ML15245A293

Initial Exam 2015-301 Draft Administrative Documents

ML15245A293
Person / Time
Site:	Catawba
Issue date:	08/31/2015
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/15-301, 50-414/15-301
Download: ML15245A293 (32)

Text

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Examination Level: RO SRO Operating Test Number: 2015301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Calculate Head Vent Time Conduct of Operations R,D G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Perform a Manual NC System Leakage Calculation G 2.1.7 Ability to evaluate plant performance and make Conduct of Operations R,M operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. 4.4/4.7 Calculate RL System Heat Rise G 2.2.44 Ability to interpret control room indications to Equipment Control R,N verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 4.2/4.4 Determine RP Requirements Radiation Control R,M G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

Admin JPMs JPM A.1 Calculate Reactor Vessel Head Venting Time (Common RO & SRO) - Bank JPM CSF-003 K/A Generic 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 Initial conditions are that a LOCA has occurred on Unit 1. The applicants are directed to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) Enclosure 5 (Allowable Hydrogen Venting Time). The applicants are given Enclosure 5 of FR-I.3 and pictures of control board meters for Containment Pressure, Hydrogen Concentration, Lower Containment Air Temperature, and Wide Range NC System Pressure which will be used in the calculation. Applicants will calculate the allowable head venting time of 3.4 - 5.2 minutes based off of bounding values determined.

JPM A.1 Perform a Manual NC System Leakage Calculation (Different RO & SRO) - Modified bank JPM NC-094 (Values changed to produce a different answer for identified, unidentified, and total accumulated leakage and to cause the plant to be in a different Selected License Commitment condition). RO applicants will just perform the calculations. SRO applicants will have to perform the calculations and determine any applicable Tech Spec/SLC actions.

K/A Generic 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR 41.5 / 43.5 / 45.12 /

45.13) RO 4.4 SRO 4.7 Initial conditions are that Unit 1 Operator Aid Computer is out of service due to emergent system failures and will not be returned to service for an estimated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The applicants are directed to perform a manual NC system leakage calculation per PT/1/A/4150/001 D (NC System Leakage Calculation). The applicants will be given a data sheet with needed values for times 2000 & 2101 (required to be > 60 minutes). SRO applicants, once calculations are complete, will determine that entry into T.S. 3.4.13 Condition A is required for Unidentified Leakage being > 1 gpm (~10.6 gpm) and entry into SLC 16.7-9 Condition B is required for Total Accumulated Leakage being > 20 gpm.

JPM A.2 - Calculate RL System Heat Rise (Common RO & SRO) - NEW JPM K/A Generic 2.2.44 Ability 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) RO 4.2 SRO 4.4 Initial conditions are a loss of Unit 1 and Unit 2 Operator Aid Computers occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

The applicants are directed to calculate the Low Pressure Service Water Heat Rise T and to determine if NPDES permit requirements are met for the day they are given the JPM, per PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation). The applicants are given a copy of PT/0/A/4250/011 Enclosures 13.4, 13.5 (Values needed to calculate are recorded in these enclosures), and 13.6.

Applicants will calculate a heat rise of between 11°F and 12°F. This value will not meet NPDES permit requirements for the month of May (Apr 1 - Sep 30 is required to be < 10°F). This will require a notification to the shift manager and a plant heat load reduction of the RL system.

JPM A.3 - Determine Radiation Protection Requirements for an Activity (Common RO & SRO) - Modified 2005 NRC JPM R03/SRO4 (Values changed and RWP requirements changed to produce a different answer).

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 41.12 / 45.10) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy of RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Exam Level: RO SRO-I SRO-U Operating Test Number: 2015301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function a.

b. Transfer ECCS to Cold Leg Recirculation A,D,EN,L,P,S 2 006 A4.07

c. Isolate Cold Leg Accumulators during Shutdown LOCA A,L,N,S 3 006 A1.13 d.

e. Control Tavg using Steam Dumps D,S 4S 039 A2.04 f.

g.

h.

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Place Hydrogen Recombiners in service D,E,L,R 5 028 A2.01

j. Start 2B Diesel Generator A,D,E 6 064 A2.01 k.

@ 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 4-6 / 4-6 / 2-3 (6/-/3)

(C)ontrol room (D)irect from bank <9 / <8 / <4 (8/-/4)

(E)mergency or abnormal in-plant >1 / >1 / >1 (3/-/3)

(EN)gineered safety feature - / - / >1 (1/-/1)

(L)ow-Power / Shutdown >1 / >1 / >1 (5/-/3)

(N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (2/-/1)

(P)revious 2 exams <3 <3 / <2 (3/-/1)

(R)CA >1 / >1 / >1 (1/-/1)

(S)imulator ES-301, Page 23 of 27 Simulator JPMs JPM b - Transfer the ECCS to Cold Leg Recirculation (Common RO & SRO) Previous 2 NRC Exams -

randomly selected from bank - Alternate Path.

K/A 006 A4.07 - Ability to manually operate and/or monitor in the control room: ECCS pumps and valves (CFR: 41.7/45.5 to 45.8) RO 4.4 / SRO 4.4 Initial conditions are a LOCA has occurred on Unit 1. Annunciator 1AD-9, E/8 FWST LO-LO LEVEL is lit and the CRS instructs the applicant to transfer to the Cold Leg Recirculation lineup using EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) step 6. During verification of automatic actions, it is determined that 1NI-184B (ND Pump 1B Cont Sump Suct) is not open.

The applicant continues to perform the lineup for CLR and when directed to open 1ND-28A (ND Supply to NV and NI Pmps), it will not open. This is where the applicant will determine that no ND train can be aligned to provide a suction to the NV and NI pumps and transitions to the RNO to begin the ALTERNATE PATH. The applicant will have to secure all NV and NI pumps to finish the JPM.

JPM c - Isolate Cold Leg Accumulators Following a Shutdown LOCA (Common RO & SRO) New -

Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 41.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to address the LOCA.

The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will have to isolate the Nitrogen going to the 1B and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. The JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

JPM e - Control Tavg using the steam dumps in manual (Common RO & SRO) Direct from bank K/A 039 A2.04 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: Malfunctioning steam dump (CFR 41.5 / 43.5 / 45.3 / 45.13) RO 3.4 SRO 3.7

Initial conditions are that Unit 1 has experienced a Load Rejection due to a Zone A Lockout.

The immediate actions of AP/1/A/5500/003 (Load Rejection) have been completed. During the runback, control rods stopped moving in auto or manual. The CRS and OATC are responding to the rod failure using AP/1/A/5500/015 (Rod Control Malfunction). The CRS directs the applicant to perform step 3 of AP/03. Applicant will recognize that the steam dump valves are not modulating and transition to the RNO. With the steam dump valves being closed and Tavg being more than 3°F higher than Tref, the applicant will take the steam dump control to manual.

After placing the steam dumps in manual, the applicants will manually open the steam dumps to initiate a cooldown. Once the cooldown is initiated and at the discretion of the examiner, the JPM may be terminated.

Plant JPMs JPM i - Place 1B Hydrogen Recombiner in Service (Common RO & SRO) Direct from bank (RCA entry required)

K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Hydrogen Recombiner power setting, determined by using plant data book (CFR 41.5 / 43.5 / 45.3 /

45.13) RO 3.4 SRO 3.6 Initial conditions are that a LOCA has occurred on Unit 1. The CRS instructs the applicant to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA). The applicant will power up the 1B Hydrogen Recombiner and warm it up by adjusting the power output in several increments. The applicant will have to determine the required power output setting per Unit 1 Revised Data Book Figure 10 for the given pressure. Due to containment hydrogen concentration being > 3%, the applicant will have to add 4 KW to value from Figure 10 for the final required power output. Following adjusting the power output to the desired value and notification to the control room of the status of 1B Hydrogen Recombiner, the JPM is complete.

JPM j - Locally Start 2B Diesel Generator (Common RO & SRO) Direct from bank - Alternate Path K/A 064 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes of water, oil, and air valves (CFR 41.5

/ 43.5 /45.3 / 45.13) RO 3.1 SRO 3.3 Initial conditions are Unit 2 has experienced a loss of all AC power to 2ETB. The reason for the loss of AC power has been corrected. 2ETB load shed is complete. The CRS instructs the applicant to energize 2ETB from 2B D/G by performing AP/2/A/5500/007 (Loss of Normal Power)

Enclosure 11 (Energizing 2ETB From D/G). The applicant will locally start 2B D/G, attain proper frequency and voltage, and close the diesel output breaker to energize 2ETB. Following powering up essential load centers, the applicant would verify proper cooling water flow by verifying the cooling water isolation valve open. This valve is not open and cant be manually opened. This begins the ALTERNATE PATH. The applicant will have to shut down 2B D/G and inform the control room of status to finish the JPM.

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Examination Level: RO SRO Operating Test Number: 2015301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Calculate Head Vent Time Conduct of Operations R,D G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Perform a Manual NC System Leakage Calculation G 2.1.7 Ability to evaluate plant performance and make Conduct of Operations R,M operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. 4.4/4.7 Calculate RL System Heat Rise G 2.2.44 Ability to interpret control room indications to Equipment Control R,N verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 4.2/4.4 Determine RP Requirements Radiation Control R,M G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 Determine NRC Reporting Requirements Emergency Procedures/Plan R,D G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.7/4.5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

Admin JPMs JPM A.1 Calculate Reactor Vessel Head Venting Time (Common RO & SRO) - Bank JPM CSF-003 K/A Generic 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 Initial conditions are that a LOCA has occurred on Unit 1. The applicants are directed to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) Enclosure 5 (Allowable Hydrogen Venting Time). The applicants are given Enclosure 5 of FR-I.3 and pictures of control board meters for Containment Pressure, Hydrogen Concentration, Lower Containment Air Temperature, and Wide Range NC System Pressure which will be used in the calculation. Applicants will calculate the allowable head venting time of 3.4 - 5.2 minutes based off of bounding values determined.

JPM A.1 Perform a Manual NC System Leakage Calculation (Different RO & SRO) - Modified bank JPM NC-094 (Values changed to produce a different answer for identified, unidentified, and total accumulated leakage and to cause the plant to be in a different Selected License Commitment condition). RO applicants will perform the calculations and determine that the Standby Makeup Pump #1 will not function as designed. SRO applicants will have to perform the calculations and determine any applicable Tech Spec/SLC actions.

K/A Generic 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR 41.5 / 43.5 / 45.12 /

45.13) RO 4.4 SRO 4.7 Initial conditions are that Unit 1 Operator Aid Computer is out of service due to emergent system failures and will not be returned to service for an estimated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The applicants are directed to perform a manual NC system leakage calculation per PT/1/A/4150/001 D (NC System Leakage Calculation). The applicants will be given a data sheet with needed values for times 2000 & 2101 (required to be > 60 minutes). RO applicants, once calculations are complete, will determine that the Standby Makeup Pump #1 will not function as designed per Step 19. SRO applicants, once calculations are complete, will determine that entry into T.S. 3.4.13 Condition A is required for Unidentified Leakage being > 1 gpm (~10.6 gpm) and entry into SLC 16.7-9 Condition B is required for Total Accumulated Leakage being > 20 gpm making the Standby Makeup Pump #1 Non-Functional.

JPM A.2 - Calculate RL System Heat Rise (Common RO & SRO) - NEW JPM K/A Generic 2.2.44 Ability 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) RO 4.2 SRO 4.4 Initial conditions are a loss of Unit 1 and Unit 2 Operator Aid Computers occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

The applicants are directed to calculate the Low Pressure Service Water Heat Rise T and to determine if NPDES permit requirements are met for the day they are given the JPM, per PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation). The applicants are given a copy of PT/0/A/4250/011 Enclosures 13.4, 13.5 (Values needed to calculate are recorded in these enclosures), and 13.6.

Applicants will calculate a heat rise of between 11°F and 12°F. This value will not meet NPDES permit requirements for the month of May (Apr 1 - Sep 30 is required to be < 10°F). This will require a notification to the shift manager and a plant heat load reduction of the RL system.

Admin JPMs JPM A.3 - Determine Radiation Protection Requirements for an Activity (Common RO & SRO) - Modified 2005 NRC JPM R03/SRO4 (Values changed and RWP requirements changed to produce a different answer).

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 41.12 / 45.10) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy of RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

JPM A.4 - Determine Reporting Per RP/0/B/5000/013 (NRC Notification Requirements) (SRO ONLY) -

Bank JPM SEP-025.

K/A Generic 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. (CFR 41.10 /

43.5 / 45.11) RO 2.7 SRO 4.5 Initial conditions are that a vendor was performing work activities in the S/G bowl area during No Mode. The vendor experienced heat exhaustion and fell into the S/G bowl area causing a compound fracture in his leg. Total dose received was 16 Rem. The individual was transferred to a local hospital due to his injuries. Site personnel are preparing a press release for immediate delivery to news vans parked just offsite. The applicants are directed to determine all applicable NRC notifications of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less per RP/013. The applicants will determine that a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification is required due to offsite notification (news release) and an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification is required for Offsite Medical (Contaminated Injury).

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Exam Level: RO SRO-I SRO-U Operating Test Number: 2015301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Emergency Borate the Reactor Coolant System A,L,P,S 1 004 A2.14

b. Transfer ECCS to Cold Leg Recirculation A,D,EN,L,P,S 2 006 A4.07

c. Isolate Cold Leg Accumulators during Shutdown LOCA A,L,N,S 3 006 A1.13

d. Establish NC system Feed and Bleed A,D,L,P,S 4P 002 A2.04

e. Control Tavg using Steam Dumps D,S 4S 039 A2.04

f. Shift Upper Containment Ventilation Units N,S 5 022 A4.01

g. Reset radiation monitor Trip setpoints D,S 7 073 A4.02

h. Loss of KC AP-21 step 8 (Reactor Trip Sequence) A,D,S 8 008 A2.01 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Place Hydrogen Recombiners in service D,E,L,R 5 028 A2.01

j. Start 2B Diesel Generator A,D,E 6 064 A2.01

k. Start Backup Diesel VI compressor D,E 8 APE065 AA1.04

@ 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 4-6 / 4-6 / 2-3 (6/-/3)

(C)ontrol room (D)irect from bank <9 / <8 / <4 (8/-/4)

(E)mergency or abnormal in-plant >1 / >1 / >1 (3/-/3)

(EN)gineered safety feature - / - / >1 (1/-/1)

(L)ow-Power / Shutdown >1 / >1 / >1 (5/-/3)

(N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (2/-/1)

(P)revious 2 exams <3 <3 / <2 (3/-/1)

(R)CA >1 / >1 / >1 (1/-/1)

(S)imulator ES-301, Page 23 of 27

Simulator JPMs JPM a - Emergency Borate the Reactor Coolant System (RO Only) Previous 2 NRC Exams - randomly selected from bank - Alternate Path.

K/A 004 A2.14 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency Boration (CFR: 41.5/43.5/45.3/45.5) RO 3.8 / SRO 3.9 Initial conditions are a valid reactor trip signal has been received, and the reactor will not trip automatically or manually from the control room. This gives a red path on the Subcriticality CSF status tree. The OATC is inserting control rods manually. The CRS directs the applicant to initiate emergency boration per EP/1/A/5000/FR-S.1 (Nuclear Power Generation/ATWS) step 4.

The applicant will open the emergency boration valve (1NV-236B) and start both boric acid transfer pumps. The applicant notices during verification that emergency boration flow is reading 0 gpm and transitions to the RNO to begin the ALTERNATE PATH. The applicant will then align the NV pump suction to the FWST and secure suction from the VCT to finish the JPM.

JPM b - Transfer the ECCS to Cold Leg Recirculation (Common RO & SRO) Previous 2 NRC Exams -

randomly selected from bank - Alternate Path.

K/A 006 A4.07 - Ability to manually operate and/or monitor in the control room: ECCS pumps and valves (CFR: 41.7/45.5 to 45.8) RO 4.4 / SRO 4.4 Initial conditions are a LOCA has occurred on Unit 1. Annunciator 1AD-9, E/8 FWST LO-LO LEVEL is lit and the CRS instructs the applicant to transfer to the Cold Leg Recirculation lineup using EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) step 6. During verification of automatic actions, it is determined that 1NI-184B (ND Pump 1B Cont Sump Suct) is not open.

The applicant continues to perform the lineup for CLR and when directed to open 1ND-28A (ND Supply to NV and NI Pmps), it will not open. This is where the applicant will determine that no ND train can be aligned to provide a suction to the NV and NI pumps and transitions to the RNO to begin the ALTERNATE PATH. The applicant will have to secure all NV and NI pumps to finish the JPM.

JPM c - Isolate Cold Leg Accumulators Following a Shutdown LOCA (Common RO & SRO) New -

Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 41.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to address the LOCA.

The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will have to isolate the Nitrogen going to the 1B and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. The JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

Simulator JPMs JPM d - Establish NC system Bleed and Feed per EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink)

(RO Only) Previous 2 NRC Exams - randomly selected from bank - Alternate Path K/A 002 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of heat sinks (CFR 41.5 / 43.5 / 45.3 / 45.5) RO 4.3 SRO 4.6 Initial conditions are that a reactor trip has occurred on Unit 1 due to a loss of both Main Feedwater Pumps. The auxiliary feedwater system will not function. The crew has entered EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink) due to a RED path on the CSF status trees.

Bleed and Feed initiation criteria are met. The CRS directs the applicant to initiate NC system Bleed and Feed by performing steps 19-24. Applicants will start with securing all reactor coolant pumps. Then they will initiate Safety Injection on both trains. B train S/I will not actuate and 1NI-9A (NV Pmp C/L Inj Isol) will not open. The applicant will not be able to verify any NV S/I flow and will transition to the RNO to begin the ALTERNATE PATH. Applicants will start the 1B NV and 1B NI pumps and will have to manually open 1NI-10B (NV Pmp C/L Inj Isol) to align the Feed path. Applicants will then open 2 Pressurizer PORVs to align a Bleed path and complete the JPM.

JPM e - Control Tavg using the steam dumps in manual (Common RO & SRO) Direct from bank K/A 039 A2.04 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: Malfunctioning steam dump (CFR 41.5 / 43.5 / 45.3 / 45.13) RO 3.4 SRO 3.7 Initial conditions are that Unit 1 has experienced a Load Rejection due to a Zone A Lockout.

The immediate actions of AP/1/A/5500/003 (Load Rejection) have been completed. During the runback, control rods stopped moving in auto or manual. The CRS and OATC are responding to the rod failure using AP/1/A/5500/015 (Rod Control Malfunction). The CRS directs the applicant to perform step 3 of AP/03. Applicant will recognize that the steam dump valves are not modulating and transition to the RNO. With the steam dump valves being closed and Tavg being more than 3°F higher than Tref, the applicant will take the steam dump control to manual.

After placing the steam dumps in manual, the applicants will manually open the steam dumps to initiate a cooldown. Once the cooldown is initiated and at the discretion of the examiner, the JPM may be terminated.

JPM f - Shift Upper Containment Ventilation Units (RO Only) New K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans (CFR 41.7 /

45.5 to 45.8) RO 3.6 SRO 3.6 NOTE TO EXAMINER - This JPM can be performed at the same time as JPM e. Both JPMs use the same simulator IC set and neither JPM should cause any alarms that would impede the other. This JPM is performed around the back of the control boards on the ventilation panel, and out of sight of the applicant performing JPM e.

Initial conditions are that Unit 1 is at 48% power. The CRS directs the applicant to shift operating Upper Containment Ventilation Units by starting 1D UCVU and stopping 1C UCVU per OP/1/A/6450/001 (Containment Ventilation (VV) Systems) Enclosure 4.12 (Shifting Operating Upper Containment Ventilation Units). Applicants will start 1D UCVU and verify required fans start. Following this, applicants will secure 1C UCVU and verify it stops.

Simulator JPMs JPM g - Reset Radiation Monitor Trip Setpoints (RO Only) Direct from bank K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR 41.7 / 45.5 to 45.8) RO 3.7 SRO 3.7 Initial conditions are that Unit 1 is at 100% power. Following a discussion with RP concerning a premature gaseous release termination, the CRS directs the applicant to reset EMF 50L setpoints per OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment). The new setpoints will have a Trip 1 value of 6300 cpm and a Trip 2 value of 9000 cpm. The OAC program EMFLIB is not available. The applicants will input the new values one at a time per procedure and perform a verification of proper setpoints per the procedure. The applicants will then fill out the appropriate setpoint log entries to finish the JPM.

JPM h - Loss of KC AP-21 step 8 (Reactor Trip Sequence) (RO Only) Direct from bank - Alternate Path K/A 008 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCW pump (CFR 41.5 / 43.5 / 45.3 / 45.13) RO 3.3 SRO 3.6 Initial conditions are Unit 1 is at 100% power. AP/1/A/5500/021 (Loss of Component Cooling) has been entered. The CRS directs the applicant to perform step 8 of AP/21. The applicant will not be able to verify KC flow to the NC pumps and transitions to the RNO. The applicant will attempt to open 1KC-425A (NC Pumps Ret Hdr Cont Isol) which will be unsuccessful and will begin the ALTERNATE PATH. The applicant will place steam dumps in Pressure control mode, ensure the reactor is tripped, when reactor power is verified < 5% will trip the NC Pumps, and will place both Pressurizer Spray Valves in manual and closed. The JPM will be terminated with a cue that the CRS is ready to begin reading EP/1/A/5000/E-0 (Reactor Trip or Safety Injection).

Plant JPMs JPM i - Place 1B Hydrogen Recombiner in Service (Common RO & SRO) Direct from bank (RCA entry required)

K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Hydrogen Recombiner power setting, determined by using plant data book (CFR 41.5 / 43.5 / 45.3 /

45.13) RO 3.4 SRO 3.6 Initial conditions are that a LOCA has occurred on Unit 1. The CRS instructs the applicant to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA). The applicant will power up the 1B Hydrogen Recombiner and warm it up by adjusting the power output in several increments. The applicant will have to determine the required power output setting per Unit 1 Revised Data Book Figure 10 for the given pressure. Due to containment hydrogen concentration being > 3%, the applicant will have to add 4 KW to value from Figure 10 for the final required power output. Following adjusting the power output to the desired value and notification to the control room of the status of 1B Hydrogen Recombiner, the JPM is complete.

JPM j - Locally Start 2B Diesel Generator (Common RO & SRO) Direct from bank - Alternate Path K/A 064 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes of water, oil, and air valves (CFR 41.5

/ 43.5 /45.3 / 45.13) RO 3.1 SRO 3.3 Initial conditions are Unit 2 has experienced a loss of all AC power to 2ETB. The reason for the loss of AC power has been corrected. 2ETB load shed is complete. The CRS instructs the applicant to energize 2ETB from 2B D/G by performing AP/2/A/5500/007 (Loss of Normal Power)

Enclosure 11 (Energizing 2ETB From D/G). The applicant will locally start 2B D/G, attain proper frequency and voltage, and close the diesel output breaker to energize 2ETB. Following powering up essential load centers, the applicant would verify proper cooling water flow by verifying the cooling water isolation valve open. This valve is not open and cant be manually opened. This begins the ALTERNATE PATH. The applicant will have to shut down 2B D/G and inform the control room of status to finish the JPM.

JPM k - Start Backup Temporary VI Compressor (RO Only) Direct from bank K/A APE 065 AA1.04 Ability to operate and/or monitor the following as they apply to the Loss of Instrument Air: Emergency air compressor (CFR 41.7 / 45.5 / 45.6) RO 3.5 SRO 3.4 Initial conditions are both units at 100% power. VI low pressure annunciator is lit and VI pressure is 75 PSIG and slowly decreasing. AP/0/A/5500/022 (Loss of Instrument Air) is implemented. The CRS directs the applicant to startup and align the Backup Temporary VI Compressor 2 to the Instrument Air Header per the local copy of EP/1/A/5000/G-1 (Generic Enclosures) Enclosure 23 (Backup VI Compressor(s)) step 3. Applicant will begin with making pre start checks of the compressor. Applicant will then start the compressor and make the necessary lineups to tie the compressor to the Instrument Air Header. Once the applicant informs the control room of the status, the JPM is complete.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Exam Level: RO SRO-I SRO-U Operating Test Number: 2015301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function a.

b. Transfer ECCS to Cold Leg Recirculation A,D,EN,L,P,S 2 006 A4.07

c. Isolate Cold Leg Accumulators during Shutdown LOCA A,L,N,S 3 006 A1.13 d.

e. Control Tavg using Steam Dumps D,S 4S 039 A2.04 f.

g.

h.

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Place Hydrogen Recombiners in service D,E,L,R 5 028 A2.01

j. Start 2B Diesel Generator A,D,E 6 064 A2.01 k.

@ 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 4-6 / 4-6 / 2-3 (6/-/3)

(C)ontrol room (D)irect from bank <9 / <8 / <4 (8/-/4)

(E)mergency or abnormal in-plant >1 / >1 / >1 (3/-/3)

(EN)gineered safety feature - / - / >1 (1/-/1)

(L)ow-Power / Shutdown >1 / >1 / >1 (5/-/3)

(N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (2/-/1)

(P)revious 2 exams <3 <3 / <2 (3/-/1)

(R)CA >1 / >1 / >1 (1/-/1)

(S)imulator ES-301, Page 23 of 27

Simulator JPMs JPM b - Transfer the ECCS to Cold Leg Recirculation (Common RO & SRO) Previous 2 NRC Exams -

randomly selected from bank - Alternate Path.

K/A 006 A4.07 - Ability to manually operate and/or monitor in the control room: ECCS pumps and valves (CFR: 41.7/45.5 to 45.8) RO 4.4 / SRO 4.4 Initial conditions are a LOCA has occurred on Unit 1. Annunciator 1AD-9, E/8 FWST LO-LO LEVEL is lit and the CRS instructs the applicant to transfer to the Cold Leg Recirculation lineup using EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) step 6. During verification of automatic actions, it is determined that 1NI-184B (ND Pump 1B Cont Sump Suct) is not open.

The applicant continues to perform the lineup for CLR and when directed to open 1ND-28A (ND Supply to NV and NI Pmps), it will not open. This is where the applicant will determine that no ND train can be aligned to provide a suction to the NV and NI pumps and transitions to the RNO to begin the ALTERNATE PATH. The applicant will have to secure all NV and NI pumps to finish the JPM.

JPM c - Isolate Cold Leg Accumulators Following a Shutdown LOCA (Common RO & SRO) New -

Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 41.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to address the LOCA.

The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will have to isolate the Nitrogen going to the 1B and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. The JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

JPM e - Control Tavg using the steam dumps in manual (Common RO & SRO) Direct from bank K/A 039 A2.04 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: Malfunctioning steam dump (CFR 41.5 / 43.5 / 45.3 / 45.13) RO 3.4 SRO 3.7 Initial conditions are that Unit 1 has experienced a Load Rejection due to a Zone A Lockout.

The immediate actions of AP/1/A/5500/003 (Load Rejection) have been completed. During the runback, control rods stopped moving in auto or manual. The CRS and OATC are responding to the rod failure using AP/1/A/5500/015 (Rod Control Malfunction). The CRS directs the applicant to perform step 3 of AP/03. Applicant will recognize that the steam dump valves are not modulating and transition to the RNO. With the steam dump valves being closed and Tavg being more than 3°F higher than Tref, the applicant will take the steam dump control to manual.

After placing the steam dumps in manual, the applicants will manually open the steam dumps to initiate a cooldown. Once the cooldown is initiated and at the discretion of the examiner, the JPM may be terminated.

Plant JPMs JPM i - Place 1B Hydrogen Recombiner in Service (Common RO & SRO) Direct from bank (RCA entry required)

K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Hydrogen Recombiner power setting, determined by using plant data book (CFR 41.5 / 43.5 / 45.3 /

45.13) RO 3.4 SRO 3.6 Initial conditions are that a LOCA has occurred on Unit 1. The CRS instructs the applicant to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA). The applicant will power up the 1B Hydrogen Recombiner and warm it up by adjusting the power output in several increments. The applicant will have to determine the required power output setting per Unit 1 Revised Data Book Figure 10 for the given pressure. Due to containment hydrogen concentration being > 3%, the applicant will have to add 4 KW to value from Figure 10 for the final required power output. Following adjusting the power output to the desired value and notification to the control room of the status of 1B Hydrogen Recombiner, the JPM is complete.

JPM j - Locally Start 2B Diesel Generator (Common RO & SRO) Direct from bank - Alternate Path K/A 064 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes of water, oil, and air valves (CFR 41.5

/ 43.5 /45.3 / 45.13) RO 3.1 SRO 3.3 Initial conditions are Unit 2 has experienced a loss of all AC power to 2ETB. The reason for the loss of AC power has been corrected. 2ETB load shed is complete. The CRS instructs the applicant to energize 2ETB from 2B D/G by performing AP/2/A/5500/007 (Loss of Normal Power)

Enclosure 11 (Energizing 2ETB From D/G). The applicant will locally start 2B D/G, attain proper frequency and voltage, and close the diesel output breaker to energize 2ETB. Following powering up essential load centers, the applicant would verify proper cooling water flow by verifying the cooling water isolation valve open. This valve is not open and cant be manually opened. This begins the ALTERNATE PATH. The applicant will have to shut down 2B D/G and inform the control room of status to finish the JPM.

ES-401 PWR Examination Outline Facility: CATAWBA Date of Exam: MAY 2015 ROKACaoyPcnts SAC-Only_Points Tier Group 1 G*

K KKKKKAIAAAG A2 Total 1 2 3 4 5 6 1j2 3 4 Total 1 1 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 1 2 2 N/A i 2 N/A 9 2 2 4 Evokions Tier Totals 4 5 5 4 5 4 27 5 5 10 1 2 2 2 2 3 3 3 3 2 3 3 28 2 3 5 2.

Plant 2 L+/-_L+/-_L +/-J !L+/-+/- L I I I 3 Systems Tier Totals 3 3 3 4 4 4 3 3 4 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3_ 3 2 2 2 1 Note: 1 Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (ie., exceptfor one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section Di .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SAC topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section Di .b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* the SAC-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for AC and SAC-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 1 0 CFR 55.43.

ES-401, REV 9 T1GI PWR EXAMINATION OUTLiNE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO7EK1 .05 -

Reactor Trip Stabilization - Recovery 3.3 3.8 1 - Decay power as a function of time

/1 009EK203 SmallBreakLOCA/3 3 3.3 S/Gs 015AG2 2 39 RCP Malfunctions I 4 39 45 - J [ Knowledge of less than one hour technical speccation action statements for systems.

025AA2.O1 Loss of RHR System I 4 2.7 2.9 Li D El El El D --

Li El [Z Proper amperage of running LPI/decay heat removal/RHR pump(s) 026AA1 .04 Loss of Component Cooling Water I 8 2.7 2.8 Jj E Li D El El El El El E CRDM high-temperature alarm system 027AG2.4.18 Pressurizer Pressure Control System 3.3 4.0 fl i [ r Li Li El El Knowledge ofthe specific bases for EOPs, Malfunction I 3 - -

038EA1 20 Steam Gen Tube Rupture I 3 38 36 AFW flow control valve reset switches and indicators 054AK1 .01 Loss of Main Feedwater I 4 4.1 4.3 MEW line break depressurizes the S/G (similar to a steam line break) 055EK1 02 Station BlackoutT6 4 1 44 . Natural circulation cooling 056AG2.4.47 Loss of Off-site Power I 6 4.2 4.2 Ability to diagnose and recognize trends in an accurate

[ r] [ H E] LI El El El and timely manner utilizing the appropriate control room reference material.

057AK3.O1 Loss of Vital AC Inst. Bus 16 4,1 4.4 Actions contained in EOP for loss of vital ac electrical IDE LI DLI LI LI Li instrument bus Page 1 of 2 09/24/2014 2:09 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SAC 058AA2.O1 Loss of DC Power I 6 3.7 4.1 i That a loss of dc power has occurred; verification that substitute power sources have come on line 062AA2.03 Loss of Nuclear Svc Water I 4 2.6 2.9 The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3 08 Loss of Instrument Air I 8 37 39 L z L El El E LZ E J Actions contained in EQP for loss of instrument air 077AA1 .03 Generator Voltage and Electric Grid 3.8 3.7 i [ [ Li Voltatge regulator controls Disturbances I 6 J fl [] J] [J WEO4EK2 1 LOCA Outside Containment 1 3 35 39 j ]

jj -

[J [ [J F - i -

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEO5EK2.2 -

Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary

[] i fl fl El El El Secondary Heat Sink I 4 coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK3.4 Loss of Emergency Coolant Recirc. /4 3.6 3.8 - AC or SAC function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

Page 2 of 2 09/24/2014 2:09PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AA1 03 Continuous Rod Withdrawal I 1 34 32 fl [ fl j [j Bonc acid pump control switch

[

036AK3 02 Fuel Handling Accident I 8 29 36 j LI JJ Li J LZ E Ei Interlocks associated with fuel handling equipment 037AK1 01 Steam Generator Tube Leak I 3 29 33 Use of steam tables 051AA2 02 Loss of Condenser Vacuum I 4 39 4 1 Conditions requiring reactor and/or turbine trip U Li Li LLZ]L Z LJ Z 068AA2lO Control Room Evac. I 8 42 4.4 fl. [j Source range count rate El El D El Li E El El 076AK2 01 High Reactor Coolant Activity I 9 26 3 Process radiation monitors WEO3EK2.2 -

LOCA Cooldown Depress. / 4 3.7 4.0 ,

Facilitys heat removal systems, ncludng primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WEO8EK3 3 RCS Overcooling PTS I 4 37 38 Manipulation of controls required to obtain desired j [ [J [j ] ti D El operating results during abnormal and emergency situations.

wel5EG2 4 3 Containment Flooding / 5 37 39 Ability to identify post accident instrumentation El E Z Page 1 of 1 09/24/2014 2:09 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K6 02 Reactor Coolant Pump 27 31 [] J [ ] ] Ej RCP seals and seal water supply 004A2 26 Chemical and Volume Contr2 8 30 [ fl [] [ ] j [ [ [J Low VCT pressure 004K202 Chemical and Volume Control 2.9 3.1 fl [j [ fl Makeup pumps 005A1 .01 Residual Heat Removal 3.5 3.6 fl [ JJ [ fl fl Heatup/cooldown rates 006K507 Emergency Core Cooling 2.7 3.0 [ Jj [ [ [ [j [ ] ] Expected temperature levels in various locations of the RCS due to various plant conditions 007G2.1 20 Pressurizer Relief/Quench Tank 4.6 4.6 [1 Ability to execute procedure steps.

[ [] ] [

008A3 05 Component Cooling Water 30 31 [ j [ [ Control of the electrically operated automatic isolation valves in the CCWS 010K6O1 PressurizerPressure Control 2.7 3.1 [ ] El El LI El El El Pressure detection systems 010K602 Pressurizer Pressure Control 3.2 3.5 ] [ ] [] fl PZR 012K2O1 Reactor Protection 3.3 3.7 El El El El El El El RPS channels, components and interconnections 013K415 Engineered Safety Features Actuation 2.6 32 El El El] Eli El El E El El El Continuous testing Page 1 of 3 09/24/2014 2:09 PM

ES-401, REV 9 T2G1 PWR EXAMiNATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SAC 022A4.01 Containment Cooling 3.6 3.6 CCS fans 022K4.03 Containment Cooling 3.6 4.0 Automatic containment isolation El El LZ Li El El 1 El i-i ElL r 1 025A4.01 Ice Condenser 3.0 2.7 v Ice condenser isolation valves 026A1 01 Containment Spray 3.9 4.2 Containment pressure El El El El Li LI El El Li 039K501 Main and Reheat Steam 2.9 3.1 ii ILl Li Definition and causes of steam/water hammer El[E El El 059A1 .03 Main Feedwater 2.7 2.9 Power level restrictions for operation of MEW pumps and El El El El Li Li Li Li:

valves.

059A3.04 Main Feedwater 2.5 2.6 Turbine driven feed pump El El El El El lE El El El lEll 061A2.08 Auxiliary/Emergency Feedwater 2.7 2.9 El Elow rates expected from various combinations of AFW pump discharge valves 061 K5.05 Auxiliary/Emergency Feedwater 2.7 3.2 Feed line voiding and water hammer El El El El ElElEl El ElEl 062A2.1 1 AC Electrical Distribution 3.7 4.1 Aligning standby equipment with correct emergency power source (DiG) 063K302 DC Electrical Distribution 3.5 3.7 Components using DC control power El El l El El El El El El El LII Page 2 of 3 09/24/2014 2:09 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K3.03 Emergency Diesel Generator 3.6 3.9 ED/G (manual loads) 073K1 .01 Process Radiation Monitoring 3.6 3.9 ,

Those systems served by PRMs 076A4.04 Service Water 3.5 3.5 El Li Li El El El El El Emergency heat loads El 076G2.4.21 Service Water 4.0 4.6 El El DEl DEED ElElL Knowledge of the parameters and logic used to assess the status of safety functions 078G2.4.8 Instrument Air 3.8 4.5 El LElElL1ElElElEl Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

1 03K1 .08 Containment 3.6 3.8 j SIS, including action of safety injection reset DEE LE ED El ED L Page 3 of 3 09/24/2014 2:09 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 Al 1 1 Control Rod Drive 37 39 [ [ [ [] H ] J] fl JJ [ Required primary system subcooling during shutdown location of indication 01 1 K5 15 Pressurizer Level Control 36 40 [J J fl [ [1 j El PZR level indication when RCS is saturated 015K4 09 Nuclear Instrumentation 28 33 [ J j El El LI El H LI Li Redundant sources of information on axialflux density distribution 028K2 01 Hydrogen Recombiner and Purge 25 28 fl j [ j j [ Hydrogen recombiners Control 041 K603 Steam Dump/Turbine Bypass Control 27 2.9 [ [] ] JJ LI El LI El Controller and positioners, including ICS, S/G, CRDS 045A4 02 Main Turbine Generator 27 26 j j [ j [J j [1 j T/G controls including breakers 055G2449 Condenser Air Removal 4.6 4.4 JJ D E El LI El LI El El El Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

056K1O3Condensate 2.6 2.6 fl ] jJ [ [ [J [ MFW 072A3 01 Area Radiation Monitonng 29 3 1 [] El H H H H H H Changes in ventilation alignment H L]

075K3.07 Circulating Water H H El H H H H H H H H ESFAS Page 1 of 1 09/24/2014 2:09 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2 1 34 Conduct of operations 27 35 Knowledge of primary and secondary chemistry limits El El -z  : ;i G2.l .45 Conduct of operations 4.3 4.3 El El El El t:i i El Li 1 El Ability to identify and interpret diverse indications to validate the response of another indication G2 2 18 Equipment Control 26 38 El El El [1 Knowledge of the process for managing maintenance

[_i F activities during sh utdown operations.

G2 2 38 Equipment Control 36 45 Knowledge of conditions and limitations in the facility El El El z z V license.

G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to El El lEli El [1 i LI E Li licensed operator duties

---i -

G2.3.14 RadiationControl 3.4 3.8 r El El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G23.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and El El El El El [1 LI El El El emergency conditions G2.4.1 1 Emergency Procedures/Plans 4.0 4.2 ,i Knowledge of abnormal condition procedures El El El El G24.20 Emergency Procedures/Plans 3.8 4.3 Knowledge of operational implications of EQP warnings, El El El El El El El El El El cautions and notes.

G2.4.25 Emergency Procedures/Plans Knowledge of fire protection procedures.

El El El El El El El El El El Page 1 of 1 09/24/2014 2:09 PM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 3.4 4.7 -

015AG2.2.40 RCP Malfunctions / 4 Ability to apply technical specifications for a system.

J 029EA2.04 ATWS/1 3.2 3.3 El D [Z El D E] E CVCS centrifugal charging pump operating indication El El 038EG2.4.41 Steam Gen. Tube Rupture /3 2.9 4.6 Knowledge of the emergency action level thresholds and Li El El El LZI IL El El classifications.

058AG2.1 .23 Loss of DC Power / 6 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

077AA2.O1 Generator Voltage and Electric Grid 3.5 3.6 Operating point on the generator capability curve Disturbances / 6 Li El] [ELL[EEiL1DDLL WEll EA2.1 Loss of Emergency Coolant Recirc. / 4 3.4 4.2 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

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ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 005AA202 Inoperable/Stuck Control Rod I 1 2.5 3 ..

fl [ [ [J [j [ [ i [ [j Difference between jog and run rod speeds effect on CRDM of stuck rod 032AG2 2 25 Loss of Source Range NI I 7 32 42 ] [j El -

1 D E 1 Knowledge of the bases in Technical Specifications for hmiting conditions for operations and safety limits.

weO8EG2.4.45 RCS Overcooling PTS I 4 4.1 4.3 Ability to prioritize and interpret the significance of each L W annunciator or alarm.

WE13EA2.2 Steam Generator Over-pressure / 4 3.0 3,4 [j Adherence to appropriate procedures and operation fl El El fl within the limitations in the facilitys license and amendments.

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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 012A2.O1 Reactor Protection 3.1 3.6 1 Faulty bistable operation 01 3A2 02 Engineered Safety Features Actuation 43 45 j Excess steam demand 061 G2 4 9 Auxiliary/Emergency Feedwater 38 42 J J i Z El EL E E v Knowledge of low power / shutdown implications in accident (eg. LOCA or loss of RHR) mitigation strategies.

076G2 2 44 Service Water 42 44 [j j -

fl J [ J j Ability 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 078A2.O1 Instrument Air 2.4 2.9 Di D El [1 fl fl Air dryer and filter malfunctions fl Page 1 of I 09/24/2014 2:09 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRQ 002G2.4.50 Reactor Coolant 4.2 4.0 - - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

01 6A2.02 Non-nuclear Instrumentation 2.9 3.2 Loss of power supply 034K4.0l Fuel Handling Equipment 2.6 3.4 F  : Fuel protection from binding and dropping E EZ 3Z El El Page 1 of 09/24/2014 2:09 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR KIK2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO G2.1 .40 Conduct of operations 2.8 39 Knowledge of refueling adm inistrative requirements G2.1 .5 Conduct of operations 2.9 3.9 Li El El El El LI D D El LZ Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.40 Equipment Control 3.4 4.7

-- V Ability to apply technical specifications for a system.

G2.2.43 Equipment Control 3.0 U U Lj Knowledge of the process used to track inoperable alarms G2.3.12 Radiation Control 3.2 3.7 U Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 EZLL1DL1DEiDLZDEiI Ability to aprove release permits G2.4.37 Emergency Procedures/Plans 3.0 4,1 Knowledge of the lines of authority during implamentation of an emergency plan.

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