ML13301A714

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VC Summer Initial Exam 2013-301 Draft Administrative Documents
ML13301A714
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/23/2013
From:
NRC/RGN-II
To:
South Carolina Electric & Gas Co
References
NRC ILO-11-01
Download: ML13301A714 (22)
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Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: VC SUMMER Date of Examination: 8/19/2013 Examination Level (circle one): RO / SRO Operating Test Number: NRC ILO-11-01 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate Head Venting Time in accordance with Conduct of Operations EOP-18.2, Response to Voids in Reactor Vessel, D,P (A1-a) Attachment 2.

K/A: 2.1.25 (RO:3.9, SRO:4.2)

Manually calculate QPTR with a dropped control rod in Conduct of Operations accordance with STP-108.001.

D (A1-b) K/A: 2.1.37 (RO:4.3, SRO:4.6)

Perform a boric acid flowpath operability verification in Equipment Control (A2) accordance with STP-104.003.

N K/A: 2.2.12 (RO: 3.7, SRO:4.1)

RO/SRO Common Radiation Control (A3) Calculate stay times for various workers in accordance M

with HPP-0153 and determine who can do the work.

K/A: 2.3.4 (RO:3.2, SRO:3.7)

Not selected for RO.

Emergency Plan (A4)

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

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

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

(P)revious 2 exams (< 1; randomly selected)

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: VC SUMMER Date of Examination: 8/19/2013 Examination Level (circle one): RO / SRO Operating Test Number: NRC ILO-11-01 Administrative Topic Type Describe activity to be performed (see Note) Code*

Review NIS Power Range Heat Balance in Conduct of Operations accordance with STP-102.002.

M (A1-a) K/A: 2.1.45: (RO:4.3, SRO:4.3)

Manually calculate QPTR with a dropped control rod in Conduct of Operations accordance with STP-108.001.

M (A1-b) K/A: 2.1.37 (RO:4.3, SRO:4.6)

Review an A train Control room Emergency Air Equipment Control (A2) Cleanup System Operability Test in accordance with N

STP-124.001.

K/A: 2.2.12 (RO: 3.7, SRO:4.1)

RO/SRO Common Radiation Control (A3) Calculate stay times for various workers in accordance M

with HPP-0153 and determine who can do the work.

K/A: 2.3.4 (RO:3.2, SRO:3.7)

Declare an Alert in accordance with EPP-001.

Emergency Plan (A4) K/A: 2.4.41 (RO:2.9, SRO: 4.6)

D NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

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

(P)revious 2 exams (< 1; randomly selected)

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: VC Summer Date of Examination: 8/19/2013 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: NRC ILO 01 Control Room Systems (8 for RO; 7 for SRO-I 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Generic Abnormal Plant Evolution 001 [NJPSF-141A] A,L,M,S 1 Continuous Rod Withdrawal (AOP-403.3, EOP-1.0, E-0)
b. System 022 [NJPSF-159] A,EN,N,S 5 Swap running RBCUs (SOP-114)
c. System 004 [NJPS-034A] D,S 2 Increase Letdown Flow to a Maximum to Improve Chemistry (SOP-102)
d. Generic Emergency Plant Evolution 038 [NJPSF-059B] A,D,S 3 Alternate Isolation of Ruptured S/G (MSIV fails to close)

(EOP-4.0/E-3)

e. System 005 [NJPS-151] D,L,S 4P Shift RHR Loops with RHR in service (SOP-115)
f. System 059 [NJPSF-161] A,N,S 4S Respond to a feed regulating valve closure (AOP-210.1)
g. System 062 [NJPS-162] N,S 6 Start and Load the Main Generator (SOP-301)
h. System 103 [NJPS-152] D,S 8 Respond to high reactor building pressure (SOP-114)

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

i. Generic Abnormal Plant Evolution 068 [JPPF-013A/B] A,E,N 8 Start and load the diesel generator during control room evacuation (AOP-600.1)
j. Generic Abnormal Plant Evolution 040 [JPP-107A] M,E 4S Locally Close and De-Energize MS Loop B and C to the Turbine Driven Emergency Feedwater Pump (EOP-3.0, E-2)
k. Generic Emergency Plant Evolution 055 [JPPF-066A] E,M,R 6 Locally Isolate RCP Seals During a Total Loss of ESF Power (EOP-6.0, ECA-0.0)

NUREG-1021, Revision 9

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

@ 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 5 (C)ontrol room (D)irect from bank 9/ 8/4 4 (E)mergency or abnormal in-plant 1/ 1/1 3 (EN)gineered safety feature NA / NA / 1 (L)ow-Power / Shutdown 1/ 1/1 2 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 7 (P)revious 2 exams 3/ 3/2 0 (R)CA 1/ 1/1 1 (S)imulator NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: VC Summer Date of Examination: 8/19/2013 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: NRC ILO 01 Control Room Systems (8 for RO; 7 for SRO-I 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Generic Abnormal Plant Evolution 001 [NJPSF-141A] A,L,M,S 1 Continuous Rod Withdrawal (AOP-403.3, EOP-1.0, E-0)
b. System 022 [NJPSF-159] A,EN,N,S 5 Swap running RBCUs (SOP-114)
c. System 004 [NJPS-034A] D,S 2 Increase Letdown Flow to a Maximum to Improve Chemistry (SOP-102)
d. Generic Emergency Plant Evolution 038 [NJPSF-059B] A,D,S 3 Alternate Isolation of Ruptured S/G (MSIV fails to close)

(EOP-4.0/E-3)

e. System 005 [NJPS-151] D,L,S 4P Shift RHR Loops with RHR in service (SOP-115)
f. System 059 [NJPSF-161] A,N,S 4S Respond to a feed regulating valve closure (AOP-210.1)
g. System 062 [NJPS-162] N,S 6 Start and Load the Main Generator (SOP-301)
h. Not selected for the SRO-I In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
i. Generic Abnormal Plant Evolution 068 [JPPF-013A/B] A,E,N 8 Start and load the diesel generator during control room evacuation (AOP-600.1)
j. Generic Abnormal Plant Evolution 040 [JPP-107A] M,E 4S Locally Close and De-Energize MS Loop B and C to the Turbine Driven Emergency Feedwater Pump (EOP-3.0, E-2)
k. Generic Emergency Plant Evolution 055 [JPPF-066A] E,M,R 6 Locally Isolate RCP Seals During a Total Loss of ESF Power (EOP-6.0, ECA-0.0)

NUREG-1021, Revision 9

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

@ 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 5 (C)ontrol room (D)irect from bank 9/ 8/4 3 (E)mergency or abnormal in-plant 1/ 1/1 3 (EN)gineered safety feature NA / NA / 1 (L)ow-Power / Shutdown 1/ 1/1 2 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 7 (P)revious 2 exams 3/ 3/2 0 (R)CA 1/ 1/1 1 (S)imulator NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: VC Summer Date of Examination: 8/19/2013 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: NRC ILO 01 Control Room Systems (8 for RO; 7 for SRO-I 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Generic Abnormal Plant Evolution 001 [NJPSF-141A] A,L,M,S 1 Continuous Rod Withdrawal (AOP-403.3, EOP-1.0, E-0)
b. System 022 [NJPSF-159] A,EN,N,S 5 Swap running RBCUs (SOP-114)
c. Not selected for the SRO-U
d. Not selected for the SRO-U
e. Not selected for the SRO-U
f. Not selected for the SRO-U
g. Not selected for the SRO-U
h. Not selected for the SRO-U In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
i. Generic Abnormal Plant Evolution 068 [JPPF-013A/B] A,E,N 8 Start and load the diesel generator during control room evacuation (AOP-600.1)
j. Generic Abnormal Plant Evolution 040 [JPP-107A] M,E 4S Locally Close and De-Energize MS Loop B and C to the Turbine Driven Emergency Feedwater Pump (EOP-3.0, E-2)
k. Generic Emergency Plant Evolution 055 [JPPF-066A] E,M,R 6 Locally Isolate RCP Seals During a Total Loss of ESF Power (EOP-6.0, ECA-0.0)

NUREG-1021, Revision 9

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

@ 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 3 (C)ontrol room (D)irect from bank 9/ 8/4 0 (E)mergency or abnormal in-plant 1/ 1/1 3 (EN)gineered safety feature NA / NA / 1(control room system) 1 (L)ow-Power / Shutdown 1/ 1/1 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 5 (P)revious 2 exams 3/ 3 / 2 (randomly selected) 0 (R)CA 1/ 1/1 1 (S)imulator NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Facility: V.C. SUMMER Date of Exam: AUGUST 2013 ROK/ACapoPo,ts SRO-OnIy_Points Tier Group 1 1 G*

1 KKIKKKKAIAAAG A2 ITotal 1 213 4 5 6 112 3 4 Total 1 . 1 1. .1. L 18 3 3 6 Emergency &

Abnormal 2 2 1 2 N/A I 2 N/A j.. 9 2 2 4 Evolufions TierTotals 5 4 5 4 5 4 27 5 5 10 1 3 3 3 3 2 3 3 2 2 2 2 28 3 2 5 2.

Plant 2 .LJ... L+/-Q I. 10 0 2 1 3 Sys ems Tier Totals 4 4 4 f- --

+/- ?_ 2_ . I 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 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., exceptfor one category in Tier 3 ofthe 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 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/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 SRQ 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. Referto Section D.1.b of ES-401 forthe applicable K/As.

8. on the following pages, enter the K/A 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.
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 I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRQ OO7EK1 .02 - -

Reactor Trip Stabilization Recovery 3.4 3.8 j Shutdown margin

/1 008AK2.03 Pressurizer Vapor Space Accident I 3 2.5 2.4 j j j j ControNersand positioners 009EK1 .02 Small Break LOCA I 3 3.5 4.2 j Use of steam tables 01 1 EG2.2.44 Large Break LOCA I 3 4.2 4.4 j j j j 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 O15AG2.l .28 RCP Malfunctions I 4 4.1 4.1 j J j j Knowledge of the purpose and function of major system components and controls.

022AK3.07 Loss of Rx Coolant Makeup /2 3 3.2 El El El El El El El [] [] [] Isolating charging 025AK2.05 Loss of RHR System /4 2.6 2.6 Reactor building sump 026AA1 .06 Loss of Component Cooling Water /8 2.9 2.9 Control of flow rates to components cooled by the CCWS O29EA1 .04 ATWS / 1 3.9 3.8 BIT inlet valve switches 040AA2.02 -

Steam Line Rupture Excessive Heat 4.6 4.7 Conditions requiring a reactor trip Transfer / 4 054AK1.0l Lossof Main Feedwater/4 4.1 4.3 El El El El El El El El El El MFW line break depressurizes the S/G (similar to a steam line break)

Page 1 of 2 7/20/2012 10:13AM

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

RO SRQ 056AG2.4.l Loss of Off-site Power I 6 4.6 4.8 j Knowledge of EOP entry conditions and immediate action steps.

062AA2.O1 Loss of Nuclear Svc Water I 4 2.9 3.5 j Location of a leak in the SWS 065AK3.08 Loss of Instrument Air I 8 3.7 3.9 j j Actions contained in EOP for loss of instrument air O77AA1 .03 Generator Voltage and Electric Grid 3.8 3.7 LI Voltatge regulator controls Disturbances / 6 WEO4EA2.2 LOCA Outside Containment /3 a64 LI Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

WEO5EK2.2 -

Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary j j LI LI LI LI 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.

WEll EK3.4 Loss of Emergency Coolant Recirc. /4 3.6 3.8 LI LI LI RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

Page 2 of 2 7/20/2012 10:13 AM

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

RO SRQ 036AA1 .04 Fuel Handling Accident / 8 3.1 3.7 LI LI LI LI El El El El LI LI Fuel handling equipment during an incident 037AA2.08 Steam Generator Tube Leak /3 2.8 3.3 LI LI D LI D D LI D LI D Failure of Condensate air ejector exhaust monitor 059AK1 .05 Atal Liquid RadWaste Rel. / 9 2.6 3.6 LI LI D LI D D LI El LI LI The calculation of offsite doses due to a rease from the power plant 069AK2.03 Loss of CTMT Integrity / 5 2.8 2.9 El LI LI LI LI LI D D El El Personnel access hatch and emergency access hatch 074EG2.l.19 mad. Core Cooling/4 3.9 3.8 LI LI El D LI El LI LI LI LI Ability to use plant computer to evaluate system or component status.

WEO1EA2.1 Rediagnosis/3 3.2 4 LI El D D D El LI LI El LI Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WEO3EK3.4 -

LOCA Cooldown Depress. /4 3.5 3.9 RO or SRQ function within the control room team as El LI LI LI LI LI LI LI El appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

WEO7EK1.2 Saturated Core Cooling Core Cooling 3.1 3.6 LI LI LI LI LI LI LI LI LI LI Normal, abnormal and emergency operating procedures

/4 associated with (Pressurized Thermal Shock).

WE1 6EK3.4 High Containment Radiation /9 3.0 3.2 LI LI LI LI LI LI LI LI LI LI RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

Page 1 of 1 7/20/2012 10:13AM

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

RO SRO 003K2.02 Reactor Coolant Pump 2.5 2.6 j J j COW pumps 004K5.02 Chemical and Volume Control 3.5 3.9 j j j j Explosion hazard associated with hydrogen containing systems 005K5.05 Residual Heat Removal 2.7 3.1 j Plant response during solid plant: pressure change due to the relative incompressibility of water 006A3.08 Emergency Core Cooling 4.2 4.3 j j j j Automatic transfer of ECCS flowpaths 006K2.02 Emergency Core Cooling 2.5 2.9 Valve operators for accumulators 007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 Quench tank cooling 008G2.4.34 Component Cooling Water 4.2 4.1 El El El El El El El [] Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 008K3.03 Component Cooling Water 4.1 4.2 El El El El El El El El El El RCP 010K2.0l Pressurizer Pressure Control 3.0 3.4 El El El El El El El El El El PZR heaters 012A1.01 Reactor Protection 2.9 3.4 El El El El El El [] El El El El Trip setpoint adjustment 012K6.10 Reactor Protection 3.3 3.5 El El El El El El El El El El Permissive circuits Pagelof3 7/20/2012 10:13AM

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

RO SRO 013A3.02 Engineered Safety Features Actuation 4.1 4.2 J J j j j j Operation of actuated equipment 013K6.O1 Engineered Safety Features Actuation 2.7 3.1 J j j j Sensors and detectors 022A1 .03 Containment Cooling 3.1 3.4 j j Containment humidity 026A4.O1 Containment Spray 4.5 4.3 j j j CSS controls 039A1 1 0 Main and Reheat Steam 2.9 3.0 Air ejector PRM j

039A2.O1 Main and Reheat Steam 3.1 3.2 El j Flow paths of steam during a LOCA 059G2.4.31 Main Feedwater 4.2 4.1 El El El LI LI LI El [] Knowledge of annunciators alarms jndicaUons or response procedures 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 El El El El El El El El El El Pumps 062K1.02 AC Electrical Distribution 4.1 4.4 El El El El El El El El El El ED/G 062K4.06 AC Electrical Distribution 2.9 3.3 El El El One-line diagram of 6.9kV distribution, including sources El El El El El El El of normal and alternative power 063K1 .03 DC Electrical Distribution 2.9 3.5 El El El El El El El El El El Battery charger and battery Page2of 3 7/20/2012 10:13AM

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

RO SRO 064A4.03 Emergency Diesel Generator 3.2 3.3 Synchroscope 073A2.01 Process Radiation Monitoring 2.52.9 LI El LI Erratic or failed power supply 076K3.07 Service Water 3.7 3.9 LI El ELILI LI LI El LI ESF loads 078K4.02 Instrument Air 3.2 3.5 Cross-over to other air systems 103K1.02 Containment 3.9 4.1 Containment isolation/containment integrity 103K3.01 Containment 3.3 3.7 LI Loss of containment integrity under shutdown conditions Page 3 of 3 7/20/2012 10:13AM

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

RO SRO 002A2.02 Reactor Coolant 4.2 4.4 j j j j Loss of coolant pressure 014G2.4.20 Rod Position Indication 3.8 4.3 j j j j j j Knowledge of operational implications of EOP warnings, cautions and notes.

016K1.12 Non-nuclear Instrumentation 3.5 3.5 S/G 027K2.O1 Containment Iodine Removal 3.1 3.4 El El El El Fans 033K3.02 Spent Fuel Pool Cooling 2.8 3.2 El El Area and ventilation radiation monitoring systems El El El El El El El El 034K6.02 Fuel Handling Equipment 2.6 3.3 El El El El El El El El El El Radiation monitoring systems 035K5.03 Steam Generator 2.8 3.1 Shrink and swell concept El El El El El El El El El El 071A3.O1 Waste Gas Disposal 2.6 2.7 HRPS El El El El El El El El El El 079K4.Ol Station Air 2.9 3.2 El El El Cross-connect with lAS El El El El El El El 086A1 .02 Fire Protection 3.0 3.2 Fire water storage tank level El El El El El El El El El El Page 1 of 1 7/20/2012 10:13 AM

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

RO SRQ G2.l .15 Conduct of operations 2.7 3.4 J j j j Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

G2.1.17 Conduct of operations 3.9 4.0 j j j j Ability to make accurate, clear and concise verbal reports.

G2.1 .7 Conduct of operations 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.39 Equipment Control 94.5 j j j j Knowledge of less than one hour technical spec Wcation action statements for systems.

G2.2.40 Equipment Control 3.4 4.7 j j j j j Ability to apply technical specifications for a system.

J G2.3.1 1 Radiation Control 3.8 4.3 J j Ability to control radiation releases.

G2.3.12 Radiation Control 3.2 3.7 j j Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.32 Emergency Procedures/Plans 3.6 4.0 El Knowledge of operator response to loss of all El annunciators.

G2.4.37 Emergency Procedures/Plans 3.0 4.1 Knowledge of the lines of authority during implamentation of an emergency plan.

G2.4.9 Emergency Procedures/Plans 3.8 4.2 Knowledge of low power / shutdown implications in El El El El El El El El El El accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 1 7/20/2012 10:13AM

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

RO SRQ 007EA2.02 -

Reactor Trip Stabilization - Recovery 4.3 4.6 Proper actions to be taken if the automatic safety func j

I1 tions have not taken place Large Break LOCA I 3 4.5 4.7 LI El LI LI D El El El El El Verification of adequate core cooling 025AA2.05 Loss of RHR System /4 3.1 3.5 J j Limitations on LPI flow and temperature rates of change 026AG2.2.44 Loss of Component Cooling Water / 8 4.2 4.4 El El El El El El 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 055EG2.4.21 Station Blackout / 6 4.0 4.6 El El El El El El El El El El Knowledge of the parameters and logic used to assess the status of safety functions 062AG2.4.30 Loss of Nucear Svc Water /4 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Page 1 of 1 7/20/2012 10:13AM

ES-401, REV 9 SRO 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 003AA2.02 Dropped Control Rod / 1 2.7 2.8 J J J j j Signal inputs to rod control system 028AA2.14 Pressunzer Level Malfunction / 2 2.6 2.8 j EJ j The effect on indicated PZR levels, given a change in ambient pressure and temperature of reflux boiling 036AG2.4.41 Fuel Handling Accident / 8 2.9 4.6 El El El Knowledge of the emergency action level thresholds and classifications.

068AG2.4.8 Control Room Evac. /8 3.8 4.5 ElElElElElElElElElEl Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 7/20/2012 10:13AM

ES-401, REV 9 SRO 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 003G2.2.25 Reactor Coolant Pump 3.2 4.2 El Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

007A202 Pressurizer Relief/Quench Tank 2.6 3.2 El El El El El El El El El El Abnormal pressure in the PRT 022G2.4.50 Containment Cooling 4.2 4.0 El El El El El El El El El El Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

064A2.03 Emergency Diesel Generator 3.1 3.1 El El El El El El El El El El Parallel operation of ED/Gs 073A2.02 Process Radiation Monitoring 2.7 3.2 El El El El El El El El El El Detector failure Page 1 of 1 7/20/2012 10:13 AM

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

RO SRO 011 A2. 12 Pressurizer Level Control 3.3 3.3 LI LI LI LI LI LI LI LI LI Operation of auxiliary spray 072G2.4.18 Area Radiation Monitoring 3.3 4.0 LI LI LI LI LI LI LI LI LI LI Knowledge of the specific bases for EOPs 086A2.04 Fire Protection 3.3 3.9 LILILILILILILILILILI Failure to actuate the FPS when required, resulting in fire damage Page 1 of 1 7/20/2012 10:13AM

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

RO SRO G2.1 .32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.

G2.l .5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.17 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.

G2.2.21 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability requirements.

G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

G2.4.40 Emergency Procedures/Plans 2.7 4.5 Knowledge of the SROs responsibilities in emergency plan implementation.

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