ML091740164

Initial Exam 2009-301 Draft Administrative Documents

ML091740164
Person / Time
Site:	Turkey Point
Issue date:	06/23/2009
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
Download: ML091740164 (26)

Text

DRAFT ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Turkey Point Units 3 & 4 Date of Examination:

02/23/2009 Exam Level: RO Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note) Al CR,N Perform a Manual RCS Leakrate Calculation Conduct of Operations A2 C,N Perform an Equipment Operability Verification Equipment Control A3 CR,M Determine Dose Rates and Radiological Requirements From a Radiation Control Survey Map A4 -RO CR,N Complete a Florida State Notification Form Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (::;3 for ROs, ::;4 for SROs) (N)ew or (M)odified from bank ('21) (P)revious 2 Exams (::;1 Randomly selected)

DRAFT ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Turkey Point Units 3 & 4 Date of Examination:

02/23/2009 Exam Level: SRO (U) & (I) Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note) (See Note) Al.a CR,N Perform a Review of a Manual RCS Leakrate Calculation Conduct of Operations Al.b CR,N Review 3-0P-062, Safety Injection Attachments Conduct of Operations A2 CR,N Determine Required Actions for Instrumentation Failure Equipment Control A3 CR,M Determine Dose Rates and Radiological Requirements From a Radiation Control Survey Map A4 -SRO CR,N Classify Event and Determine PARS Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (::;3 for ROs, :S4 for SROs) (N)ew or (M)odified from bank (P)revious 2 Exams (::;1 Randomly selected)

DRAFT ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Turkey: Point Date of Examination:

02/23/2009 Exam Level (circle one): RO Operating Test No.: 2009-301 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) System 1 JPM Title Type Code* Safety Function a Align RHR For Cold Leg Recirculation A,M,S 2 b Restore Accumulator Pressure D,S 3 c Place RHR In Service L,N,S 4 (PRI) d Manually Initiate Containment Spray A,N,S 5 e Manually Synchronize Main Generator D, L, S 6 f Respond to a L T 112 failure A,N,S 7 g Respond to a CCW system leak A,N,L,S 8 h Terminate a Waste Gas Release A,N,S 9 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Respond to ATWS Locally A,E,D 1 j Realign Opposite Units HHSI Pumps E,D,R 2 k Locally Start a Diesel Generator A,E,M 6 @ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank ::;9/::;8/::;4 (E)mergency or abnormal in-plant 2!1/2!1/2!1 (L)ow-Power 2!1/2!1/2!1 (N)ew or (M)odified from bank including 1 (A) 2!2/2!2/2!1 (P)revious 2 exams ::; 31::; 31::; 2 (randomly selected) (R)CA 2!1/2!1/2!1 (S)imulator RAFT ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Turkey Point Date of Examination:

02/23/2009 Exam Level (circle one): SRO-I Operating Test No.: 2009-301 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) System / JPM Title Type Code* Safety Function a Align RHR For Cold Leg Recirculation A,M,S 2 b Restore Accumulator Pressure D,S 3 c Place RHR In Service L,N,S 4 (PRI) d Manually Initiate Containment Spray A,N,S 5 e f Respond to a L T 112 failure A,N,S 7 g Respond to a CCW system leak A, N, L, S 8 h Terminate a Waste Gas Release A,N,S 9 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Respond to ATWS Locally A,E,D 1 j Realign Opposite Units HHSI Pumps E,D,R 2 k Locally Start a Diesel Generator A,E,M 6 @ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank ::;9/::;8/::;4 (E)mergency or abnormal in-plant ::::1/::::1/::::1 (L)ow-Power

1/::::1/::::1 (N)ew or (M)odified from bank including 1 (A) ::::2/::::2/::::1 (P)revious 2 exams ::; 3/::; 3/::; 2 (randomly selected) (R)CA ::::1/::::1/::::1 (S)imulator ,

RAFT ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Turkey: Point Date of Examination:

02/23/2009 Exam Level (circle one): SRO-U Operating Test No.: 2009-301 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) System / JPM Title Type Code* Safety Function a b Vent Accumulators D,S 3 c d Manually Initiate Containment Spray A,N,S 5 e f g Respond to a CCW system leak A, N, L,S 8 h In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Respond to ATWS Locally A,E,D 1 j Realign Opposite Units HHSI Pumps E,D,R 2 k @ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank :s;9/:S;8/:S;4 (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams :S; 3 / :S; 3 / :S; 2 (randomly selected)

• (R)CA (S)imulator DRAFT ES-401 1 Rev. 9 PWR Examination Outline Fonn ES-401*2 Facility:

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 2 1 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 3 2 3 3 2 3 2 3 2 2 3 28 2 3 5 2. 1 0 1 1 1 1 1 1 1 1 1 10 0 2 3 Plant 2 Systems Tier Totals 4 2 4 4 3 4 3 4 3 3 4 38 2 5 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category In Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that speCified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified In the table based on NRC revisions.

The final RO exam must total 75 pOints and the SRO-only exam must total 25 pOints. 3. Systems/evolutions within each group are identified on the associated 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-speclflc priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

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

7, *The generic (G) KlAs In Tiers 1 and 2 shall be selected from Section 2 of the Kf A Catalog, but the topics must be relevant to the applicable evolution or system, 8. On the following pages, enter the KIA numbers. a brief description of each toplo, the topiCS' Importanoe ratings (I Rs) for the applicable lioense level, and the point totals (I) for each system and category.

Enter the group and tier totals for each catagory in the table above; If fuel handling eqUipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not. apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Seotion 2 of the KIA catalog. and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Umit SRO selections to K/As that are linked to 10 CFR 55.43.

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

007EK2.03 Reactor Trip -Stabilization

-Recovery 11 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.5 3.6 D D D D D D D D D D Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7 145.7 1 45.8) OOSAG2..2A4 Pressurizer Vapor Space Accident/3 4..2 4.4 D D D D D D D D D D 009EA2.06 Small Break LOCA 13 015AA2.0S RCP Malfunctions / 4 022AK1.02 Loss of Rx Coolant Makeup I 2 025AG2,4,46 Loss of RHR System 14 This is a Generic, no stem statement is associated.

3.8 4.3 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:

41.10 143.51 45.13) 3,4 3.5 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) 2.7 3.1 0 0 0 DOD D DOD Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.S to 41.10 / 45.3) 4.2 4.2 D D D D D D D D D D This is a Generic, no stem statement is associated.

Page 1 of 3 FORM ES-401-2 TOPIC: Reactor trip status panel Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Whether PZR water inventory loss is imminent When to secure RCPs on high bearing temperature Relationship of charging flow to pressure differential between charging and RCS Ability to verify that the alarms are consistent with the plant conditions.

8/1S/2008 5:59 AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 KS A 1 A2 A3 A4 G RO SRO 02SAA2.06 Loss of Component Cooling Water / 8 28 3.1 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:

41.10 143.51 45.13) 029EG2.4.4 ATWS/1 4.5 4.7 0 0 0 000 0 0 0 0 040AK1.04 Steam Line Rupture -Excessive Heat 3.2 3.S Transfer 14 054AK1.02 Loss of Main Feedwater / 4 3.6 4.2 055EK2.04 Stati.on Blackout f 6 056M1.25 Loss of Off-site Power 1 6 2.9 2.9 This is a Generic, no stem statement is associated.

Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTlON):(CFR:

41.8 to 41.10 I 45.3)

Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTlON}:(CFR:

41.8 to41.10/45.3)

Knowledge ofthe interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR:

41.7 145.7/45.8)

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

41.7/45.5/

45.6) Page 2 of 3 FORM ES-401-2 TOPIC: The length of time after the loss of CCW flow to a component before that component may be damaged Ability to recognize abnonnal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Nil ductility temperature Effects of feedwater introduction on dry SfG Pumps Main steam supply valve control switch 8/1812008 5:59 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

057AK3.01 058AA1.01 062AK3.02 065AK3.04 077AA101 loss of Vital AC Inst Bus 16 loss of DC Power 16 loss of Nuclear Svc Water 14 loss of Instrument Air 18 Generator Voltage and Electric Grid Disturbances I 6 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 4.1 4.4 D 0 0 0 DOD 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOlUT10N):(CFR:

41.5/41.10 I 45.6/45.13) 3.4 3.5 DOD 0 0 0 0 0 0 0 Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOlUTION):(CFR:

41.7/45.5/

45.6) 3.6 3.9 0 0 0 0 0 0 0 0 0 0 3 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOlUTION):(CFR:

41.5 141.10 I 45.6/45.13) 3.2 D 0 0 0 DOD 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOlUTION):(CFR:

41.5/41.10 I 45.6 145.13) 3.6 3.7 0 0 0 0 0 0 0 0 0 0 Ability to operate and lor monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7 145.5 J 45.6) WE11EK2.1 loss of Emergency Coolant Recirc. 14 3.6 3.9 D DOD 0 0 0 DOD Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7 f 45.7 145.8) Page 3 of 3 FORM ES-401-2 TOPIC: Actions contained in EOP for loss of vital ac electrical instrument bus Cross-tie of the affected dc bus with the alternate supply The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS Cross-over to backup air supplies Grid frequency and voltage Components and functions of control and safety systems. including instrumentation, Signals, interlocks, failure modes and automatic and manual fealures.

8/18/2008 5:59 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

001AK3.02 Continuous Rod Withdrawal f 1 005AA1.01 Inoperable/Stuck Control Rod { 1 024AA2.01 Emergency Baration I 1 036AK3.02 Fuel Handling Accident f 8 059AK1.02 Accidental Liquid RadWaste ReI. / 9 067 AG2A.49 Plant Fire On-site 19 8 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.2 4.3 0 0 0 0 0 0 0 0 0 0 Knowledge ofthe reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION}:(CFR:

41.5 I 41.10 I 45.6/45.13) 3.6 3.4 0 0 0 0 0 0 0 0 0 0 Ability to operate and f or monitor the following as they apply to (ABNORMAL PLANT EVOLUT10N):(CFR:

41.7/45.51 45.6) 3.8 4.1 0 0 0 0 0 0 0 0 0 0 Ability to determina and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 I 43.5 I 45.13} 2.9 3.6 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' 4110' 45.6 f 45.13) 2.6 3.2 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 EVOLUT!ON):(CFR:

41.8 to 41.10 145.3) 4.6 4.4 0 0 0 0 0 0 0 0 0 0 This is a Generic. no stem statement is associated.

Page 1 of 2 FORM ES-401-2 TOPIC: Tech-Spec limits on rod operability CROS Whether boron flow and/or MOVs are malfunctioning from plant conditions Interlocks associated with fuel handling equipment Biological effects on humans of various types of radiation, exposure levels that are acceptable for nuclear power plant personnel and the units used for intensity measurements and for radiation exposure levels Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

8/18/2008 5:59 AM ES-401, REV 9 KA NAME / SAFETY FUNCT10N:

WE08EA 1.3 RCS Overcooling

-PTS I 4 WE09.EK1.3 Natural Circ. f 4 WE 14EK2.1 Loss of CTMT Integrity 15 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.6 4.0 0 0 0 0 0 0 0 0 0 0 Ability to operate and f or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.7/45.5 J 45.6) 3.3 3.6 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 EVOLUT10N):(CFR:

41.8 to 41.10 I 45.3) 3.4 3.7 0 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7145.7 I 45.8} Page 2 of 2 FORM ES-401-2 TOPIC: Desired operating results during abnormal and emergency situations.

Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

Components and functions of control and safety systems, including instrumentation, signals, interlocks.

failure modes and automatic and manual features.

8/18/2008 5:59 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

RO 003K1.13 Reactor Coolant Pump 2.S 003K6.04 Reactor Coolant Pump 2.8 004A2.13 Chemical and Volume Control 3.6 005K6.03 Residual Heat Removal 2.S 006A2.06 Emergency Core Cooling 3.3 007A4.09 Pressurizer Relief/Quench Tank 2.5 T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G SRO 2.S Knowledge of the physical connections andfor cause-effect relationships between (SYSTEM) and thefollowing:(CFR:

41.2 to 419 J 45.7 to 45.8) 3.1 Knowledge of the effect that a loss or malfunction of the follOWing will have on the (SYSTEM):(CFR:

41.7 14S.7) 3.9 o 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (bl based on those predictions.

use procedures to correct control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5!

4S.3 J 45.13) 2.6 Knowledge of the effect that a loss or malfunction of the fo[1OV11ing will have on the (SYSTEM):(CFR:

41.714S.7)

3.5 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.S!

45.3/45.13)

2.7 Ability

to manually operate and/or monitor in the control room: (CFR: 41.7 I 4S.5 to 45.8) Page 1 of 5 FORM ES*401*2 TOPIC: RCP bearing lift oil pump Containment isolation valves affecting RC P operation Low RWST RHR heat exchanger Water hemmer Relationships between PZR level and chang ing levels of the PRT and bleed holdup tank 8118/2008 6:00 AM ES-401, REV 9 KA NAME j SAFETY FUNCTION:

008A4.03 Component Cooling Water 008K3.01 Component Cooling Water 010K1.02 Pressurizer Pressure Control 010K5.01 Pressurizer Pressure Control 012A3.04 Reactor Protection 013K2.01 Engineered Safety Features Actuation 022K4.03 Containment Cooling T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 2.5 0 0 0 0 0 0 0 0 0 0 A bility to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.4 3.5 0 0 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will haw on thefoliowing:(CFR:

41] 145.6) 3.9 4.1 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following: (CFR: 41.2 to 41.9/45.71045.8) 3.5 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the operation a impncations of the following concepts as they apply to the (SYSTEM):(CFR:

41.5145.7) 2.8 2.9 0 0 0 0 0 0 0 0 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7 145.5) 3.6 3.8 0 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.6 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design fffiture(s) and or interlock(s) which provide for the following:(CFR:

41.7) Page 2 of 5 FORM ES-401-2 TOPIC: Throttling of the CCW pump discharge valve Loads cooled by CCWS ESFAS Determination of condition of fluid in PZR, using stearn tables Circuit breaker ESFAS/safeguards eqUipment control Automatic containment isolation 8118/2008 6:00 AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC: RO SRO 026A1.03 Containment Spray 3.5 3.5 Containment sump level Ability to predict and/or monnor changes in parameters associated with operating the (SYSTEM) controls incfuding:(CFR:

41.5/ 45.5) 026A2.04 Containment Spray 3.9 4.2 Failure of spray pump 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 consequEillces of those abnormal operation:(CFR:

41.5/ 43.5 ( 45.3145.13) 039A1.05 Main and Reheat steam 32 3.3 RCS T-ave Ability to predict and/or monitor changes in parameters associated.

with operating the (SYSTEM) controls incfuding:(CFR:

41.5/ 45.5) 059K3.03 Main Feedwater 3.5 3.7.

SfGS Kncmledge of the effect that a loss or malfunction of the (SYSTEM) wUI have on the foIIowing:{CFR:

41.7/45.6) 061K4.OS AuxHiary/Emergency Feedwater 4.0 4.2 AFW startup permissives Kncmledge ci (SYSTEM) design feature(s) and or interlock(s) which prollide for the following:(CFR:

41.7) OSiK6.08 AuxiliaryfEmergency Feedwater 2.6 2.7 Pumps Kncmledge ci the effect that a loss or malfunction of the follOWing will have on the (SYSTEM):(CFR:

41.7 145.7) Page3of5 8/18f2008 6:00 AM ES401, REV 9 KA NAME I SAFETY FUNCTION:

062K1.03 AC Electrical Distributicn 063K2.01 DC Electrical Distribution 06402.4.30 Emergency Diesel Generator 064K3.02 Emergency Diesel Generator 073K5.01 Process Radiaticn Monitoring 076G2.1.23 Service Water 076K4.06 Service Water T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.5 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR:

41.2 to 41.9 J 4S.7 to 45.8) 2.9 3.1 0 0 0 DOD D D D D Knowledge of electrical power supplies to the foilowing:(CFR:

41.7) 2.7 4.1 DOD 0 0 DODD 0 This is a Generic, no stem statement is associated.

4.2 4.4 0 0 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction ofthe (SYSTEM) will have on the foIlowing:(CFR:

41.7/45.6) 2.5 3.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the operations impHcatlons of the following concepts as they apply to the (SYSTEM):(CFR:

41.S J 4S.7) 4.3 4.4 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.8 32 Knowledge of (SYSTEM) design fEBture(s) and or interlock(s) which prO\lide for the foUowing:(CFR:

41.7) Page40fS FORM ES-401-2 TOPIC: DC distribution Major DC loads Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

ESFAS controlled or actuated systems Radiation theory, including sources, types, units and effects Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Service water train separation 8/18/2008 6:00AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

078A3.01 Instrument Air 103G2.2.36 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.2 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7 /45.5) 3.1 4.2 D D D D DOD D D D This is a Generic, no stem statement is associated.

Page 5 of 5 FORM ES-401-2 TOPIC: Air pressure Ability to analyze the effect of maintenance activities, such as degraded power sources, on the st<tus of limiting conditions of operations 8118/2008 6:00AM ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G RO SRO 011 K6.06 Pressurizer Level Control 2.5 2.8 D DOD 0 D DOD D Knowledge ofthe effect that a loss or malfunction of the following will have on the (SYSTEM): (CFR: 41.7 14S.7) 014G2.4.35 Rod Position Indication 3.8 4.0 DODD 0 DOD 0 D This is a Generic, no stem statement is associated.

016K3.07 Non-nuclear Instrumentation 3.6 3.7 D 0 0 DOD DOD 0 017K4.03 027A4.04 035A1.01 041K1.06 In-core Temperature Monitor Containment Iodine Removal Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 3.1 3.3 DOD DOD DOD 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 2.8 2.9 D D U 0 0 DOD D D Ability to manually operate andlor monitor in the control room:(CFR:

41.7/45.5 to 45.8) Steam Generator 3.6 3.8 DOD DOD 0 D 0 [J Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.51 45.5) Steam Dump/Turbine Bypass Control 2.6 2.9 0 0 0 0 DOD 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) Page 1 of 2 FORM ES-401*2 TOPIC: Correlation of demand signal indication on charging pump flow valve controller to the valve position Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects ECCS Range of temperature indication Filter temperature S/G wide and narrow range level during startup, shutdown and normal operations Condenser 811812008 600 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

045A2.17 Main Turbine Generator 055A3.03 Condenser Air Removal 071K5.04 Waste Gas Disposal T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 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 1 45.3/45.13) 2.5 2.7 D n D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5) 2.5 3.1 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM): (CFR: 41.5 / 45.7) Page 2 of 2 FORM ES-401*2 TOPIC: Malfunction of electro hydraulic control Automatic diversion of CARS exhaust Relationship of hydrogen/oxygen concentrations to flammability 8/1812008 6:00 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.18 Conduct of operations G2.1A5 Conduct of operations G2.2.35 Equipment Control G2.2.39 EqUipment Control G2.3.11 Radiation Control G2.3.14 Radiation Control G2.3.4 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 3.8 0 0 0 0 0 0 0 0 0 0 4.3 4.3 0 DOD DODD 0 D 3.6 4.5 0 0 0 0 0 0 0 0 0 0 3.9 4.5 0 0 0 0 0 0 0 0 0 0 3.8 4.3 0 DOD 0 0 0 0 0 0 3.4 3.8 0 0 0 0 0 0 DOD 0 3.2 3.7 0 0 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC: Ability to make accurate, clear and concise logs, records, status boards and reports. Ability to identify and interpret diverse indications to validate the response of another indication Ability to determine Technical Specification Mode of Operation Knowledge of less than one hour technical specification action statements for systems. Ability to control radiation releases.

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of radiation exposure limits under normal and emergency conditions 811812008 6:00 AM ES*401, REV 9 T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO G2.4.13 Emergency Procedures/Plans 4.0 4.6 D D D D D D D D D D G2.4.23 Emergency Procedures/Plans 3.4 4.4 D D D D D D D D D D G2.4.38 Emergency ProcedureslPlans 2.4 4.4 D D D D D D D D D D Page 2 of 2 FORM ES-401-2 TOPIC: Knowledge of crew roles and responsibilities during EOP usage. Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

8/18/2008 6:00 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

011EG2.2.37 Large Break LOCA 13 025AG2A8 Loss of RHR System 14 026AA2.01 Loss of Component Cooling Water 18 056AA2.54 Loss of Off-site Power 1 6 065AG2.2.4 Loss of Instrument Air 18 WE04EA2.1 LOCA Outside Containment 13 SRO T1G1 PWR EXAMINATION OUTLINE lR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G RO SRO 3.6 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.8 4.S 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.9 3.S 0 0 0 0 0 0 0 0 0 0 Ability to determine and intelpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/ 43.5/4S.13) 2.9 3 Ability to determine and intelprel the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10 143.5/45.13) 3.6 3.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem staternent is associated . 3.4 4.3 0 0 0 0 0 0 0 0 0 0 Ability to detefmine and intelprel the following as they apply to (EMERG ENCY PLANT EVOLUTION):(CFR:

41.10 1 43.S I 45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Ability to detefmine operability andlor ci safety related equipment Knowledge of how abnormal operating procedures are used in conjunction with EOPs. Location of a leak in the CCWS Breakef position (remote and local) (multi-unit)

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

F acillty conditions and selection of appropriate procedures during abnormal and emefgency opefalions.

8118/2008 6:00AM ES*401, REV 9 KA NAME I SAFETY FUNCTION:

003AA2.01 Dropped Control Rod 11 028AA2.03 Pressurizer Level Malfunction 1 2 068AG2.4.20 Control Room Evac. / 8 we10EG2.4.31 Natural Circ. With Seam Void/4 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.7 3.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR:

41.10 143.51 45.13) 2.8 3.3 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the follOWing as they apply to ABNORMAL PLANT EVOLUT10N):(CFR:

41.10 I 43.5 I 4S.13) 3.8 4.3 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem stat*ment is associated.

4.2 4.1 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: Rod position indication to actual rod position Charging subsystem flow indicator and controller Knowledge of operational implications of EOP warnings, cautions and notes. Knowledge of annunciators alarms, indications or response procedures 811812008 6:00AM ES401, REV 9 KA NAME I SAFETY FUNCTION:

003G2.4.31 Reactor Coolant Pump 005G2.2.25 Residual Heat Removal 007 A2.02 Pressurizer Relief/Quench Tank 010G2.1.19 Pressurizer Pressure Control 026A2.07 Containment Spray SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 4.2 4.1 DOD D DOD 0 D D This is a Generic, no stem statement is associated.

3.2 4.2 ODD DOD DOD 0 This is a Generic, no stem statement is associated.

2.6 3.2 0 DOD 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

/ 45.3/45.13) 3.9 3.8 D DOD D D DOD 0 This is a Generic, no stem statement is associated.

3.6 3.9 0 D D D DOD 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)

Page 1 of 1 FORM TOPIC: Knowledge of annunciators alarms, indications or response procedures Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Abnormal pressure in the PRT Ability to use plant computer to evaluate system or component status. Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding} or sump level below cutoff (interlock) limit 8/18/2008 6:00 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

034A3.{)2 Fuel Handling Equipment 072G2.2.44 Area Radiation Monitoring 079G2.2.3 Station Air SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 3.1 0 0 0 0 0 0 0 0 0 0 0 Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

41.71 45.5) 4.2 4.4 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.8 3.9 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: load limits Ability to interpret control room indications 10 verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions (multi-unit license) Knowledge of the design, procedural and operational differences between units. 8118/2008 6:01AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.i.18 Conduct of operations G2.2.1 Equipment Control G2.2.39 Equipment Control G2.3,4 Radiation Control G2.3.7 Radiation Control G2.4.17 Emergency Procedures/Plans G2.4,35 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 3.6 3.8 0 0 0 0 0 0 0 0 0 0 4.5 4,4 0 0 0 0 0 0 0 0 0 0 3.9 4.5 ODD 3.2 3.7 0 00 0 0 0 0 0 0 0 3.5 3.6 0 0 0 0 0 0 0 0 0 0 3.9 4.3 0 3,8 4,0 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: Ability to make accurate, clear and concise logs, records, status boards and reports, Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

Knowledge of less than one hour technical specification action statements for systems. Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of EOP terms and definitions.

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 8118/2008 6:01 AM R FT ES -401 Record of Rejected KlAs Form ES-401-4 Tier / Randomly Group Selected KIA Reason for Rejection T2G2 011 K6.06 Not part of plant equipment.

Replaced with 011 K6.03 T2G2 055A3.03 Not part of plant equipment.

Replaced with 033A3.02 T2G1 061K6.08 All information listed on sample plan is for KIA 061 K6.02. Corrected typo for listed KIA to 061 K6.02 ES -401, Page 28 of34