned special exposure limit allowed by the NRC is 5 times the annual limit (25 REM).Answer B DiscussionIncorrect. First part is correct. Second part is plausible since 50 REM is the annual limit allowed by the NRC for SDE to skin and extremities and CDE to any tissue or organ except lens of the eye.Answer C DiscussionIncorrect. First part is plausible since 2 REM is the annual dose limit allowed by Duke Energy. Second part is correct.Answer D DiscussionIncorrect. First part is plausible since 2 REM is the annual dose limit allowed by Duke Energy. Second part is plausible since 50 REM is the annual limit allowed by the NRC for SDE to skin and extremities and CDE to any tissue or organ except lens of the eye.Cognitive LevelMemoryJob LevelROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment References2009B NRC Exam Q73EAP-TCA Obj. R6OMP 1-18PD-RP-ALL-0001401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of emergency worker radiation exposure limits and when they apply.Basis for Hi CogBasis for SRO onlyGEN2.3 2.3.4 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10)Tuesday, October 06, 2015Page 151 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION73B73 Given the following Unit 1 conditions: Initial conditions: Reactor power = 90% slowly decreasing SG Primary to Secondary leak rate = 6 gpm stable AP/31 (Primary to Secondary Leakage) in progress Unit shutdown in progress Current conditions Reactor power = 60% slowly decreasing SG Primary to Secondary leak rate = 28 gpm slowly increasing Which ONE of the following describes the actions required in accordance with plant procedures? A. Continue unit shutdown using AP/31 B. Exit AP/31 and go directly to SGTR tab C. Exit AP/31, perform IMA's, then go to SGTR tab D. Perform AP/31 in parallel with performing the SGTR tab GEN2.4 2.4.16 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 152 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION73B73General DiscussionAnswer A DiscussionIncorrect: Plausible since AP/31 would still be in effect if the leak rate were < 25gpm and some AP's are self contained AP's that direct unit shutdowns and/or powerdecreases.Answer B DiscussionCorrect: There is an IAAT in AP/31 that directs going to the EOP if SG leak ratereaches 25 gpm. The entry conditions of the EOP with a SGTR > 25 gpm without a Reactor trip direct the operator to go directly to the SGTR tab.Answer C DiscussionIncorrect: Plausible since exiting AP/31 and entering the EOP is correct and thiswould be the correct EOP path for most EOP entries however entering while on linewith a SG tube rupture is a unique exception that requires going direclty to the SGTRtab.Answer D DiscussionIncorrect: Plausible since most AP's are performed in parallel with the EOP whenEOP entry is required.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion SourceILT40 Q74Student References ProvidedDevelopment ReferencesILT40 Q74 EAP-SA Obj. R21 AP/31EOP401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the hierarchy of the EOP versus AP/31.Basis for Hi CogBasis for SRO onlyGEN2.4 2.4.16 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 153 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION74B74 Given the following Unit 1 conditions: Reactor tripped from 100% power The following Statalarms actuate: - 1SA-1/C-11 (ES Channel 7 Trip) - 1SA-1/D-11 (ES Channel 8 Trip) - 1SA-2/C-4 (RC Pressurizer Level Emerg High/Low) - 1SA-2/C-8 (AFIS Header A Initiated) - 1SA-2/D-5 (HP LDST Level Interlock Initiated) - 1SA-8/A-3 (FDWPT A Trip) - 1SA-8/A-6 (FDWPT B Trip) Which ONE of the following emergency procedures has the highest priority?

A. EOP Enclosure 5.1 (ES Actuation) B. Rule 5 (Main Steam Line Break) C. EOP Enclosure 5.5 (Pzr and LDST Level Control) D. Rule 3 (Loss of Main or Emergency Feedwater) GEN2.4 2.4.45 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanAbility to prioritize and interpret the significance of each annunciator or alarm. (CFR: 41.10 / 43.5 / 45.3 / 45.12)Tuesday, October 06, 2015Page 154 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION74B74General DiscussionAnswer A DiscussionIncorrect: Plausible in that ES Actuation of all 8 Channels has most likely occurredAnswer B DiscussionCORRECT: AFIS actuation tells the operator that MSLB has occurred whichis the highest priority due to the overcooling it can cause; in fact EHT has caused all the other SA conditionsAnswer C DiscussionIncorrect: Plausible in that overcooling is causing the RCS inventory to contract tothe point of possibly emptying the Pzr and LDST; however the overcooling would bestopped by Rule 5.Answer D DiscussionIncorrect: Plausible in that AFIS has caused the MFWPs to trip; a loss of both MFWand EFW would be a higher priority than Rule 5 but there is no reason to assumethat EFW pumps are unavailable.Cognitive LevelComprehensionJob LevelROQuestionTypeBANKQuestion Source2009 NRC Exam Q74Student References ProvidedDevelopment References2009 NRC Exam Q74 Admin-OMP Obj R10, R52OMP 1-18401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to interpret the significance of statalarms, to diagnose the event,and to prioritize EOP rules and enclosuresBasis for Hi CogBasis for SRO onlyGEN2.4 2.4.45 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanAbility to prioritize and interpret the significance of each annunciator or alarm. (CFR: 41.10 / 43.5 / 45.3 / 45.12)Tuesday, October 06, 2015Page 155 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION75D75 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% Both Main Feedwater pumps trip Current conditions: REACTOR TRIP pushbutton has been depressed Reactor power = 3% slowly decreasing Which ONE of the following describes the NEXT action required in accordance with EOP Immediate Manual Actions? A. Perform Rule 1 B. OPEN 1HP-24 and 1HP-25 C. Verify RCP seal injection available D. Depress the Turbine TRIP pushbutton GEN2.4 2.4.49 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanAbility to perform without reference to procedures those actions that require immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6)Tuesday, October 06, 2015Page 156 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION75D75General DiscussionAnswer A DiscussionIncorrect: Plausible since this would be correct if power level was > 5%.. Additionalplausibility since there is a 1% power threshold for actions within Rule 2. Therefore itis plausible to believe that if power is still > 1%, going to Rule 1 is required.Answer B DiscussionIncorrect: Plausible since this is one of the first actions taken by Rule 1 during anATWS. It is plausible to believe these actions are part of IMA's since it is in IMA'sthat the ATWS is diagnosed and aligning emergency boration is critical to thesuccessful mitigation of the ATWS.Answer C DiscussionIncorrect: Plausible since this is an action taken in IMA's, however it is done after themain turbine is tripped.Answer D DiscussionCorrect: Since Rx power is < 5%, the next action is to depress the Turbine Trippushbutton.Cognitive LevelMemoryJob LevelROQuestionTypeBANKQuestion SourceILT40 Q75Student References ProvidedDevelopment ReferencesILT40 Q75 EAP-SA R24EOP IMAs401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to perform EOP Immediate Manual Actions from memory.Basis for Hi CogBasis for SRO onlyGEN2.4 2.4.49 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanAbility to perform without reference to procedures those actions that require immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6)Tuesday, October 06, 2015Page 157 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION76A76 Given the following Unit 1 conditions: RCS Tave = 480°F stable 1A HPI pump tripped 1B HPI pump failed to start and can NOT be started manually In accordance with AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection), BOTH the SSF RC Makeup Pump and the 1C HPI Pump are aligned to supply RCP seal injection In accordance with AP/14-

1) __(1)__ will be utilized to secure one of the sources of RCP seal injection.

2) An RCS Heatup of < 10ºF __(2)__ allowed as part of the strategy to maintain Pressurizer level > 100 inches A. 1. Encl. 5.1 (SSF RC Makeup) 2. is B. 1. Encl. 5.1 (SSF RC Makeup) 2. is NOT C. 1. Encl. 5.2 (Emergency Alignment of 1C HPI Pump for Normal Makeup) 2. is D. 1. Encl. 5.2 (Emergency Alignment of 1C HPI Pump for Normal Makeup) 2. is NOT APE022 2.4.20 - Loss of Reactor Coolant MakeupAPE022 GENERICKnowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 158 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION76A76General DiscussionAnswer A DiscussionCorrect. Even though the preferred method of providing Seal Injection is with the C HPI pump, both paths are pursued and then the RC Makeup pump is secured when and if the C HPI pump is successfully aligned and operating. There is a NOTE in the AP that allows heating up as much as 10 degrees to help maintain Pzr level no less than 100 inches as long as the Rx is shutdown.Answer B DiscussionIncorrect. First part is correct. Second part is plausible since it would not be allowed if the Reactor were not shut down. Also plausible to believe that heating up would not be allowed to control Pzr level since there is so much focus on controlling RCS heatup when it is occurring.Answer C DiscussionIncorrect. First part is plausible since Encl. 5.1 (SSF RC Makeup) is initiated prior to Encl. 5.2 and only secured when the 1C HPI Pump is successfully aligned per Encl. 5.2. The operator could reason that since Encl. 5.1 is initiated first, that it is the preferred method to supply seal injection. Second part is correct.Answer D DiscussionIncorrect.First part is plausible since Encl. 5.1 (SSF RC Makeup) is initiated prior to Encl. 5.2 and only secured when the 1C HPI Pump is successfully aligned per Encl. 5.2. The operator could reason that since Encl. 5.1 is initiated first, that it is the preferred method to supply seal injection.Second part is plausible since it would not be allowed if the Reactor were not shut down. Also plausible to believe that heating up would not be allowed to control Pzr level since there is so much focus on controlling RCS heatup when it is occurring.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP/APG R9AP/14401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the operational implication of a Note at step 29 of AP/14 allowing RCS heatup only if the Rx is shutdown.Basis for Hi CogBasis for SRO onlyThis question requires assessing plant conditions and determining a section of a procedure to be utilized based on that assessment. Both parts of this question meet that SRO guideline criteria since both determine steps or sections to be performed in the AP which are based solely on plant conditions. 10 CFR 55.43(b)(5).APE022 2.4.20 - Loss of Reactor Coolant MakeupAPE022 GENERICKnowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 159 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION77B77 Given the following Unit 1 conditions: Reactor in MODE 5 ALL LTOP requirements established in accordance with Tech Spec 3.4.12 (Low Temperature Overpressure Protection (LTOP) System) In accordance with Tech Spec 3.4.12-

1) The 1RC-66 setpoint is __(1)__ psig.

2) A dedicated LTOP operator __(2)__ allowed as a substitute for an inoperable PORV to prevent exceeding RCS brittle fracture pressure limits.

Which ONE of the following completes the statements above?

A. 1) 535 2) is B. 1) 535 2) is NOT C. 1) 550 2) is D. 1) 550 2) is NOT APE027 AA2.04 - Pressurizer Pressure Control System (PZR PCS) MalfunctionAbility to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR: 43.5 / 45.13)Tech-Spec limits for RCS pressure ................................. Tuesday, October 06, 2015Page 160 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION77B77General DiscussionAnswer A DiscussionIncorrect: First part is correct. Second part is incorrect. Plausible since there are 2 trains of LTOP. The trains are the PORV and Administrative Controls that limit the rate of RCS pressure increase. A dedicated LTOP operator is allowed as a substitute for one of the trains (Admin. Controls), but not the other (PORV).Answer B DiscussionCorrect: The 1RC-66 setpoint per TS 3.4.12 is 535 psig. A dedicated LTOP operator is not allowed as a substitute for an inoperable PORV.Answer C DiscussionIncorrect: First part is incorrect. Plausible since 550 psig is the setpoint for LPI actuation from ES 3/4 and is also the main steam setpoint for Automatic Feedwater Isolation (AFIS).Second part is incorrect. Plausible since there are 2 trains of LTOP. The trains are the PORV and Administrative Controls that limit the rate of RCS pressure increase. A dedicated LTOP operator is allowed as a substitute for one of the trains (Admin. Controls), but not the other (PORV).Answer D DiscussionIncorrect: First part is incorrect. Plausible since 550 psig is the setpoint for LPI actuation from ES 3/4 and is also the main steam setpoint for Automatic Feedwater Isolation (AFIS). Second part is correct.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesADMIN-TSS obj R5TS 3.4.12 and basis401-9 Comments:Remarks/StatusPreviewBasis for meeting the KARequires knowledge of the LTOP LCO as it relates to the PORV, which is part of the Pressurizer pressure control system. The malfunction portion ofthe KA is satisfied by the failure of the PORV to open. With the failure having occurred the operator is being asked to interpret the failure as it relates to exceeding the Tech Spec RCS pressure limits that would result in RCS brittle fracture.Basis for Hi CogBasis for SRO onlyIn accordance with Clarification Guidance for SRO-only Questions:This question requires knowledge from the basis of TS 3.4.12 and the Safety Limits thatis not systems knowledge. 10CFR 55.43(b)(2).

It cannot be answered by knowing 1 hr or less TS/TRM ActionIt cannot be answered solely with "above the line" information.It cannot be answered solely by knowing Safety LimitsAPE027 AA2.04 - Pressurizer Pressure Control System (PZR PCS) MalfunctionAbility to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: (CFR: 43.5 / 45.13)Tech-Spec limits for RCS pressure ................................. Tuesday, October 06, 2015Page 161 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION78A78 Given the following Unit 1 conditions: Time = 1000: MSLB on 1B SG outside containment and can NOT be steamed 1A S/G developed a SGTR EHT tab is complete EOP SGTR Tab in progress 1A S/G level = 288" XSUR slowly increasing SCM = 10°F stable Time = 1040: 1A S/G has reached the level where water can enter the main steam lines Rule 4 has been initiated and the PORV has been opened Core SCM = 0°F 1) At Time = 1000, the SGTR tab __(1)__ direct performance of Encl. 5.22 (SG Blowdown) 2) At Time = 1040, the SGTR tab will direct initiation of the __(2)__ tab.

Which ONE of the following completes the statements above?

A. 1. does 2. HPI CD B. 1. does 2. LOCA CD C. 1. does NOT 2. HPI CD D. 1. does NOT 2. LOCA CD EPE038 EA2.01 - Steam Generator Tube Rupture (SGTR)Ability to determine or interpret the following as they apply to a SGTR : (CFR 43.5 / 45.13)When to isolate one or more S/Gs ..................................Tuesday, October 06, 2015Page 162 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION78A78General DiscussionAnswer A Discussion1st part is correct because per the STGR tab (step 227) Encl 5.22 is performed if any SG with a tube rupture rises > 285". 2nd part is correct. Per step 232 and 233 in the SGTR tab, stop steaming the affected SG and if the remaining SG is not available for steam (RNO) Perform Rule 4 and GO TO the HPI CD tab.Answer B Discussion1st part is correct.2nd part is incorrect because the SGTR tab directs you to the HPI CD tab. It is plausible because if HPI FC was not in progress, it would be correct. LOSCM is the higher priority tab (normally).Answer C Discussion1st part is incorrect. The STGR tab (step 227): Encl 5.22 is performed if any SG with a tube rupture rises > 285". Plausible since 285" is a rather arbitrary number and there are actions in the EOP that occure at 290 psi RCS pressure therefore confusing the numbers would be plausible.2nd part is correct. Per step 232 and 233 in the SGTR tab, stop steaming the affected SG and if the remaining SG is not available for steam (RNO) Perform Rule 4 and GO TO the HPI CD tab.Answer D Discussion1st part is incorrect. The STGR tab (step 227): Encl 5.22 is performed if any SG with a tube rupture rises > 285". Plausible since 285" is a rather arbitrary number and there are actions in the EOP that occure at 290 psi RCS pressure therefore confusing the numbers would be plausible.2nd part is incorrect because the SGTR tab directs you to the HPI CD tab. It is plausible because if HPI FC was not in progress, it would be correct. LOSCM is the higher priority tab (normally).Cognitive LevelMemoryJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT43 Q78Student References ProvidedDevelopment ReferencesILT43 Q78SGTR TabEAP SGTR Obj R 16, R26401-9 Comments:Remarks/StatusBasis for meeting the KAThe question requires knowledge of the isolation requirements of a SG since knowing when steaming of an isolated SG is required demonstrates the ability to determin if the SG should be isolated or not.Basis for Hi CogBasis for SRO onlyThis question is SRO ONLY because it meets. 10 CFR 55.43(b)(5)It requires assessing plant conditions and determining when a section of the EOP should be performed.EPE038 EA2.01 - Steam Generator Tube Rupture (SGTR)Ability to determine or interpret the following as they apply to a SGTR : (CFR 43.5 / 45.13)When to isolate one or more S/Gs ..................................Tuesday, October 06, 2015Page 163 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION78A78Tuesday, October 06, 2015Page 164 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION79C79 Given the following Unit 1 conditions: Reactor power = 50% stable 1KI and 1KU panelboards are de-energized Which ONE of the following states the correct procedure to use to maintain Steam Generator pressure and RCS temperature?

A. AP/23 (Loss of ICS Power) B. AP/25 (Standby Shutdown Facility) C. EOP Enclosure 5.24 (Operation of the ADVs) D. EOP Enclosure 5.42 (Alignment of EFM Pump to Feed SGs)

APE057 2.4.11 - Loss of Vital AC Electrical Instrument BusAPE057 GENERICKnowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 165 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION79C79General DiscussionAnswer A DiscussionIncorrect. Plausible since the failures will meet the entry conditions for AP/23 and if the other essential inverter (KX) were lost instead of one of these two it would be a correct answer if it occurred in MODE 3 or 4.Answer B DiscussionIncorrect. Plausible since this is a method used by the EOP to maintain stable SG pressure and RCS temperature under other circumstances and with both KI and KU being lost with the unit at power a Rx trip would have occurred therefore the entry condtions to the EOP would be met.Answer C DiscussionCorrect. With both KI and KU lost the TBV's are unavailable and section 4A of AP/23 will direct using EOP Encl 5.24.Answer D DiscussionIncorrect. Plausible since Enclosure 5.42 is utilized to feed the SGs under certain loss of power scenarios.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-APG obj R9EOP IMA's and SA'sAP/23401-9 Comments:Remarks/StatusPreviewBasis for meeting the KACE allowed use of Essential Inverters since Oconee does not have AP's realted to loss of vital inverters. This question requires knowledge of Abnormal Procedures realted to a loss of essential inverters.Basis for Hi CogBasis for SRO onlyQuestion requires selection of procedure and cannot be answered based solely on entry conditions. 10 CFR 55.43(b)(5).APE057 2.4.11 - Loss of Vital AC Electrical Instrument BusAPE057 GENERICKnowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 166 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION80D80 Given the following Unit 1 conditions:

Time = 1200: Reactor trip from 100% AP/22 (Loss of Instrument Air) in progress Instrument Air (IA) and Auxiliary Instrument Air (AIA) pressure lost to the 1A Turbine Bypass Valves 1A SG pressure 935 psig stable Maintaining 1A SG pressure with Atmospheric Dump Valves (ADVs) in accordance with EOP Subsequent Actions Time = 1210: 1A SG Tube Leak = 15 gpm stable Time = 1230: 1A SG Tube Rupture = 180 gpm stable EOP SGTR in progress 1) At time = 1210, the emergency classification is __(1)__.

2) At time = 1230, the emergency classification is __(2)__. Which ONE of the following completes the statements above? REFERENCE PROVIDED A. 1. NONE 2. ALERT B. 1. NONE 2. SITE AREA EMERGENCY C. 1. UNUSUAL EVENT 2. ALERT D. 1. UNUSUAL EVENT 2. SITE AREA EMERGENCY APE065 2.4.41 - Loss of Instrument AirAPE065 GENERICKnowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5 / 45.11)Tuesday, October 06, 2015Page 167 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION80D80General DiscussionAnswer A DiscussionIncorrect: First part is incorrect. Plausible since it would be correct if the ADVs were not being used to steam 1A SG. Second part is incorrect. Plausible since it would be correct if the ADVs were not being used to steam 1A SG.Answer B DiscussionIncorrect: First part is incorrect. Plausible since it would be correct if the ADVs were not being used due to the loss of IA and AIA to 1A TBV. Second part is correct.Answer C DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since it would be correct if the ADVs were not being used to steam 1A SG.Answer D DiscussionCORRECT. The classification at 1210 is Unusual Event. This is based on receiving 3 points under Containment Barriers (Loss) on the Fission Product Barrier Matrix for "Failure of secondary side of SG results in a direct opening to the environment with SG Tube Leak >/= 10 gpm in the same SG". Unusual Event is 1 to 3 points.The classification at 1230 is Site Area Emergency. This is based on the 3 points described above plus 4 points received under RCS Barriers (Potential Loss) for "SGTR >/= 160 gpm" for a total of 7 points. SAE is 7 to 10 points.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedRP/0/A/1000/001Development ReferencesEAP-SEP Obj. R12 RP/0/A/1000/001E-Plan Basis Doc.401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires the candidate to evaluate plant conditions associated with loss of Instrument Air and SGTR and make emergency classifications based on their evaluation.Basis for Hi CogBasis for SRO onlyQuestion requires the applicant to evaluate plant conditions and make emergency classifications based on their evaluation.APE065 2.4.41 - Loss of Instrument AirAPE065 GENERICKnowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5 / 45.11)Tuesday, October 06, 2015Page 168 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION81C81 Given the following Unit 1 conditions: Time = 1200 Reactor power = 100% stable AFIS bypassed for maintenance SA-16/C-1 (230 KV Swyd Isolate ES Permit) actuated 230 KV Yellow Bus voltage = 224.2 KV increasing Time = 1201 AP/34 (Degraded Grid) in progress Main Turbine trips due to low grid frequency 230 KV Yellow Bus voltage = 226.8 KV increasing RCS pressure = 1245 psig rapidly decreasing RB pressure = 11.4 psig rapidly increasing Engineered Safeguards systems...

1) will be energized from __(1)__. 2) __(2)__ sufficient to maintain Reactor Building pressure within design limits. Which ONE of the following completes the statements above?

A. 1. CT-1 2. are B. 1. CT-1 2. are NOT C. 1. CT-4 2. are D. 1. CT-4 2. are NOT APE077 AA2.07 - Generator Voltage and Electric Grid DisturbancesAbility to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)Operational status of engineered safety features...........................Tuesday, October 06, 2015Page 169 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION81C81General DiscussionAnswer A DiscussionIncorrect. First part is plausible since it would be correct if there had not been a switchyard isolation. Second part is correct.Answer B DiscussionIncorrect. First part is plausible since it would be correct if there had not been a switchyard isolation.Second part is plausible since it would be correct if this were a MSLB since AFIS is bypassed. The basis of TS 3.3.11 (AFIS) explains that for a Main Steam Line break (which is what is occuring in this question)Answer C DiscussionCorrect.Grid voltage is low and if it stays less than 227,468 for greater than 9 seconds then an ES 1 or 2 actuation on any unit will cause a swyd isolation to occur. In the current conditions swyd voltage is still low along with low RCS pressure which causes a swyd isolation to occur due to ES 1 and 2 actuation. A swyd isolation concurrent with an ES actuation will result in power to the MFBs coming from a Keowee unit via the underground and CT-4.The basis of TS 3.6.5 (Reactor Building Spray and Reactor Building Cooling) explains that for a LOCA (which is what is occuring in this question) the highest peak containment pressure is 57.75 psigAnswer D DiscussionIncorrect.First part is correct. Second part is plausible since it would be correct if this were a MSLB since AFIS is bypassed. The basis of TS 3.3.11 (AFIS) explains that for a Main Steam Line break (which is what is occuring in this question)Cognitive LevelComprehensionJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT39 Q16Student References ProvidedDevelopment ReferencesILT39 Q16TS 3.3.11` basisTS 3.6.5 basisEL-PSL Obj 11401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of the operational status of ES components following a grid distrubance. Since without the grid distrubance, the supply to ES components would be CT-1 this question meets the KA. It is met at the SRO level since the LOCA is initiated by a turbine trip that is initiated by the grid distrubance.Basis for Hi CogBasis for SRO onlyThis question is SRO only in that it requires knowledge of design basis of plant that is not systems knowledge. This information is incorporated into the basis of Tech Spec 3.6.5 and 3.3.11and is therefore basis knowledge and as allowed by SRO clarification guidance it becomes an SRO level question. 10 CFR 55.43(b)(2)APE077 AA2.07 - Generator Voltage and Electric Grid DisturbancesAbility to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)Operational status of engineered safety features...........................Tuesday, October 06, 2015Page 170 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION81C81Tuesday, October 06, 2015Page 171 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION82C82 Given the following Unit 1 conditions:

Initial conditions: Reactor power = 100% Control Rod 3 in Group 7 indicates 0% withdrawn AP/01 (Unit Runback) initiated Current conditions: Reactor power 70% decreasing

1) With ICS in AUTO, the Regulating Rods will NOT respond to an "out" command until Reactor power is less than a MAXIMUM of __(1)__ percent. 2) The basis for the above limit on Reactor power is to maintain __(2)__ within design limits.

Which ONE of the following completes the statements above? A. 1. 55 2. Linear Heat Rate B. 1. 55 2. Shutdown Margin C. 1. 60 2. Linear Heat Rate D. 1. 60 2. Shutdown Margin APE003 AA2.02 - Dropped Control RodAbility to determine and interpret the following as they apply to the Dropped Control Rod: (CFR: 43.5 / 45.13)Signal inputs to rod control system ................................. Tuesday, October 06, 2015Page 172 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION82C82General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since it is the value for the Asymmetric Rod Runback. Second part is correct.Answer B DiscussionIncorrect. First part is incorrect. Plausible since it is the value for the Asymmetric Rod Runback. Second part is incorrect. Plausible since SDM at power is verified using curves in the COLR which utilize reactor power and control rod position. Additionally, the operator utilizes a different curve when operating with a dropped rod.Answer C DiscussionCORRECT. With an Asymmetric/dropped rod, a Regulating Rod "out inhibit" is established if in manual OR if in AUTO with NI power > 60%. The basis for the limit on reactor power is to ensure that local Linear Heat Rate increases, due to the misaligned rod, will not cause the core design criteria to be exceeded.Answer D DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since SDM at power is verified using curves in the COLR which utilize reactor power and control rod position. Additionally, the operator utilizes a different curve when operating with a dropped rod.Cognitive LevelMemoryJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesIC-CRI Obj. 11ADM-TSS Obj. R5TS 3.1.4 Bases401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires the ability to determine the power level, above which, the rod control system will not respond to an "out" command and the basis for the limit.Basis for Hi CogBasis for SRO onlyThe question cannot be answered solely by knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or less actions, "above the line" information, or TS Safety Limits. It requires knowledge of TS Bases. 10 CFR 55.43(b)(2)APE003 AA2.02 - Dropped Control RodAbility to determine and interpret the following as they apply to the Dropped Control Rod: (CFR: 43.5 / 45.13)Signal inputs to rod control system ................................. Tuesday, October 06, 2015Page 173 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION83C83 Given the following Unit 1 conditions: Reactor power = 75% stable Group 7 rod position = 72% withdrawn stable Makeup to LDST initiated

1) If the LDST makeup were diluting boron concentration, Group 7 rods would be __(1)__. 2) If the boron dilution results in NOT meeting the Regulating rod position limits of Tech Spec 3.2.1 (Regulating Rod Position Limits), Tech Spec requires that the makeup source for boration be either the __(2)__ or the Concentrated Boric Acid Storage Tank. A. 1. withdrawing 2. BWST B. 1. withdrawing 2. "A" BHUT C. 1. inserting 2. BWST D. 1. inserting 2. "A" BHUT APE024 AA2.06 - Emergency BorationAbility to determine and interpret the following as they apply to the Emergency Boration: (CFR: 43.5 / 45.13)When boron dilution is taking place ................................. Tuesday, October 06, 2015Page 174 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION83C83General DiscussionAnswer A DiscussionIncorrect. First part is plausible as it is a common error to confuse rod motion direction with boron changes vs temperature changes. Second part is correct.Answer B DiscussionIncorrect. First part is plausible as it is a common error to confuse rod motion direction with boron changes vs temperature changes. Second part is plausible since Tech Specs requires that a minimum BWST level of 46 feet be maintained as part of ECCS support therefore it is plausible to believe that TS would not direct using BWST if there were other options in order to preserve its design function availability. Since A BHUT is maintained at a higher boron concentration than RCS it is a plausible alternative to the BWST since it would result in restoring SDM. Additional plausibility is derived from the basis requirements of TS 3.1.8 which allow boration from the "best source available for unit conditions" when SDM requirements are not met therefore this would be a correct answer if the SDM requirements were not met during Physics Testing.Answer C DiscussionCorrect. If boron concentration were decreasing then control rods would be inserting to offset the decrease in boron. The basis of TS 3.2.1 requires that the boration be done in the manner described in the basis of TS 3.1.1 and that states that the boration should be from a highly borated source such as CBAST or the BWST.Answer D DiscussionIncorrect. First part is correct.Second part is plausible since Tech Specs requires that a minimum BWST level of 46 feet be maintained as part of ECCS support therefore it is plausible to believe that TS would not direct using BWST if there were other options in order to preserve its design function availability. Since A BHUT is maintained at a higher boron concentration than RCS it is a plausible alternative to the BWST since it would result in restoring SDM. Additional plausibility is derived from the basis requirements of TS 3.1.8 which allow boration from the "best source available for unit conditions" when SDM requirements are not met therefore this would be a correct answer if the SDM requirements were not met during Physics Testing.Cognitive LevelComprehensionJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT46 Q96Student References ProvidedDevelopment ReferencesILT46 Q96TS 3.2.1 basisTSTS 3.1.1 basisTS 3.1.8 basis401-9 Comments:Remarks/StatusBasis for meeting the KAThis question meets the KA in that it requires being able to determine when a boron dilution is taking place by observing the resulting control rod motion. Additionally, at the SRO level the ability to "interpret" the boron dilution would include the ability to mitigate the event and to answer that part of this question requires TS basis knowledge.Basis for Hi CogBasis for SRO onlyIn accordance with Clarification Guidance for SRO-only Questions:This question requires knowledge from the basis of TS 3.2.1 and 3.1.1 andis not systems knowledge. 10 CFR 55.43(b)(2)It cannot be answered by knowing 1 hr or less TS/TRM ActionIt cannot be answered solely with "above the line" information.It cannot be answered solely by knowing Safety LimitsAPE024 AA2.06 - Emergency BorationAbility to determine and interpret the following as they apply to the Emergency Boration: (CFR: 43.5 / 45.13)When boron dilution is taking place ................................. Tuesday, October 06, 2015Page 175 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION83C83Tuesday, October 06, 2015Page 176 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION84C84 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% ACB-3 closed Current conditions: 2SA-17/A-1 (GEN #1 EMERG. LOCKOUT) actuated 1TC, 1TD, and 1TE 4160V switchgear are Locked Out Blackout tab in progress EOP Enclosure 5.38 (Restoration of Power) has been initiated 1) Main Feeder Buses will be energized by __(1)__.

2) In accordance with the Blackout tab, once the Main Feeder Buses are energized the CRS will be directed to __(2)__.

Which ONE of the following completes the statements above?

A. 1. CT-5 2. continue in the Blackout Tab B. 1. CT-5 2. transfer back to Subsequent Actions Tab C. 1. KHU-2 2. continue in the Blackout Tab D. 1. KHU-2 2. transfer back to Subsequent Actions Tab BWA05 2.2.44 - Emergency Diesel ActuationBWA05 GENERICAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)Tuesday, October 06, 2015Page 177 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION84C84General DiscussionAnswer A DiscussionIncorrect. First part is plausible since it would be correct if neither of the KHU's were available. Second part is correct.Answer B DiscussionIncorrect. First part is plausible since it would be correct if neither of the KHU's were available. Second part is plausible since it would be correct if any one of the three 4160v buses were energized by the MFB.Answer C DiscussionCorrect. Guidance in Encl. 5.38 directs closing the underground feeder (ACB-4) for the operating KHU to see if that will get the MFBs energized before going to CT-5. The transfer back to Subsequent Actions requires at least one of the 4160v switchgear buses to be energized even after the MFB's are energized.Answer D DiscussionIncorrect. First part is correct, Second part is plausible since it would be correct if any one of the three 4160v buses were energized by the MFB.Cognitive LevelComprehensionJob LevelSROQuestionTypeBANKQuestion SourceILT45 Q85Student References ProvidedDevelopment ReferencesILT45 Q85EAP-BO Obj. R1 & R6EOP Encl. 5.38 Blackout Tab401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to interpret control room indications to determine the status of available power sources to understand which power source will be aligned to energize the Main Feeder Buses (MFBs). Also requires an understanding of operator actions to restore power such that even though power is restored to the MFBs, realize that the 4160V Switchgear is still de-energized and based on these system conditions, select the appropriate EOP section which is to continue in the Blackout Tab.Basis for Hi CogBasis for SRO onlyRequires assessing operator actions and plant conditions to determine a procedure or section of a procedure with which to proceed. 10 CFR 55.43(b)(5).BWA05 2.2.44 - Emergency Diesel ActuationBWA05 GENERICAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)Tuesday, October 06, 2015Page 178 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION85B85 Given the following Unit 1 conditions: Time = 1200: Notified by Unit 2 that 2SA-18/A-11 (TURBINE BSMT WATER EMERGENCY HIGH LEVEL) in alarm Reactor tripped from 100% EOP Turbine Building Flood (TBF) tab initiated Time = 1300: Core SCM = 0°F In accordance with the EOP TBF tab...

1) At time = 1200, initiate feeding SGs with Main and Emergency Feedwater while maintaining a MINIMUM Tave of __(1)__ºF. 2) At time = 1300, performance of Rule 4 (Initiation of HPI Forced Cooling) __(2)__ required. Which ONE of the following completes the statements above?

A. 1. 550 2. is B. 1. 532 2. is C. 1. 550 2. is NOT D. 1. 532 2. is NOT BWA07 2.4.21 - FloodingBWA07 GENERICKnowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5Tuesday, October 06, 2015Page 179 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION85B85General DiscussionAnswer A DiscussionFirst part is incorrect. Plausible since a minimum of 550 degrees Tc (550 - 555) is maintained per EOP Rule 7 during an SSF Event in Mode 1 or 2 with TDEFDWP or alternate unit providing SG Feed and the TBF tab will utilize the SSF to feed the SGs if no main or emergency FDW is available. Second part is correct. Step 20 in the TBF tab states that IAAT RCS heats to the point of losing core SCM, THEN GO TO STEP 88 (Perform Rule 4).Answer B DiscussionFirst part is correct. The EOP TBF tab initiates feeding both SGs to 95% Operating Range with Main and Emergency Feedwater. If initial Tave >/= 532 degrees, Tave is maintained >/= 532 degrees during the SG fill. Second part is correct. If Core SCM is lost due to heat up, the TBF tab directs performance of Rule 4.Answer C DiscussionFirst part is incorrect. Plausible since a minimum of 550 degrees Tc (550 - 555) is maintained per EOP Rule 7 during an SSF Event in Mode 1 or 2 with TDEFDWP or alternate unit providing SG Feed and the TBF tab will utilize the SSF to feed the SGs if no main or emergency FDW is available. Second part is incorrect. Plausible since the EHT and SGTR tabs direct transfer to the LOSCM tab when any SCM = 0 and HPI Forced Cooling is not in progress.Answer D DiscussionFirst part is correct. The EOP TBF tab initiates feeding both SGs to 95% Operating Range with Main and Emergency Feedwater. If initial Tave >/= 532 degrees, Tave is maintained >/= 532 degrees during the SG fill. Second part is incorrect. Plausible since the EHT and SGTR tabs direct transfer to the LOSCM tab when any SCM = 0 and HPI Forced Cooling is not in progress.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-TBF Obj. R4 / R5EOP TBFBasis for meeting the KAQuestion requires knowledge of a parameter (Core SCM) and logic (Core SCM lost due to heat up) during a Turbine Building Flood to assess the status of core cooling and heat removal and transfer to a different section of the EOP TBF tab to perform Rule 4 (Initiation of HPI Forced Cooling).Basis for Hi CogBasis for SRO onlyPer ES-401 Attachment 2 Clarification Guidance for SRO Only Questions, the candidate must assess plant conditions and then select a procedure or section of a procedure with which to proceed. 10 CFR 55.43(b)(5).BWA07 2.4.21 - FloodingBWA07 GENERICKnowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5Tuesday, October 06, 2015Page 180 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION85B85401-9 Comments:Remarks/StatusPreviewTuesday, October 06, 2015Page 181 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION86B86 Given the following Unit 1 conditions:

Time = 1215 Unit shutdown in progress 1A1 RCP in operation Tcold = 220°F slowly decreasing RCS Pressure 325 psig slowly decreasing LPI Cooler outlet temperature = 110°F stable Time = 1230 Tcold = 200°F slowly decreasing RCS Pressure 275 psig stable LPI Cooler outlet temperature = 110°F stable 1A LPI Pump is started Time = 1240 Tcold = 197°F stable 1A1 RCP secured Time = 1245 LPI Cooler outlet temperature = 180°F stable

1) The RCS cooldown rate __(1)__ violate the maximum cooldown rate allowed per Tech Specs?

2) When the 1A LPI pump is started at Time = 1230, the temperature transient that results from the difference in LPI Cooler Outlet temperature and Tcold __(2)__ outside the bounds of the Reactor Vessel stress analysis? Which ONE of the following completes the statements above? A. 1. does 2. is B. 1. does 2. is NOT C. 1. does NOT 2. is D. 1. does NOT 2. is NOT SYS005 2.2.25 - Residual Heat Removal System (RHRS)SYS005 GENERICKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)Tuesday, October 06, 2015Page 182 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION86B86General DiscussionAnswer A DiscussionIncorrect. First part is correct. Second part is plausible since TS specifies LPI cooler Outlet temperature as RCS temperature when on LPI (with NO RCP's operating). Since the delta temp between cooler outlet and Tcold is in excess of the allowed cooldown rate for this RCS temperature it would be plausible to believe that the cooldown limits would be exceeded.Answer B DiscussionCorrect. RCS temperature at 1215 is 220 degrees since there is an RCP in operation. At 1245 RCS temp is 180 degrees since there is only an LPI pump in operation. The cooldown would be 40 degrees. The TS limit is 25 degrees in any 1/2 hour at this RCS temperature therefore the TS limit has been exceeded. The TS basis for Cooldown Rates (TS 3.4.3) specifically addresses the RV issue as follows:An analysis examined the effects of initiating flow through a previously idle LPI train (i.e. either placing a train of LPI in operation or swapping from one train to the other) when none of the RC pumps are operating. This analysis has determined that the brief temperature excursion caused by the fluid initially in the idle LPI train can be accommodated if, at the time the LPI header is put in service, the RCS pressure is less than 295 psig.Answer C DiscussionIncorrect. First part is plausible since it would be correct if RCS temperature were > 250 degrees where cooldown rate is less restrictive. Second part is plausible since TS specifies LPI cooler Outlet temperature as RCS temperature when on LPI (with NO RCP's operating). Since the delta temp between cooler outlet and Tcold is in excess of the allowed cooldown rate for this RCS temperature it would be plausible to believe that the RV stress analysis limits would be exceeded since that analysis is in part driven by limiting heatup and cooldown rates. It is plausible to believe that even if cooldown rates are not violated that during the "brief period of stabilization" you could be outside the bounds of the RV stress analysis because that philosophy of allowing brief periods outside of a TS limit is consistent with other situations. As an example, the RCS is allowed to violate the RCS pressure Safety Limit for 5 minutes. That brief allowance would make it plausible to believe you would be allowed to briefly violate RV stress analysis.Answer D DiscussionIncorrect. First part is plausible since it would be correct if RCS temperature were > 250 degrees where cooldown rate is less restrictive. Second part is correctCognitive LevelComprehensionJob LevelSROQuestionTypeBANKQuestion SourceILT44 Q87Student References ProvidedDevelopment ReferencesILT44 Q87 ADM-TSS obj R5 TS 3.4.3 basisBasis for meeting the KAThis question is specific to the RHR system at ONS and requires information from the basis of the RCS P/T limit LCO to determine that the LPI cooler outlet temperature during the period of stabilization does not need to be considered when an LPI train is placed in service.Basis for Hi CogBasis for SRO onlyThis question requires both application of Tech Specs and knowledge of information contained in TS basis. 10 CFR 55.43(b)(2)It cannot be answered solely by1hr or less memory items.It cannot be answered solely by above the line knowledgeIt cannot be answered solely by knowing TS Safety LimitsIt does require knowledge of TS basis that is not systems knowledge in that knowledge of how LPI cooler outlet temperatures are applied to cooldown ratesIt also required application of TS's by requiring an analysis of various temperature indications and knowledge of how to apply those indication to cooldown limits provided by TS 3.4.3.SYS005 2.2.25 - Residual Heat Removal System (RHRS)SYS005 GENERICKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)Tuesday, October 06, 2015Page 183 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION86B86401-9 Comments:Remarks/StatusNo miss on ILT44 examTuesday, October 06, 2015Page 184 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION87A87 Given the following Unit 1 conditions: Initial conditions: Reactor power = 100% I&E performing Reactor Protective System (RPS) calibration procedure Current conditions: The RCS High Pressure trip setpoint is determined to be 6 psig non-conservative in 1A and 1B RPS Channels.. 1) The actual RPS trip setpoint for RCS High Pressure is __(1)__ psig. 2) In accordance with the bases of Tech Spec 3.3.1 (Reactor Protective System (RPS) Instrumentation), the 1A and 1B RCS High Pressure Trip Functions are __(2)__. Which ONE of the following completes the statements above?

A. 1. 2345 2. operable B. 1. 2345 2. inoperable C. 1. 2355 2. operable D. 1. 2355 2. inoperable SYS012 A2.05 - Reactor Protection System (RPS)Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)Faulty or erratic operation of detectors and function generators ......... Tuesday, October 06, 2015Page 185 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION87A87General DiscussionAnswer A DiscussionCorrect. The actual RPS trip setpoint for RCS High Pressure is 2345 psig. The allowable value per TS 3.3.1 is 2355 psig. According to TS Bases, when the trip setpoint is found to be incorrect, the trip functions are operable if the trip setpoint is within the allowable value.Answer B DiscussionIncorrect. First part is correct. Second part is incorrect but plausible to believe the trip function is inoperable when the setpoint is found to be incorrect in the non-conservative direction and if the setpoint was 10 psig non-conservative, it would be correct.Answer C DiscussionIncorrect. First part is incorrect. Plausible since 2355 psig is the allowable Tech Spec value. Second part is correct.Answer D DiscussionIncorrect. First part is incorrect. Plausible since 2355 psig is the allowable Tech Spec value. Second part is incorrect but plausible to believe the trip function is inoperable when the setpoint is found to be incorrect in the non-conservative direction and if the setpoint was 10 psig non-conservative, it would be correct.Cognitive LevelComprehensionJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT46 Q87Student References ProvidedDevelopment ReferencesILT46 Q87IC-RPS Obj. R30, 31, 32 TS 3.3.1TS 3.3.1 Bases401-9 Comments:Remarks/StatusBasis for meeting the KARequires the ability to predict the impact of several malfunctions on RPS and to use Tech Specs to mitigate the consequences of the failures.Basis for Hi CogBasis for SRO onlyThis question requires application of Tech Specs.It cannot be answered solely by 1hr or less memory items.

It cannot be answered solely by above the line knowledgeIt cannot be answered solely by knowing TS Safety LimitsIt does require application of generic LCO requirements. 10 CFR 55.43(b)(2)SYS012 A2.05 - Reactor Protection System (RPS)Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)Faulty or erratic operation of detectors and function generators ......... Tuesday, October 06, 2015Page 186 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION88D88 Given the following Unit 1 conditions: Reactor power = 100% RCS pressure 2155 psig stable RB pressure 0.1 psig stable ES Channel 2 actuation 1) AP/42 Enclosure 5.3 (SSF Restoration) __(1)__ required to be performed.

2) In accordance with AD-LS-ALL-0006 (Notification/Reportability Evaluation), a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ENS notification __(2)__ required. Which ONE of the following completes the statements above? REFERENCE PROVIDED A. 1. is 2. is B. 1. is NOT 2. is C. 1. is 2. is NOT D. 1. is NOT 2. is NOT SYS013 A2.06 - Engineered Safety Features Actuation System (ESFAS)Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; (CFR: 41.5 / 43.5 / 45.3 / 45.13)Inadvertent ESFAS actuation ....................................... Tuesday, October 06, 2015Page 187 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION88D88General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since it would be correct for an ES Channel 1 actuation. Second part is incorrect. Plausible since it would be correct for a valid ES actuation.Answer B DiscussionIncorrect. First part is correct. Second part is incorrect. Plausible since it would be correct for a valid ES actuation.Answer C DiscussionIncorrect. First part is incorrect. Plausible since it would be correct for an ES Channel 1 actuation. Second part is correct.Answer D DiscussionCORRECT. AP/42 Encl. 5.3 is NOT required to be performed for an ES Channel 2 actuation. It is performed following actuation of ES Channel 1. A 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ENS notification is NOT required in this case, but would be required if the actuation were valid.Cognitive LevelMemoryJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedAD-LS-ALL-0006Development ReferencesEAP-APG Obj. R9ADM-SD Obj. R22AP/42AD-LS-ALL-0006401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires the candidate to be able to determine, following an inadvertent ES Channel 2 actuation, if the SSF Restoration enclosure of AP/42 is required to be performed. Also requires knowledge of the Notification/Reportability Evaluation procedure and whether or not the ES Channel 2 actuation is reportable.Basis for Hi CogBasis for SRO onlyPer ES-401 Attachment 2 (Clarification Guidance for SRO-only Questions), requires knowledge of the NRC reporting requirements under Conditions and limitations in the facility license (10CFR55.43(b)(1).SYS013 A2.06 - Engineered Safety Features Actuation System (ESFAS)Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; (CFR: 41.5 / 43.5 / 45.3 / 45.13)Inadvertent ESFAS actuation ....................................... Tuesday, October 06, 2015Page 188 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION89B89 Given the following Unit 1 conditions: Time = 0800: Reactor power = 100% 1RIA-59 reading 10 gpm slowly increasing AP/31 (Primary to Secondary Leakage) is initiated Time = 0810: AP/29 (Rapid Unit Shutdown) is in progress Reactor power = 60% decreasing 1RIA-59 reading 28 gpm Time = 0845: Reactor is tripped 1A1 RCP restarted per Encl. 5.6 (RCP Restart) SCM = 0ºF Time = 0847 SCM = 0ºF In accordance with the SGTR Tab-

1) The MINIMUM allowed power level to utilize 1RIA-59 for leakage calculation is __(1)__ percent. 2) The EARLIEST time that a transfer to the LOSCM tab is required is __(2)__. Which ONE of the following completes the statements above?

A. 1. > 40 2. 0845 B. 1. > 40 2. 0847 C. 1. > 25 2. 0845 D. 1. > 25 2. 0847 SYS039 A2.03 - Main and Reheat Steam System (MRSS)Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Indications and alarms for main steam and area radiation monitors (during SGTR) ..........................................Tuesday, October 06, 2015Page 189 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION89B89General DiscussionAnswer A DiscussionIncorrect. 1st part is correct. If Reactor power is </= 40%, the EOP will not use RIA-59/60 for leakage calculation.2nd part is incorrect. If SCM = 0 for 2 minutes after RCP start, transition to the LOSCM tab is required. If SCM = 0 for < 2 minutes, the transition to LOSCM is not required and the CRS will remain in the SGTR tab.Answer B DiscussionCORRECT. 1st part is correct. If Reactor power is </= 40%, the EOP will not use RIA-59/60 for leakage calculation.2nd part is correct. If SCM = 0 for 2 minutes after RCP start, transition to the LOSCM tab is required.Answer C DiscussionIncorrect. 1st part is incorrect. Plausible because 25 is the leakage amount (in gpm) that requires entry into the EOP SGTR tab.2nd part is incorrect. The SGTR tab will not direct transition to the LOSCM tab unless SCM = 0 for 2 minutes.Answer D DiscussionIncorrect. 1st part is incorrect. Plausible because 25 is the leakage amount (in gpm) that requires entry into the EOP SGTR tab.2nd part is correct. If SCM = 0 for 2 minutes after RCP start, transition to the LOSCM tab is required.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesSGTR TabAP/31 EAP SGTR Obj R11401-9 Comments:Remarks/StatusPreviewBasis for meeting the KARequires knowledge of how Main Steam Radiation Monitors affect procedure application during a SGTR.Basis for Hi CogBasis for SRO onlyES-401, II.EAssessment of facility conditions and selection of appropriate procedures duringnormal, abnormal, and emergency situations. 10 CFR 55.43(b)(5)Received permission from A. Goldau to use the note information to determine procedure selection on when to transfer to LOSCM tab.SYS039 A2.03 - Main and Reheat Steam System (MRSS)Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)Indications and alarms for main steam and area radiation monitors (during SGTR) ..........................................Tuesday, October 06, 2015Page 190 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION90D90 Given the following plant conditions: Initial conditions: Unit 1 and 2 in MODE 5 Unit 3 is at 100% Current conditions: ALL units EOP Blackout tab in progress 1) Actuating Unit 1 & 2 Keowee Emergency Start Channel B switch in the Unit 2 Control Room will start __(1)__ KHU(s). 2) The switch in part 1 above __(2)__ be used to satisfy the Unit 2 Manual Keowee Emergency Start requirements of Tech Spec 3.3.22 (EPSL Manual Keowee Emergency Start Function). Which ONE of the following completes the statements above? A. 1. ONLY one 2. can B. 1. BOTH 2. can C. 1. ONLY one 2. can NOT D. 1. BOTH 2. can NOT SYS062 2.2.4 - AC Electrical Distribution SystemSYS062 GENERIC(multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)Tuesday, October 06, 2015Page 191 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION90D90General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible since all other switches associated with starting Keowee units in auto or manual are unit specific. Second part is plausible since it is a switch that is located in the Unit 2 Control Room and Unit 1 also has a switch on its control boardAnswer B DiscussionIncorrect. First part is correct. . Second part is plausible since it is a switch that is located in the Unit 2 Control Room and Unit 1 also has a switch on its control boardAnswer C DiscussionIncorrect. First part is incorrect. Plausible since all other switches associated with starting Keowee units in auto or manual are unit specific. Second part is correct.Answer D DiscussionCorrect. Any of the KHU Emergency Start switches starts both KHU's. The switch in the Unit 1 CR and the switch in the Unit 2 CR both use Unit 1's Emergency start circuits therefore the switch located in the Unit 2 Control Room can only be used to satisfy the Unit 1 TS requirements.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-BO Obj. R6Unit 2 Encl. 5.38Unit 3 Encl. 5.38TS 3.3.22 basis401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires the candidate to be able to explain the variations in control board/control room layouts pertaining to the KHU Emergency Start circuits.Basis for Hi CogBasis for SRO onlyQuestion requires knowledge of the basis of TS 3.3.22 which states that the Unit 2 switch cannot be used to satisfy the Unit 2 TS requirements.SYS062 2.2.4 - AC Electrical Distribution SystemSYS062 GENERIC(multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)Tuesday, October 06, 2015Page 192 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION91A91 Given the following Unit 3 plant conditions: Time = 1200 Reactor in MODE 1 RBNS level 20 inches increasing LPSW leak into RB Begin pumping RBNS using 3A and 3B RBNS Pumps Time = 1205 RBNS level as indicated below Time = 1230 RBNS level indication unchanged from Time = 1205 1) Condition A of Tech Spec 3.4.15 __(1)__ required to be entered.

2) __(2)__ can be used to satisfy the RIA requirements of TS 3.4.15 LCO.

Which ONE of the following completes the statements above? REFERENCE PROVIDED A. 1. is 2. 3RIA-47 B. 1. is 2. 3RIA-49 C. 1. is NOT 2. 3RIA-47 D. 1. is NOT SYS002 2.2.22 - Reactor Coolant System (RCS)SYS002 GENERICKnowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)Tuesday, October 06, 2015Page 193 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION91A91General DiscussionAnswer A DiscussionCorrect. TS 3.4.15 basis requires that:Leakage detection systems must have the capability to detect significant reactor coolant pressure boundary (RCPB) degradation as soon after occurrence as practical to minimize the potential for propagation to a gross failure. Thus, an early indication or warning signal is necessary to permit proper evaluation of all unidentified LEAKAGE. With the RBNS level off scale and no way to bring it back on scale (due to the LPSW leak size) the candidate must determine that the RBNS level indication cannot perform its safety function as is therefore inoperable in the context of TS 3.4.15.Since the LCO specifies that a particulate monitor must be used, 3RIA-47 is required. TS Bases also states RIA-47.Answer B DiscussionIncorrect: First part is correct. Second part is plausible since it is one of the RB RIA's, however it is not a particulate monitor.Answer C DiscussionIncorrect. First part is plausible since there is no malfunction or out of service equipment associated with the RBNS, however it cannot perform its safety function. Second part is correct.Answer D DiscussionIncorrect. First part is plausible since there is no malfunction or out of service equipment associated with the RBNS, however it cannot perform its safety function. Second part is plausible since it is one of the RB RIA's, however it is not a particulate monitor.Cognitive LevelComprehensionJob LevelSROQuestionTypeBANKQuestion SourceILT44 Q91Student References ProvidedTS 3.4.15Development ReferencesILT44 Q91Admin-TSS obj R5 TS 3.4.15 basis401-9 Comments:Remarks/StatusPreview - Q changed out since preview. 10/01/15.Nobody missed on ILT44.Basis for meeting the KARequires applying Tech Spec 3.4.15 in that the SRO must assess plant conditions and apply them to the LCO requirments and the required safety function of the equipment required by the LCO to determine if the LCO is met.Basis for Hi CogBasis for SRO onlyRequires knowledge from the TS Bases of TS 3.4.15 to determine that the RBNS level indication cannot perform the safety function associated with identifying RCS leakage inside containment. It cannot be answered solely by1hr or less memory items.

It cannot be answered solely by above the line knowledgeIt cannot be answered solely by knowing TS Safety LimitsIt does require knowledge of TS basis that is not systems knowledgeSYS002 2.2.22 - Reactor Coolant System (RCS)SYS002 GENERICKnowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)Tuesday, October 06, 2015Page 194 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION92A92 Given the following Unit 1 conditions: Reactor power = 100% Electrical malfunction results in loss of ALL Control Rod position indications. 1) In accordance with Tech Spec 3.1.7 (Position Indicator Channels) , the MAXIMUM time allowed to declare all Control Rods inoperable is __(1)__.

2) Assuming indications are NOT restored, Tech Spec 3.1.4 (Control Rod Group alignment limits), __(2)__ require reducing Reactor Power to a MAXIMUM of 60% RTP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of declaring all Control Rods inoperable.

Which ONE of the following completes the statements above? REFERENCE PROVIDED A. 1. immediately 2. does B. 1. immediately 2. does NOT C. 1. one hour 2. does D. 1. one hour 2. does NOT SYS014 A2.02 - Rod Position Indication System (RPIS)Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations : (CFR: 41.5 / 43.5 / 45.3 / 45.13)Loss of power to the RPIS .........................................Tuesday, October 06, 2015Page 195 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION92A92General DiscussionAnswer A DiscussionCorrect. TS 3.1.7 required declaring all rods that have no position indication operable inoperable immediately. This puts you in TS 3.1.4 where both Condition A and Condition C apply. While Condition C requires Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the Condition A requirement to be below 60% RTP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months would also still be applicable.Answer B DiscussionIncorrect. First part is correct. Second part is plausible since that requirement stems from Condition A. Condition A applies with one Control Rod inoperable. It is a common misconception when applying Tech specs that you are only in the specific CONDITION that matches plant status. i.e. I would not be in Condition A since it is for one inoperable rod because I have more than one inoperable rod. That misconception would lead the candidate to believe that only the requirements of Condition C apply. Further plausibility comes from the fact that Oconee does have an outlier SLC (16.8.3) that does work as the above "misconception" states. There is a condition for "a single battery" being inoperable and the condition only applies when there is one and ONLY one battery inoperable.Answer C DiscussionIncorrect. First part is plausible since there are many Tech Specs that allow 1 hr as a competition time and the 1 hr CT would mean that this would still be a required memory item. Second part is correct.Answer D Discussionincorrect. First part is plausible since there are many Tech Specs that allow 1 hr as a competition time and the 1 hr CT would mean that this would still be a required memory item.

Second part is plausible since that requirement stems from Condition A. Condition A applies with one Control Rod inoperable. It is a common misconception when applying Tech specs that you are only in the specific CONDITION that matches plant status. i.e. I would not be in Condition A since it is for one inoperable rod because I have more than one inoperable rod. That misconception would lead the candidate to believe that only the requirements of Condition C apply. Further plausibility comes from the fact that Oconee does have an outlier SLC (16.8.3) that does work as the above "misconception" states. There is a condition for "a single battery" being inoperable and the condition only applies when there is one and ONLY one battery inoperable.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedTS 3.1.4Development ReferencesAdmin-ITS OBJ r3TS 3.1.4TS 3.1.7401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of procedures to mitigate consequences of loss of power to RPIS. Predicting the impact is understanding that all Control Rods must be delcared inoperable and procedure use is met by applying the requirments of TS 3.1.4.Basis for Hi CogBasis for SRO onlyThis question requires application of Tech Specs.It cannot be answered solely by1hr or less memory items.It cannot be answered solely by above the line knowledgeIt cannot be answered solely by knowing TS Safety Limits It does require application of generic LCO requirements. 10 CFR 55.43(b)(2)SYS014 A2.02 - Rod Position Indication System (RPIS)Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations : (CFR: 41.5 / 43.5 / 45.3 / 45.13)Loss of power to the RPIS .........................................Tuesday, October 06, 2015Page 196 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION92A92Tuesday, October 06, 2015Page 197 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION93D93 Given the following Unit 1 conditions: Time = 1000 Mode 6 LPI aligned in Normal Decay Heat Removal mode 1A and 1B SGs in wet layup Fuel Transfer Canal flooded 1B LPI pump OOS Time = 1030 ALL available LPI pumps tripped and can NOT be restarted 1) At 1000, in accordance with OP/1/A/1104/004 (Low Pressure Injection System), the __(1)__ LPI pump should be operating. 2) In accordance with AP/26 (Loss of Decay Heat Removal), Enclosure __(2)__ will be initiated for heat removal.

Which ONE of the following completes the statements above? A. 1. 1A 2. 5.18 (SSF Operation for Loss of DHR Events) B. 1. 1C 2. 5.7 (DHR Using SF Cooling) C. 1. 1C 2. 5.18 (SSF Operation for Loss of DHR Events) D. 1. 1A 2. 5.7 (DHR Using SF Cooling) SYS033 2.4.9 - Spent Fuel Pool Cooling System (SFPCS)SYS033 GENERICKnowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 198 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION93D93General DiscussionAnswer A DiscussionIncorrect. The first part is correct. The A or B LPI Pump is operated in Decay Heat Removal (DHR), if possible, per the LPI procedure since these pumps automatically restart when power is restored following a loss of power. Second part is incorrect. Plausible since this enclosure would be utilized if the Fuel Transfer Canal were not full.Answer B DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if the 1A LPI Pump were unavailable. Second part is correct. With all LPI Pumps unavailable and the Transfer Canal flooded, AP/26 will initiate Encl. 5.7 (DHR Using SF Cooling).Answer C DiscussionIncorrect. First part is incorrect. Plausible since it would be correct if the 1A LPI Pump were unavailable. Second part is incorrect. Plausible since this enclosure would be utilized if the Fuel Transfer Canal were not full..Answer D DiscussionCorrect. With the 1B LPI Pump OOS, the A LPI Pump is operated in Decay Heat Removal (DHR), if possible, per the LPI procedure since it would automatically restart when power was restored following a loss of power. With all LPI Pumps unavailable and the Transfer Canal flooded, AP/26 will initiate Encl. 5.7 (DHR Using SF Cooling).Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-APG Obj. R9OP/1/A/1104/004 LPIAP/26401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of low power/shutdown loss of Decay Heat Removal mitigation strategies as related to Spent Fuel Pool Cooling.Basis for Hi CogBasis for SRO onlyThis question is SRO only per ES-401 Attachment 2 Clarification Guidance for SRO-only Questions due to the following:It cannot be answered solely by using systems knowledge.It cannot be answered solely by knowing immediate operator actions.It cannot be answered solely by knowing entry conditions for Aps or direct entry to the EOP.It cannot be answered solely by knowing the purpose or overall mitigation strategy of a procedure.

The question requires assessing plant conditions and then selecting the proper section of the procedure with which to proceed. 10 CFR 55.43(b)(5)SYS033 2.4.9 - Spent Fuel Pool Cooling System (SFPCS)SYS033 GENERICKnowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 199 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION94D94 Given the following Unit 1 conditions: 1A SG isolated due to a steam line break 1B SG has a tube rupture

1) Without additional station management approval, the section of the EOP that would be used to cooldown to LPI would be the section using the __(1)__SG. 2) Once RCS temperature and pressure allow alignment of LPI, the __(2)__ mode will be the INITIAL LPI alignment utilized. Which ONE of the following completes the statements above?

A. 1. 1A 2. normal DHR B. 1. 1A 2. High Pressure C. 1. 1B 2. normal DHR D. 1. 1B 2. High Pressure GEN2.1 2.1.39 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of conservative decision making practices. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 200 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION94D94General DiscussionAnswer A DiscussionFirst part is incorrect because the SGTR tab will direct you to use the SG with the tube rupture (1B) unless you have station management approval (step 61) to use the SG with the steam leak. It is plausible since it is the SG that does not have a tube leak which on the surface would logically be the SG that should cause less off site dose. Second part is incorrect because High Pressure mode is the desired lineup unless Station management deems otherwise (Note before Step 237 SGTR tab). It is plausible because if it were Unit 3, it would be correct.Answer B DiscussionFirst part is incorrect because the SGTR tab will direct you to use the SG with the tube rupture (1B) unless you have station management approval (step 61) to use the SG with the steam leak. It is plausible since it is the SG that does not have a tube leak which on the surface would logically be the SG that should cause less off site dose.Second part is correct. Per the SGTR tab, "The credited LPI alignment for SGTR design basis event is High Pressure mode and is desired unless Station management or equipment issues deem otherwise".Answer C DiscussionFirst part is correct. The SGTR tab directs using the SG with the tube leak unless station management directs using the Faulted SG.Second part is incorrect because High Pressure mode is the desired lineup unless Station management deems otherwise (Note before Step 237 SGTR tab). It is plausible because if it were Unit 3, it would be correct.Answer D DiscussionFirst part is correct. The SGTR tab directs using the SG with the tube leak unless station management directs using the Faulted SG. Second part is correct. Per the SGTR tab, "The credited LPI alignment for SGTR design basis event is High Pressure mode and is desired unless Station management or equipment issues deem otherwise".Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesEAP-SGTR Obj R27SGTR Tab401-9 Comments:Remarks/StatusBasis for meeting the KARequires knowledge of conservative decision making as it relates to ensuring off site dose is minimized during a cooldown with both a steam leak and a SGTR in opposing SG's.Basis for Hi CogBasis for SRO onlyRequired knowledge of approval levels required for Radiation hazards that arise during abnormal situations. This is SRO only criteria since it would re Process for release approvals. 10 CFR 55.43(b)(4)GEN2.1 2.1.39 - GENERIC - Conduct of OperationsConduct of OperationsKnowledge of conservative decision making practices. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 201 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION94D94Tuesday, October 06, 2015Page 202 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION95A95 In accordance with the bases of SLC 16.13.1 (Minimum Station Staffing Requirements)... 1) the NRC Communicator __(1)__ required to be a licensed or previously licensed SRO. 2) the NRC Communicator __(2)__ also be the Off-site Communicator. Which ONE of the following completes the statements above? A. 1. is 2. can B. 1. is 2. can NOT C. 1. is NOT 2. can D. 1. is NOT 2. can NOT GEN2.1 2.1.5 - GENERIC - Conduct of OperationsConduct of OperationsAbility to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 203 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION95A95General DiscussionAnswer A DiscussionCorrect.Per the bases of SLC 16.13.1, an SRO serves as the offsite communicator and the NRC communicator. This is permissible since the offsite communicator role is completed prior to the NRC communicator role starting. The initial offsite communication is required within 15 minutes of the declaration and the NRC communication is required within 60 minutes.Answer B DiscussionIncorrect.First part is correct. Second part is incorrect. Plausible since both positions are required to be staffed and have separate duties and procedures to perform during an event.Answer C DiscussionIncorrect.First part is incorrect. Plausible since some ERO positions are allowed to be staffed by a licensed or previously licensed RO (TSC Operations Superintendent Assistant, Assistant to the OSC Operations Liason, and the OSM Liason).Second part is correct.Answer D DiscussionIncorrect.First part is incorrect. Plausible since some ERO positions are allowed to be staffed by a licensed or previously licensed RO (TSC Operations Superintendent Assistant, Assistant to the OSC Operations Liason, and the OSM Liason).Second part is incorrect. Plausible since both positions are required to be staffed and have separate duties and procedures to perform during an event.Cognitive LevelComprehensionJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesADMIN-OMP Obj R5 OMP 2-1OMP 1-07ADM-TSS R5SLC 16.13.1401-9 Comments:Remarks/StatusBasis for meeting the KARequires ability to ensure the NRC Communicator and Off-site Communicator positions are properly staffed per SLC 16.31.1 (Minimum Station Staffing Requirements) as described in the bases.Basis for Hi CogBasis for SRO onlyIn accordance with Rev. 1 of "Clarification Guidance for SRO-only Questions":This question requires knowledge of the facility operating limitations in the TS (SLC) and their bases to determine required shift staffing. 10 CFR 55.43(b)(2)GEN2.1 2.1.5 - GENERIC - Conduct of OperationsConduct of OperationsAbility to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10 / 43.5 / 45.12)Tuesday, October 06, 2015Page 204 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION96B96 In accordance with OP/0/A/1108/001 (Curves and General Information) Encl. 4.17 (Evaluation for Removal of Statalarms/Control Room Indications), which ONE of the following is the MINIMUM level of approval required to remove a Statalarm from service located on 1VB1?

A. Reactor Operator B. Control Room Supervisor C. Work Control Center SRO D. Shift Manager GEN2.2 2.2.43 - GENERIC - Equipment ControlEquipment ControlKnowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 205 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION96B96General DiscussionAnswer A DiscussionIncorrect. Plausible since it would be correct if asking about preparing the removal vs approving the removal. Also, specifying 1VB1 as the panel adds plausibility since it would not be one of the "front board" alarms and is therefore perceived as less critical.Answer B DiscussionCorrect. The Control Room Supervisor must approve removing a statalarm from service on any Control Room panel.Answer C DiscussionIncorrect. Plausible since the WCC SRO, when filled by a licensed SRO, approves equipment tagouts on the unit.Answer D DiscussionIncorrect. Plausible since there are other things in the day to day operation that require a minimum of the Shift Mangers approval.Cognitive LevelMemoryJob LevelSROQuestionTypeNEWQuestion SourceStudent References ProvidedDevelopment ReferencesAdmin-OMP Obj R51108/01401-9 Comments:Remarks/StatusPreviewBasis for meeting the KARequires generic knowledge of the process required to remove a statalarm from service.Basis for Hi CogBasis for SRO onlyThis question meets SRO requirements since it requires knowledge of administrative processes for disabling annunciators per ES-401 Attachment 2, 10 CFR 55.43(b)(3).GEN2.2 2.2.43 - GENERIC - Equipment ControlEquipment ControlKnowledge of the process used to track inoperable alarms. (CFR: 41.10 / 43.5 / 45.13)Tuesday, October 06, 2015Page 206 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION97A97 Given the following Unit 1 conditions: Initial conditions: Reactor in MODE 6 Fuel offload in progress Penetration openings exist due to containment penetration work in progress Current conditions: Control Room notified that a Fuel Assembly has been dropped 1SA-8 B-9 (PROCESS MONITOR RADIATION HIGH) actuates 1RIA-3 (Fuel Transfer Canal Area Monitor) HIGH alarm actuates 1RIA-49 (RB Gas) HIGH alarm actuates Which ONE of the following states the:

1) MAXIMUM time (minutes) allowed to isolate all containment penetrations in accordance OP/1/A/1502/009 (Containment Closure Control)? 2) Abnormal Procedure that contains the actions that are required to mitigate the initiating event? A. 1. 30 2. AP/1/A/1700/009 (Spent Fuel Damage) B. 1. 30 2. AP/1/A/1700/018 (Abnormal Release of Radioactivity) C. 1. 35 2. AP/1/A/1700/009 (Spent Fuel Damage) D. 1. 35 2. AP/1/A/1700/018 (Abnormal Release of Radioactivity) GEN2.3 2.3.15 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)Tuesday, October 06, 2015Page 207 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION97A97General DiscussionAnswer A DiscussionCorrect. AP/9 has direction to notify Containment Closure Coordinator to ensure any open penetrations are isolated in accordance with the Containment Closure Control procedure. These penetration must be isolated within 30 minutes therefore AP/9 would be the AP needing immediate attention.Answer B DiscussionIncorrect: First part is correct. Second part is incorrect. Plausible since the entry conditions for the AP are met.Answer C DiscussionIncorrect: First part is incorrect. Plausible since there are other time critical actions that have to be performed in this time such as open ADVs on both Main Steam Lines within 35 minutes of a tornado. Second part is correct.Answer D DiscussionIncorrect:First part is incorrect. Plausible since there are other time critical actions that have to be performed in this time such as open ADVs on both Main Steam Lines within 35 minutes of a tornado. Second part is incorrect. Plausible since the entry conditions for the AP are met.Cognitive LevelComprehensionJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT40 Q90Student References ProvidedDevelopment ReferencesILT40 Q90EAP-APG obj R9AP/9 & AP/18OP/1502/09401-9 Comments:Remarks/StatusBasis for meeting the KAQuestion requires the knowledge of Radiation alarms and automatic actions performed by each. Meets KA at SRO level since it requires the ability to prioritize radiation alarms to determine what procedure must be used.Basis for Hi CogBasis for SRO onlyIn accordance with Clarification Guidance for SRO-only Questions, this questionrequires assessing plant conditions and selecting a procedure with which to proceed tomitigate the event. Since the entry conditions for both of the AP choices provided are met, the SRO must use knowledge of the content of the AP's to prioritize which AP should be performed first. 10 CFR 55.43(b)(5)GEN2.3 2.3.15 - GENERIC - Radiation ControlRadiation ControlKnowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)Tuesday, October 06, 2015Page 208 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION98D98 Given the following plant conditions: Time = 0400 Reactor power = 100% 1A GWD tank release in progress at 1/3 Station Limit Time = 0415 3B GWD tank release initiated at 1/3 Station Limit Time = 0430 Loss of power to RM-80 skid of 1RIA-37 (Waste Gas Effluent Monitor) 1) In accordance with OP/3/A/1104/018 (GWD System) the release at 0415 is required to be approved by the __(1)__.

2) At 0430 and in accordance with the ARGs, an RO will __(2)__. Which ONE of the following completes the statements above?

A. 1. Unit 3 CRS 2. manually close GWD-4 B. 1. Unit 3 CRS 2. verify GWD-4 has automatically closed C. 1. SM only 2. manually close GWD-4 D. 1. SM only 2. verify GWD-4 has automatically closed GEN2.3 2.3.11 - GENERIC - Radiation ControlRadiation ControlAbility to control radiation releases. (CFR: 41.11 / 43.4 / 45.10)Tuesday, October 06, 2015Page 209 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION98D98General DiscussionAnswer A DiscussionIncorrect. First part is incorrect. Plausible because it would be correct if the release was at 1/3 limit and only one release was in progress. Second part is incorrect. Plausible since it would be correct for loss of power to the 1RIA-45 RM-80 skid.Answer B DiscussionIncorrect. First part is incorrect. Plausible because it would be correct if the release was at 1/3 limit and only one release was in progress. Second part is correct.Answer C DiscussionIncorrect:. First part is correct. 2 Gaseous Waste Releases (GWRs) at 1/3 Station Limit requires Shift Manager (SM) approval. Second part is incorrect. Plausible since it would be correct for loss of power to the 1RIA-45 RM-80 skid.Answer D DiscussionCorrect: 2 Gaseous Waste Releases (GWRs) at 1/3 Station Limit requires Shift Manager (SM) approval.Loss of power to the RIA (RM-80) skid causes any associated high alarm interlocks to actuate. In this case a loss of power to the RM-80 skid for 1RIA-37 causes GWD-4 to close to isolate the release.Cognitive LevelComprehensionJob LevelSROQuestionTypeMODIFIEDQuestion SourceILT42 Q97Student References ProvidedDevelopment ReferencesILT42 Q97 OP/3/A/1104/18ARGWE-GWD Obj 07RAD-RIA401-9 Comments:Remarks/StatusNew K/ABasis for meeting the KAQuestion requires knowledge of the process for releasing a GWD gas tank including who has to approve the release.Understanding the process is paramount in the ability to control the release.Basis for Hi CogBasis for SRO onlyPer Clarification Guidance for SRO-only Questions:Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.Process for gaseous/liquid release approvals, i.e., release permits. 10 CFR 55.43(b)(4)Additionally this question is supported as SRO by an SRO ONLY objective in the WE-GWD lesson plan.GEN2.3 2.3.11 - GENERIC - Radiation ControlRadiation ControlAbility to control radiation releases. (CFR: 41.11 / 43.4 / 45.10)Tuesday, October 06, 2015Page 210 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION99A99 Given the following Unit 1 conditions:

Time = 0000 Reactor power = 75% All three seals on the1B1 RCP fail Time = 0015 SCM = 0ºF stable Time = 0019 1A1 RCP remains operating LOSCM tab in progress Rapid depressurization of BOTH steam generators is in progress 1) The reason the 1A1 RCP is NOT secured at Time = 0019 is to __(1)__.

2) The MINIMUM condition(s) that will allow the section of the LOSCM tab to be performed that reinstates the requirement to adhere to Tech Spec cooldown rate limits is once __(2)__ is/are greater than 0 degrees F.

Which ONE of the following completes the statements above?

A. 1. prevent core uncovery that could result from phase separation if the RCP were secured

2. ALL subcooling margins B. 1. provide forced circulation which enhances heat removal even with a two phase mixture

2. ALL subcooling margins C. 1. prevent core uncovery that could result from phase separation if the RCP were secured 2. ANY subcooling margin D. 1. provide forced circulation which enhances heat removal even with a two phase mixture 2. ANY subcooling margin GEN2.4 2.4.18 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13)Tuesday, October 06, 2015Page 211 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION99A99General DiscussionAnswer A DiscussionCorrect. If a RCP remains operating greater than 2 minutes after LOSCM occurs, then it is left on. Void fraction could be greater than 70% and if the pump is subsequently stopped,phase separation will occur and the core could be uncovered. LOSCM tab will require holding at a WHEN step (39) until all SCM's are >0 before continuing.Answer B DiscussionIncorrect. First part is incorrect. Plasuible because it would be correct if SCM was lost for < 2 minutes. Second part is correctAnswer C DiscussionIncorrect. First part is correct. Second part is plausible since there are various conditions in the EOP which take actions basesd soley on Core SCM (Ex. Transfer to ICC tab) and actions are taken based on any subcooling margin such as securing RCPs if any SCM is 0.Answer D DiscussionIncorrect. First part is incorrect. Plasuible because it would be correct if SCM was lost for < 2 minutes.Second part is plausible since there are various conditions in the EOP which take actions basesd soley on Core SCM (Ex. Transfer to ICC tab) and actions are taken based on any subcooling margin such as securing RCPs if any SCM is 0.Cognitive LevelComprehensionJob LevelSROQuestionTypeBANKQuestion SourceILT45 Q77Student References ProvidedDevelopment ReferencesILT45 Q77 EAP-LOSCM Obj. 15 EOP Rule 2401-9 Comments:Remarks/StatusBasis for meeting the KAThis question requires knowing the basis for specfic steps in the EOP.Basis for Hi CogBasis for SRO onlyThis question requires assessing plant conditions using that assessment to determine if or when a section of the LOSCM tab can be performed.GEN2.4 2.4.18 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13)Tuesday, October 06, 2015Page 212 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION100A100 1) In accordance with RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure) implementation of the OSAG __(1)__ require the use of 10CFR50.54(x) and(y) provisions.

2) If implemented, 10CFR50.54(x) will require the MINIMUM level of approval to be __(2)__ .

Which ONE of the following completes the statements above?

A. 1. does 2. a licensed SRO B. 1. does 2. the Emergency Coordinator C. 1. does NOT 2. a licensed SRO D. 1. does NOT 2. the Emergency Coordinator GEN2.4 2.4.29 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of the emergency plan. (CFR: 41.10 / 43.5 / 45.11)Tuesday, October 06, 2015Page 213 of 214 FOR REVIEW ONLY - DO NOT DISTRIBUTEILT48 ONS SRO NRC ExaminationQUESTION100A100General DiscussionAnswer A DiscussionCorrect. The first part of the question is correct in that any implementation of the OSAG requires a 10CFR50.54(x) declaration. The second part of the question is correct in that the MINIMUM level of approval for a 10CFR50.54(x) situation, per 10CFR50.54(y) is a licensed SRO.Answer B DiscussionIncorrect distractor. First part of distractor 'B' is correct, second part of distractor 'B' is incorrect. Second part of distractor 'B' is plausible because the Emergency Coordinator is the highest level authority on site during an emergency, is granted the authority to make a 50.54(x) declaration, and probably would be the decision-maker in this situation. However, technically speaking the second part of this distractor is incorrect because the Emergency Coordinator is not the MINIMUM required level of approval; instead, 10CFR50.54(y) specifies that the minimum level of authorization is a licensed SRO.Answer C DiscussionIncorrect distractor. First part of distractor 'C' is incorrect, second part of distractor 'C' is correct. First part of distractor 'C' is plausible because no other directed procedural transition requires a 50.54(x) declaration. A SRO applicant may incorrectly believe that use of approved procedures (OSAG) is not a departure from the license basis condition, and therefore may choose this incorrect distractor.Answer D DiscussionIncorrect distractor. Both parts of this distractor are incorrect. For plausibility descriptions, see above discussions of distractor 'B' and 'C.'Cognitive LevelMemoryJob LevelSROQuestionTypeBANKQuestion SourceILT43 Q100Student References ProvidedDevelopment ReferencesILT43 Q100EAP-SEP Obj. R10RP/0/A/1000/002401-9 Comments:Remarks/StatusBasis for meeting the KAThis question matches the K/A in that, given an extreme emergency situation (similar to Fukushima Dai-ichi), the question requires the SRO applicant to demonstrate knowledge of the requirements associated with OSAG entry and implementation of 10CFR50.54(x) and (y). These decisions are associated with the Emergency Coordinator function in the Emergency Plan implementation procedures.Basis for Hi CogBasis for SRO onlyThis question is linked to 10CFR55.43(b)(1), Conditions and limitations in the facility license, in that SRO-level authorization, at a minimum, is required to transition to the OSAG and declare a 10CFR50.54(x) condition. Licensed ROs are not allowed to make that determination.GEN2.4 2.4.29 - GENERIC - Emergency Procedures / PlanEmergency Procedures / PlanKnowledge of the emergency plan. (CFR: 41.10 / 43.5 / 45.11)Tuesday, October 06, 2015Page 214 of 214 Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 1 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO ________________________ ________________________OATC ________________________ ________________________BOP Initial Conditions: Reactor Power = 100% Turnover: Feedwater valve DP selected to 1A1 and 1B2 for maintenance ICS Diamond and FDW Masters are in HAND for Control Rod Movement PT AMSAC/DSS bypassed Event No. Malfunction No. Event Type* Event Description 0a Override Standby (1B) HPI pump auto start 0b Override Standby EHC pump fails to Auto start 1 N: OATC, SRO Control Rod Movement PT (GP 1 Only) 2 MPS120 Override C: BOP, SRO (TS) 1A HPIP Sheared Shaft, 1B HPIP fails to start in AUTO 3 MCS008 I: OATC, SRO Loop B Tc Fails low 4 Override C: OATC, SRO (TS) Group 1 Rod 6 Control Rod drops, manual power reduction 5 MPS190 C: BOP, SRO Spray valve fails open 6 Override C: BOP, SRO Lowering EHC pressure, Standby EHC pump fails to start 7 MSS010 MSS020 MSS260 MSS270 M: ALL LOHT CBPs trip requiring HPI FC 1C HPIP fails to start requiring RCS vents to be opened * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 2 of 46 Scenario 1 Event Summary Event 1: The OATC will perform PT/1/A/0600/015, Encl. 13.2 (Control Rod Movement at Power). This will be performed for group 1 rods only. Event 2: The 1A HPIP will experience a sheared shaft. Pump amps will decrease to approximately 10-15 amps, discharge pressure and flow will drop to 0. The 1B HPIP will not start in automatic requiring operator action. The crew will enter AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection), close 1HP-5, 1HP-120 and 1HP-31 and start the 1B HPIP. The crew should then restore the system to normal and enter TS for loss of the 1A HPIP. Event 3: Loop B Tc will fail low causing control rods to withdraw and feedwater demand to decrease. The crew should perform Plant Transient Response (PTR) and place the ICS Diamond and FDW Loop Masters in MANUAL. The crew will perform AP/28 (ICS Instrument Failures). ICS will remain in MANUAL for the rest of the scenario. Event 4: Control Rod Group 1 Rod 6 will drop into the core. Because ICS is in MANUAL, the OATC will have reduce power in MANUAL to < 55%. Event 5: After the power reduction, 1RC-1 (Pzr Spray Valve) fails open and will reduce RCS pressure. This will require the operator to close the block valve (1RC-3) to stabilize RCS pressure. Event 6: EHC pressure will start lowering. The standby EHC pump will fail to start at 1350 psig and the low pressure alarm will actuate at 1300 psig. The operators must start the standby EHC pump prior to a turbine trip on low EHC pressure. Event 7: Condensate Booster Pumps trip, MFWPs subsequently trip, MD EFDW pumps will fail to start and the TD EFDW pump will overspeed and trip. The crew will not be able to feed the SGs before the criteria to perform Rule 4 (HPI Forced Cooling) is satisfied. The 1C HPIP will fail to start (degraded HPI) which will require the crew to open RCS vents and transfer to the HPI CD tab of the EOP.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 3 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 1 Page 1 of 5 Event

Description:

Control Rod Movement PT (N, OATC, SRO) Time Position Applicant's Actions or Behavior SRO OATC

PT/1/A/0600/015 Crew response: SRO directs the OATC to perform PT/1/A/0600/015, Encl. 13.2 (Control Rod Movement at Power). PT/1/A/0600/015, Encl. 13.2 Rev 26 3.1 WHILE enclosure is in progress, monitor the following indications: {8} CRD position Appropriate ranged NIs RCS temperature Neutron error 3.2 Ensure Rx Diamond and FDW Masters in Hand per Enclosure for Placing Rx Diamond/FDW Masters To Hand of OP/1/A/1102/004 A (ICS Operation).(already in HAND) 3.3 IF AT ANY TIME contingency actions directed by CRS, perform Section 4 (Contingency Actions) {4} NOTE: When operating switches on Diamond, maintain switch depressed until light indication changes state. 3.4 Perform the following: (R.M.) Ensure SEQ OR is ON. Ensure SAFETY RODS OUT BYPASS is ON. Ensure RUN is ON. Ensure SINGLE SELECT SWITCH selected to ALL. NOTE: CRD Groups 1-Margin Calculation at Power enclosure of PT/1/A/1103/015 (Reactivity Balance Procedure) to be valid. 3.5 IF AT ANY TIME any CRD Group 1-6 reaches 95% during insertion, stop inserting associated group. (R.M.) This event is complete when the Control Rod Movement PT is complete and ICS is in Auto or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 4 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 1 Page 2 of 5 Event

Description:

Control Rod Movement PT (N, OATC, SRO) Time Position Applicant's Actions or Behavior OATC

PT/1/A/0600/015 Crew response: 3.6 Perform the following to test CRD Group 1: (R.M.) ___ 3.6.1 Ensure GROUP SELECT SWITCH to 1. ___ 3.6.2 Ensure Group 1 CONTROL ON lights are ON. (PI panel) {5} NOTE: 1SA-2/C-10 "CRD Safety Rods Not At Upper Limit" will alarm when Safety Groups are inserted. Control rods should NOT be left inserted. Rod withdrawal should commence immediately after insertion is complete. ___ 3.6.3 Perform the following: {3} A. Insert CRD Group 1. B. WHEN all 100% lights OFF, stop insertion. C. Begin Group 1 withdraw to 100%. NOTE: In RUN speed, all rod motion is inhibited 12 seconds after first rod reaches OUT LIMIT. D. WHEN OUT LIMIT is ON, maintain WITHDRAW until CRD TRAVEL "Out" light OFF. ___ 3.6.4 Verify all 100% lights are ON for Group 1. (PI Panel) ___ 3.6.5 Verify unit is stable. Examiner Note: Steps 3.7 - 3.13 test Control Rod Groups 2-8. When completing the PT on GP 1 Control Rods, they should proceed to step 3.14 to return ICS to AUTOMATIC. NOTE: When operating switches on Diamond, maintain switch depressed until light indication changes state. 3.14 Perform the following: (R.M.) Ensure SEQ is ON. Ensure GROUP SELECT SWITCH to OFF. Ensure SAFETY RODS OUT BYPASS is OFF. 3.15 Return Rx Diamond and FDW Masters To Automatic per OP/1/A/1102/004 A (ICS Operation). (Page 5) This event is complete when the Control Rod Movement PT is complete and ICS is in Auto or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 5 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 1 Page 3 of 5 Event

Description:

Control Rod Movement PT (N, OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/004A Encl 4.1 (in progress) Crew Response: OP/1/A/1102/004A Encl 4.1 Rev10 2.9 WHEN required, place ICS back in auto as follows: 2.9.1 Ensure "RATE SET" thumbwheels at 0.0. 2.9.2 IF TURBINE MASTER is in manual [NA] 2.9.3 IF Rx Master is in "HAND" [NA] 2.9.4 IF DIAMOND is in manual, perform the following: A. Verify REACTOR MASTER in "AUTO". B. IF both SGs are off of Level Control, perform the following: 1. IF selected Tave (O1E2086) is different from Tave setpoint (O1E2087) by more than + 0.15°F, perform the following: a. Simultaneously perform the following: Ensure 1A FDW MASTER in "HAND" Ensure 1B FDW MASTER in "HAND" NOTE: Cycling the setpoint selector may result in a Star Module failure. This is expected for this condition and entry into AP/1/A/1700/028 (ICS Instrument Failures) is NOT required. The Star Module failure shall be cleared before the ICS is returned to Auto. b. On REACTOR MASTER, cycle Tave setpoint selector between 565°F and 585°F five times. c. IF Star Module failed, perform the following: 1) Initiate Work Request to repair Star Module. 2) WHEN Star Module repaired, continue procedure.

d. On REACTOR MASTER adjust Tave setpoint (O1E2087) toward selected Tave (O1E2086). 2. Verify selected Tave is within + 0.15°F of Tave setpoint. This event is complete when the Control Rod Movement PT is complete and ICS is in Auto or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 6 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 1 Page 4 of 5 Event

Description:

Control Rod Movement PT (N, OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/004A Encl 4.1 Crew Response: C. IF either SG is on Level Control, adjust Tave setpoint (O1E2087) to 579°F. D. Place DIAMOND in "AUTO". 2.9.5 Ensure STM GENERATOR MASTER in "AUTO". 2.9.6 IF 1A OR 1B FDW Master is in "HAND", perform the following: A. Perform the following: Select 1A FDW MASTER to "MEAS VAR" Select 1B FDW MASTER to "MEAS VAR" B. IF 1A OR 1B FDW Master Measured Variable is NOT on the caret, perform the following: 1. Initiate Work Request to repair. 2. WHEN repairs are complete, continue procedure. C. Verify the following: 1A FDW MASTER Measured Variable on the caret 1B FDW MASTER Measured Variable on the caret D. Perform the following: Select 1A FDW MASTER to "POS" Select 1B FDW MASTER to "POS" E. Simultaneously perform the following: Select 1A FDW MASTER to "AUTO" Select 1B FDW MASTER to "AUTO" This event is complete when the Control Rod Movement PT is complete and ICS is in Auto or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 7 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 1 Page 5 of 5 Event

Description:

Control Rod Movement PT (N, OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/004A Encl 4.1 Crew Response: CAUTION: Adjusting THP, Tave or Delta Tc setpoint too fast can cause plant instability. 2.10 IF NOT being controlled by another procedure, perform the following: 2.10.1 IF THP (O1E2088) is NOT 2.10.2 IF Tave Setpoint (O1E2087) is NOT 2.10.3 IF Delta Tc is NOT 0.0°F. (R.M.) 2.11 IF desired adjust CTP as follows: (R.M.) 2.11.1 Review current mechanical maneuvering rates per PT/0/A/1103/020 (Power Maneuvering Predictions). 2.11.2 IF desired to increase power, perform the following: A. WHEN ICS has been in full Auto (Integrated Mode) for > 10 minutes, continue at Step 2.11.3. {6} 2.11.3 Ensure selected "HOLD".

2.11.4 Ensure desired setting selected ("%/MIN" or "%/HR") on "RATE" pushbuttons.

2.11.5 Ensure desired rate selected on "RATE SET" thumbwheels.

2.11.6 Insert desired CTPD SET using "INCREASE/DECREASE" pushbuttons. 2.11.7 Ensure "HOLD" is NOT selected.

2.11.8 WHEN desired CTP is achieved, return "RATE SET" thumbwheels to 0.0. This event is complete when the Control Rod Movement PT is complete and ICS is in Auto or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 8 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 2 Page 1 of 3 Event

Description:

A HPIP Sheared Shaft, B HPIP fails to start in AUTO (C: BOP, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/BOP

AP/1/A/1700/014 Plant Response: 1SA-2/B-2 (HP RCP Seal Injection Flow High/Low) 1SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low) RC Makeup Flow = ~0 gpm RCP SI flow = ~0 gpm 1A HPI Pump amps low = ~10 amps PZR level will begin to decrease and LDST level will begin to increase 1HP-120 throttles open due to PZR level decrease Crew Response: BOP may refer to ARGs (Both ARGs direct referral to AP/14) SRO will refer to AP/1/A/1700/014 AP/1/A/1700/014 Rev 18 Immediate Manual Actions 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following: A. __ Trip the Rx. B. __ Stop all RCPs. C. __ Initiate AP/25 (SSF EOP). 3.2 IAAT loss of suction to operating HPI pumps is indicated: Motor amps low or cycling Discharge pressure low or cycling Abnormal LDST level trend THEN GO TO Step 3.3. RNO: GO TO Step 4.7 Examiner Note: Crew should diagnose a sheared shaft and proceed to step 4.7. Supplemental Actions 4.7 Announce AP entry using PA System. This event is complete when 1HP-31 is placed in AUTO or when directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 9 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 2 Page 2 of 3 Event

Description:

A HPIP Sheared Shaft, B HPIP fails to start in AUTO (C: BOP, SRO)(TS) Time Position Applicant's Actions or Behavior BOP

AP/1/A/1700/014 Crew Response: 4.8 Verify any HPI pump operating. [With a sheared shaft on the A HPIP, this step should be interpreted as no HPIPs operating] RNO: 1. __ Close 1HP-5. 2. __ Place 1HP-120 in HAND and close. 3. __ Place 1HP-31 in HAND and close. 4. __ Attempt to start the standby HPI pump. 5. __ IF standby HPI pump started, THEN GO TO Step 4.111. 6. __ GO TO Step 4.14. 4.111 Place 1HP-31 in HAND. 4.112 Slowly open 1HP-31 in small increments until ~ 8 gpm/RCP is achieved. 4.113 Re-establish normal makeup through 1HP-120.

4.114 Ensure proper operation of the Component Cooling System. 4.115 Reduce 1HP-7 demand to 0%. 4.116 Close 1HP-6.

4.117 Open the following: __ 1HP-1 __ 1HP-2 __ 1HP-3 __ 1HP-4 4.118 Open 1HP-5. 4.119 Throttle open 1HP-4.120 Open 1HP-6. 4.121 Adjust 1HP-7 for desired letdown flow. This event is complete when 1HP-31 is placed in AUTO or when directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 10 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 2 Page 3 of 3 Event

Description:

A HPIP Sheared Shaft, B HPIP fails to start in AUTO (C: BOP, SRO)(TS) Time Position Applicant's Actions or Behavior BOP

AP/1/A/1700/014 Crew Response: 4.122 Open the following: __ 1HP-228 __ 1HP-226 __ 1HP-232 __ 1HP-230 4.123 Open 1HP-21. 4.124 IAAT SEAL INLET HDR FLOW ~ 32 gpm, THEN place 1HP-31 in AUTO.

4.125 Monitor RCP seal parameters. 4.126 Maintain RCP seal injection flows as required.

4.127 Log thermal cycle of 1A HPI header.

4.128 WHEN conditions permit, THEN EXIT this procedure. TS 3.5.2 HIGH PRESSURE INJECTIN (HPI) Condition A.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore HPI pump to OPERABLE status.

This event is complete when 1HP-31 is placed in AUTO or when directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 11 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 1 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/028 Plant Response: Loop "1B" Tc Dixson meter low (520°F) Loreads 70°F 570F 570F 1SA-2/B4 (RC Average Temperature High/Low) 1SA-2/B-5, RC COLD LEG DIFF TEMP HIGH 1SA-2/A-12, ICS Tracking Crew Response: When the Statalarms are received, the candidates should utilize the "Plant Transient Response" process to stabilize the plant. Verbalize to the CRS reactor power level and direction of movement. Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant. Note: The OATC will have to re-ratio FDW to maintain Tc 0OF + 2 OF. The CRS should: Refer to AP/28, ICS Instrument Failures Ensure SPOC is contacted to repair the failed instrument. . AP/1/A/1700/028, ICS Instrument Failures Rev 20 4.1 Provide control bands as required. (OMP 1-18 Att. I) OMP 1-18 Attachment I: 1. Plant Conditions Stable or TPB < Pre-transient Conditions NI Power + 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%. Current Tave + 2 oF. Current SG Outlet Pressure + 10 PSIG (N/A) Delta Tc 0 oF + 2 oF. This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 12 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 2 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/028 Crew Response: 4.2 Initiate notification of the following: OSM to reference the following: OMP 1-14 (Notifications) Emergency Plan STA RNO: GO TO Step 4.5. 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan. 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6: OAC alarm video OAC display points Control Board indications SPOC assistance, as needed 4.6 GO TO the applicable section per the following table: Section Failure 4A RCS Temperature AP/1/A/1700/028, Section 4A, RCS Temperature Failure NOTE If Tave instrument circuit failed high, the following may have occurred depending on initial ICS station status: Unit to TRACK due to Rx Cross Limits Control Rod insertion Feedwater flow increase If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status: Unit to TRACK due to Rx Cross Limits Control Rod withdrawal Feedwater flow decrease Feedwater re-ratio This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 13 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 3 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

AP/1/A/1700/028 Crew Response: 1. Ensure the following in HAND: __ 1A FDW MASTER __ 1B FDW MASTER 2. Ensure DIAMOND in MANUAL. 3. Notify SPOC to perform the following: __ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function). __ Investigate and repair the failed RCS temperature instrumentation. 4. PERFORM an instrumentation surveillance using applicable table in Encl 5.2 (ICS Instrument Surveillances) for the failed instrument. 5. Verify instrumentation surveillance in Encl 5.2 (ICS Instrument Surveillances) was performed satisfactorily as written. RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and OP/1/A/1105/014 (Control Room Instrumentation Operation And Information). 6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto). This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 14 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 1 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/001 Plant Response: Group 1 Rod 6 drops into the core Statalarm 1SA-2/A-10 (CRD GLOBAL SYSTEM FAULT) Statalarm 1SA-2/B-10 (CRD ASYMMETRIC ROD POSITION ERROR) Statalarm 1SA-2/D-9 (CRD OUT INHIBIT) Statalarm 1SA-4/C-1 (QUADRANT POWER TILT) () Statalarm 1SA-5/A-5 (1A RPS TROUBLE) Statalarm 1SA-5/D-5 (1D RPS TROUBLE) Crew Response: Crew should perform Plant Transient Response (PTR) and determine that no manual FDW adjustments are required and that a runback condition exists but due to ICS being in manual it is not occurring. OATC reports to the SRO reactor power level and direction of movement. The BOP reports expected AUTO Runback did not occur, and monitors RCS pressure and inventory and inserts Control Rods as needed. The OATC will adjust FDW and/or control rods as necessary to restore reactor power to the desired control band. SRO should enter AP/1/A/1700/001 (Unit Runback) AP/1/A/1700/001 Rev 15 4.1 GO TO the most limiting section per the following table: Section Runback 4H Asymmetric Control Rod (1%/min to 55%power) Section 4H 1. IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1. 2. IAAT the group average, THEN trip the Rx. This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 15 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 2 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/001 NOTE NIs should NOT be calibrated per guidelines contained in OP/1/A/1102/004 (Operation at Power) due to actual power re-distribution within the core as a result of a dropped/misaligned rod. 3. Verify Rx is critical. 4. Verify power > 55% when the rod was dropped or misaligned. 5. Verify Rx runback to 55% core thermal power in progress. CTPD set at 55% ASYMETRIC RODS Runback Light lit CTP Demand decreasing Reactor power will decrease when the runback catches up with the initial power decrease from the dropped rod. RNO: 1. Initiate power reduction to 55% core thermal power 2. IF control rods will not insert manually, THEN perform the following: A. Trip reactor. B. GO TO Unit 1 EOP. 6. Initiate Encl 5.1 (Control of Plant Equipment During Shutdown). (Page 19) NOTE: The following actions should be performed as quickly as possible due to the complexity of resetting RPS trip setpoints and Tech Spec time limits. 7. Notify SPOC to perform the following: __ Investigate cause of dropped or misaligned control rod. __ Prepare to reduce the following trip setpoints: RPS Flux/Flow-Imbalance RPS High Flux This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 16 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 3 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC

AP/1/A/1700/001 Crew Response: 8. Notify the OSM to ensure the requirements of the following Tech Specs are met: __ TS 3.1.4 (Control Rod Group Alignment Limits) __ TS 3.1.5 (Safety Rod Position Limits) __ TS 3.2.3 (Quadrant Power Tilt) Booth Cue: When SM is contacted, inform the team that the SM is occupied on Unit 3 and cannot verify TS requirements at this time. 9. __ Notify OSM to make notifications as required per OMP 1-14 (Notifications). 10. __ Verify > 1% SDM with allowance for the inoperable control rod per PT/1/A/1103/015 (Reactivity Balance Calculation) within one hour.

Examiner Note: Shutdown Margin will be adequate 11. Reduce core thermal power < the following limits, based on the number of RCPs operating, within two hours: RCPs Allowable Thermal Power (% FP) 3 45 4 60 NOTE The following ensures adequate margin in preparation for resetting RPS trip setpoints. 12. __ IAAT the power decrease is complete, AND any NI is > the following: RCPs Maximum NI Power (% FP) 3 40 4 55 THEN the operating RCP combination per Encl 5.4 (Power Reduction). This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 17 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 4 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/001 Crew Response: 13. WHEN all NIs are < the Maximum NI Power limit for the operating RCP combination, THEN notify SPOC to reduce RPS trip setpoints per AM/1/A/0315/017 (TXS RPS Channel A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions.) NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown. 14. Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure. NOTE The following will prevent a potential MODE change from MODE 2 to MODE 1 if unit power stabilizes < 5%. 15. IAAT THEN GO TO the following as necessary to shutdown the reactor prior to rod recovery. OP/1/A/1102/10 (Controlling Procedure for Unit Shutdown) OP/1/A/1102/004 (Operation at Power) 16. IAAT another runback has or should have occurred, THEN GO TO Subsequent Actions. 17. WHEN the control rod is repaired, THEN perform the following: A. __ Notify Duty Reactor Engineer for any necessary maneuvering limits. B. __ GO TO OP/1/A/1105/019 (Control Rod Drive System) to recover the control rod. This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 18 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 5 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO AP/1/A/1700/001 Crew Response: TS 3.1.4 CONTROL ROD GROUP ALIGNMENT LIMITS Condition A (1hour) Restore control rod alignment or verify SDM ( 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Reduce Thermal Power to < 60% of allowable Thermal Power. (10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) RPS trip setpoints must be reduced based on flux and flux/flow imbalance to < 65.5% of the allowable thermal power. TS 3.1.5 SAFETY ROD POSITION LIMITS Condition A (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Verify SDM and declare associated control rod INOPERABLE. TS 3.2.3 QUADRAND POWER TILT Condition A if QPT exceeds +3.5 (10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) RPS trip setpoints must be reduced > 2% RTP for each 1% of QPT greater than the steady state limit (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) QPT restored to less than or equal to the steady state limit TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF) Conditions A-E (7 days) Restore to operable status Once Reactor Power is reduced to below 85% the SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies. Conditions A-E should be entered. This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 19 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 6 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC BOP AP/1/A/1700/001 AP/1/A/1700/001 Enclosure 5.1 1. IAAT SRO determines all appropriate actions have been taken, AND the runback is complete, THEN EXIT this Enclosure. 2. Notify the WCC SRO to initiate Enclosure 5.2 (WCC SRO Support During Unit Runback). 3. Start the following pumps: __ 1A FDWP SEAL INJECTION PUMP __ 1A FDWP AUXILIARY OIL PUMP __ 1B FDWP AUXILIARY OIL PUMP __ 1B FDWP SEAL INJECTION PUMP 4. WHEN CTP < 80%, THEN stop the following pumps: {3} {4} __ 1E1 HTR DRN PUMP __ 1E2 HTR DRN PUMP 5. WHEN THEN continue this Enclosure. 6. Place the following in MANUAL and close: __ 1FDW-53 __ 1FDW-65 NOTE: 1B FDWP is the preferred pump to shut down first. 7. Verify both Main FDWPs operating. 8. Verify 1B FDWP to be shut down first. 9. Adjust the FWP bias counter-clockwise to lower 1B FWP suction flow 6 lb/hr < 1A FWP suction flow. 10. GO TO Step 12. This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 20 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 7 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO/OATC BOP AP/1/A/1700/001 Crew Response: 12. IAAT both Main FDW pumps running, AND both of the following exist: __ 1B Main FDW pump is first pump to be shut down __ Any of the following alarms occur: 1SA-16/A-3 (FWP B FLOW MINIMUM) 1SA-16/A-4 (FWP B FLOW BELOW MIN), THEN trip 1B Main FDW Pump. 13. IAAT both Main FDW pumps running, AND both of the following exist: __ 1A Main FDW pump is first pump to be shut down __ Any of the following alarms occur: 1SA-16/A-1 (FWP A FLOW MINIMUM) 1SA-16/A-2 (FWP A FLOW BELOW MIN), THEN trip 1A Main FDW Pump. 14. IAAT the operating FDWP suction flow < 1.5 x 106 lb/hr, THEN slowly throttle the associated recirc control valve to establish 2300 - 6000 gpm total Condensate flow: 1FDW-53 1FDW-65 15. Maintain Pzr level between 220" - 16. IAAT THEN perform Steps 17 - 18. 17. Stop the following: {3} __ 1A MSRH DRN PUMP __ 1B MSRH DRN PUMP 18. Place the following in DUMP: {3} __ 1HD-37 __ 1HD-52 This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 21 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 5 Page 1 of 2 Event

Description:

Spray valve fails open (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP CT-1 AP/1/A/1700/044 Plant Response: RCS pressure decreasing below 2155 psig 1RC-1 Indicates OPEN 1SA-2/D-3, RC PRESS HIGH/LOW Crew Response: BOP should recognize that 1RC-1 is open and push the CLOSE pushbutton (This is an IMA in AP/44) SRO should direct entry into AP/1/A/1700/044 Abnormal Pressurizer Pressure Control AP/1/A/1700/044 Abnormal Pressurizer Pressure Control Rev 4 IMAs 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4. 3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE. [1RC-1 Will NOT close] 3.3 IAAT all the following conditions exist: __ RC pressure < 2155 psig __ RC pressure decreasing without a corresponding decrease in PZR Level THEN close 1RC-3. Subsequent Actions 4.1 Announce AP entry using the PA system. 4.2 GO TO the applicable step per the following table: Failure Caused RCS Pressure Step Decrease 4.3 Increase 4.18 Examiner Note: TS 3.4.1 may apply depending on crew response to the failure. TS 3.4.1, REACTOR COOLANT SYSTEM Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Restore RCS DNB parameter(s) to within limit. COLR DNB Limit = 2125 psig This event is complete when the BOP closes 1RC-3 and stabilizes RCS pressure, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 22 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 5 Page 2 of 2 Event

Description:

Spray valve fails open (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP AP/1/A/1700/044 Crew Response: 4.3 Verify 1RC-4 is closed. RNO: IF PORV is open, AND 1RC-4 has failed to close, THEN perform the following: A. __ Dispatch an operator to open 1DIB Panelboard breaker #24. B. __ Manually trip the reactor. C. __ Initiate AP/02 (Excessive RCS Leakage). 4.4 Verify 1RC-3 is closed. RNO: 1. __ IF RC pressure is uncontrollable, THEN GO TO Step 4.7. 2. __ IF 1RC-1 is selected to CLOSE, THEN maintain RC pressure within desired band with 1RC-1 in manual control. 3. __ GO TO Step 4.13. 4.13 Verify PZR heaters maintaining RCS pressure within desired band. 4.14 Notify SPOC to repair malfunctioning component.

4.15 Ensure requirements of following are met: __ TS 3.4.1 (RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits) __ TS 3.4.9 (Pressurizer) __ TS 3.4.12 (Low Temperature Overpressure Protection System) __ SLC 16.5.1 (Reactor Coolant System Vents) 4.16 WHEN repairs complete, THEN place following components in desired position for current plant conditions as determined by CR SRO: __ 1RC-1 __ 1RC-3 __ 1RC-4 __ PZR heater bank #1 __ PZR heater bank #2 __ PZR heater bank #3 __ PZR heater bank #4 4.17 __ WHEN directed by CR SRO, THEN EXIT this procedure. This event is complete when the BOP closes 1RC-3 and stabilizes RCS pressure, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 23 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 6 Page 1 of 1 Event

Description:

Lowering EHC pressure, Standby EHC pump fails to start (C: BOP,SRO) Time Position Applicant's Actions or Behavior SRO/BOP 1SA-3/E-2 Plant Response: 1SA-3/E-2 EHC Hydraulic Header Pressure Low Crew Response: SRO will direct the BOP to refer to the ARG: 1SA-3/E-2 NOTE: Standby pump starts at 1350 psig decreasing. 3.1 Verify standby pump is running. Examiner Note: Per AD-OP-ALL-1000, Conduct of Operations, Section 5.17.2 Expectations: Written procedures are not necessary for situations where: (3) Conditions exist which may require timely actions due to failure of automatic control systems. In this situation, the standby EHC pump should be started in order to prevent an automatic Turbine/Reactor trip due to low EHC pressure. This event is complete when the STBY EHC pump is started, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 24 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 1 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO OATC BOP Plant Response: Both MFWPs trip Reactor Trips MD EFDWPs do NOT start TD EFDWP overspeeds and trips Crew Response: SRO directs the OATC to perform IMAs and the BOP to perform a Symptom Check If the RCS saturates, the crew will perform Rule 2 (Loss of SCM) (Page 27) IMAs EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton. 3.2 Verify reactor power < 5% FP and decreasing. 3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed. 3.5 Verify RCP seal injection available. SYMPTOM CHECK The BOP will verify the following: Power Range NIs NOT < 5% Power Range NIs NOT decreasing Rule 1, ATWS/Unanticipated Nuclear Power Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) Rule 3, Loss of Main or Emerg FDW Rule 4, Initiation of HPI Forced Cooling (Inability to feed SGs and > 2300 psig, NDT limit reached, or PZR level > 375") Uncontrolled Main steam line(s) pressure decrease Rule 5, Main Steam Line Break CSAE Offgas alarms Process monitor alarms (RIA-40, 59,60), Area monitor alarms (RIA-16/17) None (SGTR Tab is entered when identified SG Tube Leakage > 25 gpm) BOP will perform Rule 3 due to a loss of ALL feedwater: (Page 26) SRO will review IMAs and transfer to the Subsequent Actions Tab. This event is complete as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 25 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 2 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC

SUBSEQUENT ACTIONS TAB Crew Response: The SRO will transfer to the Subsequent Actions tab of the EOP and review the Parallel Action (Yellow) page.(Page 44) The SRO will transfer to the Loss of Heat Transfer (LOHT) tab due to the loss of Main and Emergency feedwater. LOHT TAB 1. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. NOTE Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0°F. 2. IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4. 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW), AND any of the following exists: __ RCS pressure reaches 2300 psig OR NDT limit THEN GO TO Step 4. RNO: NOTE 1A1 RCP provides the best Pzr spray. 1. Reduce operating RCPs to one pump/loop. 2. WHEN any exists: __ EFDW or PSW SG feed flow has been re-established by existing Rules/Enclosures __ EFDW aligned from another unit __ Operator performing Rule 3 (Loss of Main or Emergency FDW) or Encl 5.27 (Alternate Methods for Controlling EFDW Flow) reports EFDW available THEN GO TO Step 50. Examiner Note: The SRO will remain at this point of the procedure until RCS pressure = 2300 at which time IAAT step 3 will apply which will direct the SRO to GO TO step 4 (Page 29). This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 26 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 3 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior BOP

Rule 3 Crew Response

1. Verify loss of MFDW and/or EFDW was due to any of the following: __ Turbine Building Flooding __ Actions taken to increase SG level due to Turbine Building Flooding RNO: GO TO Step 3. 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW), AND any of the following exist: __ RCS pressure reaches 2300 psig OR NDT limit THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling). 4. Start operable EFDW pumps, as required, to feed all intact SGs. 5. Verify any EFDW pump operating. [No EFDW pumps will be operating] RNO: GO TO Step 7. 7. Place in MANUAL and close: __ 1FDW-315 __ 1FDW-316 8. Verify both: __ Any CBP operating [None will be operating] __ TBVs available on an intact SG RNO: GO TO Step 16 16. Verify 1 TD EFDW PUMP is operable and available for manual start. RNO: __ GO TO Step 18. 18. Verify cross-tie with Unit 2 is desired. 19. Dispatch an operator to open: __ 2FDW-313 (2A EFDW Line Disch To 2A S/G X-Conn) __ 2FDW-314 (2B EFDW Line Disch To 2B S/G X-Conn) This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 27 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 4 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior BOP

OATC/BOP Rule 3 Crew Response: 20. Dispatch an operator to 1FDW-313 and have them notify the CR when in position. 21. Notify alternate unit to: A. __ Place both EFDW control valves in manual and closed. B. __ Start their TD EFDW PUMP. 22. IAAT SGs are NOT being fed from any source, AND PSW SG feed available, THEN establish SG feed from PSW using Encl 5.45 (PSW Feed and RCP Seals). 23. WHEN either exists: __ Operator is in position at 1FDW-313 __ Unit 1 TD EFDW PUMP has been manually started THEN continue. Examiner Note: EFW from another source will NOT be made available. Rule 3 progress will stop at this point. Rule 2 Crew Response: 1. IAAT all exist: __ Any THEN perform Steps 2 and 3 2. Stop all RCPs 3. Notify CRS of RCP status 4. Verify Blackout exists RNO: GO TO Step 6 This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 28 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 5 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior OATC/BOP

Rule 2 Crew Response: 6. Open 1HP-24 and 1HP-25 7. Start all available HPI pumps 8. GO TO Step 13 13. Open 1HP-26 and 1HP-27 14. Verify at least two HPI pumps are operating using two diverse indications RNO: GO TO Step 27 27. Verify at least two HPI pumps are operating RNO: only 28. Verify RCS pressure > 550 psig 29. IAAT either exists: __ LPI FLOW TRAIN A plus __ Only one THEN GO TO Step 34 30. Dispatch two operators to perform Encl 5.24 (Operation of ADVs) (PS) 31. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER A 32. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER B 33. Notify CRS: __ Suspend Rule 3 (Loss of Main or Emergency FDW) until directed by LOSCM tab __ Degraded HPI exists 34. EXIT This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 29 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 6 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP CT-2

LOHT TAB Crew Response:

Examiner Note: When the criteria for IAAT step 3 is met, the SRO will proceed to step 4: NOTE SCM may be lost when the PORV is opened. Transition to LOSCM tab is NOT required. 4. PERFORM Rule 4 (Initiation of HPI Forced Cooling). (Page 33)

5. Verify all: __ At least two HPI pumps operating [ONE HPI pump operating] __ Acceptable HPI flow exists in both HPI headers per Rule 4 (Initiation of HPI Forced Cooling) __ PORV open __ 1RC-4 open RNO: 1. IF any HPI pump is providing injection flow, THEN GO TO Step 7. 2. GO TO Step 12. 7. Verify SSF-ASW available. 8. Dispatch a licensed operator to perform Encl 5.34 (Aligning SSF-ASW for SG Feed). Examiner Note: Stop RO from leaving CR and notify them that Unit 2 will perform Encl 5.34. 9. Verify PSW supplying power to reactor vessel head and RCS loop vents. RNO: Locally close (Unit 1 Cable Rm): __ 1SKJ-08 (1RC-155/1RC-156) __ 1SKK-08 (1RC-157/1RC-158) __ 1SKL-08 (1RC-159/1RC-160) Examiner Note: After being notified as AO to close breakers for 1RC-155 through 1RC-160, Fire Timer 15 to close the breakers. This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 30 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 7 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP CT-3

LOHT TAB Crew Response: 10. Open: __ 1RC-155 __ 1RC-156 __ 1RC-157 __ 1RC-158 __ 1RC-159 __ 1RC-160 11. GO TO HPI CD tab. HPI CD TAB HPI Cooldown Tab 1. IAAT BWST level is < 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 2. IAAT either of the following exists: __ LPI FLOW TRAIN A plus LPI FLOW TRAIN B > 3400 gpm __ Only one LPI header in operation with header flow > 2900 gpm THEN GO TO LOCA CD tab. 3. Verify all of the following exist: __ PORV open __ 1RC-4 open __ Two HPI trains injecting __ CETCs < 640°F RNO: 1.__ IF RCS vents (hot leg and vessel head) are open, THEN GO TO Step 4. 4. Perform the following: __ Ensure all RBCUs in low speed. __ Open 1LPSW-18. __ Open 1LPSW-21. __ Open 1LPSW-24. 5. __ Initiate Encl 5.35 (Containment Isolation). This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 31 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 8 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP

HPI CD TAB Crew Response:

6. IAAT all the following exist: __ Any RBS pump operating

__ RB pressure < 3 psig __ < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months into event __ Reactor Engineering confirms Condition Zero or Condition One per RP/0/B/1000/018 (Core Damage Assessment) THEN stop all RBS pumps.

7. Start: __ A Outside Air Booster Fan __ B Outside Air Booster Fan 8. Notify Unit 3 to start: __ 3A Outside Air Booster Fan __ 3B Outside Air Booster Fan 9. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit. RNO: __ Select OFF for both digital channels on AFIS HEADER A. 10. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit. RNO: __ Select OFF for both digital channels on AFIS HEADER B. 11. Verify indications of SGTR > 25 gpm. RNO: GO TO Step 17. 17. IAAT any SG with a tube rupture that has NOT reached the level at which water enters the steam lines (per Encl 5.21 (Full Range SG Level For Water In Steam Lines)) approaches either of the following: __ 1000 psig __ Overfill: Any SCM < 0°F: Loss of SCM setpoint THEN perform Steps 18 - 20. RNO: GO TO Step 21. This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 32 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 9 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP

HPI CD TAB Crew Response:

21. IAAT RCS pressure is > 1000 psig, AND any of the following exist: __ A SG with a tube rupture is at the level at which water enters the steam lines (per Encl 5.21 (Full Range SG Level For Water In Steam Lines) __ A SG with a tube rupture approaches 1000 psig THEN open: __ 1RC-155 __ 1RC-156 __ 1RC-157 __ 1RC-158 __ 1RC-159 __ 1RC-160

22. Secure makeup to the LDST.

23. Notify Chemistry of the following: A. __Sample RCS boron hourly, or as often as possible, until MODE 5. B. __Letdown status. 24. IAAT Chemistry reports that boron sample CANNOT be obtained, THEN notify TSC to provide guidance to obtain boron sample. 25. Initiate determination of minimum required boron concentration for MODE 5 using either of the following: __ Reactor Engineer __ PT/1/A/1103/015 (Reactivity Balance Procedure) 26. IAAT required boron concentration for MODE 5 is determined, THEN initiate Encl 5.11 (RCS Boration). NOTE Encl 5.12 (ECCS Suction Swap to RBES) requests an LPI discharge sample which is representative of RBES boron after ECCS suction has been swapped to RBES.

27. IAAT ECCS suction is swapped to RBES, AND RBES boron is decreasing, THEN notify TSC. This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 33 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 10 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP

Rule 4 Crew Response: Rule 4 HPI Forced Cooling 1. Verify any HPI pump powered from 1TC, 1TD, or 1TE can be operated. 2. Open: __ 1HP-24 __ 1HP-25 3. Start all available HPI pumps. [C HPI Pump will NOT start] 4. Open: __ 1HP-26 __ 1HP-27 5. Open 1RC-4. 6. Verify flow exists in any HPI header.

7. Perform the following: A. __ Place 1RC-66 SETPOINT SELECTOR to OPEN. B. __ Depress 1RC-66 OPEN PERMIT pushbutton. 8. Verify at least two HPI pumps operating. RNO: 1. __ IF NO HPI pumps are operating, THEN: A. __ Stop all RCPs. B. __ Position 1RC-66 SETPOINT SELECTOR to HIGH. C. __ GO TO Step 14. 2. __ IF 1HP-26 is closed, AND either of the following exists: __ 1A HPI PUMP operating __ 1B HPI PUMP operating THEN open 1HP-410. 3. __ GO TO Step 10. 10. Verify flow exists in any HPI header. This event is complete when the SRO transfers to the HPI Cooldown tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 34 of 46 Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 11 of 11 Event

Description:

LOHT (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP

Rule 4 Crew Response: 11. Perform the following: A. __ Place 1RC-66 SETPOINT SELECTOR to OPEN. B. __ Depress 1RC-66 OPEN PERMIT pushbutton. 12. Verify > one RCP operating. NOTE 1A1 RCP provides the best Pzr spray and is preferred to be left running in case recovery from HPI forced cooling is performed and a Pzr bubble drawn. 13. Stop all but one RCP.

14. IAAT the following limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI pumps operating with 1HP-409 open Total flow of 950 gpm (incl. seal injection) THEN throttle HPI to maximize flow < flow limit. 15. De-energize all Pzr heaters.

16. Close 1HP-5.

17. Close: __ TBVs __ 1FDW-35 __ 1FDW-44 18. IAAT all HPI is lost, THEN: A. __ Stop all RCPs. B. __ Position 1RC-66 SETPOINT SELECTOR to HIGH. 19. __ WHEN directed by CRS, THEN EXIT. This event is complete when the SRO transfers to the HPI Cooldown tab, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 35 of 46 Rule 6 HPI HPI Pump Throttling Limits HPI must be throttled to prevent violating the RV-P/T limit. HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open. HPI must be throttlegpm/pump (including seal injection for A header) when only one HPI pump is operating in a header. Total HPI flow must be throttlegpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-en. Total HPI flow must be throttled < gpm when all the following exist: - LPI suction is from the RBES - piggyback is aligned - either of the following exist: only one piggyback valve is open (1LP-15 or 1LP-16) only one LPI pump operating HPI may be throttled under the following conditions: HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress: All the following conditions must exist: Core SCM > CETCs decreasing All the following conditions must exist: All WR NI Core SCM > Pzr level increasing SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit Maintagpm indicated/pump. This is an instrument error adjusted value that ensures a real value of gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 36 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level > [ acc] will ensure Pzr heater bundles remain covered. 1. Utilize the following as necessary to maintain desired Pzr level: 1A HPI Pump 1B HPI Pump 1HP-26 1HP- 1HP-etpoint or valve demand 1HP-5 IF 1HP-26 will NOT open, THEN throttle 1HP-aintain desired Pzr level. 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT. 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT. 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following: A. Open: 1CS-26 1CS-41 B. Position 1HP-14 to BLEED. C. Notify SRO. 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 37 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. IAAT 1C HPI PUMP is required, THEN perform Ste- GO TO Ste Open: 1HP-24 1HP-25 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 8. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following: A. IF three HPI pumps are operating, THEN secure 1B HPI PUMP. B. IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers. C. GO TO Ste Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 38 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-aintain desired Pzr level. Throttle the following as required to maintain desired Pzr level: 1HP-26 1HP- 1. IF at least two HPI pumps are operating, AND 1HP-26 will NOT open, THEN throttle 1HP-aintain desired Pzr level. 2. IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-NOT open, THEN throttle 1HP-aintain desired Pzr level.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 39 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IAAT LDST level CANNOT be maintained, THEN perform Step 11. GO TO Step 12. 11. Perform the following: Open 1HP-24. Open 1HP-25. Close 1HP-16. 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 13. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP. NOTE heater bundles remain covered. 12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 40 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-Unit 1 RC Bleed Transfer Pump Rm.). 14. IAAT two Letdown Filters are desired, THEN perform the following: Open 1HP- Open 1HP-18 15. IAAT all of the following exist: Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41} GO TO Step 35. 16. Open: 1CC- 1CC-8 1. Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system. 2. GO TO Step 35. Ensure only one CC pump running. 18. Place the non-running CC pump in AUTO. Verify both are open: 1HP-1 1HP-2 1. IF 1HP-1 is closed due to 1HP-3 failing to close, THEN GO TO Step 21. 2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21. GO TO Step 23. NOTE Verification of leakage requires visual observation of East Penetration Room. 21. Verify letdown line leak in East Penetration Room has occurred. GO TO Step 23. 22. GO TO Step 35.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 41 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. Monitor for unexpected conditions while restoring letdown. 24. Verify both letdown coolers to be placed in service. 1. IF 1A letdown cooler is to be placed in service, THEN open: 1HP-1 1HP-3 2. IF 1B letdown cooler is to be placed in service, THEN open: 1HP-2 1HP-4 3. GO TO Step 26. 25. Open: 1HP-1 1HP-2 1HP-3 1HP-4 26. Verify at least one letdown cooler is aligned. Perform the following: A. Notify CR SRO of problem. B. GO TO Step 35. Close 1HP-6. 28. Close 1HP- Verify letdown temperature < 125°F. 1. Open 1HP-13. 2. Close: 1HP-8 1HP-&11 3. IF any deborating IX is in service, THEN perform the following: A. Select 1HP-14 to NORMAL. B. Close 1HP-16. 4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 42 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Open 1HP-5. 31. Adjust 1HP-for gpm letdown. 32. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL. 33. Open 1HP-6. 34. Adjust 1HP-control desired letdown flow. NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level. 35. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown). 36. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following: A. Obtain SRO concurrence to reduce running HPI pumps. B. Secure the desired HPI pumps. C. Place secured HPI pump switch in AUTO, if desired. IAAT all the following conditions exist: Makeup from BWST NOT required LDST level > All control rods inserted Cooldown Plateau NOT being used THEN close: 1HP-24 1HP-25 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 43 of 46 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST. GO TO Ste WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following: A. Stop 1A BLEED TRANSFER PUMP. B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1 RC Bleed Transfer Pump Rm.). C. Close 1CS-46. D. Start 1A BLEED TRANSFER PUMP. E. Locally throttle 1CS-48 (1A BHUT Recirc) to obta- discharge pressure. F. Stop 1A BLEED TRANSFER PUMP. Verify two Letdown Filters in service, AND only one Letdown filter is desired. GO TO Step 42. 41. Perform one of the following: Place 1HP-ch to CLOSE. Place 1HP-18 switch to CLOSE. 42. WHEN directed by CR SRO, THEN EXIT this enclosure.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 44 of 46 Subsequent Actions EP/1 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All SWGR de-energized {13} GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer GO TO EHT tab. LOHT 6. Loss of heat transfer (including loss of all Main and Emergency FDW) GO TO LOHT tab. Heat transfer is or has been excessive GO TO EHT tab. EHT 8. Indications of SGTR gpm GO TO SGTR tab. SGTR Turbine Building flooding NOT caused by rainfall event GO TO TBF tab. TBF Inadvertent ES actuation occurred Initiate AP(Inadvertent ES Actuation). ES 11. Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 12. Power lost to all SWGR and any SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 13. RCS leakage > gpm with letdown isolated Notify plant staff that Emergency Dose Limits are in affect using PA system. EDL 14. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and NS(Reportability). NOTIFY Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 45 of 46 CRITICAL TASKS CT-1 Manual control of the spray valve (1RC-1) must be taken and the spray valve must be closed before tripping the reactor on low RCS pressure.

CT-2 HPI Forced Cooling must be established when the initiation criteria has been met.

CT-3 RCS Loop and Head vents must be opened to maximize HPI pump flow due to degraded HPI.

SAFETY: Take a Minute UNIT 0 (OSM) SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO) Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 895 100% Power 100% Power RCS Leakage: 0.01 gpm No WCAP Action EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO) Component/Train OOS Date/Time Restoration Required Date/Time TS/SLC # AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO) Primary Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%). 1RIA-3 and 5 removed from RB. Control Rod Movement PT (PT/1/A/0600/015 ) is to be performed for GP 1 ONLY. Secondary Feedwater valve DP selected to A1 and B2 for maintenance AMSAC/DSS bypassed ICS Diamond and FDW Masters are in HAND for performance of Control Rod Movement PT. 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. Reactivity Management (CR SRO) RCS Boron 83 ppmB Gp 7 Rod Position: 92% Withdrawn Batch additions as required for volume control. Human Performance Emphasis (OSM) Procedure Use and Adherence Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO ________________________ ________________________OATC ________________________ ________________________BOP Initial Conditions: Reactor Power = 100% Turnover: Feedwater valve DP selected to 1A1 and 1B2 for maintenance AMSAC/DSS bypassed Event No. Malfunction No. Event Type* Event Description 0a Override EBOP Fails to Auto Start 0b 0c 1 N: OATC, SRO 5 Minute Delithiation Using Deborating IX 2 MPS290 C: BOP, SRO (TS) 1C CCW Pump trips 3 MCS004 I: OATC, SRO Controlling NR Tave Fails HIGH (586ºF) 4 Override C: BOP, R: OATC, SRO (TS) 1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip 5 Override C: BOP, SRO Bearing Oil Header Pressure LOW, EBOP fails to AUTO Start 6 MSS010 Override M: ALL Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS 1HP-25 fails closed 7 * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 2 of 49 Scenario 2 Event Summary Event 1: The OATC will perform a 5 minute delithiation using the deborating IX using OP/1/A/1103/004C Deborating IXs, Encl. 4.4 Unit 1 Deborating IX For RCS De-lith (Rx At Power). Event 2: CCW pump 1C will trip. The crew should address OAC Alarms and determine that the 1C CCW pump has tripped. The SRO should recognize Tech Spec for LPSW accumulator low level. Vacuum will start to decrease until CCW pump 1D is started. Event 3: Controlling Tave will fail High causing ICS to insert control rods and increase feedwater flow. The crew should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to MANUAL and stabilize the plant before the reactor trips. Event 4: 1B MFWP thrust bearing temperature alarm will come in. Temperature will slowly increase requiring the crew to perform a manual power reduction to secure the 1B MFWP. Event 5: Turbine oil header pressure will start decreasing causing an alarm. The EBOP will have to be started manually to prevent a turbine trip. Event 6: Turbine oil header pressure will decrease again requiring a reactor/turbine trip but control rods will not insert automatically or manually from the control room. 1HP-25 will fail closed which will limit the number of operating HPIPs to two. Approximately 4 minutes after an operator is dispatched to open RPS breakers, the reactor will trip.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 3 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 1 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior SRO OATC

OP/1/A/1103/004C Crew response: SRO directs the OATC to perform OP/1/A/1103/004C Deborating IXs, Encl. 4.4 Unit 1 Deborating IX For RCS De-lith (Rx At Power). OP/1/A/1103/004C, Encl. 4.4 Rev 25 NOTE: This procedure affects reactivity management by placing IX and Letdown Filter in service causing possible RCS boron change. (R.M.) Unit 1 Deborating IX can affect RCS boron because it contains 1200 gal of borated water. (R.M.) NOTE: If IX boron is within acceptable limits, IX may be placed in service with minimal reactivity affects (no CRD movement). (R.M.) Cation resin is used for de-lith. Cation resin will NOT remove boron from RCS. (R.M.) 2.1 IF RCS < 100 ppm AND IX boron as listed in Demineralizer Log Sheet is more than + 5 ppm of current RCS boron but is within + 25 ppm of current RCS boron, perform the following: {7}: [NA] 2.1.1 Determine RCS boron change resulting from placing IX in service (assume 1200 gal addition at boron listed in Demineralizer Log Sheet). 2.1.2 Determine RCS makeup sources and volumes required to compensate for RCS boron changes per OP/1/A/1103/004 (Soluble Poison Control).

2.1.3 Go To Step 2.4. Examiner Note: RCS Boron is 83 ppm. This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 4 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 2 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1103/004C Crew response: NOTE: Cation resin is used for de-lith. Cation resin will NOT remove boron from RCS. (R.M.) If IX boron is within acceptable limits, IX may be placed in service with minimal reactivity affects. (R.M.) Acceptable 'Demineralizer Log Sheet' boron for placing IX in service without rinsing is determined as follows: (R.M.) {4} RCS Boron Concentration Acceptable Demin Log Sheet Value > 100 ppm + 50 ppm of current RCS boron < 100 ppm +5 ppm of current RCS boron 2.2 IF Unit 1 Deborating IX boron status is NOT acceptable to place in service, perform Enclosure 4.5 (Unit 1 Deborating IX Rinse To MWHUT) until acceptable boron results are achieved. (R.M.). [NA] 2.3 Unit 1 Deborating IX has acceptable boron status to be placed in service. (R.M.) NOTE: Placing an idle Letdown Filter in service can affect core reactivity by adding ~ 60 gals of water at a different boron concentration. (R.M.) {5} {6} 2.4 IF two Letdown Filters are available AND NOT already in service, perform the following: (R.M.) {6} 2.4.1 Review Component Boron Log for out-of-service Letdown Filter boron. 2.4.2 Determine RCS boron based on placing second Letdown Filter in service. 2.4.3 RCS boron ___83_____ ppm 2.4.4 IF RCS makeup is required to achieve acceptable boron, determine RCS makeup sources and volumes per OP/1/A/1103/004 (Soluble Poison Control). [NA] This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 5 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 3 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1103/004C Crew response: 2.5 Perform one of the following (for all applicable steps 2.1 through 2.4): Verify acceptable RCS boron. Ensure appropriate RCS makeup plans determined to ensure acceptable boron. 2.6 Perform one of the following: IF two Letdown Filters available, perform the following: Ensure 1HP-17 (1A LETDOWN FILTER INLET) switch to "OPEN" Ensure 1HP-18 (1B LETDOWN FILTER INLET) switch to "OPEN" IF only one Letdown Filter available, verify Letdown pressure < 105 psig. 2.7 IF RCS makeup is required to ensure acceptable boron, makeup per OP/1/A/1103/004 (Soluble Poison Control). [NA] NOTE: Anytime IX is placed in service CRD movement may result. (R.M.) 2.8 WHILE placing Unit 1 Deborating IX in service, monitor the following indications: (R.M.) {20} Appropriate ranged NIs Primary tank levels Neutron error CRD position IX run-time for proper chemistry control 2.9 Align Unit 1 Deborating IX for service: 2.9.1 Verify closed 1CS-32 & 37 (SPARE DEBOR IX INLET & OUTLET). 2.9.2 Ensure closed 1CS-26 (LETDOWN TO RC BHUT). {17}

2.9.3 Open 1CS-27 (DEBOR IX INLET). 2.9.4 Verify 1HP-15 Controller in "MANUAL". 2.9.5 Ensure open 1HP-16 (LDST MAKEUP ISOLATION). This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 6 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 4 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1103/004C Crew response: 2.10 Position 1HP-14 (LDST BYPASS) in "BLEED" to place Unit 1 Deborating IX in service. NOTE: Chemistry procedures require a minimum of 15 minutes flush for Deborating IXs.(R.M.) Steps 2.11, 2.12, 2.13 and 2.14 may be performed in any order. 2.11 IF sample desired by Chemistry AND Unit 1 Deborating IX will be in service for > 20 minutes, notify Chemist to begin flush for sample of Unit 1 Deborating IX effluent. (R.M.) ________________________ _____ Person Notified Date 2.12 IF unexpected changes are noted, perform the following: (R.M.) Continue enclosure to remove Unit 1 Deborating IX from service. Notify CRS for evaluation. 2.13 IF AT ANY TIME RCS makeup is required for RCS volume control, perform Section 3 (RCS Makeup With Unit 1 Deborating IX In Service). NOTE: Opening 1CS-26 will remove Unit 1 Deborating IX from service. 2.14 IF AT ANY TIME desired to reduce inventory, reduce RCS inventory (Bleed): 2.14.1 Open 1CS-26 (LETDOWN TO RC BHUT). 2.14.2 WHEN complete, close 1CS-26 (LETDOWN TO RC BHUT).

2.15 IF sample required by Chemistry AND Unit 1 Deborating IX has been in service for > 20 minutes, prior to completing run time ensure Chemist has sampled Unit 1 Deborating IX effluent. (R.M.) ________________________ _____ Person Notified Date This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 7 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 5 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1103/004C Crew response: 2.16 WHEN desired to remove Unit 1 Deborating IX from service, perform the following: 2.16.1 Position 1HP-14 (LDST BYPASS) to "NORMAL". 2.16.2 Ensure closed 1HP-16 (LDST MAKEUP ISOLATION).

2.16.3 Perform one of the following: (R.M.) Verify correct IX run time per Step 1.2. Notify Chemistry for evaluation. ________________________ _____ Person Notified Date 2.16.4 Reset 1HP-15 Controller for Normal Operation.

2.16.5 Close 1CS-27 (DEBOR IX INLET). 2.16.6 Open 1CS-26 (LETDOWN TO RC BHUT).

2.17 Record IX use in Narrative Log. NOTE: 1B Letdown Filter is the preferred filter to leave in service for ALARA. 2.18 IF desired, remove one Letdown Filter from service: 2.18.1 Verify > 10 minutes since normal Letdown alignment. (R.M.) {5}

2.18.2 Perform one of the following: Position 1HP-17 (1A LETDOWN FILTER INLET) switch to "CLOSE". Position 1HP-18 (1B LETDOWN FILTER INLET) switch to "CLOSE". 2.18.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log. (R.M.) {6}

This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 8 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 6 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1103/004C Crew response: 2.19 IF Unit 1 Deborating IX will NOT be used within the next seven days, perform the following: (R.M.) NOTE: IA supply valves should be closed on idle IX(s) to reduce chance of placing wrong IX in service due to human error. (R.M.) {8} 2.19.1 Close IA-3092 (1CS-27 IA Isolation). (A-2-Rm 214) 2.19.2 Bleed off pressure from operator using petcocks. (A-2-Rm 214) NOTE: Petcock should be left in the throttled position to ensure pressure does NOT build up over time. 2.19.3 Ensure petcock left in the throttled position.

2.19.4 Place a "T/O SHEET" CR tag on 1CS-27 (DEBOR IX INLET) switch. 2.20 Record in Demineralizer Log Sheet for Unit 1 Deborating IX either of the following: (R.M.) IF Unit 1 Deborating IX sample was NOT taken, record current RCS boron. IF Unit 1 Deborating IX sample was taken, record IX effluent. This event is complete when the de-lith is complete or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 9 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 2 Page 1 of 2 Event

Description:

CCW pump trip (C, BOP, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/BOP OP/1/A/1104/012 A Plant Response: OAC Alarms: LPSW LEAKAGE ACCUMULATOR LEVEL LO LO (< 20 inches) 1C CCW LOCA/LS OFF ESV Tank Vacuum HI Condenser Vacuum will start decreasing Crew Response:

Examiner Note: The OAC LPSW Leakage Accumulator LO LO condition is TS 3.7.7. Condition B entry criteria. This alarm will clear when the D CCW pump is started. The crew should recognize the need to start the 1D CCW pump and position the LOCA Load Shed select switch to a running CCW pump. OP/1/A/1104/012 A: Rev 18 2.1 Verify seal water aligned to CCW Pump to be started per OP/0/A/1104/052 (SSW System). NOTE: Do NOT operate CCW Pumps in the same header until adjacent CCW Pump discharge valves have fully repositioned to prevent CCW Pump discharge valve malfunction. {3} 2.2 IF this is the first CCW Pump to be started, verify closed CCW Pump discharge valves on adjacent CCW Pumps. 2.3 Verify closed discharge valve on CCW Pump to be started. This event is complete when a CCW pump is started in the same header as the CCW pump that tripped and the Tech Spec determination has been made or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 10 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 2 Page 2 of 2 Event

Description:

CCW pump trip (C, BOP, SRO)(TS) Position Applicant's Actions or Behavior SRO/BOP OP/1/A/1104/012 A Crew Response: NOTE: 20% open. ESV Tank low vacuum alarms may occur during CCW Pump start. {1} LPSW Leakage Accumulator level is a function of LPSW System pressure. When CCW Pump status is changed, LPSW Leakage Accumulator level may exceed the limits of SR 3.7.7.1 until LPSW system pressure stabilizes. As a result, momentary entry into TS 3.7.7 Condition 'B' may be necessary. 2.4 Start desired CCW Pump: ____________. 2.5 Verify CCW Pump discharge valve opens.

2.6 Ensure CCWP LOAD SHED DEFEAT switch is positioned to a running CCW Pump. TS 3.7.7 LOW PRESSURE SERVICE WATER (LPSW) SYSTEM Condition B (7 days) Restore the LPSW WPS to OPERABLE status. This event is complete when a CCW pump is started in the same header as the CCW pump that tripped and the Tech Spec determination has been made or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 11 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 1 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC CT-1 AP/1/A/1700/028 Plant Response: 587.1F Controlling Tave Chessell dis587.1F 1SA-2/B4 (RC Average Temperature High/Low) 1SA-2/A12 ICS Tracking 1SA-2/C11 ICS Loss of OAC CTP Signal Controls will insert and FDW flow will increase RCS pressure will decrease Crew Response: When the Statalarms are received, the candidates should utilize the "Plant Transient Response" process to stabilize the plant. Verbalize to the CRS reactor power level and direction of movement. Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant. (decrease FDW) Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level. The CRS should: Refer to AP/28, ICS Instrument Failures Ensure SPOC is contacted to repair the failed instrument. . AP/1/A/1700/028, ICS Instrument Failures Rev 20 4.1 Provide control bands as required. (OMP 1-18 Att. I) OMP 1-18 Attachment I: 1. Plant Conditions Stable or TPB < Pre-transient Conditions NI Power + 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%. Current Tave + 2 oF. Current SG Outlet Pressure + 10 PSIG (N/A) Delta Tc 0 oF + 2 oF. This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 12 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 2 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/028 Crew Response: 4.2 Initiate notification of the following: __ OSM to reference the following: OMP 1-14 (Notifications) Emergency Plan __ STA RNO: GO TO Step 4.5. 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan. 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6: OAC alarm video OAC display points Control Board indications SPOC assistance, as needed 4.6 GO TO the applicable section per the following table: Section Failure 4A RCS Temperature AP/1/A/1700/028, Section 4A, RCS Temperature Failure NOTE If Tave instrument circuit failed high, the following may have occurred depending on initial ICS station status: Unit to TRACK due to Rx Cross Limits Control Rod insertion Feedwater flow increase If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status: Unit to TRACK due to Rx Cross Limits Control Rod withdrawal Feedwater flow decrease Feedwater re-ratio This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 13 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 3 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

AP/1/A/1700/028 Crew Response: 1. Ensure the following in HAND: __ 1A FDW MASTER __ 1B FDW MASTER 2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following: __ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function). __ Investigate and repair the failed RCS temperature instrumentation. 4. PERFORM an instrumentation surveillance using applicable table in Encl 5.2 (ICS Instrument Surveillances) for the failed instrument. 5. Verify instrumentation surveillance in Encl 5.2 (ICS Instrument Surveillances was performed satisfactorily as written. RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and OP/1/A/1105/014 (Control Room Instrumentation Operation And Information). 6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have Been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto). This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 14 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 1 of 4 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC/BOP AP/1/A/1700/029 Plant response: OAC Alarm O1A0928 FWPT 1B ACTIVE THRUST BEARING TEMP Crew Response: Refer to OAC Alarm Response for O1A0928 for HI-HI temperature > 200°F HI-HI: 1) If temperature cannot be maintained below HI-HI setpoint, refer to OP/1/A/1106/002 B (FDWPT Operation) to remove FDWP from service 2) Refer to OP/1/A/1102/004 (Operation at Power) 3) Notify Component Engineer Booth cue: If contacted, respond as the Component Engineer and recommend that the 1B FDWPT be removed from service as soon as possible. Booth cue: If contacted, respond as the SM and recommend reducing power using AP/1/A/1700/029 (Rapid Unit Shutdown) to remove the 1B FDWPT from service as soon as possible Booth cue: If an AO is dispatched, he should report that there is a strong scorching oil smell around the 1B FDWP and the bearing housing is hot to the touch. Examiner Note: The SRO will refer to AP/1/A/1700/029 (Rapid Unit Shutdown) to reduce power to below 65% in order to secure the 1B MFW Pump. The BOP should refer to OP/1/A/1106/002 B (FDWPT Operation) (Page 16) AP/1/A/1700/029 (Rapid Unit Shutdown)Rev 13 NOTE The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist. 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown). 4.2 Announce AP entry using the PA system. This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 15 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 2 of4 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC BOP AP/1/A/1700/029 Crew Response: 4.3 IAAT both of the following apply: __ It is desired to stop power decrease __ CTP > 18 % THEN perform Steps 4.4 - 4.7. RNO: GO TO Step 4.8. Examiner Note: Power decrease will be stopped when lowered to < 65%. 4.4 Verify ICS in AUTO. [ICS is in MANUAL] RNO: 1. __ Stop manual power reduction. 2. __ GO TO Step 4.6. NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown. 4.6 Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure. 4.7 WHEN conditions permit, THEN perform one of the following: __ Depress MAXIMUM RUNBACK to resume power reduction. __ GO TO appropriate operating procedure for continued operation. 4.8 Verify ICS in AUTO. [ICS is in MANUAL] RNO: 1. __ Initiate manual power reduction to desired power level. 2. __ GO TO Step 4.10. 4.10 Verify both Main FDW pumps running. This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 16 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 3 of 4 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC BOP

AP/1/A/1700/029 Crew Response: NOTE 1B Main FDW Pump is the preferred pump to be shutdown first. To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise. To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise. 4.11 Adjust bias for first Main FDW pump desired to be shutdown until Suction remaining Main FDW pump suction flow. 4.12 WHEN core thermal power is < 65% FP, THEN continue. Examiner Note: when < 65% power, IAAT step 4.3 applies which directs the performance of step 4.4-4.7 on the previous page. OP/1/A/1106/002 B OP/1/A/1106/002 B (FDWPT Operation) Encl 4.9 Shutdown Of 1B FDWPT Rev 38 2.1 IF this is first FDWPT to be shutdown: [It is the 1st FDWPT to be shutdown] 2.1.1 Verify 1SA-5/E-1 (FWPT / RX TRIP ALERT) NOT in alarm. 2.1.2 Position the following: A. Ensure 1FDW-53 (1A FDWP RECIRC CONTROL) in "MANUAL" B. Ensure Closed 1FDW-53 (1A FDWP RECIRC CONTROL) C. Ensure 1FDW-65 (1B FDWP RECIRC CONTROL) in "MANUAL" D. Ensure Closed 1FDW-65 (1B FDWP RECIRC CONTROL) 2.2 IF in FDW Heatup, perform the following: [N/A] This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 17 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 4 of 4 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC/BOP OP/1/A/1106/002 B Crew Response: 2.3 Ensure running 1B FDWP AUXILIARY OIL PUMP. 2.4 IF 1A FDWP is NOT isolated for maintenance, start 1A FDWP AUXILIARY OIL PUMP. 2.5 Place 1B MAIN FDW PUMP (ICS) in "HAND".

2.6 Slowly run 1B MAIN FDW PUMP demand signal to minimum. 2.7 IF required, verify 1A FDWPT picks up load by observing FDWPT suction flow instruments. 2.8 Immediately trip 1B FDWPT from FW TURB 1B TRIP/RESET switch. Verify closed 1B FDWPT HP stop valve Verify closed 1B FDWPT LP stop valve TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF) Conditions A-E (7 days) Restore to operable status Once Reactor Power is reduced to below 85% the SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies. Conditions A-E should be entered. This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 18 of 49 Op-Test No.:ILT48 Scenario No.: 2 Event No.: 5 Page 1 of 1 Event

Description:

Bearing Oil Header Pressure LOW, EBOP fails to AUTO Start ( C: BOP, SRO) Time Position Time SRO/ BOP 1SA-3/E7 Plant Response: 1SA-3/E7 BEARING OIL HEADER PRESSURE LOW OAC alarm TGOP RUNNING Crew Response: 1SA-3/E7 BEARING OIL HEADER PRESSURE LOW Rev 59 3.1 Verify Turning Gear Oil Pump has started. 3.2 Check BEARING HEADER pressure gauge at Turbine Front Standard. NOTE: EBOP will also start on a loss of power to Turning Gear Oil Pump Examiner Note: EBOP will fail to start automatically. 3.3 IF BEARING HEADER pressure < 15 psig, verify EBOP is on. 3.3.1 IF EBOP has NOT started, start EBOP. [BOP will start the EBOP] 3.4 IF BEARING HEADER pressure is still < 15 psig: 3.4.1 TRIP THE TURBINE 3.4.2 Place Turbine Turning Gear switch in PULL TO LOCK. 3.5 Check all 12 bearings and verify oil drain flow. 3.6 Check Main Shaft Pump discharge and suction pressure. 3.7 Check Oil Cooler flow sight glass for flow indication and for cooler leakage.

3.8 Check booster pump valve and pressure switch set points. Examiner Note: Approximately one minute after the EBOP is started, it will trip on overload. When Bearing Header Pressure decreases to below 15 psig, the crew should trip the reactor and turbine which will start the next event. This event is complete when the OATC attempts to trip the reactor, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 19 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 1 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior SRO OATC BOP EOP Plant response: 1SA-3/E7 BEARING OIL HEADER PRESSURE LOW Statalarm 1SA-01/A1, B1, C1, D1 (RP Channel A-D Trip) Crew response: Recognize that the Reactor did NOT trip Attempt to trip the reactor manually SRO will direct the OATC to perform IMAs and the BOT to perform a symptom check. IMAs EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton. [Will not trip the reactor] 3.2 Verify reactor power < 5% FP and decreasing. RNO: GO TO Rule 1 (ATWS/Unanticipated Nuclear Power Production). (Page 20) SYMPTOM CHECK The BOP will verify the following: Power Range NIs NOT < 5% Power Range NIs NOT decreasing Rule 1, ATWS/Unanticipated Nuclear Po Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) Rule 3, Loss of Main or Emerg FDW Rule 4, Initiation of HPI Forced Cooling (Inability to feed SGs and > 2300 psig, N limit reached, or PZR level > 375") Uncontrolled Main steam line(s) pressure decrease Rule 5, Main Steam Line Break CSAE Offgas alarms Process monitor alarms (RIA-40, 59,60), Area monitor alarms (RIA-16/17) None (SGTR Tab is entered when identif SG Tube Leakage > 25 gpm) BOP will inform the SRO: No symptoms to report except that Power Range NIs are > 5%, OATC is performing Rule 1. This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 20 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 2 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior OATC

RULE 1 CREW RESPONSE: Rule 1 2. Initiate manual control rod insertion to the IN LIMIT. 3. Verify Main FDW is feeding the SGs. RNO: __ Trip the turbine-generator. 4. __ Notify CRS to GO TO UNPP tab. (Page 21)

5. Open: __ 1HP-24 __ 1HP-25 [Fails Closed]

RNO: IF both are closed: __ 1HP-24 __ 1HP-25 THEN GO TO Step 32. 6. Ensure at least one operating: __ 1A HPI PUMP __ 1B HPI PUMP [Crew should NOT start due to 1HP-25 being failed closed]

Examiner Note: Per Rule 6 HPI, HPI pump operations must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-24) is open. 7. Start 1C HPI PUMP.

8. Open: __ 1HP-26 __ 1HP-27 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 21 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 3 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior OATC CT-2 SRO/BOP RULE 1 Crew Response: 9. Dispatch one operator without wearing Arc Flash PPE to open 600V CRD breakers: {33} __ 1X9-5C (U-1 CRD Norm Fdr Bkr) (U1 Equipment Rm) __ 2X1-5B (U-1 CRD Alternate Fdr Bkr) (T-3/Dd-28) Examiner Note: When the operator is dispatched to open CRD breakers, a 4 minute time will be initiated to open the CRD breakers.

10. Verify only two HPI pumps operating. 11. EXIT. UNPP Tab 1. Ensure Rule 1 (ATWS / Unanticipated Nuclear Power Production) is in progress or complete. 2. Verify Main FDW is operating and in AUTO.

3. IAAT Main FDW is NOT operating, THEN: A. __ Trip the turbine-generator. B. __ Start all available EFDW pumps. C. __ Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. 4. __ IAAT all power range NIs are < 5% FP, THEN perform Steps 5 - 6. RNO: GO TO Step 7. 5. Depress turbine TRIP pushbutton. 6. Verify all turbine stop valves closed. This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 22 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 4 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP UNPP Tab Crew Response: 7. Verify any wide range NI > 1% FP. 8. Open 1RC-4. 9. Verify 1HP-5 open.

10. Maximize letdown using 1HP-7 while maintaining letdown temperature < 120°F.

11. Verify Main FDW available. 12. Adjust Main FDW flow as necessary to control RCS temperature. 13. Verify overcooling in progress. [Over cooling is NOT in progrerss] RNO: GO TO Step 16. 16. Secure makeup to LDST. {8} 17. WHEN all wide range NIs are <1% FP, AND decreasing, THEN continue. 18. Control RCS temperature as follows: __ Tave < 555°F- Adjust SG pressure as necessary to stabilize RCS temperature using either: TBVs Dispatch two operators to perform Encl 5.24 (Operation of the ADVs). (PS) __ Tave > 555°F Utilize Rule 7 (SG Feed Control) to control SG feed rate as necessary to maintain cooldown rate within Tech Spec limits during the approach to the SG Level Control Point. 19. __ Throttle HPI per Rule 6 (HPI). (Page 25) 20. __ WHEN RCS pressure < 2300 psig, THEN continue. This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 23 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 5 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP UNPP Tab Crew Response: 21. Verify PORV closed. 22. Adjust letdown flow as desired. 23. Verify RCP seal injection available. 24. GO TO Subsequent Actions. SUBSEQUENT ACTIONS Tab 4.1 Verify all control rods in Groups 1 - 7 fully inserted. 4.2 Verify Main FDW in operation.

4.3 Verify either: __ Main FDW overfeeding causing excessive temperature decrease. __ Main FDW underfeeding causing SG level decrease below setpoint. RNO: GO TO Step 4.5. 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8. RNO: GO TO Step 4.9. 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either: __ TBVs __ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) (PS) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating. 4.11 GO TO Step 4.14. 4.14 Verify both are closed: __ 1MS-17 __ 1MS-26 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 24 of 49 Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 6 of 6 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP SUBSEQUENT ACTIONS Tab Crew Response: 4.15 Verify ES is required. RNO: 1. __ Initiate Encl 5.5 (Pzr and LDST Level Control) (Page 26) 2. __ GO TO Step 4.17. 4.17 Open: __ PCB 20 __ PCB 21 4.18 Verify Generator Field Breaker open. 4.19 Verify EXCITATION is OFF. 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure > 90 psig. 4.21 Verify ICS/NNI power available. 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized. 4.23 Verify both SGs > 550 psig. 4.24 Verify Main FDW operating. 4.25 Verify any RCP operating. 4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete. RNO: Ensure SGs approaching 25" - 35" [55" - 65" acc] S/U level. 4.27 Place switches in CLOSE: __ 1FDW-31 __ 1FDW-40 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 25 of 49 Rule 6 HPI HPI Pump Throttling Limits HPI must be throttled to prevent violating the RV-P/T limit. HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open. one HPI pump is operating in a header. ection when 1A and 1B HPI pumps are operating with 1HP-409 open. Total HPI flow must be throttled < 750 gpm when all the following exist: - LPI suction is from the RBES - piggyback is aligned - either of the following exist: only one piggyback valve is open (1LP-15 or 1LP-16) only one LPI pump operating HPI may be throttled under the following conditions: HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress: All the following conditions must exist: Core SCM > 0 CETCs decreasing All the following conditions must exist: All WR NI Core SCM > 0 Pzr level increasing CRS concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit Maintagpm indicated/pump. This is an instrument error adjusted value that ensures a real value of gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 26 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level > [ acc] will ensure Pzr heater bundles remain covered. 1. Utilize the following as necessary to maintain desired Pzr level: 1A HPI Pump 1B HPI Pump 1HP-26 1HP-7 1HP-120 setpoint or valve demand 1HP-5 IF 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain desired Pzr level. 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT. 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT. 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following: A. Open: 1CS-26 1CS-41 B. Position 1HP-14 to BLEED. C. Notify SRO. 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 27 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. IAAT 1C HPI PUMP is required, THEN perform Steps 7 - 9. GO TO Step 10. 7. Open: 1HP-24 1HP-25 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end). F. GO TO Step 8. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following: A. IF three HPI pumps are operating, THEN secure 1B HPI PUMP. B. IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers. C. GO TO Step 9.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 28 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level. 9. Throttle the following as required to maintain desired Pzr level: 1HP-26 1HP-27 1. IF at least two HPI pumps are operating, AND 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain desired Pzr level. 2. IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 29 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. IAAT LDST level CANNOT be maintained, THEN perform Step 11. GO TO Step 12. 11. Perform the following: Open 1HP-24. Open 1HP-25. Close 1HP-16. 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end). F. GO TO Step 13. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP. NOTE Maintaining Pzr level > 100" [180" acc] will ensure Pzr heater bundles remain covered. 12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 30 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.). 14. IAAT two Letdown Filters are desired, THEN perform the following: Open 1HP-17. Open 1HP-18 15. IAAT all of the following exist: Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41} GO TO Step 35. 16. Open: 1CC-7 1CC-8 1. Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system. 2. GO TO Step 35. 17. Ensure only one CC pump running. 18. Place the non-running CC pump in AUTO. 19. Verify both are open: 1HP-1 1HP-2 1. IF 1HP-1 is closed due to 1HP-3 failing to close, THEN GO TO Step 21. 2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21. 20. GO TO Step 23. NOTE Verification of leakage requires visual observation of East Penetration Room. 21. Verify letdown line leak in East Penetration Room has occurred. GO TO Step 23. 22. GO TO Step 35.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 31 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. Monitor for unexpected conditions while restoring letdown. 24. Verify both letdown coolers to be placed in service. 1. IF 1A letdown cooler is to be placed in service, THEN open: 1HP-1 1HP-3 2. IF 1B letdown cooler is to be placed in service, THEN open: 1HP-2 1HP-4 3. GO TO Step 26. 25. Open: 1HP-1 1HP-2 1HP-3 1HP-4 26. Verify at least one letdown cooler is aligned. Perform the following: A. Notify CR SRO of problem. B. GO TO Step 35. 27. Close 1HP-6. 28. Close 1HP-7. 29. Verify letdown temperature < 125°F. 1. Open 1HP-13. 2. Close: 1HP-8 1HP-9&11 3. IF any deborating IX is in service, THEN perform the following: A. Select 1HP-14 to NORMAL. B. Close 1HP-16. 4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 32 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30. Open 1HP-5. 31. Adjust 1HP-7 for 20 gpm letdown. 32. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL. 33. Open 1HP-6. 34. Adjust 1HP-7 to control desired letdown flow. NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level. 35. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown). 36. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following: A. Obtain SRO concurrence to reduce running HPI pumps. B. Secure the desired HPI pumps. C. Place secured HPI pump switch in AUTO, if desired. 37. IAAT all the following conditions exist: Makeup from BWST NOT required LDST level > All control rods inserted Cooldown Plateau NOT being used THEN close: 1HP-24 1HP-25 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 33 of 49 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST. GO TO Step 40. 39. WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following: A. Stop 1A BLEED TRANSFER PUMP. B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.). C. Close 1CS-46. D. Start 1A BLEED TRANSFER PUMP. E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure. F. Stop 1A BLEED TRANSFER PUMP. 40. Verify two Letdown Filters in service, AND only one Letdown filter is desired. GO TO Step 42. 41. Perform one of the following: Place 1HP-17 switch to CLOSE. Place 1HP-18 switch to CLOSE. 42. WHEN directed by CR SRO, THEN EXIT this enclosure.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 34 of 49 Enclosure 5.9 Extended EFDW Operation Rev 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1. Monitor EFDW parameters on EFW graphic display. 2. IAAT UST level is < 4', THEN GO TO Step 120. 3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4 - 7. GO TO Step 8. 4. Place EFDW control valve on SG with NO EFDW flow to MANUAL and closed: 1A SG 1B SG 1FDW-315 1FDW-316 5. Locally open: 1FDW-313 (1A EFDW Line Disch To 1A S/G X-Conn) (T-1, 1' N of M-16, 18' up) 1FDW-314 (1B EFDW Line Disch To 1B S/G X-Conn) (T-1, 3' S of M-24, 10' up) 6. Ensure a MD EFDWP is operating. 7. Throttle EFDW control valve on SG with NO EFDW flow to establish appropriate level per Rule 7 (SG Feed Control): 1A SG 1B SG 1FDW-315 1FDW-316 8. Perform as required to maintain UST level > 7.5': Makeup with demin water. Place CST pumps in AUTO. 9. IAAT all exist: Rapid cooldown NOT in progress MD EFDWP operating for each available SG EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 35 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. Verify 1 TD EFDW PUMP operating. GO TO Step 12. 11. Start TD EFDWP BEARING OIL COOLING PUMP. NOTE Loss of the condensate system for es results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open. If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required. 12. Notify CR SRO to set priority based on the NOTE above and EOP activities. 13. IAAT it is determined that condensate flow CANNOT be restored within 25 minutes, THEN GO TO Step 90. 14. Verify any HWP operating. 1. Place all CBP control switches to OFF. 2. GO TO Step 20. 15. Verify any CBP operating. 1. IF AP/11 restarted a HWP, THEN GO TO Step 22. 2. GO TO Step 41. 16. Verify 1C COND BOOSTER PUMP operating.{12} 1. Ensure only one CBP is operating. 2. GO TO Step 18. 17. Stop: {12} 1A COND BOOSTER PUMP 1B COND BOOSTER PUMP 18. Ensure only one HWP is operating. 19. GO TO Step 44.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 36 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20. Verify a loss of power event caused the loss of the secondary system. GO TO Step 24. 21. Ensure AP/11 (Recovery From Loss of Power) is in progress. 22. WHEN AP/11 (Recovery From Loss of Power) has restored 600v load centers, AND a HWP is operating, THEN dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21) 23. WHEN notified that all CBP Aux Oil pumps are operating, THEN GO TO Step 41. 24. Place all HWP control switches to OFF. 25. Place all CBP control switches to OFF. 26. Place valve switches to close until valve travel is initiated: 1FDW-4 1FDW-9 Continue. 27. Start: 1A FDWP AUXILIARY OIL PUMP 1B FDWP AUXILIARY OIL PUMP Start as necessary: 1A FDWP EMERGENCY BRNG OIL PUMP 1B FDWP EMERGENCY BRNG OIL PUMP 28. Verify both: FWPT A BRG LUBE OIL PRESS > 4 psig FWPT B BRG LUBE OIL PRESS > 4 psig 1. IF both FDW pumps have BRG LUBE OIL PRESS < 4 psig, THEN GO TO Step 90. 2. Perform for the FDW pump that has BRG LUBE OIL PRESS < 4 psig: Close 1FDW-1 for 1A FDW pump. Close 1FDW-6 for 1B FDW pump. 29. Place in MANUAL and close: 1FDW-53 1FDW-65 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 37 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30. Place 1C-10 FAIL SWITCH in MANUAL. 31. Close 1C-10. 32. Make plant page to clear basement and third floor of non-essential personnel. 33. Start one HWP. 34. Verify < 25 minutes elapsed since loss of condensate. 1. Stop all HWPs. 2. GO TO Step 90. 35. Throttle 1C-10 controller 10% open to satisfy 25 minute system restart criteria. 36. WHEN FWP SUCT HDR PRESS (1VB3) g, THEN open 1C-10. 37. Place 1C-10 FAIL SWITCH in FAIL OPEN. 38. Dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21) 39. Maximize total recirc flow < 1200 gpm with one of the following: 1FDW-53 1FDW-65 40. WHEN five minutes have elapsed, AND notified that all CBP Aux Oil pumps are operating, THEN continue procedure. 41. Start a second HWP. 42. Start 1C COND BOOSTER PUMP. {12} Start one available CBP. 43. Stop one operating HWP. 44. Place control switch for one secured HWP in AUTO. 45. Place control switch for one secured CBP in AUTO.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 38 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 46. Perform the following: Position HWP LOAD SHED DEFEAT switch to a running HWP. Position CBP LOAD SHED DEFEAT switch to a running CBP. 47. Place in MANUAL: 1FDW-53 1FDW-65 48. Establish 2300 - 6000 gpm total recirc flow with one of the following: 1FDW-53 1FDW-65 49. IAAT UST level CANNOT be maintained > 8.5', THEN locally open 1C-899 (Cond Recirc To UST Riser Throttle) (T-1/J-23). 50. IAAT UST level increases > 11', THEN perform as required: Throttle demin water Locally throttle 1C-899 (Cond Recirc To UST Riser Throttle) (T-1/J-23) 51. Verify closed: 1FDW-4 1FDW-9 GO TO Step 58.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 39 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 52. Position switches in CLOSE: 1FDW-33 1FDW-31 1FDW-42 1FDW-40 53. Ensure closed: 1FDW-33 1FDW-31 1FDW-42 1FDW-40 54. Locally open: 1FDW-5 (1A FDWP Discharge Bypass) (T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up) 55. WHEN FWP DISCH HDR PRESS (1VB3) is approximately equal to either of the following: O1A1014 (FDWP 1A DISCHARGE PRESS) O1A1391 (FDWP 1B DISCHARGE PRESS) THEN open: 1FDW-4 1FDW-9 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 40 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 56. Locally close: 1FDW-5 (1A FDWP Discharge Bypass) (T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up) NOTE Windmill protection may have required closure of FDW pump suction valve. 57. Verify open: 1FDW-1 1FDW-6 1. IF required, notify the WCC SRO to initiate investigation. 2. Note on Turnover sheet that FDW pump associated with closed valve is not available for use until problem resolved. 58. IAAT it is desired to re-establish Main FDW, THEN initiate Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System). 59. IAAT EFDW has been secured per Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System), THEN EXIT.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 41 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 60. WHEN UST level is < 4', THEN dispatch two operators to perform Encl 5.24 (Operation of the ADVs) in preparation for loss of vacuum. (PS) 61. Verify power available to 1V-186 by using valve position indicating light. Dispatch an operator to be in position at 1V-186 (Vacuum Breaker) (T-3, catwalk at 1C2 waterbox). NOTE 1C-573 will be closed after vacuum is broken. 62. Dispatch an operator with a safety harness to 1C-573 (MD EFDWPs Suction From UST) (T-1, SW of E-24, 8' above floor) to: Unlock and remove chain from 1C-573. Establish communication with Control Room. 63. WHEN UST level is < 3', THEN continue. 64. Open 1V-186. Notify operator to open 1V-186 (Main Condenser Vacuum Breaker) (T-3, catwalk at 1C2 waterbox). 65. Stop all main vacuum pumps. 66. Stop all CBPs. 67. Stop all HWPs. 68. Close: 1MS-47 1AS-40 Dispatch an operator to close: 1MS-49 (1A CSAE Steam Supply) (T-3/F-26) 1MS-58 (1B CSAE Steam Supply) (T-3/G-26) 1MS-67 (1C CSAE Steam Supply) (T-3/H-26)

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 42 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE 1C-573 is open unless Step 75 has been completed. While EFDW is secured, a transfer to LOHT is required only when directed by this enclosure or Rule 4 (Initiation of HPI Forced Cooling) conditions are met. 69. IAAT UST level is < 1', AND 1C-573 (MD EFDWPs Suction From UST) is open, THEN perform Steps 70 - 71. GO TO Step 72. 70. Perform the following: Stop 1A MD EFDWP. Stop 1B MD EFDWP. 71. Verify 1C-391 open. 1. Stop 1TD EFDW PUMP. 2. Close: 1FDW-315 1FDW-316 72. Perform the following: A. Reduce MD EFDWP flow to < 440 gpm per pump. B. Notify crew of MD EFDWP flow limit while aligned to hotwell. NOTE Vacuum gage or computer can be used. Vacuum is broken when either start to flat line. Do NOT change scale on computer trend once started. 73. WHEN vacuum is broken, THEN continue.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 43 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 74. IAAT MD EFDWPs are operating, OR available to operate, THEN PERFORM Steps 75 - 77. GO TO Step 78. 75. Locally close 1C-573 (MD EFDWPs Suction From UST) (T-1, SW of E-24, 8' above floor). 1. IF 1TD EFDW PUMP is operating, OR operable, THEN GO TO Step 78. 2. IF NO EFDW pumps are operating, THEN: A. Notify CR SRO that a LOHT exists from loss of EFDW suction source. B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit. C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3. 76. Verify MD EFDWPs were stopped due to UST level < 1'. GO TO Step 78. 77. Perform the following: A. Restart all MD EFDWPs that were stopped due to UST level < 1'. B. Resume feeding available SGs.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 44 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 78. Verify 1 TD EFDW PUMP operating. GO TO Step 82. 79. Dispatch operator to 1C-157 (TD EFDWP Suction From UST) to establish communication with CR (T-1/C-20). 80. WHEN operator in place at 1C-157, THEN continue. 81. Stop 1 TD EFDW PUMP. 82. Locally close 1C-157 (TD EFDWP Suction From UST) (T-1/C-20). 1. IF NO EFDW pumps are operating, THEN: A. Notify CR SRO that a LOHT exists from loss of EFDW suction source. B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit. C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3. 2. GO TO Step 84. 83. Open 1C-391. 1. Attempt to locally open 1C-391 (TD EFDWP Suction From Hotwell) (T-1/C-20). 2. IF 1C-391 CANNOT be opened, AND NO EFDW pumps are operating, THEN: A. Notify CR SRO that a LOHT exists from loss of EFDW suction source. B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit. C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 45 of 49 Enclosure 5.9 Extended EFDW Operation 84. IAAT 1 TD EFDW PUMP operation is desired, AND all exist: Hotwell level is > Vacuum is broken. 1 TD EFDW PUMP successfully aligned to hotwell. THEN: A. Start 1 TD EFDW PUMP. B. Feed available SGs as required. 85. Dispatch an operator to open: 1C-188 (Hotwell Emerg Makeup #1 Control Bypass) (T-1/W of E-24). {18} 1C-912 (UST Riser To HW Emerg Makeup #2 Auto Isol Bypass) (T-1/G-23) 86. Notify TSC to evaluate methods to maintain secondary inventory including strategies located in EM 5.1 (Engineering Emergency Response Plan) and EM 5.2 (Evaluation By Station Management in the TSC - Beyond Design Basis Mitigation Strategies).

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 46 of 49 Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 87. IAAT hotwell leve, THEN: A. Stop all EFDWPs. B. Consider all U-1 EFDW pumps inoperable, AND GO TO Rule 3. NOTE This step provides general plant directions for the SRO and Management team. The user shall continue after the notification has been made. Swapping from TBVs to ADVs prevents overfilling the hotwell/condenser. Securing steam seals limits the water (condensation) that reaches the oil systems. Vacuum must be broken to secure steam seals. Engineering will determine when to allow secondary system restart. Beginning a cooldown assumes HPI is operating. If the SSF is supplying seals, then further discussion with the Management team should be undertaken prior to cooldown. 88. Notify the CR SRO to direct the following as time and resources allow: Transfer steam control from TBVs to ADVs. Operate ADVs per U1 EOP Encl 5.24 (Operation of ADVs). Begin Unit cool down to LPI per OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) using the ADVs. Break vacuum per OP/1-2/A/1106/016 (Condenser Vacuum System). Secure Steam Seals per OP/1/A/1106/13 (Steam Seal System). 89. WHEN directed by CR SRO, THEN EXIT.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 47 of 49 Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All 4160V SWGR de-energized {13} GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = 0°F GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer GO TO EHT tab. LOHT 6. Loss of heat transfer (including loss of all Main and Emergency FDW) GO TO LOHT tab. 7. Heat transfer is or has been excessive GO TO EHT tab. EHT 8. Indications of SGTR gpm GO TO SGTR tab. SGTR 9. Turbine Building flooding NOT caused by rainfall event GO TO TBF tab. TBF 10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES Actuation). ES 11. Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 12. Power lost to all 4160V SWGR and any 4160V SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 13. RCS leakage > 160 gpm with letdown isolated Notify plant staff that Emergency Dose Limits are in affect using PA system. EDL 14. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and NSD 202 (Reportability). NOTIFY Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 48 of 49 CRITICAL TASKS CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor. Adjustment will be dependent on how much time it takes to place ICS in HAND. CT-2 Reactor trip breakers must be opened to shut down the reactor.

SAFETY: Take a Minute UNIT 0 (OSM) SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO) Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 895 100% Power 100% Power RCS Leakage: 0.01 gpm No WCAP Action EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO) Component/Train OOS Date/Time Restoration Required Date/Time TS/SLC # AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO) Primary Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%). 1RIA-3 and 5 removed from RB. OATC is to perform a 5 minute Delith using OP/1/A/1103/004C (Deborating IXs) Encl. 4.4 (Unit 1 Deborating IX For RCS De-lith (Rx At Power)) Secondary Feedwater valve DP selected to A1 and B2 for maintenance AMSAC/DSS bypassed 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. Reactivity Management (CR SRO) RCS Boron 83 ppmB Gp 7 Rod Position: 92% Withdrawn Batch additions as required for volume control. Human Performance Emphasis (OSM) Procedure Use and Adherence Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 3 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO ________________________ ________________________OATC ________________________ ________________________BOP Initial Conditions: Reactor Power = 100% Turnover: Feedwater valve DP selected to 1A1 and 1B2 for maintenance AMSAC/DSS bypassed Event No. Malfunction No. Event Type* Event Description 0a 0b 0c 1 Override C: BOP, SRO (TS) 1A RBCU high vibration, secure 1A and start 1B RBCU 2 MSI231 I: OATC, SRO 1A FDW Valve DP Signal Fails Low 3 MPS450 C: BOP, SRO (TS) 1B1 RCP Hi Vib, Power reduction 4 MPI281 I: OATC, SRO Tc fails 5 Updater C: BOP, SRO 1HP-14 fails to BLEED 6 MPS020 R: OATC, SRO (TS) 20 gpm Pri-Sec leak in 1B SG requires Manual S/D 7 MPS020 Updater M: ALL 1TA Lockout, 1B SGTR TBV on intact SG trips to MANUAL 1HP-26 fails closed * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 2 of 55 Scenario 3 Event Summary: Event 1: 1A RBCU will develop a vibration and alarm on the OAC. The OAC alarm response guide will direct the operator to attempt to reset the alarm and then secure the RBCU. The crew will contact engineering who will direct starting of the 1B RBCU in High speed. The RBCU will start in low speed first, then de-energize and change to High speed. Event 2: The feedwater valve DP will fail low causing feedwater pump speed to increase. The OATC will have to take MFWPs to MANUAL and reduce FWPT speed. The crew will perform AP/28 (ICS Instrumentation Failures). ICS will be returned to AUTO. Event 3: RCP 1B1 will experience high vibration that will require using AP/16 (RCP Malfunction) to perform a power reduction to below 70% to remove from service. Event 4: When the 1B1 RCP is tripped, Tc will fail and feedwater will not re-ratio. The OATC may attempt to control Tc with the Tc controller in MANUAL but this will not work either. The OATC will then be required to take both FDW LOOP MASTERS to HAND in order to re-ratio feedwater. Event 5: 1HP-14 will fail in the BLEED position. Crew will be required to enter AP/2, (Excessive RCS Leakage). The crew will close 1HP-6 and throttle 1HP-7 to maintain Pzr Level. Event 6: A 20 gpm SGTL in the 1B SG will require entry into AP/31, (Primary to Secondary Leakage) and perform a rapid unit shutdown using AP/29 (Rapid Unit Shutdown) with ICS in MANUAL. Event 7: Bus 1TA will lockout. This will cause the 1A1 RCP to de-energize and the Reactor to trip (only 2 RCPs operating). When the reactor trips, the SGTL will degrade into a 200 gpm SGTR. The TBV on the 1A SG will trip to MANUAL. 1HP-26 will not open requiring the crew to open 1HP-410 to inject into the RCS.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 3 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 1 Page 1 of 2 Event

Description:

1A RBCU high vibration, secure 1A and start 1B RBCU (C, BOP, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/BOP

Plant Response: OAC alarm: O1D1361, RBCU FAN 1A VIB Crew Response: BOP will Refer to OAC ARG (O1D1361, RBCU FAN 1A VIB) 1. Depress the RBCU OAC Vibration Alarm Reset Pushbutton [It will not reset] 2. If the alarm doesn't clear, stop the RBCU. [BOP will secure the 1A RBCU] [Alarm will not reset until the ALARM RESET P/B is depressed] 3. Notify Engineering for an evaluation Booth cue: Using time compression as SM & engineering request that 1B RBCU be started in HIGH SPEED. OP/1/A/1104/015 OP/1/A/1104/015 Reactor Building Cooling System, Rev 42 Encl 4.3 (RBCU Operation), Section 4, Starting RBCUs NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes. 4.1 Verify RB pressure within limits of PT/1/A/0600/001 (Periodic Instrument Surveillance). 4.2 Begin monitoring RB absolute pressure. (OAC Turn On Code: 1RBPA) {8} 4.3 IF personnel inside containment, announce over plant page that starting RBCU(s). {11} NOTE: Starting RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1RIA-47 level, RB pressure/temperature. 4.4 Place desired switch to "HIGH" or "LOW": 1A RBCU 1B RBCU 1C RBCU This event is complete when 1B RBCU is started, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 4 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 1 Page 2 of 2 Event

Description:

1A RBCU high vibration, secure 1A and start 1B RBCU (C, BOP, SRO)(TS) Time Position Applicant's Actions or Behavior BOP

OP/1/A/1104/015 Crew Response: NOTE: When changing LPSW flows, RB pressure will change as RB temperature changes. Outlet Flow to meet flow requirements of SLC 16.9.12. 4.5 Position valves as required for RB cooling: 1LPSW-18 (1A RBCU OUTLET) 1LPSW-21 (1B RBCU OUTLET) 1LPSW-24 (1C RBCU OUTLET) TS 3.6.5, REACTOR BUILDING SPRAY AND COOLING TRAINS Condition B (7 days) Restore reactor building cooling train to OPERABLE status.

This event is complete when 1B RBCU is started, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 5 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 1 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

AP/1/A/1700/028 Plant Response: FDW pump speed increases FDW Control Valves will throttle closed to limit flow FDW Pump discharge pressure increases Crew Response: Crew should perform Plant Transient Response (PTR). OATC should place both FDW pump ICS stations in MANUAL and reduce FDW pump speed to ~ pre-transient valve. The OATC may take the Diamond & both FDW Masters to HAND SRO will enter AP/1/A/1700/028, ICS Instrumentation Failure Examiner Note: OATC may take FDW Loop Masters and Diamond to HAND as well. These are standard PTR actions. AP/1/A/1700/028 Rev 20 4.1 Provide control bands as required. 4.2 Initiate notification of the following: __ OSM to reference the following: OMP 1-14 (Notifications) Emergency Plan __ STA 4.3 occurred. RNO: GO TO Step 4.5. 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan. 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6: OAC alarm video OAC display points Control Board indications SPOC assistance, as needed 4.6 GO TO the applicable section per the following table: Section Failure 4H Feedwater Valve P This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 6 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 2 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

AP/1/A/1700/028 Crew Response: AP/28, Section 4H NOTE failed high, both MFDWPs go to low speed stop. Both MFDWPs go to high speed stop Feedwater control valves close to reduce increased Feedwater flow Feedwater pump(s) may trip on high discharge pressure 1. Ensure the following in HAND: __ 1A MAIN FDW PUMP __ 1B MAIN FDW PUMP 2. Notify SPOC to investigate and repair the failed Feedwater Valve DP instrumentation. Booth Cue: When notified as SPOC, inform the crew that all work is complete on FDW Valve dp and it is now a valid signal. 3. Select a valid Feedwater Valve DP input to ICS with selector switch. 4. WHEN a valid Feedwater Valve DP input has been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl 4.4 (Placing ICS Stations To Auto). Examiner Note: Crew should select 1A2 FDW Valve dp and return ICS to AUTO. OP/1/A/1102/004 A Encl 4.4 Rev 10 1.2 Review PT/0/A/1103/020 1.3 Ensure dedicated operator assigned to monitor/operate ICS 1.4 Perform pre-job brief including precautions from SOMP 1-02 (Reactivity Management) and applicable Limits & Precautions of PT/0/A/1103/020 (Power Maneuvering Predictions) (R.M.) 1.5 Ensure R2 reactivity management controls are established in Control Room per SOMP 1-02 (Reactivity Management) This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 7 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 3 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

OP/1/A/1102/004 A Crew Response: OP/1/A/1102/004 A Encl 4.4 Section 2 2.1 Ensure "RATE SET" thumbwheels at 0.0. 2.2 IF TURBINE MASTER is in HAND, perform Section 3 (N/A) 2.3 IF either TBV is in HAND, perform Section 4 (N/A) 2.4 IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 Examiner Note: Section 5 may or may NOT be needed based on actions taken during PTR OP/1/A/1102/004 A Encl 4.4 Section 5 5.1 IF Rx Master is in HAND, perform the following: (N/A) 5.2 IF both SGs are off of Level Control, perform the following: 5.2.1 IF selected Tave (O1E2086) is different from Tave setpoint (O1E2087) by more than +/- 0.15°F, perform the following: A. Simultaneously ensure 1A & 1B FDW Masters in HAND NOTE: Cycling the setpoint selector may result in a Star Module failure. This is expected for this condition and entry into AP/28 (ICS Instrument Failures is NOT required. The Star Module failure shall be cleared before the ICS is returned to Auto. B. On REACTOR MASTER, cycle Tave setpoint selector between 565°F and 585°F five times C. IF Star Module failed, perform the following: (N/A) D. On REACTOR MASTER adjust Tave setpoint (O1E2078) towards selected Tave (O1E2086) 5.2.2 Verify selected Tave is within +/- 0.15°F of Tave setpoint 5.3 IF either SG is on Level Control, adjust Tave setopint (O1E2087) to 579°F 5.4 Place DIAMOND in AUTO 5.5 Return to Section 2 (Procedure) This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 8 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 4 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

OP/1/A/1102/004 A Crew Response: OP/1/A/1102/004 A Encl 4.4 Section 2 2.5 IF DELTA Tc is in HAND, perform Section 6 (N/A) 2.6 IF STM GENERATOR MASTER or either FDW MASTER is in HAND, perform Section 7 (Placing FDW To Auto) Section 7 may or may NOT be needed based on actions taken during PTR OP/1/A/1102/004 A Encl 4.4 Section 7 7.1 IF SG Master is in HAND, perform the following: (N/A) 7.2 IF 1A OR 1B FDW Master is NOT in AUTO, perform the following: 7.2.1 Select 1A & 1B FDW MASTERs to "MEAS VAR" 7.2.2 IF both 1A AND 1B FDW Master Measured Variables are on the caret: A. Select 1A & 1B FDW MASTERs to "POS" B. Simultaneously ensure 1A & 1B FDW MASTERs in AUTO 7.2.3 IF 1A OR 1B FDW Master Measured Variable is NOT on the caret (N/A) 7.3 Return to Section 2 (Procedure) OP/1/A/1102/004 A Encl 4.4 Section 2 2.7 IF any FDW valves are in HAND, perform Section 8 (N/A) 2.8 IF either Main FDW Pump is in HAND, perform Section 9 This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 9 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 5 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

OP/1/A/1102/004 A Crew Response: OP/1/A/1102/004 A Encl 4.4 Section 9 9.1 IF NOT just either of the following 1A MAIN FDW PUMP 1B MAIN FDW PUMP 9.3 IF 1A MAIN FDW PUMP operating in "HAND", place 1A MAIN FDW PUMP (ICS) in "AUTO". 9.4 IF 1B MAIN FDW PUMP operating in "HAND", place 1B MAIN FDW PUMP (ICS) in "AUTO". 9.5 Return to Section 2 (Procedure). OP/1/A/1102/004 A Encl 4.4 Section 2 2.9 Verify ICS in full Auto. CAUTION: Adjusting THP, Tave or Delta Tc setpoint too fast can cause plant instability. 2.10 IF NOT being controlled by another procedure, perform the following: 2.10.1 IF THP (O1E2088) is NOT , slowly adjust THP Setpoint 2.10.2 IF Tave Setpoint (O1E2087) is NOT 2.10.3 IF Delta Tc is NOT 1E2091) to 2.11 IF both FDWP suction flows are NOT within 1 x 10 6 lb/hr of each other, adjust FDWP BIAS per Enclosure 4.3 (Adjusting FDWP BIAS). This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 10 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 6 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC

OP/1/A/1102/004 A Crew Response: OP/1/A/1102/004 A Encl 4.4 Section 2 2.12 IF desired, adjust CTP as follows: (R.M.) 2.12.1 Review current mechanical maneuvering rates per PT/0/A/1103/020 (Power Maneuvering Predictions). 2.12.2 IF desired to increase power, perform the following: A. WHEN ICS has been in full Auto (Integrated Mode) for > 10 minutes, continue at Step 2.12.3. {6} 2.12.3 Ensure selected "HOLD". 2.12.4 Ensure desired setting selected ("%/MIN" or "%/HR") on "RATE" pushbuttons. 2.12.5 Ensure desired rate selected on "RATE SET" thumbwheels. 2.12.6 Insert desired CTPD SET using "INCREASE/DECREASE" pushbuttons. 2.12.7 Ensure "HOLD" is NOT selected. 2.12.8 WHEN desired CTP is achieved, return "RATE SET" thumbwheels to 0.0. This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 11 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3 Page 1 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/OATC BOP

Plant Response: 1SA9/D-2 RC Pump Vibration High in alarm 1SA9/D-2 Crew Response: SRO will direct the BOP to refer to ARG 1SA-9/D-2 1SA-9/D-2 3.1 Use one of the following means to verify RCP vibration conditions: Verify vibration reading on RCP OAC Display Group RCP. IF the OAC is unavailable, verify the alarm by referring to RCP Vibration Monitoring Chart Recorder (ON1RCCR0430). (RCP Panel on 6th floor AHU Room) NOTE: Vibration indication of both RCPs in a Loop trending up together without any changes to RCS conditions (Temp/Press) is a symptom of a Vibration Monitor power supply failure. 3.2 IF indications of both RCPs in a Loop are trending up together without any changes to RCS conditions (Temp/Press), swap Vibration Monitor power supplies as follows: [Only 1 RCP experiencing vibrations] NA 3.3 IF MODE 1 or 2, initiate AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation). NOTE: Vibrations are expected to increase due to changing RCS temperature/pressure. 3.4 IF MODE 3, 4 or 5 AND vibration increase is NOT due to changing RCS temperature/pressure, initiate AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation). 3.5 Monitor RCP parameters. 3.6 Contact PM2 Group for analysis of RCP parameters and to install additional monitoring equipment. 3.7 Initiate a CR for Engineering to document potential vibration effects on RCS Piping. This event is complete when the 1B1 RCP is tripped, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 12 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3 Page 2 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

AP/1/A/1700/016 Crew Response: AP/1/A/1700/016 Abnormal Reactor Coolant Pump Operation Rev 33 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 4.2 - 4.11. [Vibrations will NOT meet the immediate trip criteria] RNO: GO TO Step 4.12. NOTE If affected RCP has a seal failure, and immediate trip criteria not met, then continue to Section 4A (Seal Failure) to ensure Seal Failure guidance steps are read. Section 4A (Seal Failure) contains steps to quickly secure affected RCP should the need arise. 4.12 IAAT either of the following apply: __ Any RCP approaching immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria) __ There is an immediate need to stop a RCP at this time THEN perform Steps 4.13 - 4.15. RNO: GO TO Step 4.16. Examiner Note: The SRO may decide to remove the RCP from service at this time and proceed to step 4.13. It they do not, they will proceed to Step 4.16 per the RNO (Page 15). 4.13 Verify Rx Power > 70%. 4.14 Initiate Encl 5.2 (Rapid Power Reduction). (Page 16) 4.15 WHEN Rx Power is 70%, THEN GO TO Step 4.2.

4.2 Verify MODE 1 or 2.

4.3 Verify Rx power is 70% as indicated on all NIs. 4.4 Verify three RCPs will remain operating after affected RCP is tripped.

4.5 Verify any SG on Low Level Limits. RNO: GO TO Step 4.8. This event is complete when the 1B1 RCP is tripped, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 13 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 3 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP OATC AP/1/A/1700/016 Crew Response: 4.8 Verify FDW masters in Auto. 4.9 Stop the affected RCP. 4.10 Verify ICS re-ratios feedwater to establish desired Delta Tc. Examiner Note: ICS will NOT re-ratio feedwater correctly, this is Event 4.

RNO: 1. Place DELTA Tc station in HAND. 2. Manually adjust DELTA Tc station to achieve desired Delta Tc. Examiner Note: DELTA Tc controller will not function in HAND which will require the OATC to place both FDW LOOP MASTERS in HAND to control DELTA Tc. CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity. 3. IF DELTA Tc station does NOT control, THEN perform the following: A. Place the following in HAND: __ 1A FDW MASTER __ 1B FDW MASTER B. Manually adjust FDW masters to achieve desired Delta Tc. 4. IF there has been a failure of the DELTA Tc controller, THEN notify SPOC to repair. 4.11 GO TO Step 4.29. 4.29 IAAT any of the following indicate external RCP seal leakage: __ RB RIAs increasing or in alarm __ RCS Tave constant with LDST level decreasing more than normal __ Quench Tank level rate increasing __ RB Normal Sump rate increasing __ Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage). Event 3 is complete when the 1B1 RCP is tripped, Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 14 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 4 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP AP/1/A/1700/016 Crew Response: 4.30 Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (Page 20) 4.31 IAAT either of the following conditions is met: __ a RCP has been shut down for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , {9} __ a RCP with high oil level has been shut down THEN close the associated RCP motor cooler inlet/outlet valve: __ 1LPSW-7&8 (1A1 RCP) __ 1LPSW-9&10 (1B1 RCP) __ 1LPSW-13&14 (1A2 RCP) __ 1LPSW-11&12 (1B2 RCP) 4.32 IAAT either of the following has exceeded 260°F including transient situations: __ O1A1253 - O1A1256 (RCP UPPER SEAL HOUSING TEMP) __ O1A1910 - O1A1913 (RCP SEAL RETURN TEMP) THEN closely monitor seal parameters for degradation until an Engineering evaluation is completed due to potential for seal ring and elastomer damage. NOTE Operating experience has shown that failure of RC Pump components located internal to the RCS can create loose debris which can lead to fuel clad failures. These type RC Pump failures may cause Loose Parts Monitor alarms immediately and increased RCS radioactivity later.

4.33 Verify 1RIA 57 or 1RIA 58 have increased. RNO: GO TO Step 4.35. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 15 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 5 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails at (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

AP/1/A/1700/016 Crew Response: 4.35 IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart. 4.36 IAAT both are met: __ There has been a failure of the DELTA Tc controller __ The DELTA Tc controller has been repaired THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto). 4.37 Verify any RCP that was shut down had a high vibration alarm. 4.38 Initiate a PIP for Engineering to document potential vibration effects on RCS piping. 4.39 WHEN conditions permit, THEN EXIT this procedure. TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF), Once Reactor Power is reduced below 85% the SSF must be declared inoperable. Conditions A-E (7 Days) Restore to operable status. Alternate Path from step 4.12 4.16 Announce AP entry using the PA system.

4.17 Notify OSM to request evaluation by RCP Component Engineer.

4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table: Section Failure 4B Abnormal Vibration Section 4B Abnormal Vibration 1. IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 2 - 11. RNO: GO TO Step 12. [RCP Vibrations will NOT reach trip criteria] Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 16 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 6 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails at (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP AP/1/A/1700/016 Crew Response: 12. Verify RCP vibration indication is available for monitoring in Control Room. 13. Monitor RCS flow for indication of degradation. 14. Verify all CETCs < 630°F. (Turn-on code "ITC") 15. Monitor RCP parameters for operational abnormalities: __ OAC Display: (Turn-on Code "RCP") Motor bearing temperatures Seal return temperature Seal return flow RCP motor input power __ Loose Parts Monitor 16. IAAT high vibration exists per statalarm 1SA-9/D-2, (RC PUMP VIBRATION HIGH) AND vibration continues to increase with the potential to exceed trip criteria THEN perform Steps 17 - 27. RNO: GO TO Step 28. 17. Verify MODE 1 or 2. 18. Verify three RCPs will remain operating after affected RCP is tripped. RNO: 1.__Direct an RO to initiate Encl 5.2 (Rapid Power Reduction) (Page 19) 2.__WHEN Rx power is < 70% on all NIs, THEN continue this procedure. 20. Verify any SG on Low Level Limits. RNO: GO TO Step 23. 23. Verify FDW masters in Auto.

24. Stop the affected RCP. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 17 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 7 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails at (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP AP/1/A/1700/016 Crew Response: 25. Verify ICS re- RNO: 1. __ Place DELTA Tc station in HAND. 2. __ Manually adjust DELTA Tc station to CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity. Examiner Note: ICS will NOT re-ratio feedwater correctly, this is Event 4. 3. __ IF DELTA Tc station does NOT control, THEN perform the following: A. Place the following in HAND: __ 1A FDW MASTER __ 1B FDW MASTER B. __ Manually adjust FDW masters to 4. __ IF there has been a failure of the DELTA Tc controller, THEN notify SPOC to repair.

26. Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (Page 20)

27. Initiate the following notifications: __ Notify OSM to make required notifications of OMP 1-14 (Notifications). __ Notify Rx Engineering and request a power maneuver plan, if needed. __ Notify SOC if load reduction was required. __ Notify Chemistry to take RCS boron samples on a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months frequency. NOTE Operating experience has shown that failure of RC Pump components located internal to the RCS can create loose debris which can lead to fuel clad failures. These type RC Pump failures may cause Loose Parts Monitor alarms immediately and increased RCS radioactivity later.

28. Verify 1RIA-57 or 1RIA-58 have increased. RNO: GO TO Step 30. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 18 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 8 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails at (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP AP/1/A/1700/016 Crew Response: 30. IAAT THEN close the associated RCP motor cooler inlet/outlet valve: __ 1LPSW-7&8 (1A1 RCP) __ 1LPSW-9&10 (1B1 RCP) __ 1LPSW-13&14 (1A2 RCP) __ 1LPSW-11&12 (1B2 RCP) 31. IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart.

32. IAAT both are met: __ There has been a failure of the DELTA Tc controller __ The DELTA Tc controller has been repaired THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto). 33. Initiate a PIP for Engineering to document potential vibration effects on RCS piping. 34. WHEN conditions permit, THEN EXIT this procedure. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 19 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 9 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

AP/1/A/1700/016 Crew Response: Encl 5.2 Rapid Power Reduction NOTE This enclosure should be performed by an RO. The step to verify ICS in AUTO means that the ICS is capable of responding to a MAXIMUM RUNBACK signal.

1. Verify ICS in AUTO.

2. Initiate MAXIMUM 3. WHEN all NIs, THEN press MAXIMUM RUNBACK to stop runback

5. Adjust CTPD SET to match CTP DEMAND

6. Stop the 1E1 and 1E2 HTR DRN PUMPs 7. Verify Rx Power was reduced 15% within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period. 8. Notify Primary Chemistry to perform Tech Spec SR 3.4.11.2 as required. 9. EXIT this enclosure. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 20 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 10 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

OP/1/A/1102/004 Crew Response: OP/1/A/1102/004 OPERATIONS AT POWER, Encl 4.3 Special Instructions For < 4 RCP Operations Rev 144 2.1 IF conditions permit, log the current quadrant power tilt and the position of NOTE: Instructions for performing OAC trends are located in Working With Trends enclosure of OP/0/A/1103/020 A (Operator Aid Computer Use). Only the first 6 points will be displayed initially; press "Page Down" key to see second 6 points. 2.2 Using turn-on code T6 3RCP, digitally trend the following data at one minute intervals: Point ID Description O1P0889 CORE THERMAL POWER BEST O1P0877 INCORE IMBALANCE O1E3335 API GROUP AVE FOR GROUP 7 O1E3336 API GROUP AVE FOR GROUP 8 O1P0737 INCORE TILT QUADRANT W-X O1P0738 INCORE TILT QUADRANT X-Y O1P0739 INCORE TILT QUADRANT Y-Z O1P0740 INCORE TILT QUADRANT Z-W O1I0828 RC COLD LEG A1 TEMP O1I0829 RC COLD LEG A2 TEMP O1I0830 RC COLD LEG B1 TEMP O1I0831 RC COLD LEG B2 TEMP 2.3 After steady state conditions are attained, perform the following: 2.3.1 Check NI calibration. 2.3.2 IF NI calibration is NOT within requirements of Limit and Precaution Step 2.2.6, calibrate NIs to Thermal Power Best. (R.M.) NOTE: The 100% Power Imbalance curves also apply for runs at reduced power. 2.4 Maintain Control Rod position and Power Imbalance within COLR limits. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 21 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 11 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

OP/1/A/1102/004 Crew Response: NOTE: The Maximum Allowed Power Setpoint (Pmax) is reduced when operating for extended periods with a 3 RC Pump Configuration as a conservative action. 2.5 Perform the following: 2.5.1 IF expected to operate for an extended period of time with only 3 RCPs operating, notify I&E to adjust Flux/ Imbalance /Flow trip setpoints for 3 RCP operation per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.) ________________________ _____ Person Notified Date 2.5.2 IF AT ANY TIME Quadrant Power Tilt problems exist, notify I&E to Adjust Flux/Imbalance/Flow trip setpoints as required to comply with TS 3.2.3 per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.) ________________________ _____ Person Notified Date NOTE: Operations Management/Reactor Engineering Group should be consulted for value to use for high flux alarm setpoint. Instructions for Adjusting Alarm Setpoints On The NI Recorder are in OP/0/A/1108/001 (Curves And General Information). 2.6 Adjust high flux alarm setpoint per Operations Management/Reactor Engineering Group recommendations. (Alarm setpoint is adjusted on the NI Recorder). (R.M.) NOTE: 'D' bleed pressure may NOT be high enough to run the FDWP turbines.

2.7 Maintain Auxiliary Steam available to the FDWP turbines.

2.8 IF 1SSH-9 (SSH DISCH CTRL BYPASS) is being used to control Steam Seal Header pressure, throttle 1SSH-9 as required to maintain desired SSH pressure during the load reduction to secure an RCP. Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 22 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 12 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO) Tc fails (I: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATCBOP

OP/1/A/1102/004 Crew Response: NOTE: RCS pressure decrease in the loop with two RCPs running is expected. This may cause acceptance criteria of PT/1/A/0600/001 (Periodic Instrument Surveillance) NOT to be met. 2.9 Place note on CR turnover sheet indicating the following: "Be aware of the effect of the indicated pressure on the margin to trip setpoint for the Reactor Protective System trips associated with RCS pressure." Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 23 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 1 of 3 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP

AP/1/A/1700/002 Plant Response: OAC alarm: 1HP-14 = BLEED OAC alarm: 1HP-14 LDST BYPASS (NOT NORMAL) Crew Response: The SRO should initiate AP/1/A/1700/002 (Excessive RCS Leakage) AP/1/A/1700/002 (Excessive RCS Leakage) Rev 015 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5 Examiner Note: If 1HP-5 is closed , Encl 5.5 will used to re-open when required. 3.3 IAAT all the following exist: (N/A) __ RCS leakage > letdown isolated __ Pzr level decreasing __ SG Tube Leakage NOT indicated __ LPI DHR NOT providing core cooling THEN perform the following: A. Ensure Rx is tripped B. Initiate Unit 1 EOP 4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP Encl 5.5 as necessary. (Page 44) 4.2 Announce AP entry using PA system 4.3 IAAT LPI DHR in service, AND RCS leakage > LDST makeup capability THEN GO TO AP/26 (N/A) Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 24 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 2 of 3 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP

AP/1/A/1700/002 Crew Response: 4.4 Initiate the following notifications: __ OSM to reference the following: RP/0/A/1000/001 (Emergency Classification) OMP 1-14 (Notifications) Encl 5.9 (Oversight Guidlines) __ STA __ RP 4.5 Monitor the following trends to determine leak area (AB or RB) and trend for degradation: __ T6 AP/02 __ T6 WASTE __ RIAs 4.6 Verify specific leak location is identified 4.7 Initiate Encl 5.1 (Leak Rate Determination) Leak Rate = _____ + _____ - _____ - _____ = _____ MU SI LD TSR 4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure: Area/ Failure Symptoms Step 1HP-14 failure 1HP-14 failed in BLEED position T level 1A BHUT level 4.155 4.155 Verify 1A LD Filter in service RNO: 1. IF 1A LD Filter is out of service for maintenance, THEN restore 1A LD Filter per in progress procedure (N/A) 2. Open 1HP-17 Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 25 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 3 of 3 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP

AP/1/A/1700/002 Crew Response: 4.156 Close 1HP-6 NOTE Tech Spec 3.4.9 applies when indicated Pzr level > 260" (corrected value for 285") 4.157 Adjust 1HP-7, as needed, to control: BLEED flow out of failed 1HP-14 Pzr level 4.158 Dispatch an operator to open 1HP-196 (Filter Diversion Inlet) (A-2-LDST Hatch Area) 4.159 Verify CC system in operation 4.160 Position the standby HPI pump switch to OFF 4.161 Initiate monitoring RCP parameters 4.162 Throttle 1HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW 4.163 WHEN 1HP-196 (Filter Diversion Inlet) is open, THEN close 1CS-26 4,164 Close the following: __ 1CS-27 __ 1CS-32 & 37 4.165 Open 1HP-6 4.166 Throttle 1HP- 4.167 Adjust 1HP-7 to establish desired letdown flow 4.168 Position standby HPI pump switch to AUTO 4.169 WHEN 1HP-14 has been repaired, THEN perform the following: A. Ensure 1HP-14 in NORMAL B. Open 1HP-26 C. Ensure HPI valves are aligned such that a letdown path will be present after 1HP-196 is closed D. Close 1HP-196 Examiner Note: 1HP-14 will NOT be repaired. Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 26 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 1 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/031 Plant Response: 1SA8/A9 (RM AREA MONITOR RADIATION HIGH) 1SA8/E10 (N-16 RM PRIMARY TO SECONDARY TUBE LEAK) 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH) 1SA8/B9 (RM PROCESS MONITOR RADIATION HIGH) 1RIA-40 in alarm 1RIA 60 in alarm and indicating 20 gpm Crew Response: SRO will enter AP/1/A/1700/031 Primary To Secondary Leakage Rev 21 AP/1/A/1700/031 NOTE The total primary to secondary leak rate can be determined by the following means: OAC point O1P1599 (EST TOTAL PRI TO SEC LEAKRATE) if OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFF-GAS BLOWER operating). Sum of 1RIA-59 and 1RIA-60 readings if both operable and reactor power > 40%. Allowable leakage per Tech Spec 3.4.13 is 150 gpd through any one SG. Estimated SGTR leak rate formula: Leak rate = ____ + ____ - ____ - ____ = ____ MU SI LD TSR Where: MU = Makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown TSR = Total Seal Return Flow If the EOP is NOT already in progress, entry will be directly to the SGTR tab. RIA-59 / 60 and RIA-16 / 17 on the unaffected SG may indicate up to 2 % of the value of the detector on the affected SG due to radiation shine from the steam line carrying radioactive steam from the SG with the tube leak. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 27 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 2 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/031 Crew Response: 4.1 IAAT THEN GO TO Unit 1 EOP. 4.2 IAAT either of the following exists for 1RIA-54: __ is in High alarm __ inoperable THEN perform Steps 4.3 - 4.4. NOTE The white tags can be created and hung after the TBS pump breakers are opened. 4.3 Dispatch an operator to open and white tag the following: __ 1XD-R3C (1A TURBINE BUILDING SUMP PUMP BKR) __ 1XE-R3D (1B TURBINE BUILDING SUMP PUMP BKR) 4.4 Notify Secondary Chemistry to perform the following: __ Obtain a TBS sample. __ Recommend TBS release path. 4.5 Initiate notification of the following: __ OSM to reference the following: OMP 1-14 (Notifications) Emergency Plan __ STA NOTE 1RIA-59 and 1RIA-60 are considered inoperable below 40% power. 4.6 IAAT notified by Chemistry that 1RIA-40 is inoperable because the minimum detection limit is too high, AND 1RIA-59 or 1RIA-60 is inoperable, THEN perform Encl 5.9 (1RIA-40 Inoperable Due to Failure to Meet Minimum Detectable Limit). 4.7 IAAT primary to secondary leakage exceeds 30 gpd, THEN perform Steps 4.8 - 4.9. [Pri-Sec leak rate ~ 20 gpm] This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 28 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 3 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/031 Crew Response: 4.8 Dispatch AO to reroute Unit 1 CSAE drains to the CST per OP/1-2/A/1106/016 (Condenser Vacuum System). 4.9 Initiate Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination). 4.10 IAAT tube leakage is large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level, THEN GO TO Step 4.86. 4.86 Verify OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFFGAS BLOWER operating). 4.87 Determine primary to secondary leakage rate using OAC point O1P1599 (EST TOTAL PRI TO SECLEAKRATE). 4.88 GO TO Step 4.93. 4.93 Initiate log readings from the following every 15 minutes in the Auto Log: 1RIA-16 1RIA-17 1RIA-40 1RIA-59 (when Rx power > 40 %) 1RIA-60 (when Rx power > 40 %) 4.94 Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown Requirements) using the following, as applicable: AP/29 (Rapid Unit Shutdown) (Page 30) OP/1/A/1102/004 (Operation at Power) OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown) Booth Cue: If asked, Unit 2 will continue actions in AP/31 4.95 IAAT primary to secondary leakage increases, THEN modify shutdown as required by Encl 5.1 (Unit Shutdown Requirements). 4.96 Notify OSM to refer to Tech Spec. 3.10.1 Basis to determine SSF operability. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 29 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 4 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/031 Crew Response: 4.97 Notify plant personnel, using the PA system, to stay clear of the affected MS line and the powdex.

4.98 Notify Radwaste to stop all liquid releases in progress until sample results assures release rates within limits.

4.99 Stop all gaseous releases in progress until sample results assure release rates within limits. 4.100 IAAT all the following exist: __ Primary to secondary leak rate < 100 gpd (< 0.0694 gpm) __ 1RIA-40 inoperable THEN notify RP and Primary Chemistry to sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.101 Make up to the UST only as necessary to maintain UST level > 7.5 '. 4.102 Notify the following that a shutdown is in progress due to primary to secondary leakage: __ RP __ Primary Chemistry __ Secondary Chemistry 4.103 Verify affected SG identified. 4.104 Verify entry into this procedure was due to one of the following: __ Tube leakage large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level TS 3.4.13 RCS OPERATIONAL LEAKAGE, Condition B due to Primary to Secondary LEAKAGE not within limit (12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s/36 hours) Be in Mode 3 / Mode 5. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 30 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 5 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/029 Crew Response: AP/1/A/1700/029 Rapid Unit Shutdown Rev 13 NOTE The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist. 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (Page 32) 4.2 Announce AP entry using the PA system 4.3 IAAT both of the following apply: __ It is desired to stop power decrease __ CTP > 18 % THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.4 Verify ICS in AUTO RNO: 1. Stop manual power reduction 2. GO TO Step 4.6 NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown. 4.6 Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure 4.7 WHEN conditions permit, THEN perform one of the following: __ Depress MAXIMUM RUNBACK to resume power reduction __ GO TO appropriate operating procedure for continued operation 4.8 Verify ICS in AUTO RNO: 1. Initiate manual power reduction to desired power level 2. GO TO Step 4.10 This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 31 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 6 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/029 Crew Response: 4.10 Verify both Main FDW pumps running. NOTE 1B Main FDW Pump is the preferred pump to be shutdown first. To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise. To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise. 4.11 Adjust bias for first Main FDW pump desired to be shutdown until 6 lbm/hr less than remaining Main FDW pump suction flow. 4.12 WHEN core thermal power is < 65% FP, THEN continue.

Examiner Note: Power should already be < 70% due to the power reduction to remove a RCP from service. 4.13 IAAT both Main FDW pumps running, AND both of the following exist: __ 1B Main FDW Pump is first pump to be shut down __ Any of the following alarms actuate and remain in alarm: FWP B FLOW MINIMUM (1SA-16/A-3) FWP B FLOW BELOW MIN (1SA-16/A-4) THEN trip 1B Main FDW Pump. 4.14 IAAT both Main FDW pumps running, AND both of the following exist: __ 1A Main FDW Pump is first pump to be shut down __ Any of the following alarms actuate and remain in alarm: FWP A FLOW MINIMUM (1SA-16/A-1) FWP A FLOW BELOW MIN (1SA-16/A-2) THEN trip 1A Main FDW Pump.

4.15 Verify Turbine-Generator shutdown is required.

4.16 Start the TURBINE TURNING GEAR OIL PUMP. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 32 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 7 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/029 Crew Response: 4.17 Start 1A through 1E TURBINE BRNG OIL LIFT PUMPS. 4.18 Start the TURBINE MOTOR SUCTION PUMP. 4.19 IAAT both of the following apply: __ ICS in automatic __ NI THEN deselect MAXIMUM RUNBACK. 4.20 Verify Turbine-Generator shutdown is required. 4.21 __ WHEN THEN depress turbine TRIP pushbutton. 4.22 __ Verify all TURBINE STOP VALVES closed. Enclosure 5.1 Support Actions During Rapid Unit Shutdown 1. Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown). 2. Start the following pumps: __ 1A FDWP SEAL INJECTION PUMP __ 1A FDWP AUXILIARY OIL PUMP __ 1B FDWP AUXILIARY OIL PUMP __ 1B FDWP SEAL INJECTION PUMP 3. WHEN THEN continue. 4. Stop 1E1 HTR DRN PUMP. 5. Place 1HD-254 switch to OPEN. 6. Stop 1E2 HTR DRN PUMP. 7. Place 1HD-276 switch to OPEN. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 33 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 8 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS) Time Position Applicant's Actions or Behavior SRO OATC/BOP

AP/1/A/1700/029 Crew Response: 8. Verify Turbine-Generator shutdown is required. 9. Place the following transfer switches to MAN: __ 1TA AUTO/MAN __ 1TB AUTO/MAN 10. Close 1TA SU 6.9 KV FDR. 11. Verify 1TA NORMAL 6.9 KV FDR opens. 12. Close 1TB SU 6.9 KV FDR. 13. Verify 1TB NORMAL 6.9 KV FDR opens. 14. Place the following transfer switches to MAN: __ MFB1 AUTO/MAN __ MFB2 AUTO/MAN 15. Close E11 MFB1 STARTUP FDR. 16. Verify N11 MFB1 NORMAL FDR opens. 17. Close E21 MFB2 STARTUP FDR. 18. Verify N21 MFB2 NORMAL FDR opens. 19. Notify CR SRO that Unit auxiliaries have been transferred. 20. IAAT 1SSH-9 is NOT closed, AND THEN throttle 1SSH-9 to Maintain Steam Seal Header pressure 2.5 - 4.5 psig. 21. WHEN THEN place the following in MANUAL and close: __ 1FDW-53 __ 1FDW-65 22. __ IAAT THEN perform Steps 23 - 24. This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 34 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 1 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC

BOP EOP Plant Response: Rx Trip 1SA-8/B-9 RM Process Monitor Radiation High 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH) Crew Response: SRO will direct the OATC to perform IMAs and the BOP to perform a symptom check. IMAs EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton. 3.2 Verify reactor power < 5% FP and decreasing. 3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed. 3.5 Verify RCP seal injection available. SYMPTOM CHECK The BOP will verify the following: Power Range NIs NOT < 5% Power Range NIs NOT decreasing Rule 1, ATWS/Unanticipated Nuclear Po Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) Rule 3, Loss of Main or Emerg FDW Rule 4, Initiation of HPI Forced Cooling (Inability to feed SGs and > 2300 psig, N limit reached, or PZR level > 375") Uncontrolled Main steam line(s) pressure decrease Rule 5, Main Steam Line Break CSAE Offgas alarms Process monitor alarms (RIA-40, 59,60), Area monitor alarms (RIA-16/17) None (SGTR Tab is entered when identif SG Tube Leakage > 25 gpm) SRO will review IMAs and transfer to the Subsequent Actions Tab. This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 35 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 2 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

Subsequent Actions Tab Crew Response: Examiner Note: The crew may not recognize the SGTL has degraded into a SGTR initially so steps in the SA tab were included. When the crew recognizes the SGTR, they should transfer to the SGTR tab. (Page 37) as directed by the Subsequent Actions, Parallel Action Page (Page 52). 4.1 Verify all control rods in Groups 1 - 7 fully inserted. 4.2 Verify Main FDW in operation. 4.3 Verify either: __ Main FDW overfeeding causing excessive temperature decrease. __ Main FDW underfeeding causing SG level decrease below setpoint. RNO: __ GO TO Step 4.5. 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8. RNO: __ GO TO Step 4.9. 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either: __ TBVs __ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) Examiner Note: The 1A TBVs have failed closed in AUTO. They can be operated in MANUAL. 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating. 4.11 GO TO Step 4.14. 4.14 Verify both are closed: __ 1MS-17 __ 1MS-26 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 36 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 3 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

Subsequent Actions Tab Crew Response: 4.15 Verify ES is required. RNO: 1. __ Initiate Encl 5.5 (Pzr and LDST Level Control).(Page 44) 2. __ GO TO Step 4.17. 4.17 Open: __ PCB 20 __ PCB 21 4.18 Verify Generator Field Breaker open. 4.19 Verify EXCITATION is OFF. 4.21 Verify ICS/NNI power available. 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized. 4.23 Verify both SGs > 550 psig. 4.24 Verify Main FDW operating. 4.25 Verify any RCP operating. 4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete. RNO: - - 4.27 Place switches in CLOSE: __ 1FDW-31 __ 1FDW-40 4.27 Place switches in CLOSE: __ 1FDW-31 __ 1FDW-40 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 37 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 4 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

CT-1 Subsequent Actions Tab Crew Response: 4.28 Verify SFP Cooling: {42} __ SFP Cooling in service __ SFP level normal 4.29 Verify all SCMs > 0°F.

4.30 Verify both SGs intentionally isolated to stop excessive heat transfer. RNO: __ GO TO Step 4.32. 4.32 Verify heat transfer exists.

4.33 Verify primary to secondary heat transfer has been excessive. RNO: __ GO TO Step 4.35.

4.36 GO TO SGTR tab. Examiner Note: The crew should recognize that the SGTL has degraded to a SGTR at this point. SGTR Tab 1. Verify Rx tripped. - - (Pzr and LDST Level Control). (Page 44) Examiner Note: 1HP-26 has failed in the closed position. 3. Ensure Parallel Actions Page reviewed. NOTE The remainder of this page may be given to an RO. The Procedure Director may continue. 4. Start: __ A OUTSIDE AIR BOOSTER FAN __ B OUTSIDE AIR BOOSTER FAN This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 38 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 5 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

SGTR Tab Crew Response: 5. Notify Unit 3 to start: __ 3A OUTSIDE AIR BOOSTER FAN __ 3B OUTSIDE AIR BOOSTER FAN 6. Perform the following: A. __ Monitor RIAs 16 and 17 to identify all SGs with a tube rupture. B. __ Inform SRO of results. 7. Dispatch an operator to open: __ 1XD-R3C (A Turb Bldg Sump Pump Bkr) (T-1, G-27) __ 1XE-R3D (B Turb Bldg Sump Pump Bkr) (T-1, J-27) 8. Notify RP to survey both MS lines for radiation. 9. GO TO Step 28. 28. Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector, etc.). 29. Verify Main FDW or EFDW controlling properly. 30. Open: __ 1HP-24 __ 1HP-25 31. Secure makeup to LDST.

32. Maintain both SG pressures < 950 psig using either: __ TBVs __ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) Examiner Note: 1A TBVs have tripped to HAND.

33. IAAT all the following exist: __ All SCMs > 0°F __ ES Bypass Permit satisfied __ RCS pressure controllable THEN perform Steps 34 - 35. This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 39 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 6 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

SGTR Tab Crew Response: 34. Bypass applicable ES: To Bypass HPI: __ Bypass HPI CH A, B, C To Bypass LPI: __ Bypass LPI CH A, B, C 35. Bypass applicable Diverse ES: To Bypass HPI: __ Bypass Diverse HPI To Bypass LPI: __ Bypass Diverse LPI NOTE Leak rate prior to reducing SCM is input to Cool Down Plateau at Steps 103 and 203. 36. Estimate SGTR leak rate: _____ + _____ - _____ - _____ = _____ gpm MU SI LD TSR LR Where: MU =Makeup Flow SI =Seal Inlet Hdr Flow LD =Letdown Flow TSR =Total Seal Return Flow LR =Leak Rate

37. Verify any RCP operating.

38. Maintain RCP NPSH during the reduction of SCM: OAC Encl 5.18 (P/T Curves) NOTE If normal pzr spray is available, efforts should be made to minimize IF allowed by RCP NPSH requirements. If normal pzr spray is NOT available, minimize core SCM as low as safely achievable. This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 40 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 7 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP CT-2

SGTR Tab Crew Response: 39. Reduce and maintain core SCM at minimum using any/all of the following methods: __ De-energize all Pzr heaters __ Use Pzr spray - - NOTE The rate of fill of the SG with the tube rupture should be considered when deciding to use alternate depressurization methods. Pzr spray, if available, is preferred to maintain SCM at minimum after using the PORV. This will prevent repetitive cycling of the PORV. 40. IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 40 - 42. NOTE Computer point O1P3367 41 42. Close: __ 1LWD-1 __ 1LWD-2 43. Cycle PORV as necessary. 44. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit. RNO: __ Select OFF for both digital channels on AFIS HEADER A. 45. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit. RNO: __ Select OFF for both digital channels on AFIS HEADER B.

46. Verify RCS temperature > 532°F. NOTE Close monitoring of RCS pressure is essential during the cooldown if ES has not been bypassed. Slowing the cooldown and stopping Pzr spray momentarily may be needed as ES Bypass Permit is approached to avoid ES actuation. This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 41 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 8 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

SGTR Tab Crew Response: 47. Initiate a cooldown as follows: __ Decrease SG pressure to 835 - 845 psig using any of the following: TBV setpoint adjusted to 710 - 720 psig TBVs in manual ADVs __ Maximize cooldown rate limited only by the ability to maintain Pzr level 48. WHEN SG pressure is 835 - 845 psig, THEN adjust SG pressure as necessary to maintain an RCS temperature band of 525°F - 532°F. 49. IAAT any affected SG approaches overfill: THEN perform Steps 49 - 51. RNO: __ GO TO Step 52. 50. Verify TBVs available for steaming affected SGs. 51. Open on all affected SGs: 1A SG 1B SG 1MS-17 1MS-18 NOTE Steaming a SG to prevent overfill should continue even if Tech Spec cooldown rates are exceeded. 52. Steam affected SGs to prevent overfill. 53. Verify at least one open: __ 1MS-24 __ 1MS-33 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 42 of 55 Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 9 of 9 Event

Description:

1TA Lockout, 1B SGTR (M: All) Time Position Applicant's Actions or Behavior SRO OATC/BOP

SGTR Tab Crew Response: 54. Verify a SG without a tube leak is available to supply the Aux Steam header. 55. Open on the SG without a tube leak: 1A SG 1B SG 1MS-24 1MS-33 56. Close on the SG with a tube leak: 1A SG 1B SG 1MS-24 1MS-33 57. Open 1AS-40 while closing 1MS-47. 58. Close on all affected SGs: 1A SG 1B SG 1MS-79 1MS-76 1MS-82 1MS-84 1MS-35 1MS-36 59. Close 1SSH-9.

60. Verify one SG isolated due to steam leak. RNO: __GO TO Step 68. 68. Verify all SCMs > 0°F. 69. GO TO applicable step based on number of RCPs operating: Number of RCPs Operating Applicable Step 4 69 1,2 or 3 70 None 90 71. Verify steaming both SGs. RNO: __ GO TO Step 87. 87. Initiate AP/31 (Primary to Secondary Leakage) Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination). This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 43 of 55 Rule 6 HPI HPI Pump Throttling Limits HPI must be throttled to prevent violating the RV-P/T limit. HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open. HPI must be throttlegpm/pump (including seal injection for A header) when only one HPI pump is operating in a header. Total HPI flow must be throttlegpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-en. Total HPI flow must be throttled < gpm when all the following exist: - LPI suction is from the RBES - piggyback is aligned - either of the following exist: only one piggyback valve is open (1LP-15 or 1LP-16) only one LPI pump operating HPI may be throttled under the following conditions: HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress: All the following conditions must exist: Core SCM > CETCs decreasing All the following conditions must exist: All WR NI Core SCM > Pzr level increasing SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit Maintagpm indicated/pump. This is an instrument error adjusted value that ensures a real value of gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 44 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level > [ acc] will ensure Pzr heater bundles remain covered. 1. Utilize the following as necessary to maintain desired Pzr level: 1A HPI Pump 1B HPI Pump 1HP-26 1HP- 1HP-etpoint or valve demand 1HP-5 IF 1HP-26 will NOT open, THEN throttle 1HP-aintain desired Pzr level. 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT. 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT. 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following: A. Open: 1CS-26 1CS-41 B. Position 1HP-14 to BLEED. C. Notify SRO. 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 45 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. IAAT 1C HPI PUMP is required, THEN perform Ste- GO TO Ste Open: 1HP-24 1HP-25 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 8. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following: A. IF three HPI pumps are operating, THEN secure 1B HPI PUMP. B. IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers. C. GO TO Ste Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 46 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-aintain desired Pzr level. Throttle the following as required to maintain desired Pzr level: 1HP-26 1HP- 1. IF at least two HPI pumps are operating, AND 1HP-26 will NOT open, THEN throttle 1HP-maintain desired Pzr level. 2. IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-NOT open, THEN throttle 1HP-aintain desired Pzr level.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 47 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IAAT LDST level CANNOT be maintained, THEN perform Step 11. GO TO Step 12. 11. Perform the following: Open 1HP-24. Open 1HP-25. Close 1HP-16. 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 13. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP. NOTE 12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 48 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-Unit 1 RC Bleed Transfer Pump Rm.). 14. IAAT two Letdown Filters are desired, THEN perform the following: Open 1HP- Open 1HP-18 15. IAAT all of the following exist: Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41} GO TO Step 35. 16. Open: 1CC- 1CC-8 1. Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system. 2. GO TO Step 35. Ensure only one CC pump running. 18. Place the non-running CC pump in AUTO. Verify both are open: 1HP-1 1HP-2 1. IF 1HP-1 is closed due to 1HP-3 failing to close, THEN GO TO Step 21. 2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21. GO TO Step 23. NOTE Verification of leakage requires visual observation of East Penetration Room. 21. Verify letdown line leak in East Penetration Room has occurred. GO TO Step 23. 22. GO TO Step 35.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 49 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. Monitor for unexpected conditions while restoring letdown. 24. Verify both letdown coolers to be placed in service. 1. IF 1A letdown cooler is to be placed in service, THEN open: 1HP-1 1HP-3 2. IF 1B letdown cooler is to be placed in service, THEN open: 1HP-2 1HP-4 3. GO TO Step 26. 25. Open: 1HP-1 1HP-2 1HP-3 1HP-4 26. Verify at least one letdown cooler is aligned. Perform the following: A. Notify CR SRO of problem. B. GO TO Step 35. Close 1HP-6. 28. Close 1HP- Verify letdown temperature < 125°F. 1. Open 1HP-13. 2. Close: 1HP-8 1HP-&11 3. IF any deborating IX is in service, THEN perform the following: A. Select 1HP-14 to NORMAL. B. Close 1HP-16. 4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 50 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Open 1HP-5. 31. Adjust 1HP-for gpm letdown. 32. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL. 33. Open 1HP-6. 34. Adjust 1HP-control desired letdown flow. NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level. 35. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown). 36. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following: A. Obtain SRO concurrence to reduce running HPI pumps. B. Secure the desired HPI pumps. C. Place secured HPI pump switch in AUTO, if desired. IAAT all the following conditions exist: Makeup from BWST NOT required LDST level > All control rods inserted Cooldown Plateau NOT being used THEN close: 1HP-24 1HP-25 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 51 of 55 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST. GO TO Ste WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following: A. Stop 1A BLEED TRANSFER PUMP. B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1 RC Bleed Transfer Pump Rm.). C. Close 1CS-46. D. Start 1A BLEED TRANSFER PUMP. E. Locally throttle 1CS-48 (1A BHUT Recirc) to obta- discharge pressure. F. Stop 1A BLEED TRANSFER PUMP. Verify two Letdown Filters in service, AND only one Letdown filter is desired. GO TO Step 42. 41. Perform one of the following: Place 1HP-ch to CLOSE. Place 1HP-18 switch to CLOSE. 42. WHEN directed by CR SRO, THEN EXIT this enclosure.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 52 of 55 Subsequent Actions EP/1 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All SWGR de-energized {13} GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer GO TO EHT tab. LOHT 6. Loss of heat transfer (including loss of all Main and Emergency FDW) GO TO LOHT tab. Heat transfer is or has been excessive GO TO EHT tab. EHT 8. Indications of SGTR gpm GO TO SGTR tab. SGTR Turbine Building flooding NOT caused by rainfall event GO TO TBF tab. TBF Inadvertent ES actuation occurred Initiate AP(Inadvertent ES Actuation). ES 11. Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 12. Power lost to all SWGR and any SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 13. RCS leakage > gpm with letdown isolated Notify plant staff that Emergency Dose Limits are in affect using PA system. EDL 14. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and NS(Reportability). NOTIFY Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 53 of 55 SGTR EP/1 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. AFTER Rx trip pushbutton Depressed: PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All SWGR de-energized {13} GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = AND HPI forced cooling NOT in progress IF NOT previously performed, THEN GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer GO TO EHT tab. LOHT 6. Loss of heat transfer GO TO LOHT tab. Heat transfer is or has been excessive GO TO EHT tab. EHT 8. Indications of SGTR in another SG after SGTR tab initiated RETURN TO beginning of SGTR tab. SGTR Inadvertent ES actuation occurred Initiate AP(Inadvertent ES Actuation). ES Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 11. Power lost to all SWGR and any SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 14. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and AD-LS-ALL-(Notification/Reportability Evaluation). Notify plant staff that Emergency Dose Limits are in affect using PA system. NOTIFY And EDL Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 54 of 55 CRITICAL TASKS CT-1 Outside Air Booster Fans are started to minimize radiation exposure to control room personnel. (Within 30 minutes of SGTR) TCA #20 CT-2 SCM is minimized to reduce the radioactive release to the atmosphere by minimizing the Pri - Sec leak rate.

SAFETY: Take a Minute UNIT 0 (OSM) SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO) Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 894 100% Power 100% Power RCS Leakage: 0.01 gpm No WCAP Action EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO) Component/Train OOS Date/Time Restoration Required Date/Time TS/SLC # AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO) Primary Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%). 1RIA-3 and 5 removed from RB. Secondary Feedwater valve DP selected to A1 and B2 for maintenance AMSAC/DSS bypassed 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. Reactivity Management (CR SRO) RCS Boron 83 ppmB Gp 7 Rod Position: 92% Withdrawn Batch additions as required for volume control. Human Performance Emphasis (OSM) Procedure Use and Adherence Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 4 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO ________________________ ________________________OATC ________________________ ________________________BOP Initial Conditions: Reactor Power = Critical below POAH Turnover: LDST pressure low Unit startup in progress Event No. Malfunction No. Event Type* Event Description 0a 0b 0d 0c 1 Override C: BOP, SRO (TS) Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) 2 R: OATC, SRO Increase power to 6-7 % 3 Override C: BOP, SRO 1B FWPT Auxiliary Oil Pump Trip 4 Override C: BOP, SRO 1C HWP Casing Water Level Low 5 SRO (TS) TD EFDWP oil sump dry 6 Override C: OATC, SRO PORV fails open 7 MCR022 C: OATC, SRO Dropped Control Rod(s) requiring a reactor trip 8 MSS270 MSS360 M: ALL 1A MSLB inside containment 1B MD EFDW fails to start in AUTO 1C HPIP fails to start on ES * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 2 of 59 Scenario 4 Event Summary Event 1: The BOP will increase the pressure in the LDST using OP/1/A/1106/017. 1H-1 (Hydrogen to LDST valve) will fail open resulting in overpressurization of the LDST. This will cause all HPI pumps to be declared INOPERABLE until pressure is reduced. Event 2: The OATC will increase power from below POAH to ~ 6 - 7 %. Event 3: The Auxiliary Oil Pump for the 1A FWPT will trip causing the Emergency Oil Pump to start. Per the ARG, the candidate will attempt to start the Auxiliary Oil Pump which will fail. Shortly afterwards, the alarm for FWPT 1A Emergency Oil Pump Overload will alarm which will require the candidate to attempt to start the Auxiliary Oil Pump. Not being able to start it, they will be directed to stop the Turning Gear Oil Pump and Emergency Oil pump. Event 4: The 1C HWP will receive a casing low level alarm. This will require the BOP to start a standby HWP and secure the 1C HWP. Event 5: An AO reports that the TD EFDWP oil sump is dry. The SRO will address Tech Specs. The SRO should direct the OATC to place the TD EFDW pump switch in Pull To Lock (PTL). Event 6: The PORV will fail open causing RCS pressure to decrease rapidly. The operator will be required to close 1RC-4 (PORV Block valve) in order to stop the pressure decrease. Event 7: Two control rods will fall into the core requiring a manual reactor trip. Event 8: When the reactor trips, a steam line break will occur inside containment. The 1B MD EFDW pump will not start when the MFWPs trip so it will require manual start in order to feed the 1B SG. 1C HPIP will fail to start on ES which will require the operators to open 1HP-409 to provide flow to the B HPI header if required.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 3 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 1 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO)(TS) Time Position Applicant's Actions or Behavior SRO BOP OP/1/A/1106/017 Crew Response: SRO directs the BOP to add H2 to the LDST using OP/1/A/1106/017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition). OP/1/A/1106/017 Rev 122 2.1 Notify Chemistry of hydrogen addition prior to adding hydrogen. {21} ________________________ _____ Person Notified Date NOTE: OP/0/A/1108/001 (Curves And General Information) and computer may be referred to for LDST Pressure vs Level curve. {7} LDST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LDST. If Unit 1 is shutdown and will be placed in MODE 5, Nitrogen should be added to LDST to maintain LDST Pressure vs Level. If Unit 1 is shutdown and will NOT be placed in MODE 5, Hydrogen should be added to LDST to maintain LDST Pressure vs Level. 2.2 Immediately prior to pressurization determine lowest reading of diverse LDST level indications: _____ inches. 2.3 For existing LDST level determine LDST Pressure allowable per LDST Pressure vs Level curve: _____ psig. 2.4 Notify Operator at H2 Cage to pressurize primary hydrogen. NOTE: Operator should be in constant communication with CR to close 1H-26 if 1H-1 fails open. BOOTH CUE: When directed to open 1H-26, use Manual Valves and position 1H-93 approximately 20% open 2.5 Direct Operator to open 1H-26 (LDST Block). (A-2-N of LDST Rm) This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 4 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 2 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior SRO BOP OP/1/A/1106/017 Crew Response: Examiner Booth Note: Once LDST pressure is being increased, 1H-1 (LDST SUPPLY) will fail open. 2.6 Direct Operator to use explosive detector to monitor the following: Pressurized, non-welded H2 piping and fittings within local area of addition Loop seal (A-2-N of LDST Rm) 2.7 Cycle 1H-1 (H2 TO LDST) as required to pressurize LDST per LDST Pressure vs Level curve.

Booth Note: When 1H-1 is opened, Fire Timer 1 to fail it open. 2.8 WHEN Hydrogen addition complete, ensure closed 1H-1 (H2 TO LDST). Examiner Note: BOP should determine that 1H-1 has failed open and direct the AO to close 1H-26. 2.9 Direct Operator to close 1H-26 (LDST Block). (A-2-N of LDST Rm) Booth Note: 1H-26 will not be closed until LDST pressure is outside acceptable range. 1SA-02/D-2, HP Approaching LDST Operating Limits, actuates BOP refers to the ARG. 1SA-2/D-2 1SA-2/D-2 Rev 33 3.1 Verify LDST pressure/level are within the acceptable operating region of the LDST PRESSURE vs. LEVEL enclosure in OP/0/A/1108/001 (Curves and General Information). (Page 6) [It will NOT be within limits and will require Both Trains of HPI be declared INOPERABLE-. TS 3.5.2] 3.2 IF necessary, vent LDST to GWD per OP/1/A/1104/002 (HPI System). 3.3 IF necessary, add hydrogen to establish desired LDST pressure per OP/1/A/1106/017 (Hydrogen System). This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 5 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 3 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior SRO BOP OP/1/A/1104/002 Crew Response: SRO directs the BOP to vent LDST to GWD per OP/1/A/1104/002 (HPI System), Encl. 4.16, (Lowering LDST Pressure) OP/1/A/1104/002 (HPI System), Encl. 4.16, (Lowering LDST Pressure)Rev 167 3.1 Close 1GWD-20 (LDST Vent Blk). (A-2-LDST Hatch Area) 3.2 Open 1GWD-19 (LDST VENT). CAUTION: LDST pressure should be within curves of Enclosure "LDST Pressure Vs Level" of OP/0/A/1108/001 (Curves and General Information). NOTE: If LDST pressure is < 30 psig, leakage from BWST into HPI System may occur. (R.M.) 3.3 Throttle open 1GWD-20 (LDST Vent Blk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header. (A-2-LDST Hatch Area) 3.4 IF required, start Standby GWD Compressor per OP/1-2/A/1104/018 (GWD System). 3.5 WHEN desired LDST pressure obtained, close 1GWD-19 (LDST VENT). 3.6 IF started, stop Standby GWD Compressor. -20 (LDST Vent Blk). (A-2-LDST Hatch Area) TS 3.5.2, HIGH PRESSURE INJECTION Condition C.2 (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) Verify by administrative means that the ADV flow path for each steam generator is OPERABLE. Condition C.3 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore HPI train to Operable status. Condition H (Immediately) Enter LCO 3.0.3 TS 3.0.3 (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) be in Mode 3 This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 6 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 4 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior SRO BOP OP/0/A/1108/001 This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 7 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 1 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO) Time Position Applicant's Actions or Behavior SRO

OATC

OP/1/A/1102/001 Crew Response: SRO directs the OATC to increase power to ~7% using OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, starting at step 3.36 OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, Step 3.36 Rev 309 NOTE: Point Of Adding Heat (POAH) is normally achieved from 0.05 to 0.15% power on Wide Range Indications. {27} When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, and SUR will decrease with negative Moderator Temperature Coefficient. (R.M.) Wide Range indications are used since Source Range NIs saturate. (R.M.) 3.36 Begin reactor power increase to 0.5 - 1.0 % at 0.5 DPM SUR. (R.M.) 3.37 WHEN above POAH, begin reactor power increase to 2.5 - 3.5 %. (R.M.) 3.38 WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215" to 225" PZR Level. NOTE: TAVE error is blocked when on Low Level Limit and TAVE is < setpoint. Core reactivity effects are minimized with Rx in automatic. (R.M.) 3.39 WHEN at 2.5 - 3.5 % Power, perform the following: (R.M.) 3.39.1 Place REACTOR MASTER to "AUTO". 3.39.2 Place DIAMOND to "AUTO". 3.39.3 Ensure TURBINE MASTER Setpoint to 880 - 890 psig. 3.40 Perform the following: Ensure complete Enclosure "Prior To Entry Into MODE 1" of PT/1/A/0630/001 (Mode Change Verification). {55} Review mechanical maneuvering rates and allowable ramp rates in PT/0/A/1103/020 (Power Maneuvering Guidelines). {54} (R.M.) This event is complete when power is stable at ~ 6-7 %, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 8 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 2 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/001 Crew Response: 3.41 IF AT ANY TIME all the following: All operable T Cold indications > 550°F SSF inoperable only due to low decay heat, notify SM the SSF is Available for Unit 1. 3.42 Ensure acceptable point status for plant startup for MODE 1: OAC Alarm Screen Review OAC Point Processing Log NOTE: OAC Points can be found on Turn-On Code FDW02 3.43 Set temporary alarms on the following: OAC Point O1E2129 (FDW LOOP A COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%. OAC Point O1E2130 (FDW LOOP B COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%. Note on Turnover sheet temporary alarms set on Composite Valve Demand NOTE: At Composite Valve Demand of 8.8% decreasing, ICS removes a valve sequencing bias that forces the Startup Control valves open to approximately 90% and the Main Control Valves to close. At Composite Valve Demand of 9.8% increasing, ICS inserts a valve sequencing bias that forces the Startup Control valves to close to approximately 10% and the Main Control Valves to open. When Composite Valve Demand valve sequencing bias is inserted at 9.8% on a power increase and then decreases below 8.8%, the unit is subject to a possible FDW transient due to the valve sequencing bias being inserted and then subsequently removed. A power change may be required to stabilize FDW flow above OR below sequencing bias setpoints. This event is complete when power is stable at ~ 6-7 %, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 9 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 3 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/001 Crew Response: 3.44 WHILE power change is in progress, monitor the following indications: Appropriate ranged NIs Neutron error RCS Loop T (Curve for "Loop T Vs Reactor Power" is in PT/1/A/0600/001) FDW Flow (Curve for "Expected Feedwater Flow Per Header Vs Reactor Power" is in OP/0/A/1108/001) OAC Point O1E2129 (FDW LOOP A COMPOSITE VALVE DEMAND) OAC Point O1E2130 (FDW LOOP B COMPOSITE VALVE DEMAND) 3.45 Begin power increase to 6% to 7% per Enclosure 4.16 (CTP Adjustments) (Page 10) 3.46 Ensure 'E' Heater outlet temperature being maintained at upper end of 100-180OF band. 3.47 WHILE power increasing in this enclosure, throttle to maintain 2300 to 6000 gpm on operating FDWP: 1FDW-53 (1A FDWP RECIRC CONTROL) 1FDW-65 (1B FDWP RECIRC CONTROL) 3.48 WHEN Reactor Power is > 5%, perform the following: Ensure MODE 1 selected on OAC. Ensure MODE 1 selected for Unit 1 in TSAIL. Announce on Plant Page "Unit 1 has entered MODE 1". Notify Assistant Outage Manager of Unit 1 entry into MODE 1. ________________________ _____/______ Person Notified Date / Time Remove note from turnover sheet: "When in MODE 2, evaluate or restrict evolutions involving MS, FDW, and EFDW to minimize changes to RCS temperature and reactor power." (R.M.) Remove note from turnover sheet: "In MODE 1 or 2, except during PT/0/A/0711/001 (ZPPT), if either loop TAVE is < 532°F, perform SR 3.4.2.1 per PT/1/A/0600/001 (Periodic Instrument Surveillance)". Begin Primary to Secondary Leakage Monitoring During Startup per OP/0/A/1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation). This event is complete when power is stable at ~ 6-7 %, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 10 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 4 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/001 Crew Response: 3.49 Perform the following per PT/0/A/0230/001 (Radiation Monitor Check): Ensure 1RIA-48 alarm setpoints adjusted for Mode 1. Ensure 1RIA-49 alarm setpoints adjusted for Mode 1. 3.50 Ensure complete one of the following to secure minimum FDW Flow to SGs: IF in progress, Enclosure 4.10 (Providing Minimum FDW Flow to SGs) IF in progress, Enclosure "Providing Minimum FDW Flow to SGs" of OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown). OP/1/A/1102/001 Enclosure 4.16 (CTP Adjustments) 2.1 Verify REACTOR MASTER in AUTO 2.2 Verify Diamond in AUTO 2.3 IF expected power change < 1%, ensure R2 reactivity management control established per SOMP 1-02 2.4 IF expected power change > 1%, ensure R1 reactivity management control established per SOMP 1-02 3.1 WHILE enclosure is in progress, monitor the following indications: Appropriate NIs Neutron error FDW flow 3.2 IF AT ANY TIME hold in power is desired, ensure HOLD selected 3.3 IF AT ANY TIME hold in power is NOT required, ensure HOLD is NOT selected This event is complete when power is stable at ~ 6-7 %, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 11 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 5 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO) Time Position Applicant's Actions or Behavior OATC

OP/1/A/1102/001 Crew Response: OP/1/A/1102/001 Enclosure 4.16 (CTP Adjustments) 3.4 IF change in power/rate is desired, perform the following: 3.4.1 Review the following regarding current power change: Appropriate :controlling enclosure of this procedure PT/0/A/1103/020 (Power Maneuvering Predictions) IF in progress, PT/0/A/0811/001 (Power Escalation Test) IF available, Maneuvering Plan COLR for CRD Groups 5-8 position limits, Imbalance, & QPT 3.4.2 Ensure HOLD is selected 3.4.3 Ensure selected %/MIN or %/HR on RATE SET pushbutton 3.4.4 Ensure desired rate selected on RATE SET thumbwheels 3.4.5 Ensure rate selected is within above limits 3.4.6 Insert desired CTPD SET using INCREASE/DECREASE pushbuttons 3.4.7 Ensure CTPD SET is within above limits 3.4.8 Ensure HOLD is NOT selected 3.4.9 WHEN desired CTP is achieved, select 0.0 on RATE SET thumbwheels This event is complete when power is stable at ~ 6-7 %, or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 12 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 3 Page 1 of 1 Event

Description:

1B FWPT Auxiliary Oil Pump Trip (C, BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP

Plant Response: 1SA-08/C-6 FWPT "B" EMERGENCY OIL PUMP RUN in alarm FWPT B Emergency Oil Pump starts Crew Response: SRO will direct the BOP to refer to 1SA-08/C-6. 1SA-08/C-3 1SA-08/C-6 FWPT "B" EMERGENCY OIL PUMP RUN Rev 35 3.1 Verify that B FWPT emergency oil pump is running.

3.2 IF applicable, verify B FWPT is still on turning gear. [It will be]

3.3 Try to restart B FWPT auxiliary oil pump. [It will fail to start] 3.4 IF restart fails, notify Maintenance for repairs. Booth Operator Note: Approximately 2 minutes after firing timer 3, Timer 12 will auto actuate which will trip the Emergency Oil Pump and cause 1SA-08/C-7, (FWPT "B" EMERGENCY OIL PUMP OVERLOAD) to alarm. 1SA-08/C-4 1SA-08/C-7 FWPT "B" EMERGENCY OIL PUMP OVERLOAD 3.1 IF available, start Auxiliary Oil Pump and stop Emergency Oil Pump. 3.2 IF AOP is NOT available, stop Turning Gear Motor and emergency Bearing Oil Pumps. 3.3 Notify Maintenance for repairs.

3.4 As soon as EBOP OR Auxiliary Oil Pump becomes available, start pump and place Turbine on Turning Gear. This event is complete when Turning Gear Motor is secured, or as directed by the Lead Examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 13 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 4 Page 1 of 1 Event

Description:

1C HWP Casing Water Level Low (C: BOP, SRO) Time Position Applicant's Actions or Behavior SRO/BOP 1SA-9/E-5 Plant Response: 1SA-9/E-5 HWP C CASING WATER LEVEL LOW Crew Response: BOP will address the ARG 1SA-9/E-5 Rev 47 3.1 IF '1C' HWP is in operation, then immediately: Start a standby HWP. Trip '1C' HWP. Bypass Powdex. [Open 1C-14/1C-15] Decrease load. 3.2 Monitor hotwell level.

3.3 Determine cause of low level alarm (possible suction filter clogging) and initiate corrective action necessary to return pump to normal operation.

Examiner Note: The crew may use OP/1/A/1106/002 (Condensate and FDW System) to bypass Powdex OP/1/A/1106/002 Enclosure 4.19 (Placing Powdex In/Out of Service)Rev 169 3.1 IF Powdex is to be removed from service for an extended period of time AND condensate system will NOT be shutdown, perform the following: 3.1.1 Ensure MSDD System in service 3.1.2 Notify Chemist that Powdex will be removed from service for an extended period of time 3.2 Ensure Open 1C-14/1C-15 (POL DEMIN BYPASS CONTROL) 3.3 Place note on Turnover sheet that Powdex has been removed from service 3.4 Notify Chemist that Powdex has been removed from service This event is complete when the standby HWP has been started, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 14 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 5 Page 1 of 1 Event

Description:

TD EFDWP oil sump dry (SRO)(TS) Time Position Applicant's Actions or Behavior SRO

Plant response: Simulator Operator call the Control Room as the WCC SRO and report that the Basement AO found the Unit 1 TD EFDWP oil sump with no oil indicating on the dipstick. Report that the WCC and FIN-24 are investigating the situation to determine the cause of the problem. No oil has been found leaking from any equipment. Crew response: SRO should make the decision to place TD EFDWP in "Pull to Lock". TS 3.3.14 EMERGENCY FEEDWATER (EFW) PUMP INITIATION CIRCUITRY Condition B.1 (Immediately) Declare the affected EFW pump inoperable. TS 3.7.5 EMERGENCY FEEDWATER (EFW) SYSTEM Condition B.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore turbine driven EFW pump and EFW flow path to OPERABLE status. SRO refer to TS 3.3.14 Condition B. Declare the affected EFWP inoperable Immediately SRO refer to TS 3.7.5 Condition B1 Restore TD EFDWP within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Booth Cue: If asked, inform crew that the TD was on the purifier last shift.

This event is complete when the Tech Spec determination has been made or when directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 15 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 6 Page 1 of 2 Event

Description:

PORV fails open (C: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC

CT-1 AP/1/A/1700/044 Plant Response: 1SA-18/A1 ( Pressurizer Relief Valve Flow) in alarm 1RC-66 indicates open Acoustic monitor indicates 1RC-66 open RCS pressure decreasing Crew Response: BOP should recognize that RCS pressure is below PORV setpoint and close the PORV Block Valve (1RC-4). This is an Immediate Action from AP/44 Abnormal Pressurizer Pressure Control. SRO should enter AP/1/A/1700/044 AP/1/A/1700/044 Abnormal Pressurizer Pressure Control Rev 4 Immediate Manual Actions 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4. 3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE. 3.3 IAAT all the following conditions exist: __ RC pressure < 2155 psig __ RC pressure decreasing without a corresponding decrease in PZR level THEN close 1RC-3. Subsequent Actions 4.1 Announce AP entry using the PA system. 4.2 GO TO the applicable step per the following table: Failure Caused RCS Pressure Step Decrease 4.3 Increase 4.18 This event is complete when 1RC-4 is closed and RCS pressure is stable, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 16 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 6 Page 2 of 2 Event

Description:

PORV fails open (C: OATC, SRO)(TS) Time Position Applicant's Actions or Behavior SRO/OATC AP/1/A/1700/044 Crew Response: 4.3 Verify 1RC-4 is closed. 4.4 Verify 1RC-3 is closed. NOTE 1RC-3 must NOT a thermal transient in piping between 1RC-3 and the PZR spray nozzle. 4.5 Position 1RC-3 as required to maintain RC pressure within desired band. 4.6 GO TO Step 4.13. 4.13 Verify PZR heaters maintaining RCS pressure within desired band. 4.14 Notify SPOC to repair malfunctioning component. 4.15 Ensure requirements of following are met: __ TS 3.4.1 (RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits) __ TS 3.4.9 (Pressurizer) __ TS 3.4.12 (Low Temperature Overpressure Protection System) __ SLC 16.5.1 (Reactor Coolant System Vents) 4.16 WHEN repairs complete, THEN place following components in desired position for current plant conditions as determined by CR SRO: __ 1RC-1 __ 1RC-3 __ 1RC-4 __ PZR heater bank #1 __ PZR heater bank #2 __ PZR heater bank #3 __ PZR heater bank #4 TS 3.4.1, REACTOR COOLANT SYSTEM Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Restore RCS DNB parameter(s) to within limit. COLR DNB Limit = 2125 psig This event is complete when 1RC-4 is closed and RCS pressure is stable, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 17 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 7 Page 1 of 1 Event

Description:

Dropped Control Rod(s) requiring a reactor trip (C: OATC, SRO) Time Position Applicant's Actions or Behavior SRO/OATC BOP

AP/1/A/1700/001 Plant Response: Group 6 Rod 3 drops into the core Group 6 Rod 6 drops into the core Statalarm 1SA-2/A-10 (CRD GLOBAL TROUBLE) Statalarm 1SA-2/B-10 (CRD ASYMMETRIC ROD POSITION ERROR) Statalarm 1SA-2/D-9 (CRD OUT INHIBIT) Statalarm 1SA-5/A-5 (1A RPS TROUBLE) Statalarm 1SA-5/B-5 (1B RPS TROUBLE) Statalarm 1SA-5/D-5 (1D RPS TROUBLE) Crew Response: Crew should recognize 2 dropped control rods and trip the reactor in accordance with OMP 1-18 If the crew does not recognize the 2nd dropped control rod, they will enter AP/1/A/1700/001 (Unit Runback) AP/1/A/1700/001 (Unit Runback) Rev15 NOTE If more than one runback condition exists, ICS will respond by selecting the fastest runback rate and the lowest load limit. The most limiting runback will be the one with the fastest runback rate and the shortest duration. It is possible for a FDWP to become unable to feed the SGs but not be tripped. In this case a signal would not be sent to RPS or the EFDWP start circuit. 4.1 GO TO the most limiting section per the following table: 4H Asymmetric Control Rod (1% / min to 55% power) 1. IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1. 2. IAAT more than one control rod is dropped or the group average, THEN trip the Rx. This event is complete when the reactor is manually tripped, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 18 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 1 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC BOP CT-2 EOP Plant Response: 1SA-2/D-3, RC Press High/Low Statalarm 1SA-02/A-9 (MS PRESS HIGH/LOW) Crew Response: Examiner Note: Crew will be performing IMAs and Subsequent Actions as a result of the manual reactor trip due to two dropped control rods. IMAs EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed. 3.5 Verify RCP seal injection available. SYMPTOM CHECK The BOP will verify the following: Power Range NIs NOT < 5% Power Range NIs NOT decreasing Rule 1, ATWS/Unanticipated Nuclear Po Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) Rule 3, Loss of Main or Emerg FDW Rule 4, Initiation of HPI Forced Cooling (Inability to feed SGs and > 2300 psig, N limit reached, or PZR level > 375") Uncontrolled Main steam line(s) pressure decrease Rule 5, Main Steam Line Break CSAE Offgas alarms Process monitor alarms (RIA-40, 59,60), Area monitor alarms (RIA-16/17) None (SGTR Tab is entered when identif SG Tube Leakage > 25 gpm) Examiner note: BOP should manually start the 1B MD EFDWP. BOP will perform Rule 5 (Main Steam Line Break) (Page 25) SRO will review IMAs and transfer to the Subsequent Actions Tab. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 19 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 2 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC Subsequent Actions Tab Crew Response: SRO will review the Subsequent Action Tab Parallel Action (Yellow) page (Page 56) and transfer to the Excessive Heat Transfer (EHT)Tab. EHT Tab SRO will review the EHT Tab Parallel Action (Yellow) page and determine that ES has actuated and direct the OATC to perform Encl. 5.1 ES Actuation (Page 36) 1. Verify any SG pressure < 550 psig. [1A SG should be < 550 psig at this point] 2. Ensure Rule 5 (Main Steam Line Break) in progress or complete. 3. Place the following in HAND and decrease demand to zero on all affected SGs: 1A SG 1B SG 1FDW-32 1FDW-41 1FDW-35 1FDW-44 4. Close the following on all affected SGs: 1A SG 1B SG 1FDW-372 1FDW-382 1MS-17 1MS-26 1MS-79 1MS-76 1MS-35 1MS-36 1MS-82 1MS-84 1FDW-368 1FDW-369 5. Verify level in both SGs < 96% O.R. 6. IAAT core SCM is > 0°F, THEN perform Steps 7 and 8. RNO: GO TO Step 9. 7. Throttle HPI per Rule 6 (HPI). 8. Verify letdown in service. RNO: __ IF desired to restore letdown, THEN initiate Encl 5.5 (Pzr and LDST Level Control). (Page 28) This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 20 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 3 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC EHT Tab Crew Response: 9. Verify any SG has an intact secondary boundary (intact SG). [1B SG is intact] NOTE If only one SG is intact and has been isolated for SGTR, the following steps will unisolate and use it for heat removal. 10. Open the following on all intact SGs: 1A SG 1B SG 1FDW-372 1FDW-382 1FDW-368 1FDW-369 1MS-17 1MS-26 11. Start MDEFDWP associated with all intact SGs: 1A SG 1B SG 1A MDEFDWP 1B MDEFDWP

12. Feed and steam all intact SGs to stabilize RCS P/T using either: TBVs Dispatch two operators to perform Encl 5.24 (Operation of the ADVs). 13. GO TO Step 32. 32. Verify any: __ HPI has operated in the injection mode while NO RCPs were operating __ A cooldown below 400°F at > 100°F/hr has occurred RNO: GO TO Step 34. 33. Initiate Rule 8 (Pressurized Thermal Shock (PTS)). 34. Verify both closed: __ 1MS-24 __ 1MS-33 This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 21 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 4 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC EHT Tab Crew Response: 35. Open 1AS-8. 36. Close 1SSH-9. 37. Perform notifications: __ Notify Chemistry to determine RCS boron concentration. __ Notify Secondary Chemistry to check for indications of SGTR. {2} __ Notify RP to check for indications of SGTR. 38. IAAT RCS boron is determined to be insufficient for adequate SDM, THEN initiate Encl 5.11 (RCS Boration). 39. IAAT all exist: __ ES Bypass Permit satisfied __ All SCMs > 0°F __ RCS pressure controllable THEN perform Steps 40 - 41. RNO: GO TO Step 42. 40. Bypass applicable ES: To Bypass HPI: __ Bypass HPI ES CH A,B,C To Bypass LPI: __ Bypass LPI ES CH A,B,C 41. Bypass applicable Diverse ES: To Bypass HPI: __ Bypass Diverse HPI To Bypass LPI: __ Bypass Diverse LPI 42. Verify any SG is dry. NOTE Minimizing SCM reduces tensile stress on the SG. PORV should be used if Pzr spray is not available. Procedure progression may continue when actions to minimize SCM are in progress. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 22 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 5 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC EHT Tab Crew Response: 43. Maintain minimum SCM using the following methods as necessary: __ De-energize all Pzr heaters __ Use Pzr spray __ Use PORV 44. Verify any RCP operating. RNO: GO TO Step 46. 45. Maintain RCP NPSH. OAC Encl 5.18 (P/T Curves) 46. Initiate Encl 5.16 (SG Tube-to- Control). NOTE RCP 1A1 provides the best Pzr spray. 47. IAAT all exist: __ < one RCP operating in any loop __ All SCMs > 0°F __ RCP available in an idle loop THEN initiate Encl 5.6 (RCP Restart) to start one RCP in each idle loop. 48. IAAT all exist: __ RBS actuated __ RB pressure < 10 psig __ 1RIA-57 NOT in alarm __ 1RIA-58 NOT in alarm THEN stop both RBS pumps. 49. IAAT Tcold approaches 470°F, AND all RCPs are operating, THEN ensure < four RCPs are operating. 50. IAAT THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 51. Verify all SCMs > 0°F. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 23 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 6 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC EHT Tab Crew Response: RNO: __ GO TO Step 54. 54. Verify required RCS makeup flow within normal makeup capability.

55. Verify either: __ Any SG isolated __ Any SG has an unisolable steam leak 56. GO TO FCD tab. Forced Cooldown Tab 1. IAAT cooldown rate CANNOT be controlled within Tech Spec limits: THEN GO TO EHT tab. 2. Verify letdown in service. RNO: 1. __ Ensure CC System in operation. 2. __ IF 1A Letdown Cooler available, THEN open the following: __ 1HP-1 __ 1HP-3 3. __ IF 1B Letdown Cooler available, THEN open the following: __ 1HP-2 __ 1HP-4 4. Close the following: __ 1HP-6 __ 1HP-7 5. __ Open 1HP-5. 6. __ Adjust 1HP- 7. __ Open 1HP-6. 8. __ Adjust 1HP-7 to control desired letdown flow. 3. Establish and maintain appropriate level per Rule 7 (SG Feed Control) and pressure in available intact SGs. 4. IAAT Tcold approaches 470°F, THEN ensure < four RCPs operating. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 24 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 7 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior SRO/OATC Forced Cooldown Tab Crew Response: 5. IAAT Tcold approaches 300°F, THEN ensure < three RCPs operating. 6. IAAT all the following exist: __ ES Bypass Permit satisfied __ All SCMs > 0°F __ RCS pressure controllable THEN perform Steps 7 - 8. 7. Bypass applicable ES: To Bypass HPI: __ Bypass HPI ES CH A,B,C To Bypass LPI: __ Bypass LPI ES CH A,B,C 8. Bypass applicable Diverse ES: To Bypass HPI: __ Bypass Diverse HPI To Bypass LPI: __ Bypass Diverse LPI 9. IAAT any SG is < 700 psig, AND AFIS is NOT actuated on that SG, THEN select OFF on both Digital Channels 1&2 for that header: A Header B Header DIG CH 1 OFF DIG CH 1 OFF DIG CH 2 OFF DIG CH 2 OFF 10. Stabilize RCS temperature.

11. Close 1HP-26. 12. Stop 1C HPI Pump.

13. Adjust 1HP-120 for desired setpoint. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 25 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 8 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior BOP RULE 5 Crew Response: 1. Perform on affected headers: A Header B Header On AFIS HEADER A, depress CH. 1 INIT. On AFIS HEADER B, depress CH. 1 INIT. On AFIS HEADER A, depress CH. 2 INIT. On AFIS HEADER B, depress CH. 2 INIT. Select OFF for 1A MD EFDWP. Select OFF for 1B MD EFDWP. Trip both Main FDWPTs. Trip both Main FDWPTs. Close 1FDW-315. Close 1FDW-316. Place 1FDW-33 switch to CLOSE. Place 1FDW-42 switch to CLOSE. Place 1FDW-31 switch to CLOSE. Place 1FDW-40 switch to CLOSE. Close 1PSW-22. Close 1PSW-24. Close 1PSW-23. Close 1PSW-25. Examiner Note: The 1B MD EFDW Pump failed to start automatically.

2. Verify 1 TD EFDW PUMP operating. RNO: 1__IF MD EFDWP for the intact SG is operating SG is operating, THEN GO TO Step 5. [IT WILL NOT BE OPERATING] 2.__Start 1 TD EFDW PUMP. 3. Verify 1 TD EFDW PUMP is feeding affected SGs. [1FDW-315 is closed] RNO: GO TO Step 5. 5. Verify 1B SG is an affected SG. RNO: GO TO Step 7. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 26 of 59 Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 9 of 9 Event

Description:

1A MSLB inside containment (M: All) Time Position Applicant's Actions or Behavior BOP RULE 5 Crew Response: 7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either: __ TBVs __ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs). CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled. 8. WHEN all exist: __ Core SCM > 0°F __ Pzr level increasing THEN continue. 9. Verify ES HPI actuated. 10. Place Diverse HPI in BYPASS. 11. Perform both: __ Place ES CH 1 in MANUAL. __ Place ES CH 2 in MANUAL. 12. Perform the following to stabilize RCS P/T: __ Throttle HPI. __ Reduce 1HP- __ Adjust steaming of unaffected SG as necessary to maintain CETCs constant. 13. WHEN CETCs have stabilized, THEN resume use of Tc for RCS temperature control. 14. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. 15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete. 16. WHEN directed by CRS, THEN EXIT. This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 27 of 59 Rule 6 HPI HPI Pump Throttling Limits HPI must be throttled to prevent violating the RV-P/T limit. HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open. HPI must be throttlegpm/pump (including seal injection for A header) when only one HPI pump is operating in a header. Total HPI flow must be throttlegpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-en. Total HPI flow must be throttled < gpm when all the following exist: - LPI suction is from the RBES - piggyback is aligned - either of the following exist: only one piggyback valve is open (1LP-15 or 1LP-16) only one LPI pump operating HPI may be throttled under the following conditions: HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress: All the following conditions must exist: Core SCM > CETCs decreasing All the following conditions must exist: All WR NI Core SCM > Pzr level increasing SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit Maintagpm indicated/pump. This is an instrument error adjusted value that ensures a real value of gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 28 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level > [ acc] will ensure Pzr heater bundles remain covered. 1. Utilize the following as necessary to maintain desired Pzr level: 1A HPI Pump 1B HPI Pump 1HP-26 1HP- 1HP-etpoint or valve demand 1HP-5 IF 1HP-26 will NOT open, THEN throttle 1HP-aintain desired Pzr level. 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT. 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT. 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following: A. Open: 1CS-26 1CS-41 B. Position 1HP-14 to BLEED. C. Notify SRO. 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 29 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. IAAT 1C HPI PUMP is required, THEN perform Ste- GO TO Ste Open: 1HP-24 1HP-25 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 8. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following: A. IF three HPI pumps are operating, THEN secure 1B HPI PUMP. B. IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers. C. GO TO Ste Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 30 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-aintain desired Pzr level. Throttle the following as required to maintain desired Pzr level: 1HP-26 1HP- 1. IF at least two HPI pumps are operating, AND 1HP-26 will NOT open, THEN throttle 1HP-maintain desired Pzr level. 2. IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-NOT open, THEN throttle 1HP-aintain desired Pzr level.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 31 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IAAT LDST level CANNOT be maintained, THEN perform Step 11. GO TO Step 12. 11. Perform the following: Open 1HP-24. Open 1HP-25. Close 1HP-16. 1. IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following: A. Start 1A LPI PUMP. B. Start 1B LPI PUMP. C. Open: 1LP-15 1LP-16 1LP- 1LP- 1LP-6 1LP- D. IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-U1 LPI Hatch Rm, N end). F. GO TO Step 13. 2. IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP. NOTE 12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 32 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-Unit 1 RC Bleed Transfer Pump Rm.). 14. IAAT two Letdown Filters are desired, THEN perform the following: Open 1HP- Open 1HP-18 15. IAAT all of the following exist: Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41} GO TO Step 35. 16. Open: 1CC- 1CC-8 1. Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system. 2. GO TO Step 35. Ensure only one CC pump running. 18. Place the non-running CC pump in AUTO. Verify both are open: 1HP-1 1HP-2 1. IF 1HP-1 is closed due to 1HP-3 failing to close, THEN GO TO Step 21. 2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21. GO TO Step 23. NOTE Verification of leakage requires visual observation of East Penetration Room. 21. Verify letdown line leak in East Penetration Room has occurred. GO TO Step 23. 22. GO TO Step 35.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 33 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. Monitor for unexpected conditions while restoring letdown. 24. Verify both letdown coolers to be placed in service. 1. IF 1A letdown cooler is to be placed in service, THEN open: 1HP-1 1HP-3 2. IF 1B letdown cooler is to be placed in service, THEN open: 1HP-2 1HP-4 3. GO TO Step 26. 25. Open: 1HP-1 1HP-2 1HP-3 1HP-4 26. Verify at least one letdown cooler is aligned. Perform the following: A. Notify CR SRO of problem. B. GO TO Step 35. Close 1HP-6. 28. Close 1HP- Verify letdown temperature < 125°F. 1. Open 1HP-13. 2. Close: 1HP-8 1HP-&11 3. IF any deborating IX is in service, THEN perform the following: A. Select 1HP-14 to NORMAL. B. Close 1HP-16. 4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 34 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Open 1HP-5. 31. Adjust 1HP-for gpm letdown. 32. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL. 33. Open 1HP-6. 34. Adjust 1HP-control desired letdown flow. NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level. 35. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown). 36. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following: A. Obtain SRO concurrence to reduce running HPI pumps. B. Secure the desired HPI pumps. C. Place secured HPI pump switch in AUTO, if desired. IAAT all the following conditions exist: Makeup from BWST NOT required LDST level > All control rods inserted Cooldown Plateau NOT being used THEN close: 1HP-24 1HP-25 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 35 of 59 Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST. GO TO Ste WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following: A. Stop 1A BLEED TRANSFER PUMP. B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1 RC Bleed Transfer Pump Rm.). C. Close 1CS-46. D. Start 1A BLEED TRANSFER PUMP. E. Locally throttle 1CS-48 (1A BHUT Recirc) to obta- discharge pressure. F. Stop 1A BLEED TRANSFER PUMP. Verify two Letdown Filters in service, AND only one Letdown filter is desired. GO TO Step 42. 41. Perform one of the following: Place 1HP-ch to CLOSE. Place 1HP-18 switch to CLOSE. 42. WHEN directed by CR SRO, THEN EXIT this enclosure.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 36 of 59 EOP Enclosure 5.1 (ES Actuation)Rev 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1. __ Determine all ES channels that should have actuated based on RCS pressure and RB pressure:

2. __ Verify all ES channels associated with actuation setpoints have actuated. NOTE Voter OVERRIDE extinguishes the TRIPPED light on the associated channels that have auto actuated. Pressing TRIP on channels previously actuated will reposition components that may have been throttled or secured by this Enclosure. __ Depress TRIP on affected ES logic channels that have NOT previously been actuated. 3. __ IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1 - 2. 4. __ Place Diverse HPI in BYPASS. __ Place Diverse HPI in OVERRIDE. 5. Perform both: __ Place ES CH 1 in MANUAL. __ Place ES CH 2 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 1 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. Actuation Setpoint (psig) Associated ES Channel 1 & 2 3 & 4 3(RB) 1, 2, 3, 4, 5, & 6 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 37 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. __ IAAT all exist: __ Voter associated with ES channel is in OVERRIDE __ An ES channel is manually actuated __Components on that channel require manipulation THEN depress RESET on the required channel. 7. __ Verify Rule 2 in progress or complete. __ GOTO Step 73. 8. __ Verify any RCP operating. __ GOTO Step 10. 9. Open: __ 1HP-20 __ 1HP-21 10. __ IAAT any RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 11 - 14. __ GOTO Step 15. 11. Perform all: __ Place ES CH 5 in MANUAL. __ Place ES CH 6 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 5 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 6 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. 12. Open: __ 1CC-7 __ 1CC-8 __ 1LPSW-15 __ 1LPSW-6 13. __ Ensure only one CC pump operating. 14. __ Ensure Standby CC pump in AUTO.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 38 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15. __ IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 16. __ GO TO Step 53. 16. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE. 17. Perform both: __ Place ES CH 3 in MANUAL. __ Place ES CH 4 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 3 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 4 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6} 18. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22} 19. __ IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 20 - 21. __ GOTO Step 22. 20. Perform the following: __ Open 1LP-17. __ Start 1A LPI PUMP. 1. __ Stop 1A LPI PUMP. 2. __ Close 1LP-17. 21. Perform the following: __ Open 1LP-18. __ Start 1B LPI PUMP. 1. __ Stop 1B LPI PUMP. 2. __ Close 1LP-18.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 39 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22. __IAAT 1A and 1B LPI PUMPs are off / tripped, AND all exist: __ RCS pressure < LPI pump shutoff head __ 1LP-19 closed __ 1LP-20 closed THEN perform Steps 23 - 24. __ GO TO Step 25. 23. Open: __ 1LP-9 __ 1LP-10 __ 1LP-6 __ 1LP-7 __ 1LP-17 __ 1LP-18 __ 1LP-21 __ 1LP-22 24. __ Start 1C LPI PUMP. 25. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17. 26. __ IAAT 1B LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close 1LP-18. 27. Start: __ A OUTSIDE AIR BOOSTER FAN __ B OUTSIDE AIR BOOSTER FAN 28. Notify Unit 3 to start: __ 3A OUTSIDE AIR BOOSTER FAN __ 3B OUTSIDE AIR BOOSTER FAN Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 40 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29. Verify open: __ 1CF-1 __ 1CF-2 __ IF CR SRO desires 1CF-1 and 1CF-2 open, THEN open: __ 1CF-1 __ 1CF-2 30. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND. 2. __ Close 1HP-120. 31. __ Secure makeup to the LDST. 32. __ Verify all ES channel 1 - 4 components are in the ES position. 1. __ IF 1HP-3 fails to close, THEN close 1HP-1. 2. __ IF 1HP-4 fails to close, THEN close 1HP-2. 3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close: __ 1HP-228 __ 1HP-226 __ 1HP-232 __ 1HP-230 4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 33. __ Verify Unit 2 turbine tripped. __ GOTO Step 36. 34. __ Close 2LPSW-139. 35. __ Verify total LPSW flow to Unit 2 LPI coolers 6000 gpm. __ Reduce LPSW to Unit 2 LPI coolers to obtain total LPSW flow 6000 gpm. 36. __ Close 1LPSW-139. 37. Place in FAIL OPEN: __ 1LPSW-251 FAIL SWITCH __ 1LPSW-252 FAIL SWITCH 38. __ Start all available LPSW pumps.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 41 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39. Verify either: __ Three LPSW pumps operating __ Two LPSW pumps operating when Tech Specs only requires two operable __ GOTO Step 41. 40. Open: __ 1LPSW-4 __ 1LPSW-5 __ IF both are closed: __ 1LPSW-4 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'. 41. __ IAAT BWST level 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 1. __ Display BWST level using OAC Turn-on Code "SHOWDIG O1P1600". 2. __ Notify crew of BWST level IAAT step. 42. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS) 43. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON. 44. __ IAAT ES channels 5 & 6 have actuated, THEN perform Step 45. __ GOTO Step 46. NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied. 45. __ Verify all ES channel 5 & 6 components are in the ES position. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 42 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 46. __ IAAT ES channels 7 & 8 have actuated, THEN perform Steps 47 - 48. __ GOTO Step 49. 47. Perform all: __ Place ES CH 7 in MANUAL. __ Place ES CH 8 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 7 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 8 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. 48. __ Verify all ES channel 7 & 8 components are in the ES position. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 49. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open. 50. __ Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary. 51. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery). 52. __ WHEN CR SRO approves, THEN EXIT. END Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 43 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Unit Status ES Channels 3 & 4 have NOT actuated. 53. Start: __ A OUTSIDE AIR BOOSTER FAN __ B OUTSIDE AIR BOOSTER FAN 54. Notify Unit 3 to start: __ 3A OUTSIDE AIR BOOSTER FAN __ 3B OUTSIDE AIR BOOSTER FAN 55. Verify open: __ 1CF-1 __ 1CF-2 __ IF CR SRO desires 1CF-1 and 1CF-2 open, THEN open: __ 1CF-1 __ 1CF-2 56. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND. 2. __ Close 1HP-120. 57. __ Secure makeup to the LDST. 58. __ Verify all ES channel 1 & 2 components are in the ES position. 1. __ IF 1HP-3 fails to close, THEN close 1HP-1. 2. __ IF 1HP-4 fails to close, THEN close 1HP-2. 3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close: __ 1HP-228 __ 1HP-226 __ 1HP-232 __ 1HP-230 4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 59. __ Verify Unit 2 turbine tripped. __ GOTO Step 62. 60. __ Close 2LPSW-139. 61. __ Verify total LPSW flow to Unit 2 LPI coolers 6000 gpm. __ Reduce LPSW to Unit 2 LPI coolers to obtain total LPSW flow 6000 gpm. 62. __ Close 1LPSW-139.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 44 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 63. Place in FAIL OPEN: __ 1LPSW-251 FAIL SWITCH __ 1LPSW-252 FAIL SWITCH 64. __ Start all available LPSW pumps. 65. Verify either: __ Three LPSW pumps operating __ Two LPSW pumps operating when Tech Specs only requires two operable __ GOTO Step 67. 66. Open: __ 1LPSW-4 __ 1LPSW-5 __ IF both are closed: __ 1LPSW-4 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'. 67. __ IAAT BWST level 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 1. __ Display BWST level using OAC Turn-on Code "SHOWDIG O1P1600". 2. __ Notify crew of BWST level IAAT step. 68. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS ) 69. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open. 70. __ Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary. 71. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery). 72. __ WHEN CR SRO approves, THEN EXIT. END Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 45 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 73. Open: __ 1HP-24 __ 1HP-25 1. __ IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN: A. __ Start 1A LPI PUMP. B. __ Start 1B LPI PUMP. C. Open: __ 1LP-15 __ 1LP-16 __ 1LP-9 __ 1LP-10 __ 1LP-6 __ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump. E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end). F. __ GOTO Step 74. 2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN: A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP. B. __ IF< 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers. C. __ GO TO Step 75.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 46 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 74. __ Ensure at least two HPI pumps are operating. 75. Verify open: __ 1HP-26 __ 1HP-27 1. __ IF HPI has been intentionally throttled, THEN GOTO Step 76. 2. Open: __ 1HP-26 __ 1HP-27 Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 47 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 76. __ IAAT at least two HPI pumps are operating, AND HPI flow in any header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header: Figure 1 Required HPI Flow Per Header HPI Pump Runout Region For 1 Pump In Header (including seal injection for A header) Unacceptable Region (excluding seal injection) 1A Header 1B Header 1HP- 1HP-Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 48 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 77. __ Verify any RCP operating. __ GOTO Step 79. 78. Open: __ 1HP-20 __ 1HP-21 79. __ IAAT any RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 800 - 83. __ GOTO Step 84. 80. Perform all: __ Place ES CH 5 in MANUAL. __ Place ES CH 6 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 5 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 6 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. 81. Open: __ 1CC-7 __ 1CC-8 __ 1LPSW-15 __ 1LPSW-6 82. __ Ensure only one CC pump operating. 83. __ Ensure Standby CC pump in AUTO.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 49 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 84. __ IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 855. __ GO TO Step 122. 85. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE. 86. Perform both: __ Place ES CH 3 in MANUAL. __ Place ES CH 4 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 3 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 4 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6} 87. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps.{6, 22}

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 50 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 88. __ IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 89 - 90. __ GOTO Step 91. 89. Perform the following: __ Open 1LP-17. __ Start 1A LPI PUMP. 1. __ Stop 1A LPI PUMP. 2. __ Close 1LP-17. 90. Perform the following: __ Open 1LP-18. __ Start 1B LPI PUMP. 1. __ Stop 1B LPI PUMP. 2. __ Close 1LP-18. 91. __ IAAT 1A and 1B LPI PUMPs are off / tripped, AND all exist: __ RCS pressure < LPI pump shutoff head __ 1LP-19 closed __ 1LP-20 closed THEN perform Steps 92 -93. __ GO TO Step 94. 92. Open: __ 1LP-9 __ 1LP-10 __ 1LP-6 __ 1LP-7 __ 1LP-17 __ 1LP-18 __ 1LP-21 __ 1LP-22 93. __ Start 1C LPI PUMP. 94. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17. 95. __ IAAT 1B LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close 1LP-18.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 51 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 96. Start: __ A OUTSIDE AIR BOOSTER FAN __ B OUTSIDE AIR BOOSTER FAN 97. Notify Unit 3 to start: __ 3A OUTSIDE AIR BOOSTER FAN __ 3B OUTSIDE AIR BOOSTER FAN 98. Verify open: __ 1CF-1 __ 1CF-2 __ IF CR SRO desires 1CF-1 and 1CF-2 open, THEN open: __ 1CF-1 __ 1CF-2 99. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND. 2. __ Close 1HP-120. 100. __ Secure makeup to the LDST. 101. __ Verify all ES channel 1 - 4 components are in the ES position. 1. __ IF 1HP-3 fails to close, THEN close 1HP-1. 2. __ IF 1HP-4 fails to close, THEN close 1HP-2. 3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close: __ 1HP-228 __ 1HP-226 __ 1HP-232 __ 1HP-230 4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 102. __ Verify Unit 2 turbine tripped. __ GOTO Step 105. 103. __ Close 2LPSW-139. 104. __ Verify total LPSW flow to Unit 2 LPI coolers 6000 gpm. __ Reduce LPSW to Unit 2 LPI coolers to obtain total LPSW flow 6000 gpm. 105. __ Close 1LPSW-139.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 52 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 106. Place in FAIL OPEN: __ 1LPSW-251 FAIL SWITCH __ 1LPSW-252 FAIL SWITCH 107. __ Start all available LPSW pumps. 108. Verify either: __ Three LPSW pumps operating __ Two LPSW pumps operating when Tech Specs only requires two operable __ GOTO Step 110. 109. Open: __ 1LPSW-4 __ 1LPSW-5 __ IF both are closed: __ 1LPSW-4 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'. 110. __ IAAT BWST level 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 1. __ Display BWST level using OAC Turn-on Code "SHOWDIG O1P1600". 2. __ Notify crew of BWST level IAAT step. 111. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS) 112. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON. 113. __ IAAT ES channels 5 & 6 have actuated, THEN perform Step 114. __ GOTO Step 115. NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied. 114. __ Verify all ES channel 5 & 6 components are in the ES position. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 53 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 115. __ IAAT ES channels 7 & 8 have actuated, THEN perform Step 116 - 117. __ GOTO Step 118. 116. Perform all: __ Place ES CH 7 in MANUAL. __ Place ES CH 8 in MANUAL. NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels. In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch. 1. __ IF ES CH 7 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. 2. __ IF ES CH 8 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. 117. __ Verify all ES channel 7 & 8 components are in the ES position. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 118. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open. 119. __ Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary. 120. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery). 121. __ WHEN CR SRO approves, THEN EXIT.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 54 of 59 Unit Status ES Channels 3 & 4 have NOT actuated. 122. Start: __ A OUTSIDE AIR BOOSTER FAN __ B OUTSIDE AIR BOOSTER FAN 123. Notify Unit 3 to start: __ 3A OUTSIDE AIR BOOSTER FAN __ 3B OUTSIDE AIR BOOSTER FAN 124. Verify open: __ 1CF-1 __ 1CF-2 __ IF CR SRO desires 1CF-1 and 1CF-2 open, THEN open: __ 1CF-1 __ 1CF-2 125. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND. 2. __ Close 1HP-120. 126. __ Secure makeup to the LDST. 127. __ Verify all ES channel 1 & 2 components are in the ES position. 1. __ IF 1HP-3 fails to close, THEN close 1HP-1. 2. __ IF 1HP-4 fails to close, THEN close 1HP-2. 3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close: __ 1HP-228 __ 1HP-226 __ 1HP-232 __ 1HP-230 4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired. 128. __ Verify Unit 2 turbine tripped. __ GOTO Step 131. 129. __ Close 2LPSW-139. 130. __ Verify total LPSW flow to Unit 2 LPI coolers 6000 gpm. __ Reduce LPSW to Unit 2 LPI coolers to obtain total LPSW flow 6000 gpm. 131. __ Close 1LPSW-139.

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 55 of 59 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 132. Place in FAIL OPEN: __ 1LPSW-251 FAIL SWITCH __ 1LPSW-252 FAIL SWITCH 133. __ Start all available LPSW pumps. 134. Verify either: __ Three LPSW pumps operating __ Two LPSW pumps operating when Tech Specs only requires two operable __ GOTO Step 136. 135. Open: __ 1LPSW-4 __ 1LPSW-5 __ IF both are closed: __ 1LPSW-4 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'. 136. __ IAAT BWST level 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES). 1. __ Display BWST level using OAC Turn-on Code "SHOWDIG O1P1600". 2. __ Notify crew of BWST level IAAT step. 137. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS ) 138. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open. 139. __ Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary. 140. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery). 141. __ WHEN CR SRO approves, THEN EXIT. END Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 56 of 59 Subsequent Actions EP/1 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All SWGR de-energized {13} GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer GO TO EHT tab. LOHT 6. Loss of heat transfer (including loss of all Main and Emergency FDW) GO TO LOHT tab. Heat transfer is or has been excessive GO TO EHT tab. EHT 8. Indications of SGTR gpm GO TO SGTR tab. SGTR Turbine Building flooding NOT caused by rainfall event GO TO TBF tab. TBF Inadvertent ES actuation occurred Initiate AP(Inadvertent ES Actuation). ES 11. Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 12. Power lost to all SWGR and any SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 13. RCS leakage > gpm with letdown isolated Notify plant staff that Emergency Dose Limits are in affect using PA system. EDL 14. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and NS(Reportability). NOTIFY Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 57 of 59 EHT EP/1 Parallel Actions Page 1 of 1 CONDITION ACTIONS 1. PR NI FP OR NIs NOT decreasing GO TO UNPP tab. UNPP 2. All SWGR de-energized GO TO Blackout tab. BLACKOUT 3. Core SCM indicates superheat GO TO ICC tab. ICC 4. Any SCM = cooling NOT in progress IF LOSCM tab has NOT been entered due to current EHT event THEN GO TO LOSCM tab. LOSCM 5. Both SGs intentionally isolated to stop excessive heat transfer after EHT tab initiated RETURN TO beginning of EHT tab. LOHT 6. Loss of heat transfer AND at least one SG NOT isolated GO TO LOHT tab. Indications of excessive heat transfer in another SG after EHT tab initiated RETURN TO beginning of EHT tab. EHT 8. Inadvertent ES actuation occurred Initiate AP(Inadvertent ES Actuation). ES . Valid ES actuation has occurred or should have occurred Initiate Encl 5.1 (ES Actuation). ES 1. Power lost to all SWGR and any SWGR re-energized Initiate AP/11 (Recovery from Loss of Power). IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1. ROP 11. RCS leakage > gpm with letdown isolated OR SGTR .> 25 gpm Notify plant staff that Emergency Dose Limits are in affect using PA system. EDL 12. Individual available to make notifications Announce plant conditions using PA system. Notify OSM to reference the Emergency Plan and AD-LS-ALL- (Notification /Reportability Evaluation). NOTIFY Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 58 of 59 CRITICAL TASKS CT-1 The PORV must be isolated to isolate the source of RCS leakage and prevent a reactor trip. CT-2 The TD EFDW pump must be started in order to supply feedwater to the intact SG for heat removal.

SAFETY: Take a Minute UNIT 0 (OSM) SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO) Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: Below POAH Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.01 gpm No WCAP Action EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO) Component/Train OOS Date/Time Restoration Required Date/Time TS/SLC # SSF 2 days ago / 0400 5 days / 0400 3.10.1 A,B,C,D,E Shift Turnover Items (CR SRO) Primary Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%). 1RIA-3 and 5 removed from RB. Pressurize LDST with H2 per OP/1/A/1106/017 Encl. 4.5. Increase Reactor power to ~7% per OP/1/A/1102/001 Encl. 4.7 beginning at step 3.36. Secondary 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. Temporary OAC alarms set on FDW Loop A and B Composite Valve Demand @ 9.8% per OP/1/A/1102/001 Encl. 4.7. Reactivity Management (CR SRO) RCS Boron 1778 ppmB Gp 7 Rod Position: 5% Withdrawn Batch additions as required for volume control. Human Performance Emphasis (SM) Procedure Use and Adherence RO-102 Page 1 of 12 REGION II JOB PERFORMANCE MEASURE RO-102 RESPOND TO A BORON DILUTION EVENT Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-102 Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : Respond to a Boron Dilution Event Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 min K/A Rating(s): System: APE 024 K/A: AA1.04 Rating: 3.6*/3.7 Task Standard: The applicant shall borate the RCS In Accordance With AP/1/A/1700/003 (Boron Dilution)

References:

AP/1/A/1700/003 (Boron Dilution) Rev 14 Tools/Equipment/Procedures Needed: AP/1/A/1700/003 (Boron Dilution) ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-102 Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL IC or SNAP: RECALL SNAP 206 2. Give Directions: Import JPM RO-102 Simumlator Files 3. GO TO RUN RO-102 Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 startup in progress following a 28 day refueling outage Reactor Power = 70% Control Rods have been inserting due to RCS temperature increasing The Control Room SRO has determined that a boron dilution event is occurring INITIATING CUE The Control Room SRO has directed you to perform AP/3 (Boron Dilution)

RO-102 Page 5 of 12 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 4.1 Verify one of the following: __ All control rods inserted. __ RV head removed. STANDARD: Candidate determines that neither condition applies. Continues to Step 4.1 RNO COMMENTS: ___ SAT ___ UNSAT 2 4.1 RNO IF ICS is in Auto, THEN ensure the following: __ Rx power < 100% __ Control rods responding as necessary STANDARD: Candidate determines that reactor power is approximately 70% and control rods are inserting due to RCS temperature increasing. Continues to step 4.2 COMMENTS: ___ SAT ___ UNSAT 3 4.2 Make the following notifications: __ PA announcement of the event including required RB evacuation __ Notify OSM to reference the following: RP/0/A/1000/001 (Emergency Classification) NSD-202 (Reportability) OMP 1-14 (Notifications) STANDARD: Candidate makes PA announcement and notifies the OSM to reference procedures. Continues to step 4.3 COMMENTS: ___ SAT ___ UNSAT RO-102 Page 6 of 12 4 4.3 Verify HPI in operation. STANDARD: Candidate verifies that the A HPIP is in operation. Continues to step 4.4 COMMENTS: ___ SAT ___ UNSAT 5 4.4 Verify Rx at power. STANDARD: Candidate verifies that reactor power is 70%. Continues to step 4.5 COMMENTS: ___ SAT ___ UNSAT 6 4.5 Notify Chemistry to sample the following for boron concentration: RCS LDST STANDARD: Candidate notifies Chemistry to sample RCS & LDST boron concentration. Continues to step 4.6 COMMENTS: ___ SAT ___ UNSAT 7 4.6 Verify both RC bleed transfer pumps stopped. STANDARD: Candidate verifies that 1A and 1B Bleed Transfer Pumps are off on 1AB1: Green lights lit and Red lights off. Continues to step 4.7 COMMENTS: ___ SAT ___ UNSAT RO-102 Page 7 of 12 8 4.7 Place 1HP-14 in NORMAL. STANDARD: 1HP-14 (LDST BYPASS) should already be in NORMAL: Red light lit, Green light off. Continues to step 4.8 COMMENTS: ___ SAT ___ UNSAT 9 4.8 Close 1HP-16. STANDARD: 1HP-16 (LDST MAKEUP ISOLATION) should already be closed: Green light lit, Red light off. Continues to step 4.9 COMMENTS: ___ SAT ___ UNSAT 10 4.9 Verify all demineralizers out of service. STANDARD: Candidate determines that a demineralizer IS in service. Continues to Step 4.9 RNO. COMMENTS: ___ SAT ___ UNSAT RO-102 Page 8 of 12 11 4.9 RNO *1. __ IF any purification IX is in service, THEN perform the following: A. __ Open 1HP-13. B. __ Close 1HP-8. C. __ Close 1HP-9 & 11. 2. __ IF any deborating IX is in service, [NONE IN SERVICE] THEN perform the following: A. __ Close 1CS-27. B. __ Close 1CS-32 & 37. C. __ Open 1CS-26. STANDARD: Candidate determines that a purification IX IS in service and: Opens 1HP-13 (PURIFICATION IX BYPASS). Red light lit, Green light off. Closes 1HP-8 (PURIFICATION IX INLET). Red light off, Green light lit. Closes 1HP-9 & 11 (SPARE PURIF IX INOUT & OUTLET). Red light off, Green light lit. Continues to step 4.10. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT 12 4.10 Verify control rods are within allowable limits of the COLR. STANDARD: Candidate references the COLR and determines that Group 7 control rods are in the "Restricted Operation" region of the COLR. Continues to step 4.12 COMMENTS:

___ SAT ___ UNSAT RO-102 Page 9 of 12 13 4.12 Open one of the following valves to borate from the BWST: __ 1HP-24 __ 1HP-25 STANDARD: *Candidate opens either 1HP-24 (1A HPI BWST SUCTION) or 1HP-25 (1B HPI BWST SUCTION) Red light lit, Green light off for the valve chosen. Continues to step 4.13 COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT 14 4.13 Align letdown to 1A BHUT: __ Open 1CS-26. __ Open 1CS-41. __ Place 1HP-14 in BLEED. STANDARD: Candidate: Opens 1CS-26 ( LETDOWN TO RC BHUT) Red light lit, Green light off. Opens 1CS-41 ( 1A RC BHUT INLET) Red light lit, Green light off. Places 1HP-14 in BLEED Green light lit, Red light off. Continues to step 4.14 COMMENTS: ___ SAT ___ UNSAT 15 4.14 Start the standby CC pump. STANDARD: Candidate rotates the standby CC pump to the START position and verifies red light lit and green light off. Continues to step 4.15 COMMENTS: ___ SAT ___ UNSAT RO-102 Page 10 of 12 16 4.15 Throttle 1HP-7 to maximize letdown. STANDARD: Candidate will adjust 1HP-7 (LETDOWN CONTROL) to increase letdown flow from 78 gpm to 100 to 120 gpm Continues to step 4.16 COMMENTS: ___ SAT ___ UNSAT 17 4.16 Throttle the following as required to maintain PZR level 200" - 260": __ 1HP-120 __ 1HP-26 STANDARD: Candidate will throttle 1HP-120 (RC Volume Control) or 1HP-26 (1A HP INJECTION) as needed to maintain Pzr level 200" - 260". COMMENTS:

END TASK ___ SAT ___ UNSAT TIME STOP: ________

RO-102 Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 11 This step removes the source of De-Boration (a demineralizer that was not boron saturated). 13 This step injects borated water (BWST) to the RCS to stop control rod insertion.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 startup in progress following a 28 day refueling outage Reactor Power = 70% Control Rods have been inserting due to RCS temperature increasing The Control Room SRO has determined that a boron dilution event is occurring

INITIATING CUE The Control Room SRO has directed you to perform AP/3 (Boron Dilution)

RO-202 Page 1 of 11 REGION II JOB PERFORMANCE MEASURE RO-202 REMOVE 1A LETDOWN COOLER FROM SERVICE Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-202 Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Remove 1A Letdown Cooler From Service Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s): System: 004 K/A: Generic 2.2.2 Rating: 4.6/4.1 Task Standard: Remove 1A Letdown Cooler from service and completely isolate the cooler utilizing OP/1/A/1104/002 (HPI System) Enclosure 4.5 (Operation of Letdown Coolers)

References:

OP/1/A/1104/002 (HPI System) Rev 167 Tools/Equipment/Procedures Needed: OP/1/A/1104/002 (HPI System) Enclosure 4.5 (Operation of Letdown Coolers) OP/1/A/1104/002 (HPI System) Limits and Precautions

=========================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-202 Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 207 2. IMPORT FILES for RO-202 3. UPDATE status board to show RCS boron at 89 ppm

4. PROVIDE a copy of the following: OP/1/A/1104/002 Encl 4.5 beginning at Step 3.5 with steps 3.1 through 3.4 signed off. OP/1/A/1104/002 Limits & Precautions. 5. Place a clean copy of OMP 2-02 Attachment G in the Component Boron Concentration Log and ensure previous copy used for this JPM is removed. 6. Go to RUN and wait for 1RIA-50 to alarm and acknowledge before allowing the student to enter the simulator.

RO-202 Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 is at 100%

The 1A Letdown Cooler has developed a 0.5 gpm leak Unit 1 CC Surge Tank level is increasing at 4 inches per hour It is NOT desired to valve in the spare CC Cooler It is NOT desired to place a Purification IX in service OP/1/A/1104/002 Enclosure 4.5 is complete up to Step 3.5 INITIATING CUE The Control Room SRO directs you to completely isolate the 1A Letdown Cooler per OP/1/A/1104/002 Enclosure 4.5 beginning at Step 3.5

RO-202 Page 5 of 11 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 3.5 WHILE removing the 1A Letdown Cooler from service, monitor the following: Letdown Cooler CC outlet temperature Letdown temperature Letdown flow STANDARD: Monitor Letdown Cooler CC outlet temperature by referencing OAC graphic display. Monitor Letdown temperature by referencing Letdown temperature gauge located on 1UB1 or OAC graphic display. Monitor Letdown flow by referencing Letdown flow gauge located on 1UB1 or OAC graphic display. Candidate continues to Step 3.6 COMMENTS: ___ SAT ___ UNSAT 2 3.6 NOTE: Throttling 1HP-7 does NOT affect reactivity management since IXs are NOT in service. (R.M.) Changing Letdown Flow < 10 gpm / minute minimizes Letdown Cooler leaks: IF 1HP-1/CC-1 are open, reduce Letdown flow to minimum by throttling closed 1HP-7 (LETDOWN CONTROL). STANDARD: Determine that 1HP-1/1CC-1 are open by observing red open light illuminated and green closed light OFF. Reduce Letdown flow by rotating 1HP-7 setpoint dial located on 1UB1 counterclockwise until the valve is closed. Candidate continues to Step 3.7. COMMENTS: ___ SAT ___ UNSAT RO-202 Page 6 of 11 3 3.7 Verify Letdown Flow < 87 gpm. STANDARD: Verifies letdown flow on 1UB1 is < 87 gpm Candidate continues to Step 3.8.

COMMENTS: ___ SAT ___ UNSAT 4 3.8 Ensure closed 1HP-1/1CC-1 (1A LETDOWN COOLER INLET). STANDARD: Locate 1HP-1/1CC-1 switch on 1UB1 and rotates control switch clockwise to the closed position. Verify 1HP-1 closes by observing the red open light OFF and green closed light illuminated. Verify 1CC-1 closes by observing the red open light OFF and green closed light illuminated. Candidate continues to Step 3.9. COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT 5 3.9 Record date/time 1HP-1/1CC-1 closed: _______/_______ STANDARD: Record today's date/time. Candidate continues to Step 3.10. COMMENTS: ___ SAT

___ UNSAT RO-202 Page 7 of 11 6 3.10 NOTE: Maximum Letdown Flow is 87 gpm with one Letdown Cooler in service. Changing Letdown Flow < 10 gpm / minute minimizes Letdown Cooler leaks. Letdown temperature should NOT exceed 120°F for extended periods of time. Step 3.10 may be performed as many times as required. IF required, slowly adjust 1HP-7 (Letdown Control) as required to perform the following: (Continue) To provide normal letdown flow of 68-80 gpm. To maintain Letdown Cooler CC outlet temperature < 225°F. STANDARD: Adjust 1HP-7 as necessary to maintain letdown flow 68-80 gpm and maintain Letdown Cooler CC outlet temperature < 225°F. Adhere to the Note above and limits letdown flow < 125 gpm and prevent letdown temperature from exceeding 120°F for extended periods of time. Candidate continues to Step 3.11. COMMENTS: ___ SAT ___ UNSAT 7 3.11 IF required, valve in spare CC Cooler to maintain Letdown Cooler CC outlet temperature < 225°F per OP/1/A/1104/008 (Component Cooling System). STANDARD: Recognize from the Initial Conditions that it is NOT desired to place the spare CC Cooler in service. Candidate continues to Step 3.12. Examiner Cue: If the candidate asks, inform him/her that it is NOT desired to place the spare CC Cooler in service. COMMENTS: ___ SAT ___ UNSAT RO-202 Page 8 of 11 8 3.12 Record boron in Component Boron Concentration Log for 1A Letdown Cooler. (R.M.) (Continue) STANDARD: Record current RCS boron concentration, Date, Time, and Initials in the Component Boron Concentration Log (OMP 2-02 Attachment G) for the 1A Letdown Cooler. Candidate continues to Step 3.13. COMMENTS: ___ SAT

___ UNSAT 9 3.13 IF desired, place a Purification IX in service per OP/1/A/1103/004 B (Purification IXs). (R.M.) STANDARD: Recognize from the Initial Conditions that it is NOT desired to place a Purification IX in service. Candidate continues to Step 3.14. Examiner Cue: If the candidate asks, inform him/her that it is NOT desired to place a Purification IX in service. COMMENTS: ___ SAT

___ UNSAT RO-202 Page 9 of 11 10 3.14 IF complete cooler isolation required, perform one of the following: 3.14.1 IF CC Surge Tank level rate of increase is 3"/hour, close 1HP-3 (1A LETDOWN COOLER OUTLET). 3.14.2 IF CC Surge Tank level rate of increase is < 3"/hour, perform the following: NOTE: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prevents forming a vacuum in cooler as piping cools down. A. Verify 1HP-1/1CC-1 (1A LETDOWN COOLER INLET) closed for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . B. Close 1HP-3 (1A LETDOWN COOLER OUTLET). STANDARD: Recognize from the Initial Conditions that CC Surge Tank level rate of increase is 3"/hour and locates 1HP-3 control switch on 1UB1 and rotates switch in the clockwise (closed) direction. Verify 1HP-3 green closed light illuminates and red open light extinguishes. Examiner Cue: If the candidate asks, inform him/her that the CC leak rate remains unchanged. Examiner Cue: Inform the candidate that another operator will complete this procedure. COMMENTS: END TASK

CRITICAL STEP ___ SAT

___ UNSAT TIME STOP: ________

RO-202 Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 4 Step 3 is required to isolate the 1A CC Cooler from the RCS to prevent in-leakage. 10 Step 9 is required to fully isolate the 1A CC Cooler due to leakage being greater than 3" per hour

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is at 100%.

The 1A Letdown Cooler has developed a 0.5 gpm leak.

Unit 1 CC Surge Tank level is increasing at 4 inches per hour. It is NOT desired to valve in the spare CC Cooler. It is NOT desired to place a Purification IX in service.

OP/1/A/1104/002 Enclosure 4.5 is complete up to Step 3.5

INITIATING CUE The Control Room SRO directs you to completely isolate the 1A Letdown Cooler per OP/1/A/1104/002 Enclosure 4.5 beginning at Step 3.5 RO-304a Page 1 of 13 REGION II JOB PERFORMANCE MEASURE RO-304a PERFORM RULE 2 FOLLOWING A LOSCM Alternate Path: Yes Alt Path Failure: ES Channel 2 Fails to go to MANUAL Time Critical: Yes Time Critical Criteria: Secure RCPs within 2 minutes of losing SCM Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-304a Page 2 of 13 REGION II JOB PERFORMANCE MEASURE Task Title: Perform Rule 2 following a LOSCM Task Number: N/A Alternate Path: Yes Time Critical: Yes Validation Time: 10 minutes K/A Rating(s): System: E/APE 011 K/A: EA2.11 Rating: 3.9/4.3 Task Standard: Perform a symptom check and initiate Rule 2. Trip RCPs within 2 minutes. Place EVEN Voters in Override and throttle HPI flow to within limits. .

References:

EP/1/A/1800/001 (Emergency Operating Procedure) Rev 40C Tools/Equipment/Procedures Needed: EP/1/A/1800/001 (Emergency Operating Procedure) Rule 2 (Loss of SCM) ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-304a Page 3 of 13 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 208 2. IMPORT FILES for RO-304 3. Go to RUN when directed by the Lead Examiner RO-304a Page 4 of 13 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS The Reactor was operating at 100% power The Reactor has just tripped You are the BOP Reactor Operator

INITIATING CUE As the BOP, perform a Symptoms Check

RO-304a Page 5 of 13 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 Perform a Symptoms Check STANDARD: Candidate performs a Symptoms Check and determines that a Loss of SCM has occurred due to any SCM 0°F and initiates Rule 2 in accordance with OMP 1-18 Attachment C. Examiner Cue: As the SRO, if asked, concur with performing Rule 2 COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 2 1 IAAT all exist: __ Any __ __ THEN perform Steps 2 and 3. STANDARD: Candidate determines that SCM is 0°F by observing the indications on the ICCM plasma display and/or standout SCM displays both located on 1UB1. Candidate verifies Rx Power Range and/or Wide Range NIs located on 1UB1. Candidate determines has elapsed since the loss of SCM. Candidate continues to step 2. COMMENTS: ___ SAT ___ UNSAT RO-304a Page 6 of 13 3 2 Stop all RCPs. STANDARD: Stop all RCPs by locating the RCP switches located on 1AB1 and rotate the switches to the TRIP position. Verify that the green stop light is LIT and pump amps go to zero. Candidate continues to step 3. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 4 3 Notify CRS of RCP status. STANDARD: Notify CRS that all RCPs have been secured. Examiner Cue: As the SRO, acknowledge the report of RCP status. Candidate continues to step 4. COMMENTS: ___ SAT ___ UNSAT 5 4 Verify Blackout exists. STANDARD: Determine that a blackout does not exist by observing power available on the Main Feeder Bus volt meters located on 1AB1. Candidate continues to the RNO column and determine the correct procedure path is to GO TO Step 6. COMMENTS: ___ SAT ___ UNSAT RO-304a Page 7 of 13 6 6 Open: __ 1HP-24 __ 1HP-25 STANDARD: Verify that the above valves are open by observing their red open light LIT and green light off on 1UB1. Note: These valves will already be open due to ES actuation. Candidate continues to step 7. COMMENTS: ___ SAT ___ UNSAT 7 7 Start all available HPI pumps. STANDARD: Verify that all three HPI pumps are operating by observing their red lights lit and green lights off . Note: All HPI pumps will be operating due to ES actuation. Candidate continues to step 8. COMMENTS: ___ SAT ___ UNSAT 8 8 GO TO Step 13 STANDARD: Proceed to Step 13 COMMENTS: ___ SAT ___ UNSAT 9 13 Open: __ 1HP-26 __ 1HP-27 STANDARD: Verify that the above valves are open by observing their red open light LIT on 1UB1. Note: These valves will already be open due to ES actuation.

Candidate continues to step 14. COMMENTS: ___ SAT ___ UNSAT RO-304a Page 8 of 13 10 14 Verify at least two HPI pumps are operating using two diverse indications STANDARD: All 3 HPIPs will be operating due to ES actuation. Candidate continues to step 15. COMMENTS: ___ SAT ___ UNSAT 11 15 IAAT AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps 16 - 21. STANDARD: Determine that HPI flow is NOT in the unacceptable region per Figure 1. Candidate goes the RNO step and continues to step 17. COMMENTS: ___ SAT ___ UNSAT 12 17 IAAT flow limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI pumps operating with 1HP-409 open Total flow of 950 gpm (incl. seal injection) THEN perform Steps 18 - 20. STANDARD: Determine that 1B HPI Header flow is > 475 gpm by observing the 1B HPI Header Flow gauge located on 1UB1. Candidate continues to step 18. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT RO-304a Page 9 of 13 13 18 Place Diverse HPI in BYPASS. STANDARD: Depresses the DIVERSE HPI BYPASS "BYPASS" pushbutton on 1UB1. Candidate continues to step 19. COMMENTS: ___ SAT ___ UNSAT 14 19 [ALTERNATE PATH] Perform both: __ Place ES CH 1 in MANUAL. __ Place ES CH 2 in MANUAL. STANDARD: Places ES CH 1 in MANUAL and recognizes that ES CH 2 fails to go to MANUAL. Candidate continues to step 19 RNO. COMMENTS: ___ SAT ___ UNSAT 15 19 RNO 1. __ IF ES CH 1 fails to go to MANUAL, THEN place ODD voter in OVERRIDE. *2. __ IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE. STANDARD: Places the EVEN Voter in OVERRIDE. Candidate continues to step 20. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT 16 20 STANDARD: Throttles HP-27 to maximize HPI flow to less than 475 gpm. Candidate continues to step 21. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT RO-304a Page 10 of 13 17 21 Notify CRS of HPI status. STANDARD: Candidate notifies SRO that 1HP-27 has been throttled. Candidate continues to step 22. COMMENTS: ___ SAT ___ UNSAT 18 22 Verify RCS pressure > 550 psig. STANDARD: Determines that RCS pressure is < 550 psig. Candidate continues to RNO. COMMENTS: ___ SAT ___ UNSAT 19 22 RNO Ensure ES Channels 3 and 4 actuated. STANDARD: ES Channels 3 and 4 actuated when the LOCA occurred. Candidate continues to step 23. COMMENTS: ___ SAT ___ UNSAT 20 23 IAAT either exists: __ Only one LPI THEN GO TO Step 24. STANDARD: Determines that total LPI flow exceeds 3400 gpm. Candidate continues to step 24. COMMENTS: ___ SAT ___ UNSAT RO-304a Page 11 of 13 21 24 Perform the following: __ Place 1FDW-315 in MANUAL and close. __ Place 1FDW-316 in MANUAL and close. __ Place 1FDW-35 in HAND and close. __ Place 1FDW-44 in HAND and close. STANDARD: Places the above controllers in MANUAL/HAND and closes their respective valves. COMMENTS: END TASK ___ SAT ___ UNSAT TIME STOP: ________

RO-304a Page 12 of 13 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 Rule 2 should be selected based on the symptoms. 3 RCPs are required to be stopped within 2 minutes of a loss of SCM. 12 1B 15 Must place Even Voter in override to be able to throttle 1HP-27. 16 Must throttle 1HP-27 to prevent damage due to runout.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS The Reactor was operating at 100% power.

The Reactor has just tripped.

You are the BOP Reactor Operator.

INITIATING CUE As the BOP, perform a Symptoms Check.

RO-503 Page 1 of 9 REGION II JOB PERFORMANCE MEASURE RO-503 PUMP THE QUENCH TANK Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-503 Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title: Pump the Quench Tank Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s): System: 007 K/A: A1.01 Rating: 2.9/3.1 Task Standard: Utilize OP/1/A/1104/017 Enclosure 4.1 to lower Quench Tank level to 75 inches and isolate the flowpath to 1A Bleed Holdup Tank.

References:

OP/1/A/1104/017 (Quench Tank Operation) Rev 48 Tools/Equipment/Procedures Needed: OP/1/A/1104/017 Limits & Precautions OP/1/A/1104/017 Enclosure 4.1 (Pumping QT)

===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-503 Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 210 2. Place T/O sheet tags on QT Drain Pump and Component Drain Pump 3. Update Boron Status board to show: Last 1A BHUT boron sample as being > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months old 1A BHUT Boron = 2553 ppm RCS Boron = 2414 ppm 4. Provide a copy of OP/1/A/1104/017 Enclosure 4.1 with the following: Limits & Precautions Steps 1.1 through 1.4 signed off 5. Go to RUN when directed by the Lead Examiner RO-503 Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 is Shutdown Unit 1 Quench Tank level is 86 inches Quench Tank is aligned to 1A BHUT .1 (Pumping QT) of OP/1/A/1104/017 (Quench Tank Operation) is in progress and complete up to Step 2.1

INITIATING CUE The CRS directs you to use the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP to pump the Quench Tank to 1A BHUT beginning at Step 2.1 of Enclosure 4.1 of OP/1/A/1104/017 Secure pumping the Quench Tank at 75 inches

RO-503 Page 5 of 9 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.1 Ensure open: __ 1CS-5 (COMPONENT DRN PUMP SUCTION) __ 1CS-6 (COMPONENT DRN PUMP SUCTION) STANDARD: Ensure 1CS-5 and 1CS-6 are open by taking the control switches located on 1AB1 to the open position and verifying red open light illuminated and green closed light OFF. Candidate continues to Step 2.2. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 2 2.2 IF QT level will be maintained in normal operating band: 2.2.1 IF desired, start COMPONENT DRAIN PUMP. 2.2.2 IF desired, start QUENCH TANK DRAIN PUMP. 2.2.3 At desired level, perform the following: Ensure stopped COMPONENT DRAIN PUMP Ensure stopped QUENCH TANK DRAIN PUMP 2.2.4 IF . STANDARD: Recognize from the Initial Conditions that this step is not applicable due to pumping the QT below 80 inches. Marks this step as Not Applicable (N/A). Candidate continues to Step 2.3 COMMENTS: ___ SAT ___ UNSAT RO-503 Page 6 of 9 3 2.3 IF QT level is to be reduced below low level setpoint of 80 inches, perform the following: 2.3.1 Ensure RCS pressure < 45 psig. 2.3.2 *IF desired, place COMPNENT DRAIN PUMP to BYPASS 2.3.3 *IF desired, place QUENCH TANK DRAIN PUMP to BYPASS 2.3.4 *At desired level ( 75"), perform the following: Ensure stopped COMPONENT DRAIN PUMP Ensure stopped QUENCH TANK DRAIN PUMP STANDARD: Determine from the Initial Conditions that QT level will be reduced below 80 inches Locate RCS pressure from the Low Range Cooldown Pressure indication on 1UB2 and ensures that RCS pressure is < 45 psig. *Place the COMPONENT DRAIN PUMP switch in the BYPASS position AND Pull the switch up. *Place the QUENCH TANK DRAIN PUMP switch in the BYPASS position AND Pull the switch up. *Stop the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP by rotating the switch to STOP when QT level reaches 75 inches. Note: The low level cut-off for the Component Drain Pump and Quench Tank Drain Pump will trip the pumps at 80 inches if the pump switches are not taken to BYPASS and pulled up (similar to a PTL position). Note: The candidate must start either the COMPONENT DRAIN PUMP or the QUENCH TANK DRAIN PUMP in the bypass position to complete the task. The candidate's instructions were to use both pumps. Candidate continues to Step 2.4 COMMENTS: *CRITICAL STEP ___ SAT

___ UNSAT RO-503 Page 7 of 9 4 2.4 Perform the following: __ *Close 1CS-5 (COMPONENT DRN PUMP SUCTION) __ *Close 1CS-6 (COMPONENT DRN PUMP SUCTION) STANDARD: Close 1CS-5 and 1CS-6 by placing each control switch in the closed position. The green closed light illuminates and the red open light extinguishes. Candidate continues to Step 2.5 Note: Closing EITHER 1CS-5 or 1CS-6 satisfies the Critical Step. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT 5 2.5 IF 1A BHUT boron sample > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months old AND QT pumped to 1A BHUT, perform the following: 2.5.1 Verify closed 1CS-46 (1A RC BLEED XFER PUMP DISCHARGE). 2.5.2 Dispatch NEO to observe 1A Bleed Transfer Pump discharge pressure.(1CS-PG-0084) 2.5.3 Start 1A BLEED TRANSFER PUMP.

Booth Cue: When called, report as AO: "I am standing by to read 1A BTP discharge pressure at 1CS-PG-0084". STANDARD: Verifies 1CS-46 (1A RC BLEED XFER PUMP DISCHARGE) is closed by observing green closed light illuminated and red open light off. Candidate dispatches a AO to observe 1A Bleed Transfer Pump discharge pressure.(1CS-PG-0084). Candidate starts 1A BLEED TRANSFER PUMP and observes red light illuminated and green light off.

Examiner Cue: When 1A BLEED TRANSFER PUMP is started inform the candidate that another operator will continue this procedure. COMMENTS:

END TASK ___ SAT ___ UNSAT TIME STOP: ________

RO-503 Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 Step is required to align the flow path from the QT to 1A BHUT. 3 This step is required to begin the level decrease in the Quench Tank. Placing the switch in the BYPASS position is required to decrease QT level below 80 inches. Ensuring both pumps are secured is required to prevent pumping the QT below 75 inches. 4 This step isolates the flow path from the QT to 1A BHUT CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is Shutdown

Unit 1 Quench Tank level is 86 inches Quench Tank is aligned to 1A BHUT .1 (Pumping QT) of OP/1/A/1104/017 (Quench Tank Operation) is in progress and complete up to Step 2.1

INITIATING CUE The CRS directs you to use the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP to pump the Quench Tank to 1A BHUT beginning at Step 2.1 of Enclosure 4.1 of OP/1/A/1104/017 Secure pumping the Quench Tank at 75 inches RO-602 Page 1 of 10 REGION II JOB PERFORMANCE MEASURE RO-602 RESTORE SECONDARY LOADS AFTER LOSS OF OFFSITE POWER Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-602 Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task Title: Restore Secondary Loads After Loss of Offsite Power Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s): System: 062 K/A: A4.01 Rating: 3.3/3.1 Task Standard: Properly align secondary loads following a loss of offsite power by procedure.

References:

AP/1/A/1700/011 (Recovery From Loss of Power) Rev 55 Tools/Equipment/Procedures Needed: AP/1/A/1700/011 (Recovery From Loss of Power) =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-602 Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 213 2. IMPORT RO-602 files 3. PROVIDE a copy of AP/11 signed off up to step 4.27 RO-602 Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS A Switchyard Isolation has occurred from 100% power A Load Shed has NOT occurred All 4160 volt switchgear has been re-energized by the overhead power path from a Keowee Hydro unit 5 minutes have elapsed since the loss of offsite power Condensate system operation is desired AP/1/A/1700/011 (Recovery From Loss of Power) is in progress and completed up to step 4.27

INITIATING CUE The CRS directs you to continue AP/1/A/1700/011 (Recovery From Loss of Power) beginning at step 4.27

RO-602 Page 5 of 10 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 4.27 Verify both: __ Condensate flow has been lost for < 25 minutes __ Condensate system operation is desired STANDARD: Candidate recognizes from the initial conditions that Condensate flow has been lost for 5 minutes and that Condensate system operation is desired COMMENTS: ___ SAT ___ UNSAT 2 4.28 Place all HWP control switches to OFF STANDARD: Candidate places the 1A, 1B, and 1C HWP switches in the OFF position located on 1AB1. Examiner Note: It is required to place the HWP switch in the OFF position for the pump that will be started later in the JPM to satisfy the critical step. Placing the switch in the OFF position resets the breaker logic in order to start a HWP. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 3 4.29 Place all CBP control switches to OFF STANDARD: Candidate places the 1A and 1C CBP switches in the OFF position located on 1AB1. COMMENTS: ___ SAT ___ UNSAT RO-602 Page 6 of 10 4 4.30 Place in MANUAL and close: __ 1FDW-53 __ 1FDW-65 STANDARD: Candidate places the 1FDW-53 and 1FDW-65 Moore controllers in MANUAL and ensures the valves are closed located on 1VB3. COMMENTS:

___ SAT

___ UNSAT 5 4.31 Place 1C-10 FAIL SWITCH in MANUAL STANDARD: Candidate places the 1C-10 FAIL SWITCH in MANUAL located on 1VB1. COMMENTS: ___ SAT

___ UNSAT 6 4.32 Close 1C-10 STANDARD: Candidate places the 1C-10 Moore controller in MANUAL and ensures the valves is closed located on 1VB1. COMMENTS: ___ SAT ___ UNSAT 7 4.33 Make plant page to clear basement and third floor of non-essential personnel STANDARD: Candidate makes a PA announcement to clear the turbine building basement and third floor of non-essential personnel. COMMENTS:

___ SAT

___ UNSAT RO-602 Page 7 of 10 8 4.34 Start one HWP STANDARD: Candidate starts one Hotwell pump by rotating the control switch to the start positon and observing the red lit and green light off located on 1AB1. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 9 4.35 Verify < 25 minutes elapsed since loss of condensate STANDARD: Candidate verifies that < 25 minutes have elapsed since the loss of condensate. COMMENTS: ___ SAT ___ UNSAT 10 4.36 Throttle 1C-10 controller 10% open to satisfy 25 minute system restart criteria. STANDARD: Candidate throttles the 1C-10% open. COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT 11 4.37 WHEN THEN open 1C-10 STANDARD: Candidate locates FWP SUCT HDR PRESS gauge 100 psig and then opens 1C-10 using the Moore controller located on 1VB1. COMMENTS: ___ SAT

___ UNSAT RO-602 Page 8 of 10 12 4.38 Place 1C-10 Fail Open Switch in FAIL OPEN STANDARD: Candidate places the 1C-10 FAIL OPEN SWITCH in FAIL OPEN located on 1VB1. COMMENTS: ___ SAT ___ UNSAT 13 4.39 Maximize total recirc flow < 1200 gpm with one of the following: __ 1FDW-53 __ 1FDW-65 STANDARD: Candidate throttles either the 1FDW-53 or 1FDW-65 Moore controller to maximize flow to < 1200 gpm located on 1VB3. COMMENTS: END TASK ___ SAT

___ UNSAT TIME STOP: ________

RO-602 Page 9 of 10 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 2 This step is required to reset the breaker logic so a Hotwell pump can be started. 8 This step is required in order to restore condensate flow. 10 This step is required in order to restore condensate flow CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS A Switchyard Isolation has occurred from 100% power A Load Shed has NOT occurred All 4160 volt switchgear has been re-energized by the overhead power path from a Keowee Hydro unit 5 minutes have elapsed since the loss of offsite power Condensate system operation is desired AP/1/A/1700/011 (Recovery From Loss of Power) is in progress and completed up to step 4.27

INITIATING CUE The CRS directs you to continue AP/1/A/1700/011 (Recovery From Loss of Power) beginning at step 4.27 RO-803a Page 1 of 16 REGION II JOB PERFORMANCE MEASURE RO-803a ALIGN INTAKE CANAL FOR RECIRC ON DAM FAILURE Alternate Path: Yes Alt Path Failure: CCW-9 fails closed Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-803a Page 2 of 16 REGION II JOB PERFORMANCE MEASURE Task Title: Align Intake Canal for Recirc on Dam Failure Task Number: N/A Alternate Path: Yes Time Critical: No Validation Time: 20 min K/A Rating(s): System: 075 K/A: G 2.1.23 Rating: 4.3/4.4 Task Standard: Intake Canal is aligned for recirculation correctly by procedure and an AO is dispatched to manually open CCW-9.

References:

"CCW LAKE LEVEL LOW" statalarm (1SA-9, B-10) AP/1/A/1700/13, (Dam Failure) Rev 032 Tools/Equipment/Procedures Needed: AP/1/A/1700/13, (Dam Failure) =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-803a Page 3 of 16 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 214 2. IMPORT RO-803a files 3. PLACE simulator in RUN and depress the Dam Failure P/B 4. ENSURE all CCW pumps have green flags showing 5. PROVIDE a copy of AP/1/A/1700/013 (Dam Failure) with steps 4.1 through 4.57 signed off RO-803a Page 4 of 16 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS The SM has confirmed Condition 'A' for Little River Dam Unit 1 has been manually tripped The Intake Canal is intact The RCPs have been secured AP/1/A/1700/13 (Dam Failure) has been completed up to step 4.58 The Unit 2 Control Room has directed Unit 1 to supply CCW recirculation

INITIATING CUE Control Room Supervisor directs you to align the CCW Intake Canal for recirculation following a dam failure beginning at step 4.58 of AP/1/A/1700/013 (Dam Failure)

When directed by the AP, start the 1C CCW pump

RO-803a Page 5 of 16 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 4.58 NOTE Unit 2 CR will decide which unit will establish CCW recirculation. Unit 1 will only supply CCW recirculation when directed by Unit 2. IAAT Unit 2 CR has directed Unit 1 to supply CCW recirculation, THEN perform Steps 4.59 - 4.74 to start one CCW Pump and establish recirculation. STANDARD: The candidate determines from the Initial Conditions that Unit 2 CR has directed Unit 1 to supply CCW recirculation and proceeds to Step 4.59. COMMENTS: ___ SAT ___ UNSAT 2 4.59 NOTE At least one CCW Pump discharge valve is required to remain open prior to establishing forced flow. The adjacent CCW Pumps discharge valve must be closed to prevent excessive torque on the starting pumps discharge valve. The 1A and 1B CCW Pumps are adjacent, and the 1C and 1D CCW Pumps are adjacent Determine which CCW Pump will be started CCW Pump 1A 1B 1C 1D STANDARD: The candidate determines that the 1C CCW Pump will be started and continues to Step 4.60. COMMENTS: ___ SAT ___ UNSAT RO-803a Page 6 of 16 3 4.60 Place all CCW Pump switches in the trip position CCW Pump 1A 1B 1C 1D STANDARD: The candidate locates the CCW Pump controls on 1AB3 and rotates the 1A, 1B, 1C, and 1D CCW Pump control switches to the trip position. The candidate continues to Step 4.61. COMMENTS: ___ SAT ___ UNSAT 4 4.61 Verify the 1A or 1B CCW Pump is to be started STANDARD: The candidate was cued to start the 1C CCW Pump, RNO directs the operator to GO TO Step 4.64 COMMENTS: ___ SAT

___ UNSAT RO-803a Page 7 of 16 5 4.64 Verify both of the following CCW pump discharge valves are closed Pump Valve 1C 1CCW-12 1D 1CCW-13 STANDARD: Candidate verifies that 1CCW-12 indicates open by observing the red open light illuminated and the green closed light OFF on 1AB3 OR by OAC indications. Candidate verifies that 1CCW-13 is closed by observing the green closed light illuminated and red open light OFF on 1AB3 OR by OAC indications. Candidate determines that both valves are NOT closed and proceeds to Step 4.64 RNO. COMMENTS:

___ SAT ___ UNSAT 6 4.64 RNO Locally close the discharge valves from the breaker switch (Unit 1 Equipment Rm). Pump Valve Breaker 1C 1CCW-12 1XS3-2E 1D 1CCW-13 1XS1-F3C STANDARD: The candidate dispatches an operator to Unit 1 Equipment Room to close 1CCW-12 and 1CCW-13 Simulator Operator: After the candidate has dispatched an operator to Unit 1 Equipment Room to close 1CCW-12 & 1CCW-13, FIRE TIMER #1 TO CLOSE 1CCW-12. 1CCW-13 is already closed. Cue: Inform the candidate that 1CCW-12 and 1CCW-13 both indicate closed from the equipment room. Candidate continues to Step 4.65 COMMENTS:

___ SAT ___ UNSAT RO-803a Page 8 of 16 7 4.65 NOTE CCW pump amps and temperatures will read higher than normal when started with this plant configuration. CCWP motor stator temperature limit is 284°F. Start the selected CCW pump STANDARD: The candidate locates the control switch for the 1C CCW Pump on 1AB3 and rotates the control switch to the close position. The candidate observes that the 1C CCW pump discharge valve starts to travel open and when approx 20% open, the 1C CCW pump starts as indicated by red run light illuminated and 375 motor amps indicated. NOTE: CCWP motor stator temperatures are NOT modeled on the simulator OAC. Cue: If the candidate asks, inform him/her that the selected CCW Pump motor stator temperature is 200°F and stable. COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT 8 4.66 Verify the started CCW pump discharge valve opened STANDARD: The candidate verifies the 1C CCW Pump discharge valve indicates OPEN by observing the red open light illuminated and the green closed light OFF on 1AB3. The candidate may also verify selected discharge valve open by OAC indications COMMENTS: ___ SAT

___ UNSAT RO-803a Page 9 of 16 9 4.67 Ensure CCWP LOAD SHED DEFEAT switch is positioned to a running pump STANDARD: Candidate locates the CCWP LOAD SHED DEFEAT switch on VB1 and positions switch to the 1C CCW pump COMMENTS: ___ SAT

___ UNSAT 10 4.68 [ALTERNATE PATH] Verify CCW-9 is open STANDARD: Candidate observes CCW-9 indication on 2AB3 and determines that CCW-9 is closed by the red OPEN light OFF and the green CLOSED indication illuminated Candidate determines CCW-9 is closed and proceeds to step 4.68 RNO Note: CCW-9 is failed closed COMMENTS: ___ SAT

___ UNSAT RO-803a Page 10 of 16 11 4.68 RNO 1. *Stop the operating CCW pump. 2. Notify Security to meet an operator at Gate 23 (CCW Intake) to provide access to CCW-9. 3. Dispatch an operator to perform the following: A. Obtain the CCW-9 Gate Key from security box in Unit 3 Control Room storage area. B. Access the area between fences at Gate 23 leading to the CCW intake. C. *Open CCW-9 (EMERGENCY CCW DISCHARGE TO INTAKE) (between protected area fences). D. Notify Unit 1 CR when CCW-9 is open. 4. WHEN notified that CW-9 is open, THEN GO TO Step 4.59 to restart a CCW pump. STANDARD: Candidate locates the control switch for the 1C CCW Pump on 1AB2 and rotates the control switch to the trip position and observes the red ON lights OFF and the white OFF light illuminated. Candidate notifies Security to meet an operator at Gate 23 to provide access to CCW-9. Candidate dispatches an operator to obtain the CCW-9 Gate Key from the Security box in the Unit 3 Control Room storage area. The operator, along with Security, proceeds between the Protected Area fences in order to open CCW-9. Booth cue: Fire Timer 4 to open CCW-9 and using time compression and inform the candidate that CCW-9 has been opened. Candidate returns to step 4.59 to restart a CCW pump. COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT RO-803a Page 11 of 16 12 4.59 NOTE At least one CCW Pump discharge valve is required to remain open prior to establishing forced flow. The adjacent CCW Pumps discharge valve must be closed to prevent excessive torque on the starting pumps discharge valve. The 1A and 1B CCW Pumps are adjacent, and the 1C and 1D CCW Pumps are adjacent Determine which CCW Pump will be started CCW Pump 1A 1B 1C 1D STANDARD: The candidate determines that the 1C CCW Pump will be started and continues to Step 4.60. COMMENTS: ___ SAT ___ UNSAT 13 4.60 Place all CCW Pump switches in the trip position CCW Pump 1A 1B 1C 1D STANDARD: The candidate locates the CCW Pump controls on 1AB3 and rotates the 1A, 1B, 1C, and 1D CCW Pump control switches to the trip position. The candidate continues to Step 4.61. COMMENTS: ___ SAT ___ UNSAT RO-803a Page 12 of 16 14 4.61 Verify the 1A or 1B CCW Pump is to be started STANDARD: The candidate was cued to start the 1C CCW Pump, RNO directs the operator to GO TO Step 4.64 COMMENTS: ___ SAT

___ UNSAT 15 4.64 Verify both of the following CCW pump discharge valves are closed Pump Valve 1C 1CCW-12 1D 1CCW-13 STANDARD: Candidate verifies that 1CCW-12 indicates open by observing the red open light illuminated and the green closed light OFF on 1AB3 OR by OAC indications. Candidate verifies that 1CCW-13 is closed by observing the green closed light illuminated and red open light OFF on 1AB3 OR by OAC indications. Candidate determines that both valves are NOT closed and proceeds to Step 4.64 RNO. COMMENTS:

___ SAT

___ UNSAT RO-803a Page 13 of 16 16 4.64 RNO Locally close the discharge valves from the breaker switch (Unit 1 Equipment Rm). Pump Valve Breaker 1C 1CCW-12 1XS3-2E 1D 1CCW-13 1XS1-F3C STANDARD: The candidate dispatches an operator to Unit 1 Equipment Room to close 1CCW-12 and 1CCW-13 Simulator Operator: After the candidate has dispatched an operator to Unit 1 Equipment Room to close 1CCW-12 & 1CCW-13, FIRE TIMER 5 TO CLOSE 1CCW-12. 1CCW-13 is already closed. Cue: Inform the candidate that 1CCW-12 and 1CCW-13 both indicate closed from the equipment room. Candidate continues to Step 4.65 COMMENTS:

___ SAT ___ UNSAT RO-803a Page 14 of 16 17 4.65 NOTE CCW pump amps and temperatures will read higher than normal when started with this plant configuration. CCWP motor stator temperature limit is 284°F. Start the selected CCW pump STANDARD: The candidate locates the control switch for the 1C CCW Pump on 1AB3 and rotates the control switch to the close position. The candidate observes that the 1C CCW pump discharge valve starts to travel open and when approx 20% open, the 1C CCW pump starts as indicated by red run light illuminated and 375 motor amps indicated. NOTE: CCWP motor stator temperatures are NOT modeled on the simulator OAC. Cue: If the candidate asks, inform him/her that the selected CCW Pump motor stator temperature is 200°F and stable. COMMENTS: END TASK CRITICAL STEP

___ SAT ___ UNSAT TIME STOP: ________

RO-803a Page 15 of 16 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 7 Step 7 is critical to start a CCW pump. 11 Step 11 is critical to ensure the operating CCW pump is stopped and CCW-9 is opened manually to align CCW recirculation flow. 17 Step 17 is critical to start a CCW pump.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS The SM has confirmed Condition 'A' for Little River Dam Unit 1 has been manually tripped The Intake Canal is intact The RCPs have been secured AP/1/A/1700/13 (Dam Failure) has been completed up to step 4.58 The Unit 2 Control Room has directed Unit 1 to supply CCW recirculation

INITIATING CUE Control Room Supervisor directs you to align the CCW Intake Canal for recirculation following a dam failure beginning at step 4.58 of AP/1/A/1700/013 (Dam Failure)

When directed by the AP, start the 1C CCW pump RO-901a Page 1 of 16 REGION II JOB PERFORMANCE MEASURE RO-901a RELEASE GWD TANK Alternate Path: Yes Alt Path Failure: The "B" GWD tank pressure will decrease instead of the D GWD tank Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-901a Page 2 of 16 REGION II JOB PERFORMANCE MEASURE Task Title : Release GWD Tank Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 30 min K/A Rating(s): System: 071 K/A: A4.26 Rating: 3.1/3.9 Task Standard: Release a GWD tank correctly using OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release) and terminate the release when unexpected results are noted.

References:

OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release) Rev 77 PT/0/A/230/001 (Radiation Monitor Check) Rev 167 Tools/Equipment/Procedures Needed: OP/1&2/A/1104/018, Enclosure 4.9 (GWD Tank Release) & 4.10 (GWD Tank Sample Request) PT/0/A/230/001 (Radiation Monitor Check)

=========================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-901a Page 3 of 16 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 212 2. Go to RUN

RO-901a Page 4 of 16 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Release of "D" GWD tank is desired No other GWRs in progress OP/1&2/A/1104/018, Enclosure 4.9 (GWD Tank Release) is in progress and completed up to step 3.9

INITIATING CUES CRS directs you to complete the release of the "D" GWD tank beginning at step 3.9 of Enclosure 4.9 (GWD Tank Release)

RO-901a Page 5 of 16 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 3.9 NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks' radioactivity was < 2.1E- / ml when it was released, the GWD piping is considered "purged". 3.9.1 Adjust 1RIA-37 setpoints for release as follows: 3.9.2 Perform one of the following: A. IF all of the following: Calculated setpoints are < 1E+07 CPM 1RIA-37 operable GWD piping purged {15} set alarms as follows: Set 1RIA-37 Alert setpoint at _______________cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.7.1) Set 1RIA-37 High setpoint at _______________cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.7.1) NOTE: If GWD piping NOT purged on most recent release, RP independently verifies release data and 1RIA-37 setpoint is set at zero to allow the tank to be released. {15} B. IF any of the following: Calculated setpoints are > 1E+07 CPM 1RIA-37 out-of-service GWD piping NOT purged {15} perform the following: 1. Enter SLC 16.11.3, Conditions C and I 2. Override 1RIA-37 setpoints as follows: Set 1RIA-37 Alert setpoint at zero per PT/0/A/0230/001 (Radiation Monitor Check). Set 1RIA-37 High setpoint at zero per PT/0/A/0230/001 (Radiation Monitor Check). STANDARD: Refer to PT/0/A/0230/001 (Radiation Monitor Check) Encl. 13.6 (1RIA-37 and 1RIA-38 Setpoints) and using the RIA Screen insert the calculated 1RIA-37 setpoint of 2.73 E5 CPM Candidate continues to Step 3.10 COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT RO-901a Page 6 of 16 2 3.10 Adjust 1RIA-38 setpoints for release as follows: 3.10.1 Perform one of the following: A. IF calculated setpoints are < 1E+06 CPM AND 1RIA-38 operable, set alarms as follows: Set 1RIA-38 Alert setpoint at _______________cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.8) Set 1RIA-38 High setpoint at _______________cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.8) NOTE: Due to type of radiation 1RIA-38 monitors, it is NOT sensitive enough to perform an adequate N2 purge. B. IF calculated setpoints are > 1E+06 CPM OR 1RIA-38 out of service, perform the following: 1. Enter SLC 16/11/3, Conditions C and I 2. Override 1RIA-38 setpoints as follows: Set 1RIA-38 Alert setpoint at zero per PT/0/A/0230/001 (Radiation Monitor Check). Set 1RIA-38 High setpoint at zero per PT/0/A/0230/001 (Radiation Monitor Check). STANDARD: Refer to PT/0/A/0230/001 (Radiation Monitor Check) Encl. 13.6 (1RIA-37 and 1RIA-38 Setpoints) and using the RIA ENABLE CONTROLs Screen insert the calculated 1RIA-38 setpoint of 339 CPM. Candidate continues to Step 3.11 COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 3 3.11 Ensure GWR DISCHARGE FLOW CONTROL in "HAND". STANDARD: Ensure GWR DISCHARGE FLOW CONTROL in "HAND" located on 1AB3. Candidate continues to Step 3.12 COMMENTS: ___ SAT ___ UNSAT RO-901a Page 7 of 16 4 3.12 Verify GWR DISCHARGE FLOW CONTROL "CLOSED" STANDARD: Verify GWR DISCHARGE FLOW CONTROL CLOSED located on 1AB3. Candidate continues to Step 3.13 COMMENTS: ___ SAT ___ UNSAT 5 3.13 Remove "Purged / Not Purged" CR tag from GWR DISCHARGE FLOW CONTROL. STANDARD: Remove "Purged / Not Purged" CR tag from GWR DISCHARGE FLOW CONTROL located on 1AB3. Candidate continues to Step 3.14 COMMENTS: ___ SAT ___ UNSAT 6 3.14 Notify Unit 3 CR to perform the following: Begin periodically monitoring all three Unit 3 GWD tanks to determine if pressure in any tank is decreasing unexpectedly. {12} Place a note on turnover sheet "If 3RIA-45 alarms or GWD tank pressure in any tank is decreasing unexpectedly, notify Unit 1 CR to terminate GWD tank release". STANDARD: Notify Unit 3 CR to begin periodically monitoring all three Unit 3 GWD tanks to determine if pressure in any tank is decreasing unexpectedly Notify Unit 3 CR to place above note on the turnover sheet Candidate continues to Step 3.15 COMMENTS: ___ SAT ___ UNSAT RO-901a Page 8 of 16 7 3.15 Notify Unit 2 CR to place a note on turnover sheet "If 2RIA-45 alarms, notify Unit 1 CR to terminate GWD tank release". STANDARD: Notify Unit 2 CR to place above note on the turnover sheet. Candidate continues to Step 3.16 COMMENTS: ___ SAT

___ UNSAT 8 3.16 Begin monitoring all four Unit 1 GWD tanks to determine if pressure in any tank is decreasing unexpectedly. STANDARD: Begin monitoring GWD tank pressures on chart recorder on 1VB2 or OAC. Candidate continues to Step 3.17 COMMENTS:

___ SAT ___ UNSAT 9 3.17 NOTE: -1RIA-37 as N2 is added to inform CR when local readings indicate the piping is purged. IF 1RIA-37 NOT in service AND -notify RP to prepare to survey GWD piping at 1RIA-37. {15} ________________________ _____ Person Notified Date STANDARD: Determine 1RIA-37 is in service and N/A step 3.17. Candidate continues to Step 3.18 COMMENTS: ___ SAT

___ UNSAT RO-901a Page 9 of 16 10 3.18 IF AT ANY TIME any tank is decreasing unexpectedly, perform the following: 3.18.1 Close GWR DISCHARGE FLOW CONTROL. 3.18.2 Notify RP to initiate SRPMP 8-02 (Investigation of Unusual Radiological Occurrences) due to potential unplanned radioactive effluent release. ________________________ _____ Person Notified Date 3.18.3 Go To Section 4 (GWR Termination). STANDARD: Determine IAAT step is not met at this time. Candidate continues to Step 3.19 COMMENTS: ___ SAT ___ UNSAT 11 3.19 IF AT ANY TIME desired to terminate release, perform the following: 3.19.1 Close GWR DISCHARGE FLOW CONTROL. 3.19.2 Go To Section 4 (GWR Termination). STANDARD: Determine IAAT step is not met at this time. Candidate continues to Step 3.20 COMMENTS: ___ SAT

___ UNSAT 12 3.20 Open GWD-100 (Decay Tanks Discharge Header Block). (A-2-209/E 13' N of Door) STANDARD: Dispatch AO to Open GWD-100 (Decay Tanks Discharge Header Block). Candidate continues to Step 3.21 Booth Note: GWD-100 is OPEN. Cue: Inform candidate that GWD-100 is open. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT RO-901a Page 10 of 16 13 3.21 3.22 3.23 IF releasing GWD Tank A/B/C, perform the following- STANDARD: Determine NOT releasing GWD Tank A, B, and C and N/A steps 3.21, 3.22, and 3.23. Candidate continues to Step 3.24 COMMENTS: ___ SAT ___ UNSAT 14 3.24 IF releasing GWD Tank 'D' perform the following: Open GWD-205 (Decay Tank 1D Discharge Block) (IRW Building) Place GWD-207 ('D' INTERIM GWD TANK DISCH) switch to "OPEN" STANDARD: Dispatch AO to open GWD-205 (Decay Tank 1D Discharge Block). Cue: Inform candidate that GWD-205 is open. Locate GWD-207 ("D" INTERIM GWD TANK DISCH) on 1AB3 and place switch to "OPEN" Candidate continues to Step 3.25 COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT RO-901a Page 11 of 16 15 3.25 NOTE: Station Limit release rates, per SLC 16.11, will NOT be exceeded if recommended release rates per Enclosure 4.10 (GWD Tank Sample Request) are followed. The following approval levels are required for releases: {10}{13} All Station Releases in Progress Required Level of Approval (including this one) 1 GWR in progress through P/A/C filter at SRO 1 GWR in progress at 1/3 Station Limit (< 30 day holdup OR released without P/A/C filter) OSM 1 GWR in progress at 2/3 Station Limit OSM 2 GWRs in progress at 1/3 Station Limit each OSM 3 GWRs in progress at 1/3 Station Limit each OSM Circle Required Level of Approval above based on Release Conditions. STANDARD: Circle SRO on enclosure. Candidate continues to Step 3.26 COMMENTS: ___ SAT ___ UNSAT 16 3.26 Record approval granted for release: ________________________ _________ / _____ Approval Date Time STANDARD: Place approval name and date and time on enclosure. Candidate continues to Step 3.27 Cue: Inform candidate that approval is granted for release by Mitch Helms at current Date/Time. COMMENTS: ___ SAT

___ UNSAT RO-901a Page 12 of 16 17 3.27 NOTE: 30 days, the limits will be checked NA by RP on GWD Tank Sample Request. IF tank holdup < 30 days, perform the following- STANDARD: Determine tank has been held up greater than 30 days and N/A steps 3.27.1 - 3.27.2. Candidate continues to Step 3.28 COMMENTS: ___ SAT ___ UNSAT 18 3.28 IF tank is released without processing through a P/A/C filter AND Projected 31 day average gaseous effluent organ dose > limit, perform the following- STANDARD: Determine tank is being released through a P/A/C filter and N/A steps 3.28.1 - 3.28.4. Candidate continues to Step 3.29 COMMENTS: ___ SAT

___ UNSAT 19 3.29 Record recommended Release Rate from Enclosure 4.10 (GWD Tank Sample Request): ______________ cfm STANDARD: Record recommended Release Rate from Enclosure 4.10 (GWD Tank Sample Request): __4.19 E4____ cfm Candidate continues to Step 3.30 COMMENTS: ___ SAT

___ UNSAT RO-901a Page 13 of 16 20 3.30 NOTE: With Unit 1 PRV system shutdown, RIA-32 sample point for '1 PRV System Filter Discharge' is sampling air in piping between Unit 1 PRV discharge and Unit Vent, NOT the general area {2} During or just after GWD Release RIA-32 counts may increase while selected to '1 PRV System Filter Discharge' causing 1SA-8/B-9 "Process Monitor Radiation High" to alarm. Place the following note on Unit 1 Turnover sheet: "Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to '1 PRV System Filter Discharge'. IF 1SA-8/B-9 is due to RIA '1 PRV System Filter Discharge', it can be considered an expected alarm". STANDARD: Candidate should indicate that the above note will be placed on the turnover sheet. Candidate continues to Step 3.31 COMMENTS: ___ SAT ___ UNSAT 21 3.31 Adjust GWR DISCHARGE FLOW CONTROL to obtain desired release rate. STANDARD: Slowly adjust the manual loading knob to obtain the desired release rate. Candidate continues to Step 3.32 Note: Actual release rate will be much less than the maximum flow rate allowed by the release permit. Flow is monitored on VB1 recorder 1MSCCR0001 COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 22 3.32 Record "Begin GWR # _________" in Narrative Log. STANDARD: Candidate should indicate a Unit log entry would be made. Note: The "B" GWD tank pressure will decrease instead of the D GWD tank. The candidate should note this while monitoring the tank pressures and then perform IAAT Step 3.18. Candidate may also perform the IAAT because he notes that a release is occurring but the "D" GWD tank pressure is not decreasing. In both cases unexpected results were noted. COMMENTS: ___ SAT ___ UNSAT RO-901a Page 14 of 16 23 3.18 IAAT [ALTERNATE PATH] IF AT ANY TIME any tank is decreasing unexpectedly, perform the following: 3.18.1 Close GWR DISCHARGE FLOW CONTROL. 3.18.2 Notify RP to initiate SRPMP 8-02 (Investigation of Unusual Radiological Occurrences) due to potential unplanned radioactive effluent release. ________________________ _____ Person Notified Date 3.18.3 Go To Section 4 (GWR Termination). STANDARD: Determine IAAT step is met because the "B" GWD Tank pressure is decreasing. *Close GWR DISCHARGE FLOW CONTROL. Notify RP initiate SRPMP 8-02 (Investigation of Unusual Radiological Occurrences) Go To Section 4 (GWR Termination). Cue: Another operator will complete this procedure. COMMENTS: END TASK *CRITICAL STEP ___ SAT ___ UNSAT TIME STOP: ________

RO-901a Page 15 of 16 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 Required to set RIA to prevent station release above limits. 2 Required to set RIA to prevent station release above limits. 12 Required to align release flow path. 14 Required to align release flow path. 21 Required to align release flow path. 23 Required to stop the release of the wrong tank.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Release of "D" GWD tank is desired No other GWRs in progress.

OP/1&2/A/1104/018, Enclosure 4.9 (GWD Tank Release) is in progress and completed up to step 3.9

INITIATING CUES CRS directs you to complete the release of the "D" GWD tank beginning at step 3.9 of Enclosure 4.9 (GWD Tank Release).

RO-P402a Page 1 of 9 REGION II JOB PERFORMANCE MEASURE RO-P402a START FOURTH REACTOR COOLANT PUMP Alternate Path: Yes Alt Path Failure: AC OIL Lift Pump Trips Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

RO-P402a Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title: Start the fourth Reactor Coolant Pump Task Number: N/A Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s): System: 003 K/A: A4.03 Rating: 2.8/2.5 Task Standard: 1B2 RCP is started in accordance with OP/1/A/1103/006 Encl. 4.4 (Starting 1B2 RCP) and DC Oil Lift Pump secured

References:

OP/1/A/1102/001 (Controlling Procedure for Unit Startup) OP/1/A/1103/006 (RCP Operation) Rev 86 Tools/Equipment/Procedures Needed: OP/1/A/1103/006 Encl. 4.4 (Starting 1B2 RCP) =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments RO-P402a Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS 1. RECALL SNAP 209 2. IMPORT FILES for RO-P402 3. ENSURE all breaker flags are set to current plant conditions 4. ENSURE a marked up copy of Enclosure 4.4 is provided to Examiner for candidate 5. Go to RUN when directed by the Lead Examiner RO-P402a Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS OP/1/A/1102/001 (Controlling Procedure for Unit Startup) Enclosure 4.6 (Unit Startup From 335°F/540 psig (MODE 3) To 532°F/2155 psig (MODE 3)) in progress and completed up to Step 6.2 which directs starting the fourth RCP RCS Pressure = 1660 psig slowly increasing in accordance with OP/1/A/1102/001 RCS Temperature = 474°F slowly increasing in accordance with OP/1/A/1102/001 INITIATING CUE The CRS directs you to start the 1B2 RCP per OP/1/A/1103/006 Encl. 4.4 beginning with Step 2.2.1

RO-P402a Page 5 of 9 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.2.1 NOTE: No more than two RCP(s) may be operated when RCS is <300°F. AC and DC Oil Lift Pumps will automatically trip after 3 minutes. Oil Lift Pump may NOT start unless switch has been placed to "OFF" after last start. Announce "Starting 1B2 RCP" via plant page. STANDARD: Announces "Starting 1B2 RCP" via plant page. Candidate continues to step 2.2.2. COMMENTS: ___ SAT ___ UNSAT 2 2.2.2 IF AT ANY TIME Oil Lift Pump low discharge pressure clears, Go To Step 2.2.6 STANDARD: Reads IAAT step and determines that it does not currently apply Candidate continues to step 2.2.3. COMMENTS: ___ SAT ___ UNSAT 3 2.2.3 NOTE: AC Oil Lift Pump may take > 2 minutes to develop adequate discharge pressure. IF available, start AC Oil Lift Pump on 1B2 RCP. STANDARD: Determines AC Oil Lift Pump is available and: Rotates AC Oil Lift Pump switch to start Observes red light on and green light off Monitors discharge pressure status on OAC Candidate continues to step 2.2.4. COMMENTS: ___ SAT

___ UNSAT RO-P402a Page 6 of 9 4 2.2.4 NOTE: Operating either AC or DC Oil Lift Pump is adequate to start RCP. IF AC Oil Lift Pump is unavailable, start DC Oil Lift Pump STANDARD: Determines AC Oil Lift Pump is available and N/A's this step Candidate continues to step 2.2.5. COMMENTS: ___ SAT ___ UNSAT 5 2.2.5 [ALTERNATE PATH] IF AC Oil Lift Pump automatically trips prior to Oil Lift Pump low discharge pressure clearing, start DC Oil Lift Pump. STANDARD: Determines the AC Oil Lift Pump has tripped and starts the DC Oil Lift Pump by performing the following: *Rotates DC Oil Lift Pump switch to start Observes red light on and green light off Monitors discharge pressure status on OAC Time DC OLP started: ________ Candidate continues to step 2.2.6. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT 6 2.2.6 WHEN Oil Lift Pump low discharge pressure clears AND > 60 seconds has elapsed since starting oil lift pumps, start 1B2 RCP. STANDARD: Once the DC Oil Lift Pump low discharge pressure has cleared, start the 1B2 RCP as follows: *Rotate 1B2 RCP switch to START Verify red lights on and green light off Verify starting current Verify OAC indications support pump start Candidate continues to step 2.2.7. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT

RO-P402a Page 7 of 9 7 2.2.7 After RCP is at full speed, perform the following: A. Ensure the following stopped: AC Oil Lift Pump DC Oil Lift Pump B. IF AC Oil Lift Pump was operated, position AC Oil Lift Pump switch to "OFF". C. IF DC Oil Lift Pump was operated, position DC Oil Lift Pump switch to "OFF" STANDARD: Once 1B2 RCP is at rated speed, Rotates AC Oil Lift Pump switch to OFF Rotates the DC Oil Lift Pump Switch to OFF Examiner Cue: Inform the candidate that another operator will complete the procedure. COMMENTS: END TASK ___ SAT ___ UNSAT TIME STOP: ________

RO-P402a Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 5 This step is required to be able to start the 1B2 RCP. 6 This step is required to actually start the 1B2 RCP.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS OP/1/A/1102/001 (Controlling Procedure for Unit Startup) Enclosure 4.6 (Unit Startup From 335°F/540 psig (MODE 3) To 532°F/2155 psig (MODE 3)) in progress and completed up to Step 6.2 which directs starting the fourth RCP RCS Pressure = 1660 psig slowly increasing in accordance with OP/1/A/1102/001 RCS Temperature = 474°F slowly increasing in accordance with OP/1/A/1102/001 INITIATING CUE The CRS directs you to start the 1B2 RCP per OP/1/A/1103/006 Encl. 4.4 beginning with Step 2.2.1 AO-101 Page 1 of 8 REGION II JOB PERFORMANCE MEASURE AO-101 SWAP CRD FILTERS Alternate Path: No Alt Path Failure: ____________________________________________________________ Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

AO-101 Page 2 of 8 REGION II JOB PERFORMANCE MEASURE Task Title : Swap CRD Filters Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 20 Min K/A Rating(s): System: 001 K/A: G 2.3.13 Rating: 3.4/3.8 Task Standard: Place standby CRD filter in service and remove other CRD filter from service.

References:

OP/1/A/1104/008 Component Cooling System Rev 75 Tools/Equipment/Procedures Needed: OP/1/A/1104/008 Component Cooling System, Encl. 4.19 Placing 1A OR 1B CRD Filter In Service =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments AO-101 Page 3 of 8 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA AO-101 Page 4 of 8 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS The 1B CRD filter P is 11 psid It has been determined that the operating CRD filters have to be swapped INITIATING CUES The CRS directs you to place the 1A CRD filter in service and remove the 1B CRD filter from service using OP/1/A/1104/008 Component Cooling System, Encl. 4.19 Placing 1A OR 1B CRD Filter In Service

AO-101 Page 5 of 8 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.1 IF required, place 1A CRD Filter in service: STANDARD: Per the cue sheet, the 1A CRD Filter will be placed in service. COMMENTS: ___ SAT ___ UNSAT 2 2.1.1 Ensure open 1CC-72 (1A CRD Filter Inlet). STANDARD: Candidate opens 1CC-72 by turning the hand wheel in the counter clockwise direction until it comes to a hard stop. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 3 2.1.2 Open 1CC-136 (1A CRD Filter Sightglass Outlet). STANDARD: Candidate opens 1CC-136 by turning hand wheel in the counter clockwise direction until it comes to a hard stop. COMMENTS: ___ SAT ___ UNSAT 4 2.1.3 Throttle 1CC-73 (1A CRD Filter Vent) to vent 1A CRD Filter. STANDARD: Candidate throttles open 1CC-73 by turning the hand wheel in the counter clockwise direction until flow is noticed in the sight glass.

Examiner Cue: Several seconds after 1CC-73 is throttled open, inform the candidate that a solid stream is noticed in the sight glass. COMMENTS: ___ SAT

___ UNSAT AO-101 Page 6 of 8 5 2.1.4 WHEN vented, position the following: Close 1CC-73 (1A CRD Filter Vent) Close 1CC-136 (1A CRD Filter Sightglass Outlet) STANDARD: When the candidate notices a solid stream of water in the sightglass, they close1CC-73 and 1CC-136 by turning the hand wheels in the clockwise direction until they come to a hard stop. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 6 2.1.5 Open 1CC-74 (1A CRD Filter Outlet). STANDARD: Candidate opens 1CC-74 by turning the valve in the counter clockwise direction until the handwheel comes to a hard stop. COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT 7 2.1.6 IF desired, remove 1B CRD Filter from service: Close 1CC-92 (1B CRD Filter Inlet) Close 1CC-93 (1B CRD Filter Outlet) STANDARD: Candidate closes 1CC-92 and 1CC-93 by turning the hand wheels in the clockwise direction until they come to a hard stop. COMMENTS: END TASK CRITICAL STEP

___ SAT ___ UNSAT TIME STOP: ________

AO-101 Page 7 of 8 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 2 This step is required to allow flow into the CRD filter. 5 This step is required to prevent draining the CC system. 6 This step is required to place the 1A CRD filter in the fluid stream. 7 This step is required to remove the 1B CRD filter from service CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS The 1B CRD filter P is 11 psid It has been determined that the operating CRD filters have to be swapped INITIATING CUES The CRS directs you to place the 1A CRD filter in service and remove the 1B CRD filter from service using OP/1/A/1104/008 Component Cooling System, Encl. 4.19 Placing 1A OR 1B CRD Filter In Service AO-602 Page 1 of 10 REGION II JOB PERFORMANCE MEASURE AO-602 STARTUP A VITAL BUS INVERTER Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

AO-602 Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task Title : STARTUP A VITAL BUS INVERTER Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 12 min K/A Rating(s): System: 062 K/A: A3.04 Rating: 2.7/2.9 Task Standard: Vital Bus Inverter placed in service correctly.

References:

OP/2/A/1107/04 (Operation Of Vital Bus, Computer, ICS And Auxiliary Inverters) rev. 30 Tools/Equipment/Procedures Needed: OP/2/A/1107/04 Enclosure 4.2 (Startup of Vital Bus Inverters) Inverter Drawing ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments AO-602 Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA AO-602 Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit #2 is at 100% power Earlier today the 2DIA Vital Bus Inverter on Unit 2 was shutdown for maintenance. I&E personnel have just notified the Control Room SRO that they have completed their work on the inverter and it is ready to be returned to service.

All tags have been cleared. The Inverter Temporary Precharge Switch is NOT installed The affected 120VAC Vital Instrumentation Power Panelboard is being supplied by Regulated AC Panelboard 2KRA. OP/2/A/1107/004 Enclosure 4.2 is complete through step 1.3 INITIATING CUES The Control Room SRO directs you to startup the 2DIA Vital Bus Inverter per OP/2/A/1107/004 Enclosure 4.2.

AO-602 Page 5 of 10 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.1 EXAMINER CUE: Once the 2DIA inverter is located, if desired provide the included picture to establish the as-found condition of the inverter. IF DC power to inverter was isolated, close breaker #33 on associated 2DIA DC panelboard (2DIA, 2DIB, 2DIC, 2DID). EXAMINER CUE: 2DIA BKR #33 is closed. STANDARD: Candidate continues to step 2.2 COMMENTS: ___ SAT ___ UNSAT AO-602 Page 6 of 10 2 2.2 NOTE: Pressing PRECHARGE SWITCH pushbutton charges the inverter input filter capacitors and will cause the PRECHARGE light to come on. When pushbutton is released capacitors will begin to discharge. Closing DC Input breaker should be performed in a timely manner before PRECHARGE light goes off and input filter capacitors discharge. Steps 2.2 and 2.3 need to be performed prior to placekeeping/signing 2.3. This is an exception to standard placekeeping methodology. Perform one of the following: 2.2.1 IF temporary Precharge Switch installed in Step 1.3, press PRECHARGE SWITCH pushbutton on temporary Precharge Switch and hold for 10 - 12 seconds after PRECHARGE light comes on before releasing. {2} {4} [It is NOT installed]

2.2.2 IF temporary Precharge Switch NOT installed in Step 1.3, press PRECHARGE SWITCH pushbutton and hold for 10 - 12 seconds after PRECHARGE light comes on before releasing. {2} {4} STANDARD: The candidate presses the PRECHARGE SWITCH pushbutton until the PRECHARGE light comes on and keeps the button depressed for an additional 10 - 12 seconds before releasing. EXAMINER CUE: Indicate to the candidate that the PRECHARGE light is ON. If the pushbutton is not held for an additional 10 - 12 seconds, inform the candidate that the PRECHARGE light is now OFF. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 3 2.3 CLOSE DC INPUT circuit breaker STANDARD: The DC INPUT circuit breaker is CLOSED EXAMINER CUE: Indicate to the candidate that the DC INPUT breaker is in the ON position. EXAMINER NOTE: If the DC INPUT breaker is not closed in a timely manner, the PRECHARGE light will go back OFF and the DC INPUT circuit breaker will trip back open. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT AO-602 Page 7 of 10 4 2.4 IF installed in Step 1.3, ensure temporary Precharge Switch removed. STANDARD: Candidate should mark this step NA. COMMENTS: ___ SAT ___ UNSAT 5 2.5 STANDARD: Candidate verifies Inverter Output volt meter indicates 120 volts. Examiner Cue. If this inverter is actually operating, inform the operator that volt meter reads "as you see it". If not, use pointer or other training aid to simulate 120 Volts. COMMENTS: ___ SAT ___ UNSAT 6 2.6 CLOSE the INVERTER OUTPUT circuit breaker. STANDARD: The INVERTER OUTPUT circuit breaker is CLOSED. EXAMINER CUE: Indicate to the candidate that the INVERTER OUTPUT breaker is in the ON position. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 7 2.7 VERIFY IN SYNC light is on STANDARD: Green IN SYNC. light is verified ON. EXAMINER CUE: Indicate to candidate that the IN SYNC light is ON. COMMENTS: ___ SAT ___ UNSAT AO-602 Page 8 of 10 8 2.8 POSITION the MANUAL BYPASS SWITCH to the "NORMAL SOURCE" position. STANDARD: Candidate rotates the Manual Bypass Switch from the ALTERNATE SOURCE position to the NORMAL SOURCE position. EXAMINER CUE: Indicate to the candidate that the Manual Bypass Switch is in the NORMAL SOURCE position. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 9 2.9 VERIFY the following indications: INVERTER OUTPUT volt meter 120 volts Inverter Output frequency meter 60.6 59.4Hz INVERTER OUTPUT amp meter increases and stabilizes to match SYSTEM OUTPUT amp meter. STANDARD: The following indications are verified: INVERTER OUTPUT volts 120. INVERTER OUTPUT frequency meter 60.6 59.4 Hz. INVERTER OUTPUT amp meter increases and stabilizes to match SYSTEM OUTPUT amp meter. EXAMINER CUE: Provide the following indications to the candidate: INV. OUTPUT volts = 120 INV. OUTPUT freq. = 60 INV. OUTPUT amps = 30 SYS. OUTPUT amps = 30 COMMENTS: END TASK ___ SAT ___ UNSAT TIME STOP: ________

AO-602 Page 9 of 10 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 2 Must precharge the capacitors on the DC Bus so there will not be a low voltage when the DC Breaker is closed. 3 Necessary to provide DC input voltage to the inverter. 6 Necessary to apply NORMAL SOURCE voltage up to the Manual Bypass switch. 8 Applies Inverter AC output voltage from the NORMAL SOURCE to the Vital Bus Panelboards (Loads the Inverter).

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit #2 is at 100% power Earlier today the 2DIA Vital Bus Inverter on Unit 2 was shutdown for maintenance.

I&E personnel have just notified the Control Room SRO that they have completed their work on the inverter and it is ready to be returned to service.

All tags have been cleared. The Inverter Temporary Precharge Switch is NOT installed The affected 120VAC Vital Instrumentation Power Panelboard is being supplied by Regulated AC Panelboard 2KRA.

OP/2/A/1107/004 Enclosure 4.2 is complete through step 1.3

INITIATING CUES The Control Room SRO directs you to startup the 2DIA Vital Bus Inverter per OP/2/A/1107/004 Enclosure 4.2.

AO-802a Page 1 of 11 REGION II JOB PERFORMANCE MEASURE AO-802a ISOLATE HPSW AND LPSW DURING AN AB FLOOD Alternate Path: Yes Alt Path Failure: _______HPSW-959 will not close_________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

AO-802a Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Isolate HPSW and LPSW during an AB Flood Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 16 min K/A Rating(s): System: BW/A07 K/A: AA2.2 Rating: 3.3/3.7 Task Standard: Isolate portions of the HPSW and LPSW systems during an AB Flood using AP/3/A/1700/030 AUXILIARY BUILDING FLOOD

References:

AP/3/A/1700/030 Rev 18 Tools/Equipment/Procedures Needed: AP/3/A/1700/030 Encl. 5.1 (HPSW AB Flood Isolation) and Encl. 5.2 (LPSW AB Flood Isolation) ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments AO-802a Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA AO-802a Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS All 3 units are at 100% power Unit 3 Auxiliary Building flooding is occurring The source of flood water has not yet been determined

INITIATING CUES The Control Room Supervisor directs you to perform AP/3/A/1700/030 Encl. 5.1 (HPSW AB Flood Isolation) AND Encl. 5.2 (LPSW AB Flood Isolation)

AO-802a Page 5 of 11 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 Examiner Note: If candidate performs Enclosure 5.2 first, it begins on JPM step 7. 2 En.5.1 1 IAAT the source of flooding is isolated, THEN notify Control Room. STANDARD: The candidate notes the source of flooding is not isolated. CUE: If asked, flooding is still occurring. Candidate continues to step 2. COMMENTS: ___ SAT ___ UNSAT 3 2 NOTE Keys for valve locks are available in any Emergency Equipment cabinet. [ALTERNATE PATH] Close HPSW-959 (HPSW SUPPLY TO FLOW LIMITER BLOCK VALVE) (T-1/M-21 south, west of RCW Heat Exchangers). STANDARD: The candidate locates and attempts to close HPSW-959. Examiner Note: Operators would normally carry keys to these locks. Examiner Cue: When the candidate locates and attempts to close HPSW-959, inform candidate that HPSW-959 chain will not move. Candidate continues to step 2 RNO. COMMENTS: ___ SAT ___ UNSAT AO-802a Page 6 of 11 4 2 RNO Close HPSW-962 (HPSW SUPPLY TO AUX BLDG BLOCK VALVE) (T-1/M-21 south, west of RCW Heat Exchangers). STANDARD: The candidate locates and closes HPSW-962 rotating it in the clockwise direction until it stops. Cue: When the candidate rotates the hand wheel in the clockwise direction, inform the candidate that HPSW-962 is fully clockwise and on the hard stop. Candidate continues to step 3. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 5 3 Notify control Room HPSW isolation is complete. STANDARD: The candidate notifies the control Room HPSW isolation is complete. Candidate continues to step 4. COMMENTS: ___ SAT ___ UNSAT 6 4 EXIT this enclosure. STANDARD: Candidate EXITS enclosure 5.1 and proceeds to Enclosure 5.2 COMMENTS: ___ SAT ___ UNSAT AO-802a Page 7 of 11 7 En.5.2 1 IAAT the source of flooding is isolated, THEN notify Control Room. STANDARD: The candidate notes the source of flooding is not isolated. CUE: If asked, flooding is still occurring. Candidate continues to step 2 COMMENTS: ___ SAT ___ UNSAT 8 2 Close 3LPSW-844 (AUX BLDG AHU SUPPLY) (T-1/M-46, 6' SE). STANDARD: The candidate locates and closes 3LPSW-844 rotating it in the clockwise direction until it stops. Cue: When the candidate rotates the hand wheel in the clockwise direction, inform the candidate that the valve is fully clockwise and on the hard stop. Candidate continues to step 3. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 9 3 Close 3LPSW-770 (AUX BLDG AHU SUPPLY) (T-1/M-46, 8' S). STANDARD: The candidate locates and closes 3LPSW-770 rotating it in the clockwise direction until it stops.. Cue: When the candidate rotates the hand wheel in the clockwise direction, inform the candidate that the valve is fully clockwise and on the hard stop. Candidate continues to step 4. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT AO-802a Page 8 of 11 10 4 Open 3LPSW-501 (UNIT 3 AHU RETURN TO STORM DRAINS) (T-1/L-47, W 12' up). STANDARD: The candidate locates and opens 3LPSW-501rotating it in the counter-clockwise direction until it stops. Cue: When the candidate rotates the hand wheel in the counter clockwise direction, inform the candidate that the valve is on the hard stop. Candidate continues to step 5. COMMENTS: ___ SAT ___ UNSAT 11 5 Close 3LPSW-500 (UNIT 3 AHU RETURN TO CCW DISCHARGE) (T-1/L-47, NW 12' up). STANDARD: The candidate locates and closes 3LPSW-500 rotating it in the clockwise direction until it stops. Cue: When the candidate rotates the hand wheel in the clockwise direction, inform the candidate that the valve is fully clockwise and on the hard stop. Candidate continues to step 6. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 12 6 Notify Unit 3 control Room LPSW isolation is complete. STANDARD: The candidate notifies the control Room LPSW isolation is complete. Candidate continues to step 7. COMMENTS: ___ SAT ___ UNSAT AO-802a Page 9 of 11 13 7 EXIT this enclosure. STANDARD: Candidate EXITS enclosure 5.2 and returns CUE Sheet to examiner. COMMENTS: END TASK ___ SAT ___ UNSAT TIME STOP: ________

AO-802a Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 4 Step ensures proper isolation of HPSW leak. 8 Step ensures proper isolation of LPSW leak. 9 Step ensures proper isolation of LPSW leak. 11 Step ensures proper isolation of LPSW leak.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS All 3 units are at 100% power Unit 3 Auxiliary Building flooding is occurring The source of flood water has not yet been determined

INITIATING CUES The Control Room Supervisor directs you to perform AP/3/A/1700/030 Encl. 5.1 (HPSW AB Flood Isolation) AND Encl. 5.2 (LPSW AB Flood Isolation)

Admin 106 Page 1 of 8 REGION II JOB PERFORMANCE MEASURE Admin 106 CALCULATE RUN TIME FOR DEBORATING DEMINERALIZER Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin 106 Page 2 of 8 REGION II JOB PERFORMANCE MEASURE Task Title: Calculate Run Time for Deborating Demineralizer Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 20 Min K/A Rating(s): System: Gen K/A: 2.1.37 Rating: 4.3/4.6 Task Standard: Calculate the Run Time and volume "flowed thru the IX" for the Deborating IX by procedure.

References:

OP/1/A/1103/004 (Soluble Poison Control) Rev 105 OP/1/A/1103/004 C (Deborating IXs) Rev 25 Tools/Equipment/Procedures Needed: OP/1/A/1103/004C (Deborating IXs) Enclosure 4.2 (Unit 1 Deborating IX For RCS Deboration (Rx at power) OP/1/A/1103/004 (Soluble Poison Control) Encl 4.1

=========================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin 106 Page 3 of 8 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin 106 Page 4 of 8 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 is at 100% full power Current RCS Boron concentration is 50 ppmB Letdown Flow is 78 gpm with BOTH Letdown Filters in service The OAC is NOT available Assume 1 ppm for IX effluent OP/1/A/1103/004 C (Deborating IXs) Enclosure 4.2 (Unit 1 Deborating IX For RCS Deboration (Rx At Power) is in progress and has been completed through Step 1.6 INITIATING CUE The Unit 1 CRS directs you to perform Enclosure 4.2 steps 2.1 - 2.2 to determine the volume of RCS that must be flowed through the Unit 1 Deborating IX and the corresponding Deborating IX run time to reduce the RCS Boron concentration to 45 ppmB. SHOW ALL WORK Round calculations to three (3) decimal places.

Volume of RCS thru the IX ____________ Gallons

Deborating IX run Time ____________ Minutes

Admin 106 Page 5 of 8 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.1 Determine volume required to make desired RCS boron change: NOTE: Placing an idle Letdown Filter in service can affect core reactivity by 2.1.1 IF two Letdown Filters are available AND NOT already in service, perform the following: ____A. Review Component Boron Log for out-of-service Letdown Filter boron. ____B. Determine final RCS boron based on placing Letdown Filter in service. 2.1.2 Review Demineralizer Log Sheet to determine IX effluent boron or assume 1 ppm for IX effluent. 2.1.3 Determine volume required to get desired RCS boron change. *2.1.4 Volume required ____________gallons. STANDARD: Determine two Letdown Filters are in service and N/A Step 2.1.1 Assume 1 ppm for IX effluent Refer to OP/1/A/1103/004 (Soluble Poison Control) to determine RCS Hot Volume = 58,681 gal B = Boe -Ft/V Bo = Initial Conc (ppm) B = Final Conc (ppm) F = Feed and Bleed Flow Rate (gpm) V = Total System Volume t = Time Feed and Bleed (min) -(ln B/Bo) x V = t /F = volume passing through the IX -(ln 45/50) 58,681 gal = 6182.660 gal - (-0.105) 58,681 gal = 6161.505 gal (ln 45/50 Rounded) 6182 gallons. (6161 - 6183) Note: The order the calculations are performed is not critical. COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT Admin 106 Page 6 of 8 2 2.2 NOTE: Allowing Unit 1 Deborating IX to be in service an incorrect amount of time can change final RCS boron and cause unanticipated reactivity changes. (R.M.) Calculate Unit 1 Deborating IX run time: (R.M.) Run Time = Volume required ÷ letdown flow _____ Run Time (minutes) = Volume _____ gal ÷ letdown flow _____ (gpm) STANDARD: Determine run Time is 79.265 minutes. (78.9 to 79.3) 79.265 Run Time (minutes) = Volume 6182.660 gal ÷ letdown flow _78_ (gpm) 6161 gal min = 78.987 min 78 gal 6183 gal min = 79.269 min 78 gal COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT TIME STOP: ________

Admin 106 Page 7 of 8 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 This step is required to determine the volume of water thru the Demin to change the RCS Boron concentration. 2 This step is required to determine the amount of time letdown will be diverted thru the Demin.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS Unit 1 is at 100% full power Current RCS Boron concentration is 50 ppmB Letdown Flow is 78 gpm with BOTH Letdown Filters in service

The OAC is NOT available Assume 1 ppm for IX effluent OP/1/A/1103/004 C (Deborating IXs) Enclosure 4.2 (Unit 1 Deborating IX For RCS Deboration (Rx At Power) is in progress and has been completed through Step 1.6 INITIATING CUE The Unit 1 CRS directs you to perform Enclosure 4.2 steps 2.1 - 2.2 to determine the volume of RCS that must be flowed through the Unit 1 Deborating IX and the corresponding Deborating IX run time to reduce the RCS Boron concentration to 45 ppmB. SHOW ALL WORK Volume of RCS thru the IX ____________ Gallons

Deborating IX run Time ____________ Minutes Admin S106 Page 1 of 10 REGION II JOB PERFORMANCE MEASURE ADMIN S106 EVALUATE ITEMS FOR ENTRY INTO CONTAINMENT Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin S106 Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task Title: Evaluate the list of items and determine if they can be taken into Containment while in Mode 4 Task Number: N/A Alternate Path: No Time Critical: No Validation Time: (15 Min) K/A Rating(s): System: Gen K/A: 2.1.13 Rating: 2.5/3.2 Task Standard: Evaluate the list of items provided to determine if they can be carried into containment.

References:

SD 1.3.9 - Containment Material Control Rev 14 Tools/Equipment/Procedures Needed: SD 1.3.9 - Containment Material Control

===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin S106 Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin S106 Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit startup in progress Reactor is in MODE 4 Startup has been delayed waiting on completion of valve repair inside Containment Valve work is taking place outside the secondary shielding on the 2nd grating level You are working as the WCC SRO INITIATING CUES The containment hatch monitor has requested you evaluate the list of items provided to determine if they can be carried into containment by the crew performing the valve repairs Indicate on the attached list if each item is allowed to be carried into Containment to facilitate the repairs

Admin S106 Page 5 of 10 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 Evaluate red 1 gallon plastic bucket. STANDARD: Determines that the red bucket can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.M.2 (Pg 24/35). COMMENTS: ___ SAT ___ UNSAT 2 Evaluate yellow plastic bag with wrenches. STANDARD: Determines that the bag with wrenches is allowed into containment per SD 1.3.9, Enclosure 7.5, 4.I.1 (Pg 22/35). COMMENTS: ___ SAT ___ UNSAT 3 Evaluate 25 feet of nylon rope with ends melted STANDARD: Determines that the nylon rope can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.D (Pg 21/35). COMMENTS: ___ SAT

___ UNSAT 4 Evaluate roll of gray Duct Tape STANDARD: Determines the roll of Duct Tape can NOT be taken into Containment per SD 1.3.9, Enclosure 7.5, 4.B.3 (Pg 21/35). COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Admin S106 Page 6 of 10 5 Evaluate the Electric Wrench STANDARD: Determines that the electric wrench can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.I.1 (Pg 22/35). COMMENTS: ___ SAT ___ UNSAT 6 Evaluate the two sockets STANDARD: Determines that the sockets can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.I.1 (Pg 22/35). COMMENTS: ___ SAT ___ UNSAT 7 Evaluate the valve wrapped in clear poly STANDARD: Determines that the valve wrapped in clear poly can NOT be taken into containment due to the clear poly per SD 1.3.9, Enclosure 7.5, 4.H.7 (Pg 22/35). CUE: If asked, no engineering evaluation has been performed to allow the clear poly to be taken into containment. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 8 Evaluate the absorptive paper STANDARD: Determines that the absorptive paper can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.A since it is not

> 25 sq. ft (Pg 20/35). COMMENTS: ___ SAT

___ UNSAT Admin S106 Page 7 of 10 9 Evaluate the hammer STANDARD: Determines that the hammer can be taken into containment per SD 1.3.9, Enclosure 7.5, 4.I.1 (Pg 22/35). COMMENTS: END TASK ___ SAT ___ UNSAT TIME STOP: ________

Admin S106 Page 8 of 10 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 4 Critical to prevent Chloride and Fluoride stress corrosion on stainless steel piping inside containment 7 Critical to prevent blockage of the LPI Emergency Sump suction path during a LOCA.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit startup in progress Reactor is in MODE 4 Startup has been delayed waiting on completion of valve repair inside Containment Valve work is taking place outside the secondary shielding on the 2nd grating level You are working as the WCC SRO INITIATING CUES The containment hatch monitor has requested you evaluate the list of items provided to determine if they can be carried into containment by the crew performing the valve repairs Indicate on the attached list if each item is allowed to be carried into Containment to facilitate the repairs List of items for evaluation: Assume all items will be documented as taken in and then removed from Containment when the crew leaves unless otherwise indicated. 1) Red 1 gallon plastic bucket. _______

2) *Yellow plastic bag that contains contaminated tools. _______ *Per maintenance the bag contains two Stainless Steel wrenches (3/4" and 1").

3) 25 feet of nylon rope with ends melted. ______

4) Roll of gray duct tape. ______

5) Electric wrench. ______

6) 2 sockets (3/4" and 1"). ______

7) 2" valve wrapped in clear poly. ______ *A PIP has already been generated by Maintenance directing engineering to evaluate leaving the poly inside containment if this crew has to leave RB before repairs are completed. The evaluation is in progress.

8) 10 feet X 2 feet sheet of absorptive paper. ______

9) Hammer ______

Admin 107 Page 1 of 9 REGION II JOB PERFORMANCE MEASURE ADMIN 107 DETERMINE IF RO LICENSE REQUIREMENTS ARE MET Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin 107 Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title: Determine if RO License requirements are met per NSD 512 for minimum On-Shift Experience Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 15 Min K/A Rating(s): System: Gen K/A: 2.1.4 Rating: 3.3/3.8 Task Standard: Completes Form 512-1 and determines requirements of NSD 512 are NOT met.

References:

NSD 512 (Maintenance of RO/SRO NRC Licenses) Rev 7 Tools/Equipment/Procedures Needed: NSD 512 (Maintenance of RO/SRO NRC Licenses) =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin 107 Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin 107 Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Today's date is 10/29/15. You are a Reactor Operator. Your work history for October of this year is as follows: 10/12/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP on Unit 1 (day shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/13/15 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as OATC on Unit 1 and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OATC doing crew JIT training on Simulator A (day shift). Took turnover at beginning and gave turnover at end of both of these assignments. 10/14/15 Worked 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months as BOP on Unit 1 (day shift). Took turnover at beginning of shift. 10/19/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP on Unit 1 (night shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/20/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as OATC on Unit 3 (night shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/21/15 Worked 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months as OATC on Unit 3 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months as BOP on Unit 1 (night shift). Took turnover at beginning of shift and did NOT give turnover at end of shift. 10/27/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as AO on Unit 3 (day shift). Took turnover at beginning of shift and gave turnover at end of shift. INITIATING CUES The SM directs you to review your work history for October, complete Section 3 of form NSD 512-1 based on the above work history, and determine if you meet NSD 512 requirements to maintain an active RO license for the following quarter.

Admin 107 Page 5 of 9 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION Examiner note: Evaluating each work period is a critical step. The initiating cue is to fill out Section 3 of NSD 512. In filling out Section 3, the operator is stating which shifts DO count. So by filling in the shifts that count, the operator is in effect, stating the other shifts DO NOT count so they have addressed all 7 shifts. 1 Evaluate 10/12/15 work period STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with Turnover at beginning and end of shift. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 2 Evaluate 10/13/15 work period STANDARD: Determines that requirement is not met because Simulator time does not count toward maintain RO license requirements COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT 3 Evaluate 10/14/15 work period STANDARD: Determines that requirement is not met. No turnover at end of shift, <12hrs worked in position. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Admin 107 Page 6 of 9 4 Evaluate 10/19/15 work period STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with Turnover at beginning and end of shift. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 5 Evaluate 10/20/15 work period STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with Turnover at beginning and end of shift. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 6 Evaluate 10/21/15 work period STANDARD: Determines that requirement is not met. No turnover at end of shift and position not filled for entire shift. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 7 Evaluate 10/27/15 work period STANDARD: Determines that NEO is not a required position and cannot be credited toward maintenance of RO license COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT Admin 107 Page 7 of 9 8 Compares credited time vs minimum requirements STANDARD: Determines that there are only 3 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts that can be credited and therefore his minimum fourth quarter requirements to maintain his active RO License are not met. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT TIME STOP: ________

Admin 107 Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met 2 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 3 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 4 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 5 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 6 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 7 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met. 8 This step makes the determination regarding minimum license requirement.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS Today's date is 10/29/15. You are a Reactor Operator. Your work history for October of this year is as follows: 10/12/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP on Unit 1 (day shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/13/15 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as OATC on Unit 1 and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OATC doing crew JIT training on Simulator A (day shift). Took turnover at beginning and gave turnover at end of both of these assignments. 10/14/15 Worked 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months as BOP on Unit 1 (day shift). Took turnover at beginning of shift. 10/19/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP on Unit 1 (night shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/20/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as OATC on Unit 3 (night shift). Took turnover at beginning of shift and gave turnover at end of shift. 10/21/15 Worked 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months as OATC on Unit 3 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months as BOP on Unit 1 (night shift). Took turnover at beginning of shift and did NOT give turnover at end of shift. 10/27/15 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as AO on Unit 3 (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

INITIATING CUES The SM directs you to review your work history for October, complete Section 3 of form NSD 512-1 based on the above work history, and determine if you meet NSD 512 requirements to maintain an active RO license for the following quarter.

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE Nuclear Policy Manual - Volume 2 NSD 512 REVISION 7 1 VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE FORMS Form 512-1512-1512-1512-1 Documentation Documentation of Operating Experience Maintenance for Active Licensed Operators 1. Licensee's Name _______________________ _____________________________ Employee Number NOTE: Time as the extra RO/SRO on a Outage Unit or as a RO/SRO in the Outage Control Center can not be counted as an ACTIVE LICENSED OPERATOR position. 2. ACTIVE LICENSED OPERATOR POSITION a. Shift Manager (SRO) b. Control Room Supervisor (SRO) c. Operator at the Controls (RO) d. Balance of Plant Operator (RO) 3. A minimum of five 12-hour shifts per calendar quarter performing one or more of the functions listed in item 2 shall be worked and documented below to maintain active status. The position must be filled for the entire shift period including both turnovers to obtain credit. Licensed Duty Letter (A - D) Shift Start Date (Month/Day/Year) Shift (day / night) D 10/12/15 day D 10/19/15 night C 10/20/15 night 4. I hereby certify that the information set forth above is accurate and complete. Licensed Operator Signature ________________________________ 5. When complete, send a copy of this form to Operations Administrative Support and keep a copy for your personal records. 6. Update /verify LOQR Initial _____ Date_____ 7. Send completed form to Operations Training Group for filing with the individuals training record.

Admin 203 Page 1 of 9 REGION II JOB PERFORMANCE MEASURE ADMIN 203 PERFORM NI SURVEILLANCE AND DETERMINE ANY REQUIRED ACTIONS Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin 203 Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title: Perform NI Surveillance and Determine Any Required Actions Task Number: N/A Alternate Path: (No) Time Critical: (No) Validation Time: (10 Min) K/A Rating(s): System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard: Perform SR 3.3.1.2 in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and determine that actions should be taken to correct NI calibration but a PIP is NOT required.

References:

PT/1/A/0600/001 (Periodic Instrument Surveillance) Rev 336 OP/1/A/1102/004 (Operation at Power) Rev 144 Tools/Equipment/Procedures Needed: PT/1/A/0600/001 (Periodic Instrument Surveillance) OP/1/A/1102/004 (Operation at Power) ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin 203 Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin 203 Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Power escalation to 100% concluded at midnight last shift Current Time is 07:30 Power history is attached

INITIATING CUES Using the attached power history, you are to perform the Day Shift RPS Instrumentation Heat Balance Check Power Range Amplifiers Surveillance (SR 3.3.1.2) on Page 8 of 29 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Enclosure 13.1 (Mode 1&2) and determine the current minimum actions required (if any) and reason at Time = 0730. Assume NO previous actions have been taken.

Admin 203 Page 5 of 9 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 Determine if the unit is at Steady State NOTE: Steady State is defined as being +2% of a steady power level for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months STANDARD: Using the NOTE above and the attached power history, determine that the unit is at Steady State as defined by this surveillance (+2% of a steady power level for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). COMMENTS: ___ SAT ___ UNSAT 2 IF in Mode 1 during steady state conditions AND Rx Power > 90% power, verify Rx Power within applicable limits: Refer to Limits and Precautions of OP/1/A/1102/004 (Operation At Power) for applicable limits. STANDARD: Candidate refers to Limits and Precautions of OP/1/A/1102/004 (Operation At Power) L&P 2.2.6.C.1 COMMENTS: ___ SAT ___ UNSAT 3 Determine the magnitude of NI offset. STANDARD: Candidate refers to the power history provided and determines: At 0700 CTP was 99.9876% and NI-5 was 97.71% and therefore NI-5 is out of calibration by 2.286% At 0730 CTP is 99.996% and NI-5 = 97.91% therefore NI-5 is out of calibration by 2.086% COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Admin 203 Page 6 of 9 4 Determine if NI offset is conservative or non-conservative. STANDARD: Candidate refers to the Note for limit and precaution step 2.2.5 and determines that NI-5 is non-conservative since Core Thermal Power is > NI-5. COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT 5 Determine which Limit and Precaution contains guidance needed. STANDARD: Based on power history, 2.2.6 C applies since it is for use "During operation with Reactor > 90% CTP (power maneuvering OR steady state)" COMMENTS ___ SAT

___ UNSAT 6 Determine actions required by Limit and Precaution 2.2.6 C. STANDARD: Determine that the following is required: Take actions to restore NI's to allowable range (perform NI calibration) Note: Since NI's have been out by 2% for < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the actions of 2.2.6.C.1 (Stop power increase and take actions to restore NIs to allowable range) are required . 2.2.6.C.2 (Generate PIP describing occurrence and Consult with Rx Eng) are NOT required. COMMENTS CRITICAL STEP

___ SAT

___ UNSAT TIME STOP: ________

Admin 203 Page 7 of 9 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 3 Determining the magnitude of NI error is required to determine the correct NI tolerance allowed for the current plant conditions. 4 Determining that NI's are non-conservative is required to determine the correct NI tolerance allowed for the current plant conditions 6 These actions are required based on current status of NI's to ensure Safety Analysis assumptions are met CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Power escalation to 100% concluded at midnight last shift Current Time is 07:30 Power history is attached

INITIATING CUES Using the attached power history, you are to perform the Day Shift RPS Instrumentation Heat Balance Check Power Range Amplifiers Surveillance (SR 3.3.1.2) on Page 8 of 29 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Enclosure 13.1 (Mode 1&2) and determine the current minimum actions required (if any) and reason at Time = 0730. Assume NO previous actions have been taken.

Unit 1 Power history is as follows: O1P0899 Core Thermal Power O1E4066 NI-5 O1E4067 NI-6 O1E4068 NI-7 O1E4069 NI-8 0500 99.962% 99.79% 99.99% 99.99% 99.99% 0700 99.987% 97.71% 100.00% 99.91% 100.01% 0715 100.001% 97.88% 99.99% 99.98% 99.99% 0730 99.996% 97.91% 100.00% 100.00% 100.00%

Admin S202 Page 1 of 9 REGION II JOB PERFORMANCE MEASURE ADMIN S202 Complete a Surveillance Evaluation Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin S202 Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title: Complete PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 20 Min K/A Rating(s): System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard: Complete PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

References:

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) page 25 of 26 Rev 336 PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.9 (RCP Power Supply Verification) PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation) Tools/Equipment/Procedures Needed: PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) page 25 of 26 PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.9 (RCP Power Supply Verification) PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation) Surveillance Frequency List ===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin S202 Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin S202 Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Time/Date = 0830 on Saturday, June 8. RCS Temperature = 298°F. 1/0 RCP operation in progress (1A1 RCP in operation). PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) in progress. SR 3.4.5.2 on page 25 of 26 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) is being performed. Step 2.2 of Encl. 13.9 (RCP Power Supply Verification) is determined to NOT be satisfied because neither the 1B1 nor the 1B2 RCP has power available.

INITIATING CUE Based on the above conditions, complete PT/1/A/0600/001 (Periodic Instrument Surveillance)

Encl. 13.12 (Surveillance Evaluation)

Admin S202 Page 5 of 9 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 2.1 Surveillance

Description:

STANDARD: Documents that this is a Tech Spec required verification of correct RCP breaker alignment of power available to the required pump this is not in operation COMMENTS: ___ SAT ___ UNSAT 2 2.2 Applicable TS(s)/SLC(s)/Site Directive(s), etc.: STANDARD: Determines that Tech Spec 3.4.5 (RCS Loops Mode 3) is applicable and documents in Step 2 COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT 3 2.3 Description of discrepancy/deficiency: STANDARD: Documents that the required RCP Breaker alignment does not exist. NOTE: TS 3.4.5 requires that either the 1B1 or 1B2 have power available COMMENTS: ___ SAT ___ UNSAT Admin S202 Page 6 of 9 4 2.4 Is surveillance applicable for present plant conditions? STANDARD: Marks "yes" COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 5 2.5 If surveillance is applicable, what is the latest due date for surveillance OR applicable LCO? STANDARD: Documents that the latest due date is 0830 on Tuesday, June 11 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from discovery) per Condition A of TS 3.4.5 COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT 6 2.6 Is applicable TS(s)/SLC(s)/Site Directive(s), etc. satisfied with existing discrepancy/deficiency? STANDARD: *Marks "no" Explains in justification that TS 3.4.5 requires both RCS loops be Operable and with no power available to the 1B1 and 1B2 RCP's, the B RCS loop is NOT operable COMMENTS: *CRITICAL STEP ___ SAT ___ UNSAT Admin S202 Page 7 of 9 7 2.7 Support personnel/groups contacted (if any) AND information provided: STANDARD: Candidate may indicate requesting SPOC assistance to determine why neither of the required RCP breakers are racked in however since there is no indication of mechanical failures it would not be required. COMMENTS: ___ SAT ___ UNSAT 8 2.8 Describe corrective/compensatory actions being taken (procedure change, WR, PIP, etc.), and resolution date for those actions. STANDARD: Corrective/Compensatory Action: Candidate should indicate that actions will commence to establish the required breaker alignment. This could be by issuing a Work Request, writing a NCR, or dispatching personnel to determine why the breakers are open and if the breakers could be racked in. Resolution Date: This blank may be left open at this time since the investigation is just beginning however in no case should a date and time that would result in exceeding the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time be entered. COMMENTS: ___ SAT ___ UNSAT 9 2.9 Approval: STANDARD: Signs and Dates either of the blanks provided COMMENTS: ___ SAT ___ UNSAT TIME STOP: ________

Admin S202 Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 2 Required to determine the applicable Tech Spec 4 Required to determine if this Tech Spec is applicable in Mode 3 5 Incorrect documentation could lead to exceeding allowed time to complete Tech Spec Required Actions. 6 Required to determine if the LCO is met CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Time/Date = 0830 on Saturday, June 8. RCS Temperature = 298°F. 1/0 RCP operation in progress (1A1 RCP in operation). PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) in progress. SR 3.4.5.2 on page 25 of 26 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) is being performed. Step 2.2 of Encl. 13.9 (RCP Power Supply Verification) is determined to NOT be satisfied because neither the 1B1 nor the 1B2 RCP has power available. INITIATING CUE Based on the above conditions, complete PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

ADM-303 Page 1 of 7 REGION II JOB PERFORMANCE MEASURE ADM-303 CALCULATE MAXIMUM PERMISSIBLE STAY TIME Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________ Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

ADM-303 Page 2 of 7 REGION II JOB PERFORMANCE MEASURE Task Title : Calculate Maximum Permissible Stay Time Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 20 Min K/A Rating(s): System: (Gen) K/A: (2.3.4) Rating: (3.2/3.7) Task Standard: Calculate the maximum permissible stay time for radiation workers.

References:

PD-RP-ALL-0001, Radiation Worker Responsibilities Rev 3 Tools/Equipment/Procedures Needed: PD-RP-ALL-0001, Radiation Worker Responsibilities if requested. =====================================================================================

Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments ADM-303 Page 3 of 7 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA ADM-303 Page 4 of 7 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Two new employees with no previous radiation exposure arrived on site on November 1 in preparation for a refueling outage. Employee 1: 25 year old male. Received 1200 mrem TEDE between November 1 and Dec 31 and received 300 mrem TEDE between Dec 31 and Jan 31. Employee 2: 25 year old female. Received 300 mrem TEDE between November 1 and Dec 31 and received 50 mrem TEDE between Dec 31 and Jan 31. On Feb 1, makes pregnancy declaration (estimated conception date is Nov 1). Today is Feb 1 and in order to complete the outage, a job must be completed in an area with a 100 mrem/hr radiation field. INITIATING CUE Determine the maximum time that each employee could spend in the area for this job while staying within station limits for allowable radiation exposure. Do NOT consider the precautionary Alert, Exclusion notifications or ED alarms as these limits are approached. Assume that NO permissions have been granted by Supervision / Management for any extensions /entry after any station limit has been reached.

ADM-303 Page 5 of 7 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 NA Determine the dose that each employee is allowed. Then calculate the time allowed in the area. STANDARD: Employee 1: TEDE received so far this calendar year is 300 mrem. Duke energy administrative limit for TEDE to the whole body 2000 mrem/year. 2000-300 = 1700 mrem allowed dose. 1700 mrem / 100 mrem/hr = 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months Employee 2: TEDE received for the gestation period = 350 mrem. Duke Energy administrative limit for declared pregnant female = 450 mrem for the entire gestation period AND 50 mrem per month. Therefore allowed dose = 50 mrem. 50 mrem / 100 mrem/hr = 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or 30 minutes. Per PD-RP-ALL-0001, Radiation Worker Responsibilities, 5.3.5 Dose Monitoring Warning Flags and ED Alarms: Alert Flag: Notification that individual reached 80% or greater but less than 90% of established administrative limit. Workers that receive an Alert Flag will notify his/her supervisor and must receive RP supervision approval to enter a High Radiation Area or LHRA. COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT TIME STOP: ________

ADM-303 Page 6 of 7 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 This step is required to prevent exceeding Duke Energy radiation exposure administrative limits.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Two new employees with no previous radiation exposure arrived on site on November 1 in preparation for a refueling outage.

Employee 1: 25 year old male. Received 1200 mrem TEDE between November 1 and Dec 31 and received 300 mrem TEDE between Dec 31 and Jan 31.

Employee 2: 25 year old female. Received 300 mrem TEDE between November 1 and Dec 31 and received 50 mrem TEDE between Dec 31 and Jan 31. On Feb 1, makes pregnancy declaration (estimated conception date is Nov 1).

Today is Feb 1 and in order to complete the outage, a job must be completed in an area with a 100 mrem/hr radiation field. INITIATING CUE Determine the maximum time that each employee could spend in the area for this job while staying within station limits for allowable radiation exposure. Do NOT consider the precautionary Alert, Exclusion notifications or ED alarms as these limits are approached. Assume that NO permissions have been granted by Supervision / Management for any extensions /entry after any station limit has been reached.

Admin S403 Page 1 of 11 REGION II JOB PERFORMANCE MEASURE ADMIN-S403 Determine Emergency Classification And Complete The Initial Emergency Notification Form Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (Yes) Time Critical Criteria: Classification < 15 Minutes Complete Notification Form < 15 Minutes of Classification Prepared By: Date: EP Review By: Date: Reviewed By: Date: Approved By: Date:

Admin S403 Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Determine Emergency Classification and complete the initial Emergency Notification Form Task Number : N/A Alternate Path: No Time Critical: Yes Validation Time: 30 Min K/A Rating(s): System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard: Appropriate classification is determined and associated Emergency Notification Form is completed.

References:

RP/0/A/1000/01, Emergency Classification Rev 2 RP/0/A/1000/02, Control Room Emergency Coordinator Procedure Rev 9 RP/0/A/1000/015A, Offsite Communications From The Control Room Rev 4 BASIS Document (Volume "A", Section "D" of the Emergency Plan) Tools/Equipment/Procedures Needed: RP/0/A/1000/01, Emergency Classification RP/0/A/1000/02, Control Room Emergency Coordinator Procedure

===================================================================================== Candidate: __________________________________ Time Start: _______________ NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE ===================================================================================== Comments Admin S403 Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS NA Admin S403 Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS (0800) Unit 1 experienced a Small Break LOCA The reactor failed to automatically trip The Reactor failed to trip in Manual CURRENT CONDITIONS 4 Minutes later Reactor Trip Breakers were opened locally All full length control rods are fully inserted RCS pressure = 1500 psig stable Core SCM = 6°F (this is the lowest SCM during the event)

INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/001, Emergency Classification: 1. Determine Emergency Classification at present time. 2. Complete appropriate Emergency Notification Form for the current conditions.

Inform the examiner when you have made the classification.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, an operator will maintain the Emergency Coordinator's Log and assume the duties of the Control Room Offsite Communicator.

Admin S403 Page 5 of 11 START TIME: _______ SEQ STEP PROC STEP DESCRIPTION 1 Classify the Event STANDARD: Refer to RP/0/A/1000/01 (Emergency Classification) and classify the event as follows: Encl 4.1 (Fission Product Barrier Matrix) RCS Leakrate > 160 gpm = 4 pts ALERT Encl 4.4 (Loss of Shutdown Functions) SAE 1. FAILURE OF RPS TO COMPLETE OR INITIATE A RX SCRAM. SAE The event should be classified as a Site Area Emergency (SAE) (4.4.S.1). TIME CRITICAL (Classification must be declared < 15 minutes from the start of the JPM). COMMENTS: CRITICAL STEP ___ SAT ___UNSAT Admin S403 Page 6 of 11 2 1.1 Commence the Off-Site Notification Form. STANDARD: Go to RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure) and initiate procedure by determining symptoms for entry exist and check Step 1.1 COMMENTS: ___ SAT

___UNSAT 3 2.1 IF an EAL exists, Declare the appropriate Emergency Classification level. Classification ___________ (UE, Alert, SAE, GE) Time Declared: __________ STANDARD: Applicant declares a SAE and records the time that the classification was made. COMMENTS: CRITICAL STEP ___ SAT

___UNSAT 4 2.2 IF A Security event is in progress, THEN GO TO Step 2.4. STANDARD: Applicant determines that a security event is NOT in progress and proceeds to step 2.3. COMMENTS: ___ SAT

___UNSAT Admin S403 Page 7 of 11 5 2.3 IF ERO has NOT yet been activated AND ERO activation is needed, perform the following: *2.3.1: Circle the applicable initial notification code below. EAL classification Notification Codes (see Enclosure 4.11 for descriptions) DRILL EMERGENCY None F1a NOUE D1a E1a Alert D2a E2a SAE D3a E3a GE D4a E4a 2.3.2 IF a qualified individual is available to notify the ERO, provide the circled notification code above to a qualified individual and direct them to begin Enclosure 4.10 (Activation of the Emergency Response Organization). STANDARD: Applicant determines that the notification code is either D3a or E3a. COMMENTS: *CRITICAL STEP ___ SAT

___UNSAT 6 2.4 Direct Control Room Offsite Communicator(s) to perform the following: REFER TO RP/0/A/1000/015A (Offsite Communications From The Control Room), Immediate Actions steps 2.1 and 2.2 AND Enclosure 4.7 (Guidelines for Manually Transmitting a Message) in preparation for notifying offsite agencies. STANDARD: There is no offsite communicator for this JPM. COMMENTS: ___ SAT

___UNSAT Admin S403 Page 8 of 11 7 2.5 IAAT Changing plant conditions require an emergency classification upgrade, THEN Notify Offsite Communicator to complete in-progress notifications per RP/0/A/1000/15A (Offsite Communications From The Control Room), AND Start a new clean copy of this procedure for the upgraded classification AND stop working on this copy, noting the time in your log that each new copy started. STANDARD: No upgrade will be required for this JPM. COMMENTS: ___ SAT

___UNSAT Admin S403 Page 9 of 11 8 2.6 Obtain the applicable Offsite Notification form in the control room and complete as follows: ___ 2.6.1 Ensure EAL # as determined by RP/0/A/1000/001 matches Line 4. ___ 2.6.2 Line 1 - Mark appropriate box "Drill" or "Actual Event" ___*2.6.3 Line 1 - Enter Message # ___ 2.6.4 Line 2 - Mark Initial ___ 2.6.5 Line 6 - A. Mark "Is Occurring" if any of the following are true: B. Mark "None" if none of the above is applicable. ___ 2.6.6 Line 7 - If Line 6 Box B or C is marked, mark Box D. Otherwise mark Box A. ___*2.6.7 Line 8 - Mark "Stable" unless an upgrade or additional PARs are anticipated within an hour. ___*2.6.8 Line 10 - Military time and date of declaration (Refer to date/time in Step 2.1) ___ 2.6.9 Line 11 - Evaluate the following for classification for all units. Mark or select ALL if event affects the emergency classification on more than one unit. If event only affects one (1) unit OR one (1) unit has a higher emergency class, select or mark the appropriate unit. ___*2.6.10 Line 12 - Mark unit(s) affected (reference Line 11) AND enter percent power for each unit affected. {14} date. ___2.6.11 Line 13 - If the SM has no remarks, write "None" ___2.6.12 If Condition "A" exists ensure following PARs are included on Line 5. A. Evacuate: Move residents living downstream of the B. Other: Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed. ___2.6.13 Line 17 - SM signature, CURRENT Time/Date STANDARD: Correctly fills out Emergency Notification Form in accordance with Key. COMMENTS: *CRITICAL STEP

___ SAT ___UNSAT TIME STOP: ________

Admin S403 Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ STEP # Explanation 1 The candidate needs to be able to utilize the procedure and determine the conditions meet a Site Area Emergency classification. 3 This is a time critical step. The candidate needs to declare the SAE within 15 minutes of beginning the JPM. (The start of the JPM is the beginning of the assessment period) 5 The candidate must select the correct notification code for a SAE. 8 The emergency notification form is accurately filled-out; identified steps from the KEY are critical items within 15 minutes from the time the EAL was declared. (Declaration time is the time recorded in JPM step 3)

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS (0800) Unit 1 experienced a Small Break LOCA The reactor failed to automatically trip The Reactor failed to trip in Manual CURRENT CONDITIONS 4 Minutes later Reactor Trip Breakers were opened locally All full length control rods are fully inserted RCS pressure = 1500 psig stable Core SCM = 6°F (this is the lowest SCM during the event)

INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/001, Emergency Classification: 1. Determine Emergency Classification at present time. 2. Complete appropriate Emergency Notification Form for the current conditions.

Inform the examiner when you have made the classification.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, an operator will maintain the Emergency Coordinator's Log and assume the duties of the Control Room Offsite Communicator.

Nuclear Power Plant Emergency Notification Form SITE AREA EMERGENCY RP/0/A/1000/015 A Enclosure 4.2.A Page 1 of 1 1. A DRILL B ACTUAL EVENT MESSAGE # _______ 2. A INITIAL B FOLLOW-UP NOTIFICATION: TIME___________ DATE_____/_____/_____ AUTHENTICATION # ________ 3. SITE: Oconee Nuclear Site Confirmation Phone # (864)_882-7076_________ 4. EMERGENCY CLASSIFICATION: A UNUSUAL EVENT B ALERT C SITE AREA EMERGENCY D GENERAL EMERGENCY BASED ON EAL #______________ EAL DESCRIPTION: ________________________________________________________ _________________________________________________________________________________________________________ _________________________________________________________________________________________________________ 5. PROTECTIVE ACTION RECOMMENDATIONS: A NONE B EVACUATE _________________________________________________________________________________________________________ C SHELTER _________________________________________________________________________________________________________ D CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY. E OTHER____________________________________________________________________________________________ 6. EMERGENCY RELEASE: A None B Is Occurring C Has Occurred 7. RELEASE SIGNIFICANCE: A Not applicable B Within normal operating limits C Above normal operating limits D Under evaluation 8. EVENT PROGNOSIS: A Improving B Stable C Degrading 9. METEOROLOGICAL DATA: Wind Direction* from _______ degrees Wind Speed* _______mph (*Not Required for Initial Notifications) Precipitation* _______ Stability Class* A B C D E F G 10. A DECLARATION B TERMINATION Time ________________ Date _____/______/_______ 11. AFFECTED UNIT(S): 1 2 3 All 12. UNIT STATUS: (Unaffected Unit(s) Status Not Required for Initial Notifications) A U1 _____% Power Shutdown at Time _____________ Date ___/_____/____ B U2 _____% Power Shutdown at Time _____________ Date ___/_____/____ C U3 _____% Power Shutdown at Time _____________ Date ___/_____/____ 13. REMARKS: ________________________________________________________________________________________________ _____________________________________________________________________________________________________________

_____________________________________________________________________________________________________________ FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications) EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED. 14. RELEASE CHARACTERIZATION: TYPE: A Elevated B Mixed C Ground UNITS: A Ci B Ci/sec C µCi/sec MAGNITUDE: Noble Gases:__________ Iodines:___________ Particulates:__________ Other: ____________ FORM: A Airborne B Liquid Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____ Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____ 15. PROJECTION PARAMETERS: Projection period: ________Hours Estimated Release Duration ________Hours Projection performed: Time _________ Date ___/_____/____

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem) Site boundary 2 Miles 5 Miles 10 Miles 17. APPROVED BY: ___________________________ Title Emergency Coordinator Time _________ Date___/_____/____ NOTIFIED BY:___________________________ RECEIVED BY: _____________________________ Time _________ Date ___/_____/____

ML17174B288

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