ML12194A388

Initial Exam 2012-301 Draft Administrative Documents

ML12194A388
Person / Time
Site:	Harris
Issue date:	07/10/2012
From:	NRC/RGN-II
To:	Progress Energy Co
References
50-400/12-301
Download: ML12194A388 (18)

Text

ES-301- Administrative Topics OutIine Form ES3011 Facility: Harris Nuclear Plant Date of Examination: February 13, 2012 Examination Level: RO

• SRO Operating Test Number: 05000400/2012301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Requirements for Makeup to RWST During a Large Break LOCA after Cold Leg Recirculation has been established (JPM ADM-105) Common Conduct of Operations N, R K/A G2. 1.25 2012 NRC RO I SRO Al-i Determine Subcooling with the Subcooling Margin Monitor Unavailable (JPM ADM-031) Common Conduct of Operations K/A G 2.1.23 R

2012 NRC ROISROA1-2 Perform a Quadrant Power Tilt Ratio (QPTR) calculation with a control rod misaligned. (JPM ADM-010)

Equipment Control D,R K/AG2.2.12 2012 NRC RO A2 Determine the approval requirements and stay time limit for working in a Locked High Radiation Area.

(JPM ADM-043) Common Radiation Control D, R K/A G2.3.4 2012 NRC RO I SRO A3 NOT SELECTED FOR RO Emergency Procedures/Plan N/A 2012 NRC RO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (2)

(N)ew or (M)odified from bank ( 1) (1)

(P)revious 2 exams ( 1; randomly selected) (1) 12/26/2011 Rev. 1

ES-301 Administrative Topics Outline Form ES-3d-i Facility: Harris Nuclear Plant Date of Examination: February 13, 2011 Examination Level: RD SRO Operating Test Number: 05000400/2012301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Requirements for Makeup to RWST During a Large Break LOCA after Cold Leg Recirculation has

. been established (JPM ADM-105) Common Conduct of Operations N, R K/A G2.1.25 2012 NRC RO/SRO Al-i Determine Subcooling with the Subcooling Margin Monitor Unavailable (JPM ADM-031) Common Conduct of Operations K/A G 2.1.23 R

2O12NRCRO/SROA1-2 Perform a Quadrant Power Tilt Ratio (QPTR) calculation with a control rod misaligned.

(JPM ADM-010)

Equipment Control D R KJAG2.2.12 2012 NRC SRO A2 Determine the approval requirements and stay time limit for working in a Locked High Radiation Area.

(JPM ADM-043) Common Radiation Control D, R K/A G2.3.4 2012 NRC RO/SRO A3 Given a Set of Plant Conditions Classify An Event and make a Protective Action Recommendation.

Emergency Procedures/Plan N, R K/A G2.4.41 2012 NRC SRO A4 NOTE: All items (5 total) are required for SROs. RD applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (2)

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1; randomly selected) (1) 12/26/2011 Rev. 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Harris Nuclear Plant Date of Examination: 02/13/2012 Exam Level: RO SRO-l SRO-U (bold) Operating Test No.: 05000400/2012301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF bold) -

System / JPM Title Type Code* Safety Function

a. Pull control rods to POAH, two Safeties tail OPEN after A, D, L, S 1 Reactor is at POAH 001 A1.07

b. Take Corrective Action For The Failure of a CSIP Mini-Flow Valve to Reposition (PATH-i) A D L S 2

(JPM-CR-225)

K/A 006 A4.07

c. Pressurizer Pressure Master Controller Failure (AOP-O1 9) A, N, S 3 (JPM-CR-251)

K/A APE 027AA2.15

d. Initiate RCS Feed and Bleed (FRP-H.i) A, D, L, S 4P (J PM-CR068)

K/A EPEEO5EA1.1

e. Perform a Main Turbine Overspeed Trip Test (OPT-i 075) N, S 4S (JPM-CR-251)

K/A 045 A3.08

f. Containment Cooling to Max Cooling Mode (OP-i 69) D, 5 5 (JPM CR-033) RO Only K/A 022A4.01

g. LOSP While Paralleling a Emergency Diesel Generator A, EN, P, S 6 from the Main Control Room for Testing (OP-i 55)

(JPM-CR-203)

K/A 056 A2.14

h. Fuel Handling Accident with Fuel Handling In Progress A, D, S, L 8

• Dropped Fuel Assembly (AOP-013)

(JPM CR-035)

K/A 034 A2.01 11/28/2011 Rev. 0

In-Plant Systems@ (3 for RO); (3 for SAC-I); (2 or 3 for SRO-U - BOLD)

I. Shift AFW Pump Suction Locally (PATH 1, Attachment 12 E, D, R 4s (JPM-IP-004)

K/A 061 K401

j. Reset Safety Injection Locally (PATH 1, Attachment 1) E, D 7 (JPM-IP-231)

K/A 013 A2.06

k. Perform Local Actions For Placing a Failed Pressurizer EN, P 3 Pressure channel In TEST (OWP-RP-02)

(JPM-IP-247) k/A APE 027 AA2. 16

@ All AC and SRO-l 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 SAC-I / SAC-U (A)lternate path 4-6 I 4-6 / 2-3 (6, 6, 3)

(C)ontrol room (D)irect from bank 9/ 8/ 4 (7, 6, 3)

(E)mergency or abnormal in-plant 1 / 1 / 1 (2, 2, 2)

(EN)gineered safety feature - / - / 1 (2, 2, 1)

(L)ow-PowerlShutdown 1 / 1 I 1 (4,4,1)

(N)ew or (M)odifled from bank including 1 (A) 2I 2/ 1 (2, 2, 1)

(P)revious 2 exams 3I 3I 2 (2, 2, 1)

(R)CA 1I1I1 (1,1,1)

(S)imulator 11/28/2011 Rev. 0 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: SHEARON HARRIS Date of Exam: FEBRUARY 2012 SRO-OnIy Points Tier Group 1 1 1 G*

K K K K K KIAIAIA A G A2 Total

=

1 =

2 =

3 =

4 5 6111213

= = =

4

• Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 .1. N/A 2 2 N/A ._L. 9 2 2 4 Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 323223323 32 28 3 2 5 2.

Plant 2 11111111110 10 0 2 1 3 Systems Tier Totals 4 3 4 3 3 4 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 I 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A 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 K/A 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 SIRO-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/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant*specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1 .b of ES-401 for the applicable K/As.

8. On the following pages. enter the KJA 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 0 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-onty exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit 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 / SAFETY FUNCTION: IR Ki 1(2 1(3 1(4 1(5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 007EK1 .02 Reactor Trip Stabilization Recovery

- - 3.4 3.8 [i ri El El [1 H H H H H H Shutdown margin 009EK2.03 Small Break LOCA /3 3 3.3 H I Li H H H H H H H Ei. SIGs 015AG2.l .20 RCP Malfunctions 14 4.6 4.6 H H H H H H H H H H j Ability to execute procedure steps.

025AA2.07 Loss of RHR System / 4 3.4 3.7 H H H H H Li H i H H H Pump cavitation 026AA1.05 Loss of Component Cooling Water! 8 3.1 3.1 H H H H H H H H H H The CCWS surge tank, including level control and level alarms and radiation alarm 027AG2.4.35 Pressurizer Pressure Control System 3.8 4.0 H H H H H H H H H H Knowledge of local auxiliary operator tasks during Malfunction I 3 emergency and the resultant operational effects 038EA1 .40 Steam Gen. Tube Rupture 13 4 H H H H H H 1J H H H H Adding boron to raise its ppm to the required shutdown concentration.

054AK1 .02 Loss of Main Feedwater / 4 3.6 4.2 IJ H H H [1 Li H H H H H Effects of feedwater introduction on dry S/G 055EK1 02 Station Blackout / 6 4.1 4.4 [ J LI H H H H H H H H Natural drculatioa cooling 056AG2.4.46 Loss of Oft-site Power / 6 4.2 4.2 H H H H H H H H H H Ability to verify that the alarms are consistent with the plant conditions.

057AK3.01 Loss of Vital AC Inst. Bus / 6 4.1 4.4 H H II H H H H H H H LI Actions contained in EOP for loss of vital ac electrical instrument bus Page 1 of 2 8/18/2011 9:59 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 1(3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

HO SRO 058AA2.03 Loss of DC Power / 6 3.5 3.9 [] [! U U U U U DC loads lost; impact on ability to operate and monitor plant systems 062AA2.01 Loss of Nudear Svc Water! 4 2.9 3.5 [] fl fl [] U LI LI i LI LI LI Location of a leak in the SWS 065AK3.04 Loss of Instrument Air/B 3 3.2 fJ j J Crossover to backup air supplies 077AA1 .03 Generator Voltage and Electric Grid 3.8 3.7 [J [] LI [1 L] [1 J [1 J [J LI Voltatge regulator controls Disturbances / 6 WEO4EK2.1 LOCA Outside Containment /3 3.5 3.9 LI LI LI LI LI LI LI LI El LI components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEO5EK2.2 Inadequate Heat Transfer Loss of

- 3.9 4.2 LI [I LI E] LI [1 LI LI LI LI [] Facilitys heat removal systems, including primary Secondary Heat Sink /4 coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK3.2 Loss of Emergency Coolant Recirc. / 4 3.5 4.0 LI LI Ii H U LI Li LI LI LI Normal, abnormal and emergency operating procedures associated with (Loss of Emergency coolant Recir).

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

RO SRO OO1AA1 .03 Continuous Rod Withdrawal! 1 3.4 3.2 fl LI LI LI LI LI LI LI [1 LI Boric acid pump control switch 036AK3.03 Fuel Handling Accident /8 3.7 4.1 H H LI LI H H fi LI LI LI Guidance contamed in EOP for fuel handling incident 037AK1 .02 Steam Generator Tube Leak / 3 3.5 3.9 ] LI fl LI LI LI LI LI LI LI LI Leak rate vs. pressure drop 051AA2.02 Loss of Condenser Vacuum /4 3.9 4.1 H H H H H H H fl fl fl Conditions requiring reactor and/or turbine trip 068AA2.ll Control Room Evac. 18 4.3 4.4 LI LI LI LI LI LI El [) LI LI [E] Indications of natural circulation 076AK2.0l High Reactor Coolant Activity /9 2.6 3 LI LI LI LI LI LI LI LI H LI Process radiation monitors WEO3EA1 .2 LOCA Cooldown Depress. /4

- 3.7 3.9 H F] LI LI LI LI t] LI LI LI LI Operating behavior characteristics of the facility.

WEO8EK3.3 RCS Overcooling PTS / 4

- 3.7 3.8 LI LI {I LI LI LI LI LI LI LI *LI Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

Ability to evaluate plant and make

[VVVVJ wel5EG2.1 .7 Containment Flooding / 5 4.4 4.7 H LI LI LI LI [**** LI LI LI ]j performance operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Page 1 of 1 8/18/2011 9:59AM

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

RO SRO 003A1.06 ReactorCoolantPump 2.9 3.1 fl fl [] [] [ [] [J [J L] PZRsprayflow 004G2.2.39 Chemical and Volume Control 3.9 4.5 LI LI LI H [i El E] LI LI Knowledge of less than one hour technical specification

- action statements for systems.

004K4.07 Chemical and Volume Control 3.0 3.3 El LI LI Li LI LI [] fl [] Water supplies 005K3.05 Residual Heat Removal 3.7 3.8 LI iL] U Li LI U U Li ECCS 005K6.03 Residual Heat Removal 2.5 2.6 fl LI Li LI LI ] LI LI El LI Li RHR heat exchanger 006A1 .16 Emergency Core Cooling 4.1 4.2 LI LI [I U [] fl fl RCS temperature, including superheat, saturation and subcooled 006K6.03 Emergency Core Cooling 3.6 3.9 LI LI LI LI LI LI LI LI LI LI Safety Injection Pumps 007K3.01 Pressurizer Relief/Quench Tank 3.3 3.6 Li El LI [1 fl fl fl [] J Containment 008A3.10 Component Cooling Water 2.9 3.0 Li j J J LI LI L] LI [J fl CCW pump instruments and their respective sensors, including flow, pressure, oil level and discharge temperature 008A4.1 1 Component Cooling Water 3.0 2.9 LI LI LI LI LI LI LI LI LI CCW pump recirculation valve and its three-way control switch 010K6.0l Pressurizer Pressure Control 2.7 3.1 LI LI LI LI LI Li LI Li LI LI Pressure detection systems Page lof 3 8118/2011 9:59AM

ES-401, REV 9 T2G1PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 012A4.06 Reactor Protection 4.3 4.3 [J fl fl [1 [] [J Li EE1Lfl Reactor trip breakers 01 3K5 02 Engineered Safety Features Actuation 29 33 [J El Li LI 1i E] El [Z El El FL Safety system logic and reliability 022A4.03 Containment Cooling 3.2 3.2 [] [] Li Li Li Li Li LI El Ii Li Dampers in the CCS 026A2.08 Containment Spray 3.2 3.7 [] L] Li Li LI Li Li l Li Li Li Safe securing of containment spray when it can be done) 039G2A.21 Main and Reheat Steam 4.0 4.6 Li Li Li Li Li El LI LI Li Li [J Knowledge of the parameters and logic used to assess the status of safety functions 059K4.02 Main Feedwater 3.3 3.5 Li El: El I LI LI [1 [1 LI El LI Automatic turbine/reactor trip runback 061 K5.05 Auxiliary/Emergency Feedwater 2.7 3.2 Li Li Li Li 1 Li LI Li Li LI Li Feed line voiding and water hammer 062A1 .03 AC Electrical Distribution 2.5 2.8 LI LI El El LI El El LI El El Effect on instrumentation and controls of switching power supplies 062K2.01 AC Electrical Distribution 3.3 3.4 Li I] LI El Li El El LI Li El LI Major system loads 063A3.01 DC Electrical Distribution 2.7 3.1 fl fl LI El El El El [Li [I El El Meters, annunciators, dials, recorders and indicating lights 064A2.14 Emergency Diesel Generator 2.7 2.9 LiLiLiLiLiLiLiLiLiLi Effects (verification) of stopping ED/G under load on isolated bus Page 2 of 3 8118/2011 9:59AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki 1(2 1(3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

nO SRO 064K1 .01 Emergency Diesel Generator 4.1 4.4 fl L] Li Li LI El El El LI fl AC distribution system Those systems served by PRMs 0731(1 .01 Process Radiation Monitoring 3.6 3.9 [] Li El El El El El Li Li L 076K2.01 Service Water 2.7 2,7 El [j El El El El El El El [1 El Service water 078A3.01 Instrument Air 3.1 3.2 El El LI El LI LI Li [I I El El Air pressure 078K3.03 Instrument Air 3.0 3.4 [] 1I El LI LI El LI El LI [1 Cross-tied units Containment 3.1 3.5 fl J Shield building vent system 1031(1.03 J Page 3 of 3 8/18/2011 9:59 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002K1.12 Reactor Coolant 3.5 3.6 [] [] fl [] [] [J fl [j U MS 011K2.01 Pressurizer Level Control 3.1 3.2 fl J [1 U J U U U U U Charging pumps 014K3.02 Rod Position Indication 2.5 2.8 j U [El L] [El [1 U [3 [3 Plant computer 01 7A3.01 In-core Temperature Monitor 3.6 3.8 [E] [3 [3 [3 [3 [3 [3] [3] [3 [3 Indications of normal, natural and interrupted circulation of RCS High temperature in the filter system 027A2.0l Containment Iodine Removal 3.0 3.3 LI U Li Li LI LI U [l [3] [3 [1 2.9 3.1 [3 [3 [3 [3 [3 [3 [3 Negative pressure in containment 029K4.02 Containment Purge [3 [33 [3 033A1 .02 Spent Fuel Pool Cooling 2.8 3.3 LI U [3] U Li U [ Li Li [3] [3 Radiation monitoring systems 3.0 F] j [3 [3] [3 [3 [3 SIG level detector 035K6.03 Steam Generator 2.6 [3 [3 [3 [3 068K5.04 Liquid Radwaste 3.2 3.5 [3 [3 [3 [3 [3] [3 [3] [3] [3 [3] BiologicaL hazards of radiation and the resulting goal of ALARA 079A4.01 Station Air 2.7 2.7 [3 [3 [3 [3] [3 [3 [][3 [3 [ [3 Cross-tie valves with lAS Page 1 of 1 8/18/2011 9:59 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME / SAFETY FUNCTION: IR Ki 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.36 Conduct of operations 3.0 4.1 EL1flflEODflLH Knowledge of procedures and limitations involved in core alterations G2.1 .45 Conduct of operations 4.3 4.3 L1LiDEE1E1E1L Ability to identify and interpret diverse indications to validate the response of another indication G2.2.18 Equipment Control 2.6 3.8 EDDELH1 Knowledge of the process for managing maintenance activities during shutdown operations.

G2.2.38 Equipment Control 3.6 4.5 L1E1LiE Knowledge of conditions and limitations in the facility license.

G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3. 13 Radiation Control 3.4 3.8 flELLLULI Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 ((1 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.1 1 Emergency Procedures/Plans 4.0 4.2 El LI El El DLI [1 El LI 1i Knowledge of abnormal condition procedures.

G2.4.25 Emergency Procedures/Plans 3.3 3.7 El LI U U DflDDDE Knowledge of fire protection procedures.

G2.4.29 Emergency Procedures/Plans 3.1 4.4 U [LI U U U U U U {J U {j Knowledge of the emergency plan.

Page 1 of 1 8/18/2011 9:59 AM

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

RO SRO 015AA2.09 RCP Malfunctions /4 3.4 3.5 U [J U U U U When to secure RCPs on high stator temperatures 029EG2.4.20 ATWS / 1 3.8 4.3 U J U U LI U LI U U Knowledge of operational implications of EOP warnings, cautions and notes.

038EA2.13 Steam Gen. Tube Rupture /3 3.1 3.7 U U U U U U U LI U U Magnitude of rupture 055EG2.4.9 Station Blackout / 6 3.8 4.2 U U LI LI LI LI LI LI LI LI Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RI-IR) mitigation strategies.

058AA2.02 Loss of DC Power / 6 3.3 3.6 LI LI LI LI LI LI LI LI [] LI 125V dc bus voltage, low/critical low, alarm 077AG2.4.3 Generator Voltage and Electric Grid 3.7 3.9 LI U U U U U U U U U Ability to identity post-accident instrumentation.

Disturbances / 6 Page 1 of 1 811&2011 9:59AM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 005AG2.2.22 Inoperable/Stuck Control Rod I I 4.0 4.7 Knowledge of limiting conditions for operations and safety Iimts.

4.2 Knowledge of annunciators alarms, indications or 032AG2.4.31 Loss of Source Range NI /7 4.1 UL1L1L1E1LiL1 response procedures

[1 LI LI Adherence to appropriate procedures and operation WEO8EA2.2 RCS OercooIing PTS / 4

- 3.5 4.1 EL. ED Li DLI within the limitations in the facilitys license and amendments.

Facility conditions and selection of appropriate WE13EA2.1 Steam Generator Over-pressure / 4 2.9 3.4 DL1ELiDLiLIE1LiLi procedures during abnormal and emergency operations.

Page 1 of 1 8/18/2011 9:59 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO 01 2A2.04 Reactor Protection 3.1 3.2 Li [1 Li Li Li Li LI [] [j Erratic power supply operation 013A2.03 Engineered Safety Features Actuation 4.4 4.7 H Li Li H Li fl H H Li Li Rapid depressurization 061G2.2.40 Auxiliary/Emergency Feedwater 34 4.7 Lj [] [1 Li J H H Ability to apply technical specifications for a system.

076G2.1.7 Service Water 4.4 4.7 [] [J Li Li Li Li Li Li Li Li ] Abilitytoevaluateplantperformanceandmake operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

078A2.01 Instrument Air 2.4 2.9 Li Li Li Li Li Li Li I] Li Li Li Air dryer and filter malfunctions Page 1 of 1 &18/2011 9:59AM

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

RO SRO Voltage to instruments, both too high and too low 016A2.04 Non-nuclear Instrumentation 2.5 2.6 [] LI El El LI El LI ll [1 El El Knowledge symptom based EOP mitigation strategies.

068G2.4.6 Uquid Radwaste 3.7 4.7 [] [] El El El LI LI El El El ll 071 A2.08 Waste Gas Disposal 2.5 2.8 LI El El El El El El l] El El El Meteorological changes Page 1 of 1 &181201 1 9:59 AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTUNE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl 1(2 1(3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .41 Conduct of operations 2.8 3.7 El El LI El El El C] [] [] C] [ Knowledge of the refueling processes G2.2.25 Equipment Control 3.2 4.2 C] C] C] C] [] C] C] C] C] ] Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.2.43 Equipment Control 3.0 3.3 IE] C] C] C] C] C] LI C] LI LI [] Knowledge of the process used to track inoperable alarms G2.3.12 Radiation Control 3.2 3.7 C] LI LI C] C] [1 [1 El LI El ] Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 [] C] C] C] C] C] J C] C] C] Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.30 Emergency Procedures/Plans 2.7 4.1 C] [] C] C] C] C] C] C] Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

G2.4.8 Emergency Procedures/Plans 3.8 4.5 C] LI LI C] C] LI LI LI LI El E Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 8/18/2011 9:59 AM