ML091740164

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Initial Exam 2009-301 Draft Administrative Documents
ML091740164
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/23/2009
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
Download: ML091740164 (26)
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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 Determine Dose Rates and Radiological Requirements From a CR,M 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 Determine Dose Rates and Radiological Requirements From a CR,M 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 (~1)

(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 LT 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 LT 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 ~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 :S; 3 / :S; 3 / :S; 2 (randomly selected)
  • (R)CA ~1/~1/~1 (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.

2 1 0 1 1 1 1 1 1 1 1 1 10 0 2 3 Plant 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. 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 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 D ~ D D D D D D D D D Reactor trip status panel 11 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 ~ Ability to interpret control room indications to verify the status and operation of a system, and understand how This is a Generic, no stem statement is operator actions and directives affect plant and system associated. conditions 009EA2.06 Small Break LOCA 13 3.8 4.3 D D D D D D D ~ D D D Whether PZR water inventory loss is imminent Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 143.51 45.13) 015AA2.0S RCP Malfunctions / 4 3,4 3.5 D D D D D D D ~ D D D When to secure RCPs on high bearing temperature Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):{CFR: 41.10/43.51 45.13) 022AK1.02 Loss of Rx Coolant Makeup I 2 2.7 3.1 ~ 0 0 0 DOD D DOD Relationship of charging flow to pressure differential between charging and RCS 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) 025AG2,4,46 Loss of RHR System 14 4.2 4.2 D D D D D D D D D D ~ Ability to verify that the alarms are consistent with the plant conditions.

This is a Generic, no stem statement is associated.

Page 1 of 3 8/1S/2008 5:59 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KS A 1 A2 A3 A4 G TOPIC:

RO SRO 02SAA2.06 Loss of Component Cooling Water / 8 28 3.1 0 0 0 0 0 0 0 ~ 0 0 0 The length of time after the loss of CCW flow to a component before that component may be damaged 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 ~ Ability to recognize abnonnal indications for system operating parameters which are entry-level conditions for This is a Generic, no stem statement is emergency and abnormal operating procedures.

associated.

040AK1.04 Steam Line Rupture - Excessive Heat 3.2 3.S ~OOODODDDOO Nil ductility temperature Transfer 14 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) 054AK1.02 Loss of Main Feedwater / 4 3.6 4.2 ~ODOOODDOOO Effects of feedwater introduction on dry SfG Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTlON}:(CFR: 41.8 to41.10/45.3) 055EK2.04 Stati.on Blackout f 6 D~DDDDDDDDD Pumps Knowledge ofthe interrelations between (EMERGENCY PLANT EVOLUTION) and the following:(CFR: 41.7 145.7/45.8) 056M1.25 Loss of Off-site Power 1 6 2.9 2.9 DOOOOO~DODO Main steam supply valve control switch 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 8/1812008 5:59 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 057AK3.01 loss of Vital AC Inst Bus 16 4.1 4.4 D 0 ~ 0 0 DOD 0 0 0 Actions contained in EOP for loss of vital ac electrical instrument bus 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) 058AA1.01 loss of DC Power 16 3.4 3.5 DOD 0 0 0 ~ 0 0 0 0 Cross-tie of the affected dc bus with the alternate supply Ability to operate and I or monitor the following as they apply to (ABNORMAL PLANT EVOlUTION):(CFR: 41.7/45.5/

45.6) 062AK3.02 loss of Nuclear Svc Water 14 3.6 3.9 0 0 ~ 0 0 0 0 0 0 0 0 The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 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) 065AK3.04 loss of Instrument Air 18 3 3.2 D 0 ~ 0 0 DOD 0 0 0 Cross-over to backup air supplies 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) 077AA101 Generator Voltage and Electric Grid 3.6 3.7 0 0 0 0 0 0 ~ 0 0 0 0 Grid frequency and voltage Disturbances I 6 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 Components and functions of control and safety systems.

including instrumentation, Signals, interlocks, failure Knowledge of the interrelations between modes and automatic and manual fealures.

(EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 f 45.7 145.8)

Page 3 of 3 8/18/2008 5:59 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 001AK3.02 Continuous Rod Withdrawal f 1 3.2 4.3 0 0 ~ 0 0 0 0 0 0 0 0 Tech-Spec limits on rod operability 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) 005AA1.01 Inoperable/Stuck Control Rod { 1 3.6 3.4 0 0 0 0 0 0 ~ 0 0 0 0 CROS Ability to operate and f or monitor the following as they apply to (ABNORMAL PLANT EVOLUT10N):(CFR: 41.7/45.51 45.6) 024AA2.01 Emergency Baration I 1 3.8 4.1 0 0 0 0 0 0 0 ~ 0 0 0 Whether boron flow and/or MOVs are malfunctioning from plant conditions Ability to determina and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 I 43.5 I 45.13}

036AK3.02 Fuel Handling Accident f 8 2.9 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Interlocks associated with fuel handling equipment Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5' 4110' 45.6 f 45.13) 059AK1.02 Accidental Liquid RadWaste ReI. / 9 2.6 3.2 ~ 0 0 0 0 0 0 0 0 0 0 Biological effects on humans of various types of radiation, exposure levels that are acceptable for nuclear Knowledge of the operational implications power plant personnel and the units used for radiation-of the following concepts as they apply to intensity measurements and for radiation exposure levels the (ABNORMAL PLANT EVOLUT!ON):(CFR: 41.8 to 41.10 145.3) 067 AG2A.49 Plant Fire On-site 19 8 4.6 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to perform without reference to procedures those actions that require immediate operation of system This is a Generic. no stem statement is components and controls.

associated.

Page 1 of 2 8/18/2008 5:59 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCT10N: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO WE08EA 1.3 RCS Overcooling - PTS I 4 3.6 4.0 0 0 0 0 0 0 ~ 0 0 0 0 Desired operating results during abnormal and emergency situations.

Ability to operate and f or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7/45.5 J 45.6)

WE09.EK1.3 Natural Circ. f 4 3.3 3.6 ~ 0 0 0 0 0 0 0 0 0 0 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Knowledge of the operational implications Operations).

of the following concepts as they apply to the EMERGENCY PLANT EVOLUT10N):(CFR: 41.8 to 41.10 I 45.3)

WE 14EK2.1 Loss of CTMT Integrity 15 3.4 3.7 0 ~ 0 0 0 0 0 0 0 0 0 Components and functions of control and safety systems, including instrumentation, signals, interlocks. failure Knowledge of the interrelations between modes and automatic and manual features.

(EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7145.7 I 45.8}

Page 2 of 2 8/18/2008 5:59 AM

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

RO SRO 003K1.13 Reactor Coolant Pump 2.S 2.S ~DDDDDDDDDD RCP bearing lift oil pump Knowledge of the physical connections andfor cause-effect relationships between (SYSTEM) and thefollowing:(CFR: 41.2 to 419 J 45.7 to 45.8) 003K6.04 Reactor Coolant Pump 2.8 3.1 DDDDD~DDDDD Containment isolation valves affecting RC P operation Knowledge of the effect that a loss or malfunction of the follOWing will have on the (SYSTEM):(CFR: 41.7 14S.7) 004A2.13 Chemical and Volume Control 3.6 3.9 o 0 0 0 0 0 D'~ 0 0 0 Low RWST 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) 005K6.03 Residual Heat Removal 2.S 2.6 DDDOD~DDDDO RHR heat exchanger Knowledge of the effect that a loss or malfunction of the fo[1OV11ing will have on the (SYSTEM):(CFR: 41.714S.7) 006A2.06 Emergency Core Cooling 3.3 3.5 DDDDDOD~DDO Water hemmer 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) 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 DDDDDDDDD~D Relationships between PZR level and chang ing levels of the PRT and bleed holdup tank Ability to manually operate and/or monitor in the control room: (CFR: 41.7 I 4S.5 to 45.8)

Page 1 of 5 8118/2008 6:00 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME j SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 008A4.03 Component Cooling Water 2.7 2.5 0 0 0 0 0 0 0 0 0 ~ 0 Throttling of the CCW pump discharge valve A bility to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 008K3.01 Component Cooling Water 3.4 3.5 0 0 ~ 0 0 0 0 0 0 0 0 Loads cooled by CCWS Knowledge of the effect that a loss or malfunction of the (SYSTEM) will haw on thefoliowing:(CFR: 41] 145.6) 010K1.02 Pressurizer Pressure Control 3.9 4.1 ~ 0 0 0 0 0 0 0 0 0 0 ESFAS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following: (CFR: 41.2 to 41.9/45.71045.8) 010K5.01 Pressurizer Pressure Control 3.5 4.0 0 0 0 0 ~ 0 0 0 0 0 0 Determination of condition of fluid in PZR, using stearn tables Knowledge of the operation a impncations of the following concepts as they apply to the (SYSTEM):(CFR: 41.5145.7) 012A3.04 Reactor Protection 2.8 2.9 0 0 0 0 0 0 0 0 ~ 0 0 Circuit breaker Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 145.5) 013K2.01 Engineered Safety Features Actuation 3.6 3.8 0 ~ 0 0 0 0 0 0 0 0 0 ESFAS/safeguards eqUipment control Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 022K4.03 Containment Cooling 3.6 4.0 0 0 0 ~ 0 0 0 0 0 0 0 Automatic containment isolation Knowledge of (SYSTEM) design fffiture(s) and or interlock(s) which provide for the following:(CFR: 41.7)

Page 2 of 5 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 DDDDDD~DDDD 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 DDDDDDD~DDD 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 DDDDDD~DDDD 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. DD~DDDDDDDD 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 DDD~DDDDDDD 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 DDDDD~DDDDD 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 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 062K1.03 AC Electrical Distributicn 3.5 4.0 ~ 0 0 0 0 0 0 0 0 0 0 DC distribution 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) 063K2.01 DC Electrical Distribution 2.9 3.1 0 ~ 0 0 DOD D D D D Major DC loads Knowledge of electrical power supplies to the foilowing:(CFR: 41.7) 06402.4.30 Emergency Diesel Generator 2.7 4.1 DOD 0 0 DODD 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside This is a Generic, no stem statement is agencies.

associated.

064K3.02 Emergency Diesel Generator 4.2 4.4 0 0 ~ 0 0 0 0 0 0 0 0 ESFAS controlled or actuated systems Knowledge of the effect that a loss or malfunction ofthe (SYSTEM) will have on the foIlowing:(CFR: 41.7/45.6) 073K5.01 Process Radiaticn Monitoring 2.5 3.0 0 0 0 0 ~ 0 0 0 0 0 0 Radiation theory, including sources, types, units and effects Knowledge of the operations impHcatlons of the following concepts as they apply to the (SYSTEM):(CFR: 41.S J 4S.7) 076G2.1.23 Service Water 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to perform specific system and integrated plant procedures during all modes of plant operation.

This is a Generic, no stem statement is associated.

076K4.06 Service Water 2.8 32 DDD~DDDDDDD Service water train separation Knowledge of (SYSTEM) design fEBture(s) and or interlock(s) which prO\lide for the foUowing:(CFR: 41.7)

Page40fS 8/18/2008 6:00AM

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 078A3.01 Instrument Air 3.1 3.2 D D D DD DDD ~ D D Air pressure Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7 /45.5) 103G2.2.36 Containment 3.1 4.2 D D D D DOD D D D ~ Ability to analyze the effect of maintenance activities, such as degraded power sources, on the st<tus of limiting This is a Generic, no stem statement is conditions of operations associated.

Page 5 of 5 8118/2008 6:00AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G TOPIC:

RO SRO 011 K6.06 Pressurizer Level Control 2.5 2.8 D DOD 0 ~ D DOD D Correlation of demand signal indication on charging pump flow valve controller to the valve position 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 ~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects This is a Generic, no stem statement is associated.

016K3.07 Non-nuclear Instrumentation 3.6 3.7 D 0 ~ 0 DOD DOD 0 ECCS Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 017K4.03 In-core Temperature Monitor 3.1 3.3 DOD ~ DOD DOD 0 Range of temperature indication Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 027A4.04 Containment Iodine Removal 2.8 2.9 D D U 0 0 DOD D ~ D Filter temperature Ability to manually operate andlor monitor in the control room:(CFR: 41.7/45.5 to 45.8) 035A1.01 Steam Generator 3.6 3.8 DOD DOD ~ 0 D 0 [J S/G wide and narrow range level during startup, shutdown and normal operations Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 041K1.06 Steam Dump/Turbine Bypass Control 2.6 2.9 ~ 0 0 0 0 DOD 0 0 0 Condenser 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 811812008 600 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 045A2.17 Main Turbine Generator 2.7 2.9 D D D D D D D ~ D D D Malfunction of electro hydraulic control 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) 055A3.03 Condenser Air Removal 2.5 2.7 D n D DD DD~DD Automatic diversion of CARS exhaust Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 071K5.04 Waste Gas Disposal 2.5 3.1 D D D D ~ D D D D D D Relationship of hydrogen/oxygen concentrations to flammability Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM): (CFR: 41.5 / 45.7)

Page 2 of 2 8/1812008 6:00 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.18 Conduct of operations 3.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ability to make accurate, clear and concise logs, records, status boards and reports.

G2.1A5 Conduct of operations 4.3 4.3 0 DOD DODD 0 D ~ Ability to identify and interpret diverse indications to validate the response of another indication G2.2.35 Equipment Control 3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~ Ability to determine Technical Specification Mode of Operation G2.2.39 EqUipment Control 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification action statements for systems.

G2.3.11 Radiation Control 3.8 4.3 0 DOD 0 0 0 0 0 0 ~ Ability to control radiation releases.

G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 DOD 0 ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation exposure limits under normal and emergency conditions Page 1 of 2 811812008 6:00 AM

ES*401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO G2.4.13 Emergency Procedures/Plans 4.0 4.6 D D D D D D D D D D ~ Knowledge of crew roles and responsibilities during EOP usage.

G2.4.23 Emergency Procedures/Plans 3.4 4.4 D D D D D D D D D D ~ Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

G2.4.38 Emergency ProcedureslPlans 2.4 4.4 D D D D D D D D D D ~ Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

Page 2 of 2 8/18/2008 6:00 AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: lR K1 K2 K3 K4 KS K6 Ai A2 A3 A4 G TOPIC:

RO SRO 011EG2.2.37 Large Break LOCA 13 3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to detefmine operability andlor availabil~y ci safety related equipment This is a Generic, no stem statement is associated.

025AG2A8 Loss of RHR System 14 3.8 4.S 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

This is a Generic, no stem statement is associated.

026AA2.01 Loss of Component Cooling Water 18 2.9 3.S 0 0 0 0 0 0 0 ~ 0 0 0 Location of a leak in the CCWS Ability to determine and intelpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/ 43.5/4S.13) 056AA2.54 Loss of Off-site Power 1 6 2.9 3 DOODOOO~ODD Breakef position (remote and local)

Ability to determine and intelprel the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 143.5/45.13) 065AG2.2.4 Loss of Instrument Air 18 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions This is a Generic, no stem staternent is between units at a facility.

associated .

WE04EA2.1 LOCA Outside Containment 13 3.4 4.3 0 0 0 0 0 0 0 ~ 0 0 0 Facillty conditions and selection of appropriate procedures during abnormal and emefgency opefalions.

Ability to detefmine and intelprel the following as they apply to (EMERG ENCY PLANT EVOLUTION):(CFR: 41.10 143.S I 45.13)

Page 1 of 1 8118/2008 6:00AM

ES*401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003AA2.01 Dropped Control Rod 11 3.7 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Rod position indication to actual rod position Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTlON):(CFR: 41.10 143.51 45.13) 028AA2.03 Pressurizer Level Malfunction 1 2 2.8 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Charging subsystem flow indicator and controller Ability to determine and interpret the follOWing as they apply to ABNORMAL PLANT EVOLUT10N):(CFR: 41.10 I 43.5 I 4S.13) 068AG2.4.20 Control Room Evac. / 8 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications of EOP warnings, cautions and notes.

This is a Generic, no stem statment is associated.

we10EG2.4.31 Natural Circ. With Seam Void/4 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of annunciators alarms, indications or response procedures This is a Generic, no stem statement is associated.

Page 1 of 1 811812008 6:00AM

ES401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES401~2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO 003G2.4.31 Reactor Coolant Pump 4.2 4.1 DOD D DOD 0 D D ~ Knowledge of annunciators alarms, indications or response procedures This is a Generic, no stem statement is associated.

005G2.2.25 Residual Heat Removal 3.2 4.2 ODD DOD DOD 0 .~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

This is a Generic, no stem statement is associated.

007A2.02 Pressurizer Relief/Quench Tank 2.6 3.2 0 DOD D D D ~ D D D Abnormal pressure in the PRT 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) 010G2.1.19 Pressurizer Pressure Control 3.9 3.8 D DOD D D DOD 0 ~ Ability to use plant computer to evaluate system or component status.

This is a Generic, no stem statement is associated.

026A2.07 Containment Spray 3.6 3.9 0 D D D DOD ~ D D D Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump Ability to (a) predict the impacts of the screen, pump inlet high temperature exceeded cavitation, following on the (SYSTEM) and (b) based voiding} or sump level below cutoff (interlock) limit on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

Page 1 of 1 8/18/2008 6:00 AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401*2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 034A3.{)2 Fuel Handling Equipment 2.5 3.1 0 0 0 0 0 0 0 0 0 0 0 load limits Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.71 45.5) 072G2.2.44 Area Radiation Monitoring 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications 10 verify the status and operation of a system, and understand how This is a Generic, no stem statement is operator actions and directives affect plant and system associated. conditions 079G2.2.3 Station Air 3.8 3.9 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

This is a Generic, no stem statement is associated.

Page 1 of 1 8118/2008 6:01AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2K3 K4 K5 K6 Ai A2 A3 A4 G TOPIC:

RO SRO G2.i.18 Conduct of operations 3.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ability to make accurate, clear and concise logs, records, status boards and reports, G2.2.1 Equipment Control 4.5 4,4 0 0 0 0 0 0 0 0 0 0 ~ Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.39 Equipment Control 3.9 4.5 ODD DDOODO~ Knowledge of less than one hour technical specification action statements for systems.

G2.3,4 Radiation Control 3.2 3.7 0 00 0 0 0 0 0 0 0 ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.17 Emergency Procedures/Plans 3.9 4.3 0 O[JODOODDI~ Knowledge of EOP terms and definitions.

G2.4,35 Emergency Procedures/Plans 3,8 4,0 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 1 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

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