ML092120016

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Initial Exam 2009-301 Draft Administrative Documents
ML092120016
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 07/31/2009
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
Download: ML092120016 (30)
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{{#Wiki_filter:ES-301 Administrative Topics Outline Form ES-301-1 Facility: Shearon Harris Date of Examination: 3/9/2009 Exam Level: RO Operating Test No.: 05000400 Administrative Topic Type Describe activity to be performed (see Note) Code* M,R Determine Rod Misalignment Using Thermocouples (JPM-CR-139) Conduct of Operations KIA G2.1.7 2009a NRC RO A1-1 D,R Perform A Manual Shutdown Margin Calculation (JPM-ADM-019) Conduct of Operations KIA G2.1.25 2009a NRC RO A1-2 M,R Perform Quadrant Power Tilt Ratio Surveillance (JPM-CR-036) Equipment Control KIA G2.2.12 2009a NRC RO A2 D,R Determine TEDE While Working in a High Airborne Area (JPM-ADM-022) Radiation Control KIA G2.3.4 2009a NRC RO A3 (Common) N/A Emergency Procedures/Plan NOT SELECTED FOR RO NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

(N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (S 1; randomly selected) Form ES-301-1 RO Rev. 1

2009a NRC RO Admin JPM Summary 2009a NRC RO A1 Determine Rod Misalignment Using Thermocouples (JPM-CR-139 Modified) G2.1. 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 The plant is at 90% power with a load decrease in progress when a control rod is observed indicating 24 steps higher than group demand. The candidate must perform Attachment 2 of AOP-001, Malfunction of Rod Control and Indication System, to calculate the temperature difference between the affected thermocouple and its symmetric thermocouples. This is a bank JPM that has been modified by changing the initial conditions, the misaligned rod, and the final outcome (the calculation will be within 10°F, indicating that the rod is NOT misaligned rod but instead is a rod position indication problem). 2009a NRC RO A1 Perform A Manual Shutdown Margin Calculation (JPM-ADMIN-019) G2. 1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41. 10/43.5/45. 12) RO 3. 1 SRO 2.8 The plant is operating at 75% power and the USCG will direct the candidate to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, for the current plant conditions. 2009a NRC RO A2 - Perform Quadrant Power Tilt Ratio Surveillance (JPM-CR-036 Modified) G2.2. 12 Knowledge of surveillance procedures (CFR: 41.10/45.13) RO 3.7 SRO 4.1 The candidate will perform a QPTR calculation as required for a misaligned rod in accordance with OST-1039, Calculation of Quadrant Power Tilt Ratio. This is a bank JPM that has been modified by changing the NIS values and the initial power level. 2009a NRC RO A3 - Determine TEDE While Working in a High Airborne Area (JPM-ADM-022) G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4/45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator is required or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time. Fonn ES-301-1 RO Rev. 1 2

DR FT ES-301 Administrative Topics Outline Form ES-301-1 ( Facility: Shearon Harris Date of Examination: 3/9/2009 Exam Level: SRO Operating Test No.: 05000400 Administrative Topic Type Describe activity to be performed (see Note) Code* Determine Rod Misalignment Using Thermocouples Conduct (JPM-CR-139) of Operations M,R G2.1.7 2009a NRC SRO A1-1 Determine Boric Acid Addition Following Control Room Evacuation Conduct (JPM-IP-049) of Operations D,R KIA G2.1.25 2009a NRC SRO A1-2 Perform Quadrant Power Tilt Ratio Surveillance (JPM-CR-036) Equipment Control M,R KIA G2.2.12 2009a NRC SRO A2 Determine TEDE While Working in a High Airborne Area D,R (J PM-ADM-022) Radiation Control G2.3.4 2009a NRC SRO A3 (Common) Classify an Event Emergency (JPM-CR-193) Procedures/Plan D,R G2.4.41 2009a NRC SRO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 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) ( Form ES-301-1 SRO Rev. 1

2009a NRC SRO Admin JPM Summary c 2009a NRC SRO A1 Determine Rod Misalignment Using Thermocouples (JPM-CR-139 Modified) G2.1.7 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 The plant is at 90% power with a load decrease in progress when a control rod is observed indicating 12 steps higher than group demand. The candidate must perform Attachment 2 of AOP-001, Malfunction of Rod Control and Indication System, to calculate the temperature difference between the affected thermocouple and its symmetric thermocouples. This is a bank JPM that has been modified by changing the initial conditions, the misaligned rod, and the final outcome (the calculation will be within 10°F, indicating that the rod is NOT misaligned but instead is a rod position indication problem). The SRO will determine Tech Spec requirements for the determined conditions. 2009a NRC SRO A1 Determine Boric Acid Addition Following Control Room Evacuation (JPM-IP-049) G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10/43.5/45.12) RO 3.9 SRO 4.2 The Control Room has been evacuated and the MCB transfer to the ACP has been completed. Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. Given an OST-1036 cold shutdown boron requirement, the candidate must use curves to calculate gallons of Boric Acid and change in Boric Acid Tank level to complete section 3.2 step 25. 2009a NRC SRO A2 - Perform Quadrant Power Tilt Ratio Surveillance (JPM-CR-036 Modified) G2.2.12 Knowledge of surveillance procedures (CFR: 41.10/45.13) RO 3.7 SRO 4.1 The candidate will perform a QPTR calculation as required for a misaligned rod in accordance with OST-1039, Calculation of Quadrant Power Tilt Ratio. This is a bank JPM that has been modified by changing the NIS values and the initial power level. The SRO will determine Tech Spec requirements for the determined conditions. 2009a NRC SRO A3 - Determine TEDE While Working in a High Airborne Area (JPM-ADM-022) G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4 /45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator is required or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time. Form ES-301-1 SRO Rev. 1 2

2009a NRC SRO Admin JPM Summary 2009a NRC SRO A4 - Classify an Event (JPM-CR-193) ( G2.4.41 Knowledge of the emergency action level thresholds and classifications (CFR: 41.10/43.5/45.11) RO 2.9 SRO 4.6 Given a set of initial conditions and the EAL Flow Path, the candidate must classify the appropriate Emergency Action Level for the event in progress. (~ c Form ES-301-1 SRQ Rev. 1 3

R FT ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ( Facility: Shearon Harris Date of Examination: 3/9/2009 Exam Level: RO SRO-I SRO(U) Operating Test No.: 05000400 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. Restore Power to Emergency Buses N,S 6 (EPP-001, Attachment 1)

KIA 062A4.01

b. Use ESW System As A Backup Source of Water To AFW L,D,S 4S (PATH-1, OP-137) (JPM-CR-107)

KIA 054AA1.01

c. Manually Align SI Equipment After LOSP A,D,EN,S 2 (EOP-EPP-003) (JPM-CR-056)

KIA 006 A4.02

d. Place Normal Letdown In Service A, D, S 1 (OP-107) (JPM-CR-222)

KIA 004 A4.06

e. Containment Cooling to Max Cooling Mode D,S 5 (OP-169) (JPM-CR-033)

KIA 022 A4.01 RO ONLY

f. Loss of All CCW P,A,S 8 (AOP-014) (2007 NRC Exam JPM h.)

KIA 008 A2.01

g. Respond to High RCS Pressure while Solid L, D, S 3 (AOP-019) (JPM-CR-052)

KIA 010A1.07

h. Startup a Reactor Coolant Pump following Maintenance A, L, M,S 4P (OP-100) (JPM-CR-005)

KIA 003 A2.02 Form ES-301-2 Rev. 1

DR ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Shearon Harris Date of Examination: 3/9/2009 Exam Level: RO SRO-I SRO(U) Operating Test No.: 05000400 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Reset Safety Injection Locally E, N 2 (PATH 1, Attachment 1)

KIA 013 A2.06

j. Local Inspection of Annunciator Cabinets D,E 7 (AOP-037, Attachment 1) (JPM-IP-144)

KIA 016 A2.02

k. Local M/U to VCT via Manual Emergency Boration D,E,R 1 (AOP-003, Attachment 2) (JPM-IP-088)

KIA 004 A2.14 

@           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 (4/4/2)

(C)ontrol room (D)irect from bank :59/:58/:54 (7/6/4) (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (3/3/2) (EN)gineered safety feature - / - / ;::1 (1/1/1) (L)ow-Power / Shutdown  ;::1/;::1/;::1 (3/3/2) (N)ew or (M)odified from bank including 1(A)  ;::2/;::2/;::1 (3/3/1) (P)revious 2 exams :53/:53/:52 (1/1/0) (R)CA  ;::1/;::1/;::1 (1/1/1) (S)imulator Fonn ES-301-2 Rev. 1 2

2009a NRC Control Roomlln-Plant JPM Summary JPM a - Restore Power to Emergency Buses (New) 062 A4.01 Ability to manually operate andlor monitor in the control room: All breakers (including available switchyard) (CFR: 41.7 145.51to 45.8) RO 3.3 SRO 3.1 A loss of offsite power and a failure of both diesels has occurred requiring entry into EPP-001, Loss of AC Power to 1A-SA and 1B-SB Buses. The candidate will be informed that Offsite Power has been restored. The task will be to restore power to both of the Emergency Buses from Offsite Power using Attachment 1 of EPP-001. JPM b - Using ESW System As A Backup Source of Water To AFW (JPM-CR-107) 054 AA 1.01 - Ability to operate and 1 or monitor the following as they apply to the Loss of Main Feedwater AFW controls, including the use of alternate AFW sources (CFR 41.7145.5145.6) RO 4.51 SRO 4.4 Following a LOCA the operator is informed that a leak developed in the Condensate Storage Tank (CST). The CST level has decreased to < 10%. The candidate is directed to supply ESW from the A Header to both the A AFW Pump and the Turbine Driven AFW pumps. This will require shutting down the B MDAFW Pump and 'A' Train of Containment Fan Coolers in addition to the ESW valve alignment. JPM c - Manually Align SI After LOSP (JPM-CR-056) Alternate Path, Engineered Safety Feature 006 A4. 02 Ability to manually operate andlor monitor in the control room: Valves (CFR: 41.7145.5 to 45.8) RO 4.0 SRO 3.8 Following a reactor trip and loss of offsite power, the crew transitions to recovery procedure EPP-003, Loss of All AC Power Recovery with SI Required. The candidate will be directed to align SI valves and establish an injection flow path for SI. During the lineup a CSIP Alternate Miniflow valve will fail to stoke requiring the candidate to complete the alternate path step to shut the associated block valve. JPM d - Place Normal Letdown in Service (JPM-CR-222) Alternate Path 004 A4. 06 - Ability to manually operate andlor monitor in the control room: Letdown isolation and flow control valves (CFR: 4111 1 45.5 to 45.8) RO 3.61 SRO 3.1 With the plant operating at 100% steady state the candidate will be informed that letdown was out of service for maintenance. Maintenance has been completed. The clearance has been removed and Excess letdown has just been taken off. The candidate will place letdown in service lAW OP-107. When the candidate places the letdown pressure control valve in automatic it will fail closed causing letdown pressure to rapidly increase. The candidate will be expected to recognize the failure and return pressure to normal. This can be accomplished by either closing the in service letdown valve or place the pressure controller back to manual (per OMM-001 guidance), adjust pressure to normal and report the failure to the SCO. Form ES-301-2 Rev. 1 3

2009a NRC Control Room/In-Plant JPM Summary (continued) JPM e - Containment Cooling to Max Cooling Mode (JPM-CR-033) 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 In preparation for an upcoming Containment entry, Containment Cooling is to be placed in Maximum Cooling Mode. This will require the candidate to realign fans and dampers in accordance with OP-169, Containment Cooling System. The candidate will also have to verify the correct damper alignment using status light box indications. JPM f - Loss of All CCW (2007 NRC Exam JPM h) Alternate Path 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 With the plant at 100% power and one CCW pump under clearance the candidate will be tasked with responding to a loss of the running CCW pump. This will require the candidate to obtain AOP-014, Loss of Component Cooling Water, and complete the actions of loss of all CCW. The candidate will be required to complete the RNO actions of isolating letdown and charging. Since CCW will not be available in less than 10 minutes the candidate will be required to manually trip the Reactor, secure the Reactor Coolant Pumps and shut the Pressurizer Spray Valves. ( JPM 9 - Respond to High RCS Pressure while Solid (JPM-CR-OS2) Time Critical 010 A 1. 07 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS pressure (CFR: 41.5/45.5) RO 3.7 SRO 3.7 Solid plant Mode 4 operations will be in progress. The candidate will have to respond to a failure of the RCS pressure control valve that causes ReS pressure to rapidly increase. The candidate will perform the immediate actions of AOP-019, Malfunction of RCS Pressure Control, and stop the running CSIP in less than 2 minutes from the onset of the pressure excursion. JPM h - Startup a Reactor Coolant Pump following Maintenance (JPM-CR-005 Modified) Alternate Path 003 A2. 02 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP (CFR: 41.5/43.5/45.3/45/13) RO 3.7 SRO 3.9 A plant startup will be in progress with the 'A' and '8' RCPs in operation. Maintenance has been completed on the 'C' RCP and the candidate will be directed to start the 'C' RCP in accordance with OP-1 00, Reactor Coolant System. Soon after the RCP is started it will develop abnormal vibrations as indicated on the RCP Vibration Monitor in the MCR and MC8 annunciators. The candidate will be expected to determine that entry conditions are met for AOP-018, Reactor Coolant Pumps Abnormal Conditions and enter the AOP. The RCP vibrations will continue to rise until they exceed the operational trip limits of AOP-018 Attachment 1 (>20 mils shaft). The candidate is expected to secure the 'C' RCP lAW AOP-018. Form ES-301-2 Rev. 1 4

2009a NRC Control Roomlln-Plant JPM Summary (continued) JPM i-Reset Safety Injection Locally (New) Alternate Path 013 A2. 06 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; Inadvertent ESFAS actuation (CFR: 41.5/43.5/45.3/45.13) RO 3.7/ SRO 4.0 Following an inadvertent SI actuation and meeting SI termination criteria per Path-1 the crew is directed to reset SI. The candidate will be informed that SI Train 'B' did not reset from the MCR. The candidate will then be directed to locally reset Safeguards Train 'B' per Attachment 12 of PATH-1 Guide. This will require the candidate to go to the SSPS cabinet and simulate placing protection system breakers to the OFF position and then positioning the appropriate test switch to locally place the Protection System Train 'B' in test. JPM i - Local Inspection of Annunciator Cabinets (JPM-IP-144) 016 A2. 02 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of power supply (CFR:41.5/43.5/45.3/45.5) R03.9 SR03.2 The candidate will be directed by the MCR to locally inspect System 1 Annunciator Power Supply Cabinets for the cause of a MCR alarm using Attachment 1 of AOP-037, Loss of Main Control Room Annunciators. They will be required to locate the cabinets, determine which power supplies have failed, and then report the findings to the MCR. ( JPM k - Local Makeup to VCT via Manual Emergency Boration (JPM-IP-088) 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 The candidate will be informed that the Reactor Makeup Control System has malfunctioned requiring the candidate to locally makeup to the VCT in accordance with Attachment 2 of AOP-003, Malfunction of Reactor Makeup Control. Using this procedure the candidate will be directed to locate the manual Emergency Boration and Reactor Makeup Water valves and then simulate positioning these valves to the control rooms mark. Form ES-301-2 Rev. 1 5

DRAFT ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: HARRIS Date of Exam: MARCH (TBD) 2009 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

2 2 1 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 3 3 3 2 2 2 3 2 3 2 3 28 3 2 5 2. 2 1 1 1 1 1 1 1 0 1 1 1 10 2 1 3 Plant Systems Tier Totals 4 4 4 3 3 3 4 2 4 3 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 I I1 2 I I2 2 I I
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e .. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 outl ine; systems or evolutions that do not apply at the facility should be deleted andjustified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA 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 SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the following pages, enter the KIA 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* on the SRO-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 RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 ~ooooo 000 Reactor trip status panel 11 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:{CFR: 41.7 1 45.7 1 45.8) 009EA2.15 Small Break LOCA 1 3 3.3 3.4 ooooooo~ooo RCS parameters Ability to (a) predict the impacts of the following on the (SYSTEM) and-{b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:{CFR: 41.5/43.5/45.3/45.13) 011 EG2.2.44 Large Break LOCA 1 3 4.2 4.4 n 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications to verify the status and operation of a system, and understand how This is a Generic, no stem statement is operator actions and directives affect plant and system associated. conditions - 022AK1.03 Loss of Rx Coolant Makeup 1 2 3 3.4 ~ 0 0 0 0 0 0 0 0 0 0 Relationship between charging flow and PZR level Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):{CFR: 41.8 to 41.10/45.3) 025AG2.4.34 Loss of RHR System 14 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant This is a Generic, no stem statement is operational effects associated. 026AA2.04 Loss of Component Cooling Water 18 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 The normal values and upper limits for the temperatures of the components cooled by CCW Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):{CFR: 41.10 1 43.5 1 45.13) Page 1 of 3 8/21/2008 1:39 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 027AA1.03 Pressurizer Pressure Control System 3.6 3.5 0 0 0 0 0 0 ~ 0 0 0 Pressure control when on a steam bubble Malfunction 1 3 Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 1 45.5 1 45.6) 029EG2.1.20 ATWS 1 1 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to execute procedure steps. This is a Generic, no stem statement is associated. 038EK1.01 Steam Gen. Tube Rupture 1 3 3.1 3.4 ~ 0 0 0 0 0 0 0 0 0 0 Use of steam tables Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 057AA2.04 Loss of Vital AC Inst. Bus 1 6 3.7 4 DDDDDDD~DDD ESF system panel alarm annunciators and channel status indicators Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 1 43.5 1 45.13) 058AA1.02 Loss of DC Power 1 6 3.1 3.1 0 0 0 0 0 0 ~ 0 0 0 0 Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 1 45.5 1 45.6) 062AK3.03 Loss of Nuclear Svc Water 1 4 4 4.2 DD~DDDDDDDD Guidance actions contained in EOP for Loss of nuclear service water Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5 141.10 1 45.6/45.13) Page 2 of3 8/21/2008 1:39 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 065AK3.04 Loss of Instrument Air 1 8 3 3.2 0 ~ 0 0 0 0 000 Cross-over to backup air supplies Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5 141.10 1 45.6/45.13) 077AA1.05 Generator Voltage and Electric Grid 3.9 4.0 0 0 0 0 0 0 ~ 0 0 0 0 Engineered Safety Features Disturbances 1 6 Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 145.5 1 45.6) WE04EK2.2 LOCA Outside Containment 1 3 3.8 4.0 o~ooooo 000 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal Knowledge of the interrelations between systems and relations between the proper operation of (EMERGENCY PLANT EVOLUTION) and these systems to the operation of the facility. the foliowing:(CFR: 41.7 1 45.7 1 45.8) - ------~------ WE05EK3.2 Inadequate Heat Transfer - Loss of 3.7 4.1 OO~OOOODDDD Normal, abnormal and emergency operating procedures Secondary Heat Sink 1 4 associated with (Loss of Secondary Heat Sink). Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5 1 41.10 1 45.6 1 45.13) WE 11 EK2.1 Loss of Emergency Coolant Recirc. 14 3.6 3.9 D ~ 0 DOD 0 D D D 0 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure Knowledge of the interrelations between modes and automatic and manual features. (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) WE12EK1.2 Steam Line Rupture - Excessive Heat 3.5 3.8 ~ DOD 0 DOD DOD Normal, abnormal and emergency operating procedures Transfer 14 associated with (Uncontrolled Depressurization of all Knowledge of the operational implications Steam Generators). of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) Page 3 of 3 8/21/2008 1:39 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 001AA1.05 Continuous Rod Withdrawal/ 1 4.3 4.2 DDDDDD~DDDD Reactor trip switches Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 /45.5 / 45.6) 005AG2.4.31 Inoperable/Stuck Control Rod /1 4.2 4.1 DDDDDDDDDD~ Knowledge of annunciators alarms, indications or response procedures This is a Generic, no stem statement is associated. 024AK1.02 Emergency Boration /1 3.6 3.9 ~DDDDDDDDDD Relationship between boron addition and reactor power Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 033AK1.01 Loss of Intermediate Range NI/ 7 2.7 3 ~DDDDDDDDDD Effects of voltage changes on performance Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):{CFR: 41.8 to 41.10/45.3) 037AA2.05 Steam Generator Tube Leak / 3 2.8 3.3 DDDDDDD~DDD Past history of leakage with current problem Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):{CFR: 41.10 / 43.5 / 45.13) 074EA1.27 Inad. Core Cooling / 4 4.2 4.2 DDDDDD~DDDD ECCS valve control switches and indicators Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5/ 45.5) Page 1 of2 8/21/2008 1:40 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 076AK3.05 High Reactor Coolant Activity 1 9 2.9 3.6 D D ~ D D D D D D D D Corrective actions as a result of high fission-product radioactivity level in the RCS Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 145.6) WE03EK2.2 LOCA Cooldown - Depress. 14 3.7 4.0 D ~ D D D D D D D D D Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal Knowledge of the interrelations between systems and relations between the proper operation of (EMERGENCY PLANT EVOLUTION) and these systems to the operation of the facility. the foliowing:(CFR: 41.7/45.7/45.8) WE09EK3.2 Natural Circ. 14 3.2 3.6 D D ~ D D D D D D D D Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations). Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5 1 41.10/45.61 45.13) Page 2 of2 8/21/2008 1:40 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 003A4.04 Reactor Coolant Pump 3.1 3.0 D D D D D D D D D ~ D RCP seal differential pressure instrumentation Ability to manually operate and/or monitor in the control room:{CFR: 41.7/ 45.5 to 45.8) 004G2.1.19 Chemical and Volume Control 3.9 3.8 D D D D D D D D D D ~ Ability to use plant computer to evaluate system or component status. This is a Generic, no stem statement is associated. 004K1.06 Chemical and Volume Control 3.1 3.1 ~ D D D D D D D D D D Makeup system to VCT Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:{CFR: 41.2 to 41.9/45.7 to 45.8) 005K6.08 Residual Heat Removal 2.2 2.4 D D D D D ~ D D D D D Controllers and positioners Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):{CFR: 41.7/45.7) 006A1.01 Emergency Core Cooling 3.1 3.4 D D D D D D ~ D D D D Avoidance of thermal and pressure stresses due to pump startup Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:{CFR: 41.5/ 45.5) 007A3.01 Pressurizer Relief/Quench Tank 2.7 2.9 D D D D D D D D ~ D D Components which discharge to the PRT Ability to monitor automatic operations of the (SYSTEM) inciuding:{CFR: 41.7 /45.5) Page 1 of 5 8121/2008 1:41 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 007G2.4.31 Pressurizer Relief/Quench Tank 4.2 4.1 D D D D' D D D D D D ~ Knowledge of annunciators alarms, indications or response procedures This is a Generic, no stem statement is associated. 008K3.02 Component Cooling Water 2.9 3.1 D D ~ D D D D D D D D CRDS Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 /45.6) 008K4.09 Component Cooling Water 2.7 2.9 D D 0 ~ D D D D D D D The "standby" feature for the CCW pumps Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 010K2.03 Pressurizer Pressure Control 2.8 3.0 D ~ D D D D D D D D D Indicator for PORV position Knowledge of electrical power supplies to the foilowing:(CFR: 41.7) 012A1.01 Reactor Protection 2.9 3.4 D D D D D D ~ D DOD Trip setpoint adjustment Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5/ 45.5) 012K5.02 Reactor Protection 3.1 3.3 D D D D ~ D D D D D D Power density Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 013K3.03 Engineered Safety Features Actuation 4.3 4.7 D D ~ D D D D D D D D Containment Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 /45.6) Page 2 of 5 8121/2008 1:41 PM 

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 022K2.01 Containment Cooling 3.0 3.1 D~DDDDDDDDD Containment cooling fans Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 026A1.01 Containment Spray 3.9 4.2 DDDDDD~DDDD Containment pressure Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/ 45.5) 026K1.01 Containment Spray 4.2 4.2 ~DDDDDDDDDD ECCS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 039K5.05 Main and Reheat Steam 2.7 3.1 DDDD~DDDDDD Bases for RCS cool down limits Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 059A4.08 Main Feedwater 3.0 2.9 DDDDDDDDD~D Feed regulating valve controller Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 061A2.02 Auxiliary/Emergency Feedwater 3.4 3.5 DDDDDDD~DDD Air or MOV failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 / 43.5 / 45.3/45.13) Page 3 of 5 8/21/2008 1:41 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KS A1 A2 A3 A4 G TOPIC: RO SRO OS2K4.03 AC Electrical Distribution 2.B 3.1 0 0 0 ~ 0 0 0 0 0 0 Interlocks between automatic bus transfer and breakers Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 063K2.01 DC Electrical Distribution 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 Major DC loads Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) OS3K3.01 DC Electrical Distribution 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 ED/G Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/ 45.S) OS4A3.13 Emergency Diesel Generator 3.0 2.9 0 0 0 0 0 0 0 0 ~ 0 0 Rpm controller/megawatt load control (breaker-open/ breaker-closed effects) Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7 /45.5) OS4KS.OB Emergency Diesel Generator 3.2 3.3 0 0 0 0 0 ~ 0 0 0 0 0 Fuel oil storage tanks Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 073A2.01 Process Radiation Monitoring 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 Erratic or failed power supply Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 / 43.5 / 45.3 /45.13) Page 4 of 5 8I21/200B 1:41 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 076A3.02 Service Water 3.7 3.7 0 0 0 0 0 0 0 0 ~ 0 0 Emergency heat loads Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7 /45.5) 078G2.2.44 Instrument Air 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications to verify the status and operation of a system, and understand how This is a Generic, no stem statement is operator actions and directives affect plant and system associated. conditions 103K1.02 Containment 3.9 4.1 ~ 0 0 0 0 0 0 0 0 0 0 Containment isolation/containment integrity Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) Page 5 of 5 8121/2008 1:41 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 001K2.05 Control Rod Drive 3.1 3.5 0 ~ 0 0 0 0 0 0 0 0 0 MIG sets Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 011A1.01 Pressurizer Level Control 3.5 3.6 ooooo~ 000 PZR level and pressure Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.51 45.5) 014A4.01 Rod Position Indication 3.3 3.1 0 0 0 0 0 0 0 0 0 ~ 0 Rod selection Ability to manually operate andlor monitor in the control room:(CFR: 41.7/45.5 to 45.8) 015K5.11 Nuclear Instrumentation 3.3 3.7 0 0 0 0 ~ 0 0 000 Axial flux imbalance, including long-range effects Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5 I 45.7) 017K3.01 In-core Temperature Monitor 3.5 3.7 0 0 ~ 0 0 0 0 0 000 Natural circulation indications Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 I 45.6) 035G2.2.42 Steam Generator 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to recognize system parameters that are entry-level conditions for Technical Specifications This is a Generic, no stem statement is associated. 045A3.05 Main Turbine Generator 2.6 2.9 0 0 0 0 0 0 0 0 ~ 0 0 Electrohydraulic control Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45.5) Page 1 of2 8/21/2008 1:41 PM

ES*401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 071K4.04 Waste Gas Disposal 2.9 3.4 D D D ~ D D D D D D D Isolation of waste gas release tanks Knowledge of (SYSTEM) design feature{s) and or interlock{s) which provide for the foliowing:{CFR: 41.7) 079K1.01 Station Air 3.0 3.1 ~ D D D D D D D D D D lAS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:{CFR: 41.2 to 41.9/45.7 to 45.8) 086K6.04 Fire Protection 2.6 2.9 D D D D D ~ D D D D D Fire, smoke and heat detectors Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):{CFR: 41.7/45.7) Page 2 of2 8/21/2008 1:41 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO G2.1.30 Conduct of operations 4.4 4.00 0 0 0 0 0 0 0 0 0 ~ Ability to locate and operate components, including local controls. G2.1.44 Conduct of operations 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of RO duties in the control room during fuel handling. G2.2.20 Equipment Control 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for managing troubleshooting activities. __ .____ ~ ___ ._ ... _0. _____ - G2.2.25 Equipment Control 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. G2.3.11 Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to control radiation releases. G2.3.5 Radiation Control 2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~ Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions Page 1 of 2 8/21/2008 1:42 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: I R K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC: RO SRO G2.4.17 Emergency Procedures/Plans 3.9 4.3 t;l] Knowledge of EOP terms and definitions. G2.4.32 Emergency Procedures/Plans 3.6 4.0 [] [] ~ Knowledge of operator response to loss of ali annunciators. G2.4.9 Emergency Procedures/Plans 3.8 4.2 i~ Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. Page 2 of 2 8/21/2008 1:42 PM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 025AG2.2.36 Loss of RHR System / 4 3.1 4.2 DDDDDDDDDD~ Ability to analyze the effect of mairitenance activities, sLich as degraded power sources, on the status of limiting This is a Generic, no stem statement is conditions of operations associated. 029EA2.09 ATWS /1 4.4 4.5 DDDDDDD~DDD Occurrence of a main turbine/reactor trip Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 / 43.5 / 45.3/45.13) 055EA2.03 Station Blackout / 6 3.9 4.7 DDDDDDD~DDD Actions necessary to restore power Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 / 43.5/ 45.13) 057AG2.2.40 . Loss of Vital AC Inst. Bus / 6 3.4 4.7 DDDDDDDDDD~ Ability to apply technical specifications for a system. This is a Generic, no stem statement is associated. 058AG2.4.20 Loss of DC Power / 6 3.8 4.3 DDDDDDDDDD~ Knowledge of operational implications of EOP warnings, cautions and notes. This is a Generic, no stem statement is associated. 077AA2.10 Generator Voltage and Electric Grid 3.6 3.8 DDDDDDD~DDD Generator overheating and required actions Disturbances / 6 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/45.13) Page 1 of 1 8121/2008 1:43 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 051AA2.02 Loss of Condenser Vacuum 14 3.9 4.1 D D D D D D D ~ D D D Conditions requiring reactor andlor turbine trip Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 1 43.5 1 45.13) 061 AG2.4.41 ARM System Alarms 1 7 2.9 4.6 D D D D D D D D D D ~ Knowledge of the emergency action level thresholds and classifications. This is a Generic, no stem statement is associated. we08EG2.4.47 RCS Overcooling - PTS 14 4.2 4.2 D DOD D D D D D ~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room This is a Generic, no stem statement is reference material. associated. WE13EA2.1 Steam Generator Over-pressure 14 2.9 3.4 0 D DOD 0 D ~ D D 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations. Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.51 45.13) Page 1 of 1 8/21/2008 1:43 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 006A2.13 Emergency Core Cooling 3.9 4.2 0 0 0 0 0 0 0 ~ 0 0 0 Inadvertent SIS actuation Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3 /45.13) 012A2.01 Reactor Protection 3.1 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Faulty bistable operation Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 039A2.02 Main and Reheat Steam 2.4 2.7 DDDDDDD~DDD Decrease in turbine load as it relates to steam escaping from relief valves Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 076G2.4.30 Service Water 2.7 4.1 DDDDDDDDDD~ Knowledge of events related to system operations/status that must be reported to internal'orginizations or outside This is a Generic, no stem statement is agencies. associated. 103G2AA----Containment 4.5 4.7 0 0 0-0-00 0 D~D -0~ --Ability to recognize abnormalindications-for-system---- operating parameters which are entry-level conditions for This is a Generic, no stem statement is emergency and abnormal operating procedures. associated. Page 1 of 1 8/21/2008 1:44 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 002A2.01 Reactor Coolant 4.3 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Loss of coolant inventory Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 1 43.51 45.3/45.13) --- --_._- -- -----~---- .. - -- 034G2.1.23 Fuel Handling Equipment 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to perform specific system and integrated plant procedures during all modes of plant operation. This is a Generic, no stem statement is associated. 068A2.04 Liquid Radwaste 3.3 3.3 0 0 0 0 0 0 ~ 0 0 0 Failure of automatic isolation Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) Page 1 of 1 8/21/2008 1:44 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO G2.1.41 Conduct of operations 2.8 3.7 DOD 0 0 0 0 0 0 0 ~ Knowledge of the refueling processes . G2.2.13 Equipment Control 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of tagging and clearance procedures. G2.2.40 Equipment Control 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability to apply technical specifications for a system. G2.3.12 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 

~ --------------- - - - - - -                                                             ------------------------

G2.4.30 Emergency Procedures/Plans 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies. G2.4.46 Emergency Procedures/Plans 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to verify that the alarms are consistent with the plant conditions. Page 1 of 1 8/21/2008 1:45 PM}}

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