ML092400597

McGuire Initial Exam 2009-301 Draft Administrative Documents Region Ii/Drs/Operator Licensing Branch/Initial Examinations/Mcguire/Exam 2009-301

ML092400597
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/26/2009
From:	NRC/RGN-II/DRS/OLB
To:	Duke Energy Carolinas
References
50-369/09-301, 50-370/09-301
Download: ML092400597 (30)

Text

FACILITY NAME: McGuire Nulear Plant Section 1 REPORTNUMBER:

____

____ _ DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

ci Draft Written Exam sample plan (ES-401-1/2) ct.Draft Administrative Topics Outline (ES-301-1)

[i'Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)

Location of Electronic Files: Submitted By: ----->0,,+--

______ _ VerifiedBy1J!J L xL (j FACILITY NAME: McGuire Nulear Plant Section *1 REPORTNUMBER:

____

____ _ DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

ci Draft Written Exam sample plan (ES-401-1/2)

[1, Draft Administrative Topics Outline (ES-301-1)

[i' Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)

Location of Electronic Files: Submitted By: ----'-<+--

______ _

ES-301 Facility:

McGuire Examination Level: Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Emergency Procedures/Plan Administrative Topics Outline Draft Form ES-301-1 Date of Examination:

5/11/09 RO Operating Test Number: N09-1 Type Code* Describe activity to be performed 2.1.25 (3.9) Ability to interpret reference materials, such M,R as graphs, curves, tables, etc. JPM: Determine Boric Acid Addition to FWST 2.1.7(4.4)

Ability to evaluate plant performance and make operational judgments based on M,R operating characteristics, reactor behavior, and instrument interpretation.

JPM: Calculate QPTR 2.2.44 (4.2) Ability to interpret control room indications to verify the status and operation of a system, and understand how operator N,S actions and directives affect plant and system conditions.

JPM: Perform Daily Surveillance Items Checklist 2.4.39 (3.9) Knowledge of RO responsibilities in D,S emergency plan implementation.

JPM: Conduct a Site Assembly NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (2) or Class(R)oom (2) (D)irect from bank (:5: 3 for ROs; :5: 4 for SROs & RO retakes) (1) (N)ew or (M)odified from bank (:: 1) (3) (P)revious 2 exams (:5: 1; randomly selected)

(0) NUREG-1 021, Revision 9 ( ES-301 Facility:

McGuire Examination Level: Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Emergency Procedures/Plan Administrative Topics Outline Draft Form ES-301-1 Date of Examination:

5/11/09 RO Operating Test Number: N09-1 Type Code* Describe activity to be performed 2.1.25 (3.9) Ability to interpret reference materials, such M,R as graphs, curves, tables, etc. jPM: Determine Boric Acid Addition to FWST 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on M,R operating characteristics, reactor behavior, and instrument interpretation.

jPM: Calculate QPTR 2.2.44 (4.2) Ability to interpret control room indications to verify the status and operation of a system, and understand how operator N,S actions and directives affect plant and system conditions.

jPM: Perform Daily Surveillance Items Checklist 2.4.39 (3.9) Knowledge of RO responsibilities in D,S emergency plan implementation.

jPM: Conduct a Site Assembly NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

'Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (2) or Class(R)oom (2) (D)irect from bank (::; 3 for ROs;::; 4 for SROs & RO retakes) (1) (N)ew or (M)odified from bank (?: 1) (3) (P)revious 2 exams (::; 1; randomly selected)

(0) NUREG-1 021, Revision 9 ES-301 Administrative Topics Outline Draft RO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A162001014, "Refueling Water System" is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480" using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/1/A162001014, "Refueling Water System." The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST as 7,912 gallons +/- 372 gallons. A1b This is a modified JPM using bank JPM ADM-NRC-A1-004 as its basis. With the plant at 100% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/1/A146001021A, Loss of Operator Aid Computer while in Mode 1. The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/1/A14600/21A Loss of Operator Aid Computer while in Mode 1. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4, Quadrant Power Tilt Ratio, has been exceeded.

A2 This is a new JPM. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, and provided with a just completed portion of PT/1/A146001003B, "Daily Surveillance Items," that reflects those items NOT simulated.

The operator will be directed to perform Enclosure 13.1, Daily Surveillance Items Checklist in accordance with PT/1/A146001003B.

The operator will be required to identify four items on the Checklist that do not meet the identified acceptance criteria, and one item that requires CRSRO notification.

A4 This is bank JPM ADM-NRC-A4-005.

The operator will told that Unit 1 was at 100% power when it experienced a loss of electrical power, that an ALERT has been declared, and that a Site Assembly is required.

The operator will be directed to conduct a Site Assembly in accordance with Step 1 of Enclosure 4.3, OSM Actions for Site Assembly, of RP/OIAl57001011, "Conducting a Site Assembly, Site Evacuation or Containment Evacuation." The operator will be expected to inform the Security Department that a Site Assembly is being performed, determine whether or not the Card Reader System is functioning properly, turn the Outside Page Speakers on and off, operate the Site Assembly alarm, make announcements pertinent to a Site Assembly, and direct the Security Department to ensure that the Site Assembly is thorough.

NUREG-1 021, Revision 9 ( ( ( ES-301 A1a A1b Administrative Topics Outline Draft RO Admin JPM Summary Form ES-301-1 This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/6200/014, "Refueling Water System" is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480" using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/1/A/6200/014, "Refueling Water System." The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST as 7,912 gallons +/- 372 gallons. This is a modified JPM using bank JPM ADM-NRC-A 1-004 as its basis. With the plant at 100% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/1/A/4600/021A, Loss of Operator Aid Computer while in Mode 1. The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/1/A/4600/21A Loss of Operator Aid Computer while in Mode 1. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4, Quadrant Power Tilt Ratio, has been exceeded.

A2 This is a new JPM. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, and provided with a just completed portion of PT/1/A/4600/003B, "Daily Surveillance Items," that reflects those items NOT simulated.

The operator will be directed to perform Enclosure 13.1, Daily Surveillance Items Checklist in accordance with PT/1/A/4600/003B.

The operator will be required to identify four items on the Checklist that do not meet the identified acceptance criteria, and one item that requires CRSRO notification.

A4 This is bank JPM ADM-NRC-A4-005.

The operator will told that Unit 1 was at 100% power when it experienced a loss of electrical power, that an ALERT has been declared, and that a Site Assembly is required.

The operator will be directed to conduct a Site Assembly in accordance with Step 1 of Enclosure 4.3, OSM Actions for Site Assembly, of RP/0/A/5700/011, "Conducting a Site Assembly, Site Evacuation or Containment Evacuation." The operator will be expected to inform the Security Department that a Site Assembly is being performed, determine whether or not the Card Reader System is functioning properly, turn the Outside Page Speakers on and off, operate the Site Assembly alarm, make announcements pertinent to a Site Assembly, and direct the Security Department to ensure that the Site Assembly is thorough.

NUREG-1 021, Revision 9 ES-301 *"'" ',' TAdministrative Topics Outline ,:, ' i!l"'" Draft , ..... k g/ :4Im Form ES-301-1 Facility:

McGuire Date of Examination:

5/11/09 Examination Level: SRO Operating Test Number: N09-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2,1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc. JPM: Determine Boric Acid Addition to FWST 2.1.5 (3.9) Ability to use procedures related to shift Conduct of Operations staffing, such as minimum compliment N,R overtime limitations, etc. JPM: Determine Proper Shift Staffing 2.2.42 (4.6) Ability to recognize system parameters that Equipment Control are entry level conditions for Technical N,R Specifications.

JPM: Perform Daily Surveillance Items Checklist 2.3.6 (3.8) Ability to approve release permits. Radiation Control M,R JPM: Approve a Gaseous Waste Release Permit 2.4.41 (4.6) Knowledge of emergency action level Emergency thresholds and classifications.

Procedures/Plan N,R JPM: Classify an Emergency Event NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5) (D)irect from bank (=::; 3 for ROs; =::; 4 for SROs & RO retakes) (0) (N)ew or (M)odified from bank <==. 1) (5) (P)revious 2 exams (=::; 1; randomly selected)

(0) DRAFT NUREG-1 021, Revision 9 ES-301 Form ES-301-1 Facility:

McGuire Date of Examination:

5/11/09 Examination Level: SRO Operating Test Number: N09-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations M,R as graphs, curves, tables, etc. JPM: Determine Boric Acid Addition to FWST 2.1.5 (3.9) Ability to use procedures related to shift Conduct of Operations staffing, such as minimum compliment N,R overtime limitations, etc. JPM: Determine Proper Shift Staffing 2.2.42 (4.6) Ability to recognize system parameters that Equipment Control are entry level conditions for Technical N,R Specifications.

JPM: Perform Daily Surveillance Items Checklist 2.3.6 (3.8) Ability to approve release permits. Radiation Control M,R ( JPM: Approve a Gaseous Waste Release Permit 2.4.41 (4.6) Knowledge of emergency action level Emergency thresholds and classifications.

Procedures/Plan N,R JPM: Classify an Emergency Event NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5) (D)irect from bank (:0; 3 for ROs; :0; 4 for SROs & RO retakes) (0) (N)ew or (M)odified from bank 1) (5) (P)revious 2 exams (:0; 1; randomly selected)

(0) DRAFT NUREG-1 021, Revision 9 ES-301 Administrative Topics Outline Draft SRO Admin JPM Summary Form ES-301-1 A 1 a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A162001014, "Refueling Water System" is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Separate Verification of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480" using the RHT. The operator will discover two errors within the RO's calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION. The operator will be required to identify that ACTION C is applicable after one hour. A 1 b This is a new JPM that combines elements of two bank JPMs, ADM-NRC-A 1-001 and ADM-NRC-A1-010.

The operator will be told that Units 1 and 2 are at 100% power and that it is a specific time and date. The operator will be provided with a Work Schedule of personnel that are reporting for work, and told that three individuals have expressed concerns regarding overtime limitations, and present their recent work history. After being provided a work history for those that have expressed concerns, the operator will be directed to evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.

The operator will directed to identify any arriving personnel that cannot be assigned to a shift position; and to hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met. The operator will be expected to evaluate the work history of three individuals in accordance with section 200.6 of NSD 200, and determine that one RO cannot report for work, however, the other individuals with work history concerns may report for work. The operator will also be expected to assign all other personnel reporting to work in accordance with an attached Key, identifying that that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.

A2 This is a new JPM. The operator will be provided with a completed Enclosure 13.1, "Daily Surveillance Items Checklist" of PT/1/A146001003B, as well as a completed Enclosure 13.2, "NAC-UMS Cask Monitoring" of PT/1/A146001003B and directed to evaluate the completed Enclosures in accordance with PT/1/A146001003B, and identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken. The operator will need to evaluate the four discrepancies discovered against the Technical NUREG-1021, Revision 9 ( ( ( ES-301 A1a Administrative Topics Outline Draft SRO Admin JPM Summary Form ES-301-1 This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A/62001014, "Refueling Water System" is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Separate Verification of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480" using the RHT. The operator will discover two errors within the RO's calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION. The operator will be required to identify that ACTION C is applicable after one hour. A 1 b This is a new JPM that combines elements of two bank JPMs, ADM-NRC-A 1-001 and ADM-NRC-A1-010.

The operator will be told that Units 1 and 2 are at 100% power and that it is a specific time and date. The operator will be provided with a Work Schedule of personnel that are reporting for work, and told that three individuals have expressed concerns regarding overtime limitations, and present their recent work history. After being provided a work history for those that have expressed concerns, the operator will be directed to evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.

The operator will directed to identify any arriving personnel that cannot be assigned to a shift position; and to hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met. The operator will be expected to evaluate the work history of three individuals in accordance with section 200.6 of NSD 200, and determine that one RO cannot report for work, however, the other individuals with work history concerns may report for work. The operator will also be expected to assign all other personnel reporting to work in accordance with an attached Key, identifying that that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.

A2 This is a new JPM. The operator will be provided with a completed Enclosure 13.1, "Daily Surveillance Items Checklist" of PT/1/A/46001003B, as well as a completed Enclosure 13.2, "NAC-UMS Cask Monitoring" of PT/1/A/46001003B and directed to evaluate the completed Enclosures in accordance with PT/1/A/46001003B, and identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken. The operator will need to evaluate the four discrepancies discovered against the Technical NUREG-1 021, Revision 9 ES-301 Administrative Topics Outline Draft Form ES-301-1 Specifications and Selected Licensee Commitments, and identify all required actions. A3 This is a modified JPM using bank JPM ADM-NRC-A3-001 as its basis. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, that OP/O/A/62001019, Enclosure 4.1, Waste Gas Decay Tank Release to Unit Vent, is in progress in preparation for release of the C WGDT, and completed through Step 3.11, and that RP has just delivered the GWR package # 2009010 to the Control Room. The operator will be directed to review and approve GWR Package # 2009010 for the C Waste Gas Decay Tank by performing Step 3.12 of Enclosure 4.1 of OP/O/A/62001019, Waste Gas Decay Tank Release. The operator will be expected to discover three errors in the submitted release package, and delay approval of the package until the errors are corrected.

A4 This is a new JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where each procedure identifies a need to address RP/O/A/57001000, Classification of Emergency.

The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, the Unusual Event is updated at the second procedure direction, and that a Site Area Emergency exists upon entry into the EOP network. NUREG-1 021, Revision 9 ( ( ES-301 A3 A4 Administrative Topics Outline Draft Form ES-301-1 Specifications and Selected Licensee Commitments, and identify all required actions. This is a modified JPM using bank JPM ADM-NRC-A3-001 as its basis. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, that OP/O/A/6200/019, Enclosure 4.1, Waste Gas Decay Tank Release to Unit Vent, is in progress in preparation for release of the C WGDT, and completed through Step 3.11, and that RP has just delivered the GWR package # 2009010 to the Control Room. The operator will be directed to review and approve GWR Package # 2009010 for the C Waste Gas Decay Tank by performing Step 3.12 of Enclosure 4.1 of OP/O/A/6200/019, Waste Gas Decay Tank Release. The operator will be expected to discover three errors in the submitted release package, and delay approval of the package until the errors are corrected.

This is a new JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where each procedure identifies a need to address RP/O/A/5700/000, Classification of Emergency.

The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, the Unusual Event is updated at the second procedure direction, and that a Site Area Emergency exists upon entry into the EOP network. NUREG-1 021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Draft Form ES-301-2 Facility:

McGuire Date of Examination:

5/11/09 Exam Level one): RO (only) / SRO(I) I SRO (U) Operating Test No.: N09-1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. 004 Chemical and Volume Control System S,D,A 1 Emergency Borate the Reactor Coolant System Using the PO Pump b. 006 Emergency Core Cooling System S,D,A,EN 2 Align the ND, NI, and NV Systems to Cold Leg Recirculation

c. 010 Pressurizer Pressure Control System S,D,L 3 Place L TOP in Service d. 059 Main Feedwater System S,D 4S Establish Feedwater Flow to the SIG's Following a Reactor Trip e. 028 Hydrogen Recombiner and Purge Control System S,N,EN 5 Manually Align Phase B HVAC Equipment

f. 064 Emergency Diesel Generators S,N,A 6 Perform Diesel Generator Operability Test g. 015 Nuclear Instrumentation System S,D,A 7 Restore Repaired Power Range Channel to Service h. 008 Component Cooling Water System S,D 8 Place Standby Component Cooling Train in Operation In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i. APE 054 Loss of Main Feedwater Reset Unit 2 Turbine Driven CA Pump Stop Valve per Generic D,R,E 4S Enclosure 24 j. APE 065 Steam Loss of Instrument Air D,A,E 8 Aligning Nitrogen To Supply Control Air to D, E and F VI Compressors

k. APE 058 Loss of DC Power D,R,E 6 Swap Battery Charger EVCA Power Supply from Unit 1 to Unit 2 NUREG-1 021, Revision 9 ( ES-301 Control Room/In-Plant Systems Outline Draft Form ES-301-2 Facility:

McGuire Date of Examination:

5/11/09 Exam Level (ciTde one): RO (only) 1 SRO(I) I SRO (U) Operating Test No.: N09-1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code' Safety Function a. 004 Chemical and Volume Control System S,D,A 1 Emergency Borate the Reactor Coolant System Using the PD Pump b. 006 Emergency Core Cooling System S,D,A,EN 2 Align the ND, NI, and NV Systems to Cold Leg Recirculation

c. 010 Pressurizer Pressure Control System S,D,L 3 Place L TOP in Service d. 059 Main Feedwater System S,D 4S Establish Feedwater Flow to the SIG's Following a Reactor Trip e. 028 Hydrogen Recombiner and Purge Control System S,N,EN 5 Manually Align Phase B HVAC Equipment

f. 064 Emergency Diesel Generators S,N,A 6 Perform Diesel Generator Operability Test g. 015 Nuclear Instrumentation System S,D,A 7 Restore Repaired Power Range Channel to Service h. 008 Component Cooling Water System S,D 8 Place Standby Component Cooling Train in Operation In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i. APE 054 Loss of Main Feedwater Reset Unit 2 Turbine Driven CA Pump Stop Valve per Generic D,R,E 45 Enclosure 24 j. APE 065 Steam Loss of Instrument Air D,A,E 8 Aligning Nitrogen To Supply Control Air to D, E and F VI Compressors

k. APE 058 Loss of DC Power D,R,E 6 Swap Battery Charger EVCA Power Supply from Unit 1 to Unit 2 NUREG-1021, Revision 9

( ES-301 Control Room/ln-Plant Systems Outline Draft Form ES-301-2 @ 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 I SRO-II SRO-U (A)lternate path 4-6 (5) 14-6 (5) 12-3 (3) (C)ontrol room (D)irect from bank 9 (9) 1:0: 8 (8) I ::: 4 (4) (E)mergency or abnormal in-plant 1 (3) I: 1 (3) I 1 (2) (EN)gineered Safety Feature I I 1 (1) (Control Room System) (L)ow-Power I Shutdown 1 (1)/:1 (1)1 1 (1) (N)ew or (M)odified from bank including 1 (A) 2 (2) I 2 (2) I 1 (1) (P)revious 2 exams 3 (0) I 3 (0)1 2 (0) (Randomly Selected) (R)CA 1 (2 )/;.: 1 (2) I 1 (1) (S)imulator JPM Summary JPM A This is bank JPM PS-NV-200A.

The operator will be told that Unit 1 was at 100% power with "A" NV pump tagged for maintenance, when a failure of an automatic reactor trip occurred causing entry into EP/1/N5000/FR-S.1, Response to Nuclear Power Generation/A TWS. The operator will be directed to emergency borate the NC System per Step 5 of EP/1/N5000/FR-S.1.

During the course of the procedure implementation the operator will discover that the "B" NV Pump has tripped (Alternate Path). The operator will be expected to place the PD pump in service in accordance with EP/1/N5000/G-1, Generic Enclosures, Enclosure 17, PD Pump Startup, and complete the emergency boration.

JPM B This is Bank JPM-ECC-NI-116A.

The Operator will be placed in a post-Large Break LOCA situation at Unit 1 with the FWST trending toward Cold Leg Recirculation Switchover Criteria.

The operator will be told that the unit is presently implementing EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant. The operator will be asked to monitor FWST level and perform transfer to Cold Leg Recirculation at the appropriate time. During the transfer to Cold Leg Recirculation in accordance with EP/1/N5000/ES-1.3, Transfer to Cold Leg Recirculation, 1 NI-184B, RB Sump to Train B ND & NS, will fail to open, and the B ND Pump will need to be stopped (Alternate Path). The operator will place the A Train of ND, NI and NV on Cold Leg Recirculation.

JPM C This is a bank JPM. The Operator will be placed in a situation in which Unit 1 IS In a cooldown and depressurization in accordance with OP/1/N6100/SD-4, "Cooldown to 240 Degrees F." The operator will be told that the 1A and 1 B NCPs are operating, that NC System pressure is 340 psig and NC System temperature is 306-312°F.

The operator will be asked to Place the L TOP System in operation in accordance with Enclosure 4.1 of OP/1/N61 00/SO-1 0, "Controlling Procedure for L TOP Operation," and monitor for proper operation.

JPM D This is bank JPM CF-CF-036.

The operator will be told that Unit 1 has experienced a Reactor Trip, that EP/1/N5000/ES-0.1, "Reactor Trip Response," has been completed through step 11, total feed flow to S/G's is < 450 gpm, that no CA Pumps are running or available, and that CF Isolation has not occurred.

The operator will be directed to place NUREG-1021, Revision 9 ( ( ES-301 Control Room/ln-Plant Systems Outline Draft Form ES-301-2 @ 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 I SRO-II SRO-U (A)lternate path 4-6 (5) 14-6 (5) 12-3 (3) (C)ontrol room (D)irect from bank 9 (9) h; 8 (8) I::: 4 (4) (E)mergency or abnormal in-plant 1 (3) I: 1 (3) I?:: 1 (2) (EN)gineered Safety Feature I I:: 1 (1) (Control Room System) (L)ow-Power I Shutdown 1(1)/>1(1)1 1 (1) (N)ew or (M)odified from bank including 1 (A) > 2 (2) I > 2 (2) I ** ** 1 (1) (P)revious 2 exams < 3 (0) I < 3 (0)1 <; 2 (0) (Randomly Selected) (R)CA > 1 (2 )/> 1 (2) I 1 (1) (S)imulator JPM Summary JPM A This is bank JPM PS-NV-200A.

The operator will be told that Unit 1 was at 100% power with "A" NV pump tagged for maintenance, when a failure of an automatic reactor trip occurred causing entry into EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/A TWS. The operator will be directed to emergency borate the NC System per Step 5 of EP/1/A/5000/FR-S.1.

During the course of the procedure implementation the operator will discover that the "B" NV Pump has tripped (Alternate Path). The operator will be expected to place the PD pump in service in accordance with EP/1/A/5000/G-1, Generic Enclosures, Enclosure 17, PD Pump Startup, and complete the emergency boration.

JPM B This is Bank JPM-ECC-NI-116A.

The Operator will be placed in a post-Large Break LOCA situation at Unit 1 with the FWST trending toward Cold Leg Recirculation Switchover Criteria.

The operator will be told that the unit is presently implementing EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant. The operator will be asked to monitor FWST level and perform transfer to Cold Leg Recirculation at the appropriate time. During the transfer to Cold Leg Recirculation in accordance with EP/1/A/5000/ES-1.3, Transfer to Cold Leg Recirculation, 1 NI-184B, RB Sump to Train B ND & NS, will fail to open, and the B ND Pump will need to be stopped (Alternate Path). The operator will place the A Train of ND, NI and NV on Cold Leg Recirculation.

JPM C This is a bank JPM. The Operator will be placed in a situation in which Unit 1 IS In a cooldown and depressurization in accordance with OP/1/A/6100/SD-4, "Cooldown to 240 Degrees F." The operator will be told that the 1A and 1 B NCPs are operating, that NC System pressure is 340 psig and NC System temperature is 306-312°F.

The operator will be asked to Place the L TOP System in operation in accordance with Enclosure 4.1 of OP/1/A/61 00/SO-1 0, "Controlling Procedure for L TOP Operation," and monitor for proper operation.

JPM D This is bank JPM CF-CF-036.

The operator will be told that Unit 1 has experienced a Reactor Trip, that EP/1/A/5000/ES-0.1, "Reactor Trip Response," has been completed through step 11, total feed flow to S/G's is < 450 gpm, that no CA Pumps are running or available, and that CF Isolation has not occurred.

The operator will be directed to place NUREG-1 021, Revision 9

( ES-301 Control Room/In-Plant Systems Outline Draft Form ES-301-2 the 1A CF Pump in service, and establish CF to the S/G's in accordance with Enclosure 4 of EP/1/A/SOOO/ES-0.1.

The operator will be expected to place the 1A CF Pump in service and provide feedwater flow to all four S/G's. The operator will be told that if, as expected, a Red Path occurs on Heat Sink, to continue with the assigned task. JPM E This is a new JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, "Phase B HVAC Equipment," of EP/1/A/SOOO/E-0, "Reactor Trip or Safety Injection." During the performance of Enclosure 2, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems. JPM F This is a new JPM. The operator will be told that Unit 1 is operating at 100% power, that a monthly test of the 1 B Emergency Diesel Generator is required, and that the System Engineer wants to start and stop the Diesel from the Control Room. The operator will be directed to conduct a Slow Start of the 1 B Emergency Diesel Generator using Enclosure-13.1 of PT/1/A/43S0/002B, "Diesel Generator 1 B Operability Test." During the performance of Enclosure 13.1, a sudden loss of crankcase vacuum will be indicated together with a loss of engine speed (Alternate Path). The operator will be expected to stop the engine with the normal stop switch. JPM G This is a bank JPM. The Operator will be placed in a situation with Unit 1 at 100% power. The operator will be told that Power Range Channel N43 has previously failed high, and that the channel has been defeated in accordance with AP/1/A/SSOO/16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." The operator will be asked to restore Power Range Channel N43 to service in accordance with Step 22 of AP16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." During the restoration, N43 will fail a second time, rendering this an Alternate Path JPM. The operator will be required to use, an Annunciator Response/Abnormal Response Procedure and place Rod Control manual. JPM H This is bank JPM PSS-KC-029.

The operator will be told that Unit 1 is in a post-trip situation with "A" train RN and KC in service, and that 1A 1 KC pump has tripped on overcurrent and will not restart. The crew has implemented AP/1/A/SSOO/21, "Loss of KC or KC System Leakage," and has completed step 8. The operator will be directed to start the standby KC train starting at Step 9 of AP/1/A/SSOO/21.

The operator will be expected to place the B Train of KC in service, and place the A Train of KC in standby. JPM I This is Bank JPM CF-CA-248.

The Operator will be told that the Unit 2 reactor has tripped due to a loss of all offsite power, that 2ETA and 2ETB are deenergized, that the crew has entered EP/2/A/SOOO/ECA-0.0, "Loss of All AC Power," and that the "TD CA PUMP STOP VLV NOT OPEN" alarm (2AD-S, F-3) is lit. The operator will be directed to reset the stop valve PER EP/2/A/SOOO/G-1, "Generic Enclosures," Enclosure 24, "Resetting TD CA Stop Valve." The operator will be expected to reset 2SA-3 in accordance with Generic Enclosure

24. JPM J This is bank JPM SS-VI-110A.

The operator will be told that a total loss of VI has occurred.

The operator will be directed to perform AP/1/A/SSOO/22, "Loss of VI, Enclosure 6, "D, E, and F VI Compressor Operation With Low Control Air." During the implementation of Enclosure 6, the operator will discover that the Breathing Air (VB) NUREG-1 021, Revision 9 ( ( ES-301 Control Room/ln-Plant Systems Outline Draft Form ES-301-2 the 1A CF Pump in service, and establish CF to the S/G's in accordance with Enclosure 4 of EP/1/A/5000/ES-0.1.

The operator will be expected to place the 1A CF Pump in service and provide feedwater flow to all four S/G's. The operator will be told that if, as expected, a Red Path occurs on Heat Sink, to continue with the assigned task. JPM E This is a new JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, "Phase B HVAC Equipment," of EP/1/A/5000/E-0, "Reactor Trip or Safety Injection." During the performance of Enclosure 2, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems. JPM F This is a new JPM. The operator will be told that Unit 1 is operating at 100% power, that a monthly test of the 1 B Emergency Diesel Generator is required, and that the System Engineer wants to start and stop the Diesel from the Control Room. The operator will be directed to conduct a Slow Start of the 1 B Emergency Diesel Generator using Enclosure-13.1 of PT/1/A/43501002B, "Diesel Generator 1 B Operability Test." During the performance of Enclosure 13.1, a sudden loss of crankcase vacuum will be indicated together with a loss of engine speed (Alternate Path). The operator will be expected to stop the engine with the normal stop switch. JPM G This is a bank JPM. The Operator will be placed in a situation with Unit 1 at 100% power. The operator will be told that Power Range Channel N43 has previously failed high, and that the channel has been defeated in accordance with AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." The operator will be asked to restore Power Range Channel N43 to service in accordance with Step 22 of AP16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." During the restoration, N43 will fail a second time, rendering this an Alternate Path JPM. The operator will be required to use, an Annunciator Response/Abnormal Response Procedure and place Rod Control manual. JPM H This is bank JPM PSS-KC-029.

The operator will be told that Unit 1 is in a post-trip situation with "A" train RN and KC in service, and that 1A 1 KC pump has tripped on overcurrent and will not restart. The crew has implemented AP/1/A/5500/21 , "Loss of KC or KC System Leakage," and has completed step 8. The operator will be directed to start the standby KC train starting at Step 9 of AP/1/A/5500/21.

The operator will be expected to place the B Train of KC in service, and place the A Train of KC in standby. JPM I This is Bank JPM CF-CA-248.

The Operator will be told that the Unit 2 reactor has tripped due to a loss of all offsite power, that 2ETA and 2ETB are deenergized, that the crew has entered EP/2/A/5000/ECA-0.0, "Loss of All AC Power," and that the "TD CA PUMP STOP VLV NOT OPEN" alarm (2AD-5, F-3) is lit. The operator will be directed to reset the stop valve PER EP/2/A/5000/G-1, "Generic Enclosures," Enclosure 24, "Resetting TD CA Stop Valve." The operator will be expected to reset 2SA-3 in accordance with Generic Enclosure

24. JPM J This is bank JPM SS-VI-110A.

The operator will be told that a total loss of VI has occurred.

The operator will be directed to perform AP/1/A/5500/22, "Loss of VI, Enclosure 6, "D, E, and F VI Compressor Operation With Low Control Air." During the implementation of Enclosure 6, the operator will discover that the Breathing Air (VB) NUREG-1021, Revision 9 ES-301 Control Room/ln-Plant Systems Outline Draft Form ES-301-2 Compressors are tripped, and that another strategy will need to be implemented to restore VI System pressure (Alternate Path). The operator will be expected to align Nitrogen from backup cylinders to D, E, and F VI compressors with pressure set between 90-100 psig. JPM K This is bank JPM EL-EPL-166T.

The operator will be told that Unit 1 has just experienced a Loss of Offsite Power, that the 1A DIG will not start, and that 1 ETA is energized.

AP/1/A/5500107, "Loss of Electrical Power," Case 1 has been implemented.

The operator will be directed to swap power supplies to the EVCA Battery Charger from Unit 1 to Unit 2 in accordance with AP/1/A/5500107, "Loss of Electrical Power," Enclosure 22, Swapping Battery Charger Power Supplies." The operator will be expected to place Battery Charger EVCA in service with power being supplied from Unit 2 within 20 minutes of dispatch.

This is a Time Critical JPM. NUREG-1021, Revision 9 ( ( ( ES-301 Control Room/ln-Plant Systems Outline Draft Form ES-301-2 Compressors are tripped, and that another strategy will need to be implemented to restore VI System pressure (Alternate Path). The operator will be expected to align Nitrogen from backup cylinders to D, E, and F VI compressors with pressure set between 90-100 psig. JPM K This is bank JPM EL-EPL-166T.

The operator will be told that Unit 1 has just experienced a Loss of Offsite Power, that the 1A DIG will not start, and that 1 ETA is energized.

AP/1/A/5500107, "Loss of Electrical Power," Case 1 has been implemented.

The operator will be directed to swap power supplies to the EVCA Battery Charger from Unit 1 to Unit 2 in accordance with AP/1/A/5500107, "Loss of Electrical Power," Enclosure 22, Swapping Battery Charger Power Supplies." The operator will be expected to place Battery Charger EVCA in service with power being supplied from Unit 2 within 20 minutes of dispatch.

This is a Time Critical JPM. NUREG-1 021, Revision 9

ES-401, Rev. 9 PWR Examination Outline Form ES-401*2 Facility:

&u. l..!:'--oate of Exam: --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 1 2 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 5 5 5 4 4 27 5 5 10 1 2 3 4 2 3 1 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 3 4 5 3 4 2 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 3 3 2 2 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 (Le., except"for one category in Tier 3 ofthe 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 outline; systems or evolutions that do not apply at the facility should be deleted and justified; 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 KIAs 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 t and 2 from the shaded systems and KIA categories.

7. *The generic (G) KIAs 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. S. 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 a"pply). 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 KIAs that are linked to 10 CFR 55.43. Ir/z/zOOilP .

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:

1Vf.c, l!t---Date of Exam: --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 1 2 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 5 5 5 4 4 27 5 5 10 1 2 3 4 2 3 1 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 3 4 5 3 4 2 4 2 4 3 4 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 1. 2. 3. 4. 5. 6. 7. 8. 9. Categories 3 3 2 2 1 2 2 2 Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (Le., 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). 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems 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.

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.

Absent a plant-specific priority, only those KIAs 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

• The generic (G) KIAs 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. 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. 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 KIAs that are linked to 10 CFR 55.43.

DRAFT 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 / 007EK1.06 Reactor Trip -Stabilization

-Recovery 3.7 4.1 D D D D D, D D D D D Relationship of emergency feedwater flow to SIG and 11 decay heat removal following reactor trip Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.8 to 41.10 145.3) 008AK3.05 Pressurizer Vapor Space Accident 1 3 4 4.5 D D D D D D D D D D 009EK3.21 Small Break LOCA 1 3 011 EK3.11 Large Break LOCA 1 3 3.14 015AA2.11 RCP Malfunctions 1 4 022AK1.03 Loss of Rx Coolant Makeup 1 2 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5 1 41.101 45.6/45.13) 4.2 4.5 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:

41.5/41.10/45.61 45.13) 3.3 3.4 D D D D D D D D D D 4 1 14' "7 Knowledge of the reasons for the following . . [; responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10 1 45.61 45.13) 3.4 3.8 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:

41.10/43.51 45.13) 3 3.4 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10 145.3) Page 1 of3 ECCS termination or throttling criteria .,/ Actions contained in EOP for small break LOCAlleak v / 4> .' , . --Rep

't2EQu l retUe0 ( t' When to jog RCPs during ICC,\ . ( r fIO.dequq,k G fe

/' Relationship between charging flow and PZR level ,/ 9/23/2008 4:38 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 /

007EK1.06 008AK3.05 Reactor Trip -Stabilization

-Recovery 3.7 4.1 0 0 0 0 0 0 0 0 0 0 Relationship of emergency feedwater flow to S/G and 11 decay heat removal following reactor trip 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)

Pressurizer Vapor Space Accident 13 4 4.5 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5 141.101 45.6/45.13)

ECCS termination or throttling criteria 009EK3.21 Small Break LOCA 13 4.2 4.5 0 0 0 0 0 0 0 0 0 0 Actions contained in EOP for small break LOCAIleak 011EK3.11 Large Break LOCA 1 3 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.61 45.13) 3.3 3.4 0 0 0 0 0 0 0 0 0 0 4114 7 Knowledge of the reasons for the following . . V responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5 1 41.10/45.61 45.13) NC and PC t? Rep 'T£(ppi tJ<l r' Ability to determine and interpret the ( . rlnO . i. f' C' t' ) 022AK1.03 Loss of Rx Coolant Makeup 1 2 3 l ,(;tc'"' jlJ'trf..

LP(e: following as they apply to ABNORMAL J PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 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)

Page 1 of 3 Relationship between charging flow and PZR level 9/23/2008 4:38 PM /

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025AK2.01 Loss of RHR System 14 029EA2.10 ATWS/1 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 2.9 2.9 D D D D D D D D D D 3.1 3.4 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) t 5 0 2/3.3 EA 2.ot Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10 I 43.5 I 45.13) 040AG2.1.31 Steam Line Rupture -Excessive Heat Transfer 14 054AA1.04 Loss of Main Feedwater I 4 055EK2.04 Station Blackout I 6 056AG2.4.35 Loss of Off-site Power /6 057AA2.09 Loss of Vital AC Inst. Bus 16 4.6 4.3 D D D D D D D D D D 4.4 4.5 3.8 4.0 This is a Generic, no stem statement is associated.

Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7 I 45.5 I 45.6)

Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7 I 45.7 I 45.8)

This is a Generic, no stem statement is associated.

3.1 3.4 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:

41.10 143.5 I 45.13) Page 2 of 3 FORM ES-401-2 TOPIC: RHR heat exchangers

/ Positive displacement charging pumps 'Z.-.IJ /' . /"

.,/"

--JJjJ:) '5 eves Gzl'ttr:

8fX.J(Cti("()j Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. HPI, under total feedwater loss conditions ci-63<.ee J C,:+erl-V 0 I(.. Pumps Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects T-ave. and T-ref. chart recorder 9/23/2008 4:38 PM / V / j/"/ /' ES-401, REV 9 KA NAME I SAFETY FUNCTION:

025AK2.01 Loss of RHR System /4 029EA2.10 ATWS /1 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 D D D D D D D D D D Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.1 3.4 D D D D D D D D D D Se/33 t fA Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 040AG2.1.31 Steam Line Rupture -Excessive Heat Transfer / 4 054AA1.04 Loss of Main Feedwater / 4 055EK2.04 Station Blackout / 6 056AG2.4.35 Loss of Off-site Power /6 057AA2.09 Loss of Vital AC Ins!. Bus / 6 4.6 4.3 D D D D D D D D D D This is a Generic, no stem statement is associated.

4.4 4.5 D D D D D D D D D D Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6)

Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.8 4.0 D D D D D D D D D D This is a Generic, no stem statement is associated.

3.1 3.4 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:

41.10/43.5/

45.13) Page 2 of 3 FORM ES-401-2 TOPIC: RHR heat exchangers

/ Positive displacement charging pumps 'Z....u / . r"C OU I vc;z., -AlQ ') eves Gznfr:

8p2(f Jk'S lndiCU-hO./lf Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. HPI, under total feedwater loss conditions Pumps Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects T -ave. and T -ref. chart recorder 9/23/2008 4:38 PM V' ..

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

058AA1.03 Loss of DC Power 1 6 062AG2.2.40 Loss of Nuclear Svc Water 1 4 065AA1.01 077AK2.07 Loss of Instrument Air 1 8 Generator Voltage and Electric Grid Disturbances 1 6 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.3 D D D D D D D D D D 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) 3.4 4.7 D D D D D D D D D D This is a Generic, no stem statement is associated. 2.7 2.5 D D D D D D D D D D Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.71 45.5 1 45.6) 3.6 3.7 D D D D D D D D D D Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7 1 45.7 1 45.8) WE11EK1.2 LossofEmergencyCoolantRecirc./4 3.6 4.1 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.8 to 41:10 145.3) Page 3 of3 FORM ES-401-2 TOPIC: Vital and battery bus components

/ Ability to apply technical specifications for a system. Remote manual loaders ? ./' Turbine 1 Generator control / Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recir). 9/23/2008 4:38 PM / ES-401, REV 9 KA NAME / SAFETY FUNCTION:

058AA1.03 Loss of DC Power / 6 062AG2.2.40 Loss of Nuclear Svc Water / 4 065AA1.01 077AK2.07 Loss of Instrument Air /8 Generator Voltage and Electric Grid Disturbances / 6 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.1 3.3 0 0 0 0 0 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.4 4.7 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 2.7 2.5 0 0 DOD 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.6 3.7 0 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8)

WE11 EK1.2 Loss of Emergency Coolant Recirc. / 4 3.6 4.1 0 0 0 0 0 0 0 0 0 0 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: Vital and battery bus components Ability to apply technical specifications for a system. Remote manual loaders ? Turbine / Generator control Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recir). 9/23/2008 4:38 PM I ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003AK3.10 Dropped Control Rod / 1 028AA1.07 Pressurizer Level Malfunction / 2 051AG2.4.6 Loss of Condenser Vacuum / 4

,'" ) 068AK2.02 Control Room Evac. / 8 WE03EA 1.3 LOCA Cooldown -Depress. / 4 WE07EK1.3 Saturated Core Cooling Core Cooling /4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 4.2 D D D D D D D D D D Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.10/

45.6/45.13) 3.3 3.3 D D D D D D D D D D 3.7 4.7 3.7 3.9 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6)

This is a Generic, no stem statement is associated.

Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.7 4.1 D D D D D D D D D D Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.2 3.6 D D D D D D D D D D 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 1 of 2 FORM ES-401-2 TOPIC: RIL and PDIL V'/ Charging pumps maintenance of PZR level (including 1 manual backup) . Knowledge symptom based EOP mitigation strategies.

/ (iOpJ Reactor trip system Desired operating results during abnormal and emergency situations.

Annunciators and conditions indicating signals, and remedial actions associated with the ('PFsGGuri.ed 9fluvihtD Gve lklZ J 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003AK3.10 Dropped Control Rod / 1 028AA1.07 Pressurizer Level Malfunction / 2 051AG2.4.6 Loss of Condenser Vacuum /4 068AK2.02 Control Room*"tvac. / 8 WE03EA 1.3 LOCA Cooldown -Depress. /4 WE07EK1.3 Saturated Core Cooling Core Cooling /4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 4.2 D D D D D D D D D D 3.3 3.3 3.7 4.7 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5 /41.10/ 45.6/45.13)

Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6)

This is a Generic, no stem statement is associated. 3.7 3.9 D D D D D D D D D D Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR:

41.7 / 45.7/ 45.8) 3.7 4.1 D D D D D D D D D D Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.2 3.6 D D D D D D D D D D 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 1 of 2 FORM ES-401-2 TOPIC: RIL and PDIL Charging pumps maintenance of PZR level (including .j/ manual backup) Knowledge symptom based EOP mitigation strategies.

1./

AiJpj Reactor trip system Desired operating results during abnormal and emergency situations.

Annunciators and conditions indicating signals. and remedial actions associated with the (,Press'lri*eL 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

WE08EK2.1 RCS Overcooling

-PTS 1 4 WE09EK3.2 Natural Circ. 1 4 WE16EA2.1 High Containment Radiation 19 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.7 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:

41.5/41.10/45.61 45.13) 2.9 3.3 D D D D D D D D D D Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) Page 2 of 2 FORM ES-401-2 TOPIC: Components and functions of control and safety systems, :7 including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

WE08EK2.1 RCS Overcooling

-PTS 14 WE09EK3.2 Natural Circ. 1 4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.7 D D D D D D D D D D 3.2 3.6 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8)

Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.61 FORM ES-401-2 TOPIC: Components and functions of control and safety system7s including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

45.13)

WE16EA2.1 High Containment Radiation 1 9 2.9 3.3 IYJ 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 2 of 2 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

003K1.03 Reactor Coolant Pump 004K5.50 Chemical and Volume Control 005K6.03 Residual Heat Removal 006A3.06 Emergency Core Cooling 007A2.05 Pressurizer Relief/Quench Tank 007K5.02 Pressurizer Relief/Quench Tank T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.3 3.6. 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections andlor cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 2.6 2.7 0 0 0 0 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5 1 45.7) 2.5 2.6 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) 3.9 4.2 0 0 0 0 0 0 0 0 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7 1 45.5) 3.2 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) 3.1 3.4 DOD 0 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5 145.7) Page 1 of 5 FORM ES-401-2 TOPIC: RCP seal system / Design basis letdown system temperatures:

resin integrity/

RHR heat exchanger

/ Valve lineups -yo Exceeding PRT high-pressure limits / / r/ Method of forming a steam bubble in the PZR 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003K1.03 Reactor Coolant Pump 004KS.SO Chemical and Volume Control 00SK6.03 Residual Heat Removal 006A3.06 Emergency Core Cooling 007A2.0S Pressurizer Relief/Quench Tank 007KS.02 Pressurizer Relief/Quench Tank T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.3 3.6 D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR:

41.2 to 41.9/ 4S.7 to 4S.8) 2.6 2.7 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.S / 4S.7) 2.S 2.6 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/ 4S.7) 3.9 4.2 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) incJuding:(CFR:

41.7/ 4S.S) 3.2 3.6 D D D D D D D D D D 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.S / 43.S / 45.3 / 45.13) 3.1 3.4 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.S / 4S.7) Page 1 of 5 FORM ES-401-2 TOPIC: RCP seal system Design basis letdown system temperatures:

resin integrity RHR heat exchanger

/ Valve lineups Exceeding PRT high-pressure limits Method of forming a steam bubble in the PZR 9/23/2008 4:38 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 I 008K3.03 Component Cooling Water 4.1 4.2 RCP ./ .. Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 010A4.01 Pressurizer Pressure Control 3.7 3.5 PZR spray valve Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 012A1.01 Reactor Protection 2.9 3.4 Trip setpoint adjustment

,// Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR:

41.51 45.5) 012K3.01 Reactor Protection 3.9 4.0 CRDS / Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 013K2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) .;/ 022K1.04 Containment Cooling 2.9 2.9 Chilled water / 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) 022K2.02 Containment Cooling 2.5 2.4 Chillers v/' Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) Page 2 of 5 9/23/2008 4:38 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 I 008K3.03 Component Cooling Water 4.1 4.2 RCP ./ .. Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7 1 45.6) 010A4.01 Pressurizer Pressure Control 3.7 3.5 PZR spray valve Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 012A1.01 Reactor Protection 2.9 3.4 Trip setpoint adjustment

,// Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR:

41.5 1 45.5) 012K3.01 Reactor Protection 3.9 4.0 CROS /" Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 013K2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control / Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) , i 022K1.04 Containment Cooling 2.9 2.9 Chilled water /l 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) .,'-022K2.02 Containment Cooling 2.5 2.4 Chillers v/ Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) Page 2 of 5 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

025K5 01 Ice Condenser 026G2.1.32 Containment Spray 039G2.2.39 Main and Reheat Steam 059A4.03 Main Feedwater 061A2.05 Auxiliary/Emergency Feedwater 062A3.05 AC Electrical Distribution 062G2.2.39 AC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.4 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) 3.8 4.0 D D D D D D D D D D 3.9 4.5 2.9 2.9 3.1 3.4 3.5 3.6 3.9 4.5 This is a Generic, no stem statement is associated.

This is a Generic, no stem statement is associated.

Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8)

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 43.5 1 45.3 1 45.13)

Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7/45.5)

This is a Generic, no stem statement is associated.

Page 3 of 5 FORM ES-401-2 TOPIC: Relationships between pressure and temperature

// Ability to explain and apply all system limits and ....-precautions.

/ Knowledge of less than one hour technical specification action statements for systems. ) I (

K

,:>c il f C9 /\ d: C<.:"'s Q.nJ ((\ 4Ul llCeVCs,e.

Feedwater control during power increase and decrease t//

/" / Safety-related indicators and controls v/ Knowledge of less than one hour technical specification

"/ action statements for systems. 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025K5 01 Ice Condenser 026G2.1.32 Containment Spray 039G2.2.39 Main and Reheat Steam 059A4.03 Main Feedwater 061A2.05 Auxiliary/Emergency Feedwater 062A3.05 AC Electrical Distribution 062G2.2.39 AC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.0 3.4 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) 3.8 4.0 D D D D D D D D D D 3.9 4.5 2.9 2.9 3.1 3.4 3.5 3.6 3.9 4.5 This is a Generic, no stem statement is associated.

This is a Generic, no stem statement is associated.

Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8)

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:

41.5/43.5/45.3 145.13)

Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7/45.5)

This is a Generic, no stem statement is associated.

Page 3 of 5 FORM ES-401-2 TOPIC: Relationships between pressure and temperature Ability to explain and apply all system limits and precautions.

// Knowledge of less than one hour technical specification action statements for systems. I, I -k*(/otf f( f Co /,,1: L "':"'.5 C(1'i <;.l (f\ 4lQ Feedwater control during power increase and decrease t/

fi;tf

// / Safety-related indicators and controls / Knowledge of less than one hour technical specification action statements for systems. 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

063A3.01 DC Electrical Distribution 063K2.01 DC Electrical Distribution 064K4.11 Emergency Diesel Generator 073A1.01 Process Radiation Monitoring 073K3.01 Process Radiation Monitoring 076A1.02 Service Water 078K3.02 Instrument Air T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 3.1 0 0 0 0 0 0 0 0 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7/ 45.5) 2.9 3.1 0 0 0 0 0 0 0 0 0 0 3.5 4.0 3.2 3.5 3.6 4.2 2.6 2.6 3.4 3.6 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7)

Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7)

Ability to predict and/or mOllitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR:

41.5 / 45.5)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Page 4 of 5 FORM ES-401-2 TOPIC: Meters, annunciators, dials, recorders and indicating lig.trts Major DC loads Automatic load sequencer:

safeguards 7 Radiation levels 7 Radioactive effluent releases V Reactor and turbine building closed cooling water temperatures.

Systems having pneumatic valves and controls v/ 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

063A3.01 DC Electrical Distribution 063K2.01 DC Electrical Distribution 064K4.11 Emergency Diesel Generator 073A1.01 Process Radiation Monitoring 073K3.01 Process Radiation Monitoring 076A1.02 Service Water 078K3.02 Instrument Air T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 3.1 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5) 2.9 3.1 D D D D D D D D D D Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.5 4.0 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) 3.2 3.5 D D D D D D D D D D Ability to predict and/or mOfjitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR:

41.51 45.5) 3.6 4.2 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) 2.6 2.6 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 inciuding:(CFR:

41.51 45.5) 3.4 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:

41.7/45.6)

Page 4 of 5 FORM ES-401-2 TOPIC: Meters, annunciators, dials, recorders and indicati7ts Major DC loads Automatic load sequencer:

safeguards Radiation levels Radioactive effluent releases Reactor and turbine building closed cooling water temperatures.

Systems having pneumatic valves and controls 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

103K4.01 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.7 D D D Ii'] 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) Page 5 of 5 FORM ES-401-2 TOPIC: Vacuum breaker protection 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

i03K4.0i Containment T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.0 3.7 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) Page 5 of 5 FORM ES-401-2 TOPIC: Vacuum breaker protection 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

011A3.03 015K5.02 017K6.01 027K2.01 028K3.01 Pressurizer Level Control Nuclear Instrumeritation In-core Temperature Monitor Containment Iodine Removal Hydrogen Recombiner and Purge Control 033G2.4.21 Spent Fuel Pool Cooling 3l 034K1.02 Fuel Handling Equipment T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.3 0 0 0 0 0 0 0 0 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7 / 45.5) 2.7 2.9 DOD 0 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply!o the (SYSTEM):(CFR:

41.5 / 45.7) 2.7 3.0 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) 3.1 3.4 0 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.3 4.0 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:

41.7/45.6) 4.0 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.5 3.2 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 1 of2 FORM ES-401-2 TOPIC: Charging and letdown 7' Discriminator/compensation operation

-:7 Sensors and detectors

/ Fans / Hydrogen concentration in containment

/ /' Knowledge of the parameters and logic used to assess -/ the status of safety functions i/ RHRS 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

011A3.03 015K5.02 017K6.01 027K2.01 028K3.01 Pressurizer Level Control Nuclear Instrumentation In-core Temperature Monitor Containment Iodine Removal Hydrogen Recombiner and Purge Control 033G2.4.21 Spent Fuel Pool Cooling 034K1.02 Fuel Handling Equipment T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.3 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.7/45.5) 2.7 2.9 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) . 2.7 3.0 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 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.3 4.0 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) 4.0 4.6 D D D D D D D D D D This is a Generic, no stem statement is associated.

2.5 3.2 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) Page 1 of 2 FORM ES-401-2 TOPIC: Charging and letdown 7 Discriminator/compensation operation 7 Sensors and detectors Fans Hydrogen concentration in containment Knowledge of the parameters and logic used to assess // the status of safety functions V RHRS 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

071A1.06 Waste Gas Disposal 079A4.01 Station Air 086K4.02 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 2.8* 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controlsinciuding:(CFR:

41.5/ 45.5) 2.7 2.7 0 0 0 0 0 0 0 0 0 0 Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.0 3.4 0 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) Page 2 of2 FORM ES-401-2 TOPIC: Ventilation system v Cross-tie valves with lAS / Maintenance of fire header pressure t/ 9/23/2008 4:38 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

071A1.06 Waste Gas Disposal 079A4.01 Station Air 086K4.02 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 2.8 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls inciuding:(CFR:

41.5 1 45.5) 2.7 2.7 0 0 0 0 0 0 0 0 0 0 Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.0 3.4 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR:

41.7) Page 2 of2 FORM ES-401-2 TOPIC: Ventilation system Cross-tie valves with lAS / Maintenance of fire header pressure 9/23/2008 4:38 PM ES-401, REV 9 T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.1.1 Conduct of operations 3.8 4.2 0 0 0 0 0 0 0 0 0 0 G2.1.27 Conduct of operations 3.9 4 G2.1.37 Conduct of operations 4.3 4.6 G2.2.17 Equipment Control 2.6 3.8 0 0 0 0 0 0 0 0 0 0 G2.2.4 Equipment Control 3.6 3.6 G2.2.40 Equipment Control 3.4 4.7 Radiation Control 3.4 3.8 Page 1 of 2 FORM ES-401-2 TOPIC: Knowledge of conduct of operations requirements.

VI / Knowledge of system purpose and or function.

! V / Knowledge of procedures, guidelines or limitations 7 associated with reactivity management v' Knowledge of the process for managing maintenance c, / activities during power operations.

fI (multi-unit)

Ability to explain the variations in control board layouts, systems, instrumentation and procedural I actions between units at a facility. . Ability to apply technical specifications for a system. V/ Knowledge of radiation or contamination hazards that c/ may arise during normal, abnormal, or emergency conditions or activities 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.1 Conduct of operations G2.1.27 Conduct of operations T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.2 D D D D D D D D D D 3.9 4 D D D D D D D D D D FORM ES-401-2 TOPIC: Knowledge of conduct of operations requirements.

Knowledge of system purpose and or function.

/ V' /1

/Ii associated with reactivity management V G2.2.17 Equipment Control 2.6 3.8 D D D D D D D D D D G2.2.4 Equipment Control 3.6 3.6 G2.2.40 Equipment Control 3.4 4.7 G2.3.14 Radiation Control 3.4 3.8 Page 1 of 2 Knowledge of the process for managing maintenance activities during power operations. (multi-unit)

Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

Ability to apply technical specifications for a system. Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 9/23/2008 4:38 PM I V / / / \I V/

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.3.4 Radiation Control 3.2 3.7 G2.4.39 Emergency Procedures/Plans 3.9 3.8 D D D D D D D D D D G2.4.45 Emergency Procedures/Plans 4.1 4.3 D D D D D D D D D D Page 2 of2 FORM ES-401-2 TOPIC: Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of the RO's responsibilities in emergency plan / implementation.

/ Ability to prioritize and interpret the significance of each / annunciator or alarm. V 9/23/2008 4:38 PM ES-401, REV 9 T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.3.4 Radiation Control 3.2 3.7 G2.4.39 Emergency Procedures/Plans 3.9 3.8 0 0 0 0 0 0 0 0 0 0 G2.4.45 Emergency Procedures/Plans 4.1 4.3 0 0 0 0 0 0 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC: Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of the RO's responsibilities in emergency plan implementation.

/ Ability to prioritize and interpret the significance of each annunciator or alarm. vi" 9/23/2008 4:38 PM ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EG2.4.35 Reactor Trip -Stabilization

-Recovery 3.8 4.0 11 This is a Generic, no stem statement is associated.

008AA2.10 Pressurizer Vapor Space Accident 1 3 3.6 3.6 022AG2.4.4 025AA2.07 027AA2.03 Loss of Rx Coolant Makeup 1 2 Loss of RHR System 14 Pressurizer Pressure Control System Malfunction 1 3 062AG2.1.31 Loss of Nuclear Svc Water I 4 4.5 4.7 3.4 3.7 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 1 43.5 1 45.13)

This is a Generic, no stem statement is associated.

Abifity to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 1 43.5 1 45.13) 3.3 3.4 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) 4.6 .4.3 D D D D D D D D D D This is a Generic, no stem statement is associated.

Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects t/ High-pressure injection valves and controllers Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

/' t/ Pump cavitation

/ Effects of RCS pressure changes on key components in plant t/' Ability to locate control room switches, controls and indications and to determine that they are correctly

/' reflecting the desired plant lineup. V 9/23/2008 4:38 PM ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EG2.4.35 Reactor Trip -Stabilization

-Recovery 3.8 4.0 0 0 0 0 0 0 0 0 0 0 / 1 This is a Generic, no stem statement is associated.

008AA2.10 Pressurizer Vapor Space Accident / 3 3.6 3.6 0 0 0 0 0 0 0 0 0 0 022AG2.4.4 025AA2.07 027AA2.03 Loss of Rx Coolant Makeup / 2 Loss of RHR System /4 Pressurizer Pressure Control System Malfunction / 3 062AG2.1.31 Loss of Nuclear Svc Water / 4 4.5 4.7 3.4 3.7 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/ 43.5 / 45.13)

This is a Generic, no stem statement is associated.

Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 / 43.5 / 45.13) 3.3 3.4 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:

41.10/43.5/

45.13) 4.6 .4.3 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects High-pressure injection valves and controllers Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Pump cavitation Effects of RCS pressure changes on key components in plant Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. 9/23/2008 4:38 PM [1/

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

003AG2.4.11 Dropped Control Rod /1 051AA2.02 Loss of Condenser Vacuum / 4 WE15EA2.2 Containment Flooding /5 we16EG2.4.49 High Containment Radiation

/9 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 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 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 / 43.5 / 45.13) 2.9 3.3 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10 / 43.5 / 45.13) 4.6 4.4 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC: Knowledge of abnormal condition procedures.

J Conditions requiring reactor and/or turbine trip r/ Adherence to appropriate procedures and operation/'

within the limitations in the facility's license and amendments.

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. (ljD 7cJA) Z*4,4{ Page 1 of 1 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003AG2.4.11 Dropped Control Rod 1 1 051AA2.02 Loss of Condenser Vacuum 1 4 WE15EA2.2 Containment Flooding 1 5 we16EG2.4.49 High Containment Radiation 1 9 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.2 D D D D D D D D D D This is a Generic, no stem statement is associated.

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 3.3 D D D D D D D D D D Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 4.6 4.4 D D D D D D D D D D This is a Generic, no stem statement is associated.

FORM ES-401-2 TOPIC: Knowledge of abnormal condition procedures.

/ J Conditions requiring reactor and/or turbine trip Adherence to appropriate procedures and within the limitations in the facility's license and amendments.

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

(/JiJ 5 F=U1 t./ Z*4 ,4 ( Page 1 of 1 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

004G2.1.20 Chemical and Volume Control 012G2.1.19 Reactor Protection 063A2.02 DC Electrical Distribution 076A2.01 Service Water 078A2.01 Instrument Air SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.6 0 0 0 0 0 0 0 0 0 0 3.9 3.8 This is a Generic, no stem statement is associated.

000 This is a Generic, no stem statement is associated.

2.3 3.1 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) 3.5 3.7 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)

G; 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 1 of 1 FORM ES-401-2 TOPIC: Ability to execute procedure stepsU Ability to use plant computer to evaluate system or component status. Loss of ventilation during battery charging // J //" /" Loss ofSWS Air dryer and filter malfunctions 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

004G2.1.20 Chemical and Volume Control 012G2.1.19 Reactor Protection 063A2.02 DC Electrical Distribution 076A2.01 Service Water 078A2.01 Instrument Air SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.6 0 0 0 0 0 0 0 0 0 0 3.9 3.8 2.3 3.1 3.5 3.7 l:' 2.9 This is a Generic, no stem statement is associated.

This is a Generic, no stem statement is associated.

cJia -" 2 'S"l... i l 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:

41.5/43.5/45.3 145.13)

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)

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 1 45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Ability to execute procedure stepsu Ability to use plant computer to evaluate system or // component status. Loss of ventilation during battery charging /" r-/ /' V Loss ofSWS Air dryer and filter malfunctions 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

034G2.4.20 Fuel Handling Equipment 2<4-*!l 072A2.02 Area Radiation Monitoring 086A2.03 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.3 D D D D D D D D D D This is a Generic, no stem statement is associated.

'2 I ! 2.8 2.9 D D D DOD D D D D 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) 2.7 2.9 D D D D D D D D D D 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:

41.5/43.5/45.3 145.13) Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of operational implications of EOP warnings, cautions and notes. v' Detector failure 'V Inadvertent actuation of the FPS due to circuit failure or welding / 9/23/2008 4:38 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

034G2.4.20 Fuel Handling Equipment 072A2.02 Area Radiation Monitoring 086A2.03 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.3 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 2.8 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:

41.5 143.5/45.3 145.13) 2.7 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 1 of 1 FORM ES-401-2 TOPIC: Knowledge of operational implications of EOP warnings, cautions and notes. Detector failure Inadvertent actuation of the FPS due to circuit failure or welding / 9/23/2008 4:38 PM ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO G2.1.S Conduct of operations 2.9 3.9 G2.2.11 Equipment Control 2.3 3.3 0 0 0 0 0 0 0 0 0 0 G2.2.3 Equipment Control 3.8 3.9 0 0 0 0 0 0 0 0 0 0 G2.3.12 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 G2.3.14 Radiation Control 3.4 3.8 G2.4.20 Emergency Procedures/Plans 3.8 4.3 G2.4.23 Emergency Procedures/Plans 3.4 4.4 Page 1 of 1 FORM ES-401-2 TOPIC: Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Knowledge of the process for controlling temporary design changes. (multi-unit license) Knowledge of the design, procedural and operational differences between units. v' /' Knowledge of radiological safety principles pertaining to / licensed operator duties vi' Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of operational implications of EOP warnings, cautions and notes. Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

9/23/2008 4:38 PM vii / V j U ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.5 Conduct of operations G2.2.11 Equipment Control G2.2.3 Equipment Control G2.3.12 Radiation Control G2.3.14 Radiation Control G2.4.20 Emergency ProcedureslPlans G2.4.23 Emergency ProcedureslPlans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.9 2.3 3.3 D D D D D D D D D D 3.8 3.9 D D D D D D D D D D 3.2 3.7 3.4 3.8 3.8 4.3 D D D D D D D D D D 3.4 4.4 D D D D D D D D D D Page 1 of 1 FORM ES-401-2 TOPIC: Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Knowledge of the process for controlling temporary design changes. (multi-unit license) Knowledge of the design, procedural and operational differences between units. 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

/ V Knowledge of operational implications of EOP warnings, . cautions and notes. \// Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

Vi 9/23/2008 4:38 PM