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 Conduct of Operations (JPM-CR-139) KIA G2.1.7 2009a NRC RO A1-1 D,R Perform A Manual Shutdown Margin Calculation Conduct of Operations (JPM-ADM-019) KIA G2.1.25 2009a NRC RO A1-2 M,R Perform Quadrant Power Tilt Ratio Surveillance Equipment Control (JPM-CR-036) KIA G2.2.12 2009a NRC RO A2 D,R Determine TEDE While Working in a High Airborne Area Radiation Control (JPM-ADM-022) KIA G2.3.4 2009a NRC RO A3 (Common) Emergency Procedures/Plan N/A 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 Equipment Control (JPM-CR-036) M,R KIA G2.2.12 2009a NRC SRO A2 Determine TEDE While Working in a High Airborne Area Radiation Control D,R (J PM-ADM-022) 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

c 2009a NRC SRO Admin JPM Summary 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

( (~ c 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. 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 1 B-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 (>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 2 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.

1 1 1 1 1 1 1 0 1 1 1 10 2 1 3 Plant 2 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 I 1 I 2 I 3 I 4 I 7 I Categories 2 2 3 3 1 2 2 2

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. 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 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 ~ooooo 000 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 011 EG2.2.44 Large Break LOCA 1 3 022AK1.03 Loss of Rx Coolant Makeup 1 2 025AG2.4.34 Loss of RHR System 14 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) 4.2 4.4 n 0 0 0 0 0 0 0 0 0 ~ 3 This is a Generic, no stem statement is associated. 3.4 ~ 0 0 0 0 0 0 0 0 0 0 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) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ This is a Generic, no stem statement is associated. 026AA2.04 Loss of Component Cooling Water 18 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 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 FORM ES-401*2 TOPIC: Reactor trip status panel RCS parameters 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 Relationship between charging flow and PZR level Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects The normal values and upper limits for the temperatures of the components cooled by CCW 8/21/2008 1 :39 PM

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

ES-401, REV 9 KA 065AK3.04 077AA1.05 WE04EK2.2 NAME / SAFETY FUNCTION: Loss of Instrument Air 1 8 Generator Voltage and Electric Grid Disturbances 1 6 LOCA Outside Containment 1 3

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

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

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

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

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 007G2.4.31 Pressurizer Relief/Quench Tank 008K3.02 Component Cooling Water 008K4.09 Component Cooling Water 010K2.03 Pressurizer Pressure Control 012A1.01 Reactor Protection 012K5.02 Reactor Protection 013K3.03 Engineered Safety Features Actuation T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.1 D D D D' D D D D D D ~ This is a Generic, no stem statement is associated. 2.9 3.1 D D ~ D D D D D D D D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7 /45.6) 2.7 2.9 D D 0 ~ D D D D D D D Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 2.8 3.0 D ~ D D D D D D D D D Knowledge of electrical power supplies to the foilowing:(CFR: 41.7) 2.9 3.4 D D D D D D ~ D DOD Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5/ 45.5) 3.1 3.3 D D D D ~ D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 4.3 4.7 D D ~ D D D D D D D D 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 FORM ES-401*2 TOPIC: Knowledge of annunciators alarms, indications or response procedures CRDS The "standby" feature for the CCW pumps Indicator for PORV position Trip setpoint adjustment Power density Containment 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 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 KA NAME / SAFETY FUNCTION: OS2K4.03 AC Electrical Distribution 063K2.01 DC Electrical Distribution OS3K3.01 DC Electrical Distribution OS4A3.13 Emergency Diesel Generator OS4KS.OB Emergency Diesel Generator 073A2.01 Process Radiation Monitoring T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 KS A1 A2 A3 A4 G RO SRO 2.B 3.1 0 0 0 ~ 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/ 45.S) 3.0 2.9 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7 /45.5) 3.2 3.3 0 0 0 0 0 ~ 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 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 FORM ES-401*2 TOPIC: Interlocks between automatic bus transfer and breakers Major DC loads ED/G Rpm controller/megawatt load control (breaker-open/ breaker-closed effects) Fuel oil storage tanks Erratic or failed power supply 8I21/200B 1 :41 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 076A3.02 Service Water 078G2.2.44 Instrument Air 103K1.02 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.7 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7 /45.5) 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ This is a Generic, no stem statement is associated. 3.9 4.1 ~ 0 0 0 0 0 0 0 0 0 0 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 FORM ES-401*2 TOPIC: Emergency heat loads 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 Containment isolation/containment integrity 8121/2008 1 :41 PM

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

ES*401, REV 9 KA NAME / SAFETY FUNCTION: 071K4.04 Waste Gas Disposal 079K1.01 Station Air T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.4 D D D ~ D D D D D D D Knowledge of (SYSTEM) design feature{s) and or interlock{s) which provide for the foliowing:{CFR: 41.7) 3.0 3.1 ~ D D D D D D D D D D 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) FORM ES-401*2 TOPIC: Isolation of waste gas release tanks lAS 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 KA NAME I SAFETY FUNCTION: G2.1.30 Conduct of operations G2.1.44 Conduct of operations G2.2.20 Equipment Control G2.2.25 Equipment Control G2.3.11 Radiation Control G2.3.5 Radiation Control G2.3.7 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.00 0 0 0 0 0 0 0 0 0 ~ 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~ 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ 2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~ 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~ Page 1 of 2 FORM ES-401-2 TOPIC: Ability to locate and operate components, including local controls. Knowledge of RO duties in the control room during fuel handling. Knowledge of the process for managing troubleshooting activities. __. ____ ~ ___._... _0. _____ - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Ability to control radiation releases. Ability to use radiation monitoring systems Ability to comply with radiation work permit requirements during normal or abnormal conditions 8/21/2008 1 :42 PM

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

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

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

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

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 002A2.01 Reactor Coolant

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034G2.1.23 Fuel Handling Equipment 068A2.04 Liquid Radwaste SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.4 0 0 0 0 0 0 0 ~ 0 0 0 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) 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~ This is a Generic, no stem statement is associated. 3.3 3.3 0 0 0 0 0 0 ~ 0 0 0 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 FORM ES-401-2 TOPIC: Loss of coolant inventory Ability to perform specific system and integrated plant procedures during all modes of plant operation. Failure of automatic isolation 8/21/2008 1 :44 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: G2.1.41 Conduct of operations . G2.2.13 Equipment Control G2.2.40 Equipment Control G2.3.12 Radiation Control G2.3.14 Radiation Control SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 DOD 0 0 0 0 0 0 0 ~ 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~ 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~ 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ FORM ES-401-2 TOPIC: Knowledge of the refueling processes Knowledge of tagging and clearance procedures. Ability to apply technical specifications for a system. Knowledge of radiological safety principles pertaining to licensed operator duties 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 ~ Page 1 of 1 Ability to verify that the alarms are consistent with the plant conditions. 8/21/2008 1:45 PM}}

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