ML120690513

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Initial Exam 2012-301 Draft Administrative Documents
ML120690513
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/21/2012
From:
NRC/RGN-II
To:
Gerald Laska
Shared Package
ML120550268 List:
References
Download: ML120690513 (22)
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DJFT ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Sequoyah DateofExam: 2011 RO K/A Category Points SRO-Only Points Tier Group KK KK K KAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

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

2 1 2 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions TierTotals 4 5 5 4 5 4 27 5 5 10 1 23223333223 28 2 3 5 Plant 2 11011111111 10 1 2 3 Systems Tier Totals 3 4 2 3 4 4 4 4 3 3 4 38 3 5 8 1 2 3 4 10 1 2 3 4 7

3. GenericKnowledgeandAbilities Categories 3 2 2 3 1 2 2 2
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 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 section 0.1 .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 I and 2 from the shaded systems and K/A categories.
7. *The generic (G) K/As in Tiers I 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 D.1 .b of ES-401 for the applicable KA5.
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 # I 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 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRQ OO7EA1.10 -

Reactor Trip Stabilization - Recovery 3.7 3.7 S/G pressure

/1 008AK2.03 Pressurizer Vapor Space Accident I 3 2.5 2.4 j Controllers and positioners 009EK2.03 Small Break LOCA /3 3 3.3 D D E S/Gs O11EK1.01 Large Break LOCA/ 3 4.1 4.4 E Natural circulation and cooling, including reflux boiling.

01 5AK2.08 RCP Malfunctions / 4 2.6 2.6 E CCWS 022AA1 .03 Loss of Rx Coolant Makeup! 2 3.2 3.2 t PZR level trend 025AA2.Ol Loss of RHR System / 4 2.7 2.9 E Proper amperage of running LPlldecay heat removal/RHR pump(s) 027AG2.l.30 Pressurizer Pressure Control System 4.4 4.0 Ability to locate and operate components, including local Malfunction / 3 controls.

029EG2.2.36 ATWS I 1 3.1 4.2 j Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 038EA1 .07 Steam Gen. Tube Rupture / 3 2.5 2.6 J E LI LI PRT tank temperature, pressure, and selpoints.

054AA2.03 Loss of Main Feedwater / 4 4.1 4.2 LI LI LI LI LI LI LI LI LI LI Conditions and reasons for AFW pump startup Page 1 of 2 03/28/2011 12:43 PM

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

RO SRO 055EK1.02 Station Blackout/6 4.1 4.4 Natural circulation cooling 056AG2.4.34 Loss of Off-site Power / 6 4.2 4.1 LI LI LI LI LI Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 057AK3.Ol Loss of Vital AC Inst. Bus/6 4.1 4.4 fl LI Actions contained in EOP for loss of vital ac electrical instrument bus 062AA2.03 Loss of Nuclear Svc Water / 4 2.6 2.9 LI The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK3.08 Loss of Instrument Air / 8 3.7 3.9 LI Actions contained in EOP for loss of instrument air WEO5EK1.3 Inadequate Heat Transfer- Loss of 3.9 4.1 LI Annunciators and conditions indicating signals, and Secondary Heat Sink / 4 remedial actions associated with the (Loss of Secondary Heat Sink).

WE12EK3.2 Steam Line Rupture - Excessive Heat 3.3 3.9 Normal, abnormal and emergency operating procedures Transfer / 4 LI LI LI LI LI LI LI LI LI LI associated with (Uncontrolled Depressurization of all Steam Generators).

Page 2 of 2 03/28/2011 12:43 PM

ES-401, REV 9 TIG2 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 003AK3.07 Dropped Control Rod / 1 3.8 3.9 ElElElEElElElElElEl Tech-Spec limits for T-ave 024AA2.04 Emergency Boration I 1 3.4 4.2 El El El El El El Availability of BWST 036AK2.Ol Fuel Handling Accident! 8 2.9 3.5 El El El El El El El El El El Fuel handling equipment 059AK3.02 Accidental Liquid Rad Waste Rel. / 9 3.2 4.5 El El El El El El El El El El Implementation of E-plan 069AA1 .01 Loss of CTMT Integrity / 5 3.5 3.7 El El El El El El El El El El Isolation valves, dampers and electropneumatic devices.

074EA2.03 Inad. Core Cooling /4 3.8 4.1 El El El El El El El El El El Availability of turbine bypass valves for cooldown weOlEG2.l.30 Rediagnosisl3 4.4 4.0 El El El El El El. El. El El El Ability to locate and operate components, including local controls.

WE13EK2.2 Steam Generator Over-pressure/4 3.0 3.2 El El El El El El El El El El Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE16EKI.3 High Containment Radiation / 9 3.0 3.3 ElElElEElElElElElEl Annunciators and conditions indicating signals, and remedial actions associated with the (High Containment Radiation).

Page 1 of 1 03/28/2011 12:44 PM

ES-401, REV 9 T2GI 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 .05 Reactor Coolant Pump 3.4 3.5 RCS flow 003A4.05 Reactor Coolant Pump 3.1 3.0 RCP seal leakage detection instrumentation 004K6.31 Chemical and Volume Control 3.1 3.5 Seal injection system and limits on flow range 005K1.1 I Residual Heat Removal 3.5 3.6 j j RWST 005K5.01 Residual Heat Removal 2.6 2.9 El El El El El El El [ Nil ductility transition temperature (brittle fracture) 006K1.l1 EmergencyCoreCooling 2.8 3.2 CCWS 006K6.03 Emergency Core Cooling 3.6 3.9 Safety Injection Pumps 007G2.1 .30 Pressurizer Relief/Quench Tank 4.4 4.0 Ability to locate and operate components, including local controls.

010K5.01 Pressurizer Pressure Control 3.5 4.0 El El El El El El El El El El Determination of conditioc of fluid in PZR, using steam tables 012K2.01 Reactor Protection 3.3 3.7 El El El El El El El El El El RPS channels, components and interconnections 012K6.02 Reactor Protection 2.9 3.1 El El El El El El El El El El Redundant channels Page 1 of 3 03/28/2011 12:45 PM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 013K2.01 Engineered Safety Features Actuation 3.6 3.8 [1 ESFAS/safeguards equipment control 013K5.02 Engineered Safety Features Actuation 2.9 3.3 [] [ Safety system logic and reliability 022K2.02 Containment Cooling 2.5 2.4 Chillers 026A1.06 Containment Spray 2.7 3.0 Containment spray pump cooling 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 039K4.05 Main and Reheat Steam 3.7 3.7 Automatic isolation of steam line 059A3.04 Main Feedwater 2.5 2.6 Turbine driven feed pump 061A2.02 Auxiliary/Emergency Feedwater 3.2 3.6 Loss of air to steam supply valve 062G2.4.1l AC Electrical Distribution 4.0 4.2 [] [1 Knowledge of abnormal condition procedures.

062K3.0l AC Electrical Distribution 3.5 3.9 Major system loads 063K3.02 DC Electrical Distribution 3.5 3.7 EJ Components using DC control power Page 2 of 3 03/28/2011 12:45 PM

ES-401, REV 9 T2GI 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 064A1.05 Emergency Diesel Generator 2.5 2.5 ED/G room temperature 064G2.4.8 Emergency Diesel Generator 3.8 4.5 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

073A4.0l Process Radiation Monitoring 3.9 3.9 Effluent release 076K4.03 Service Water 2.9 3.4 Automatic opening features associated with SWS isolation valves to CCW heat exchanges 103A2 03 Containment 3.5 3.8 Phase A and B isolaUon 103A2.05 Containment 2.9 3.9 Emergencycontainmententry El Page 3 of 3 03/28/2011 12:45 PM

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 SRQ 002K6.06 Reactor Coolant 2.5 2.8 LI Sensors and Detectors 015K2.01 Nuclear Instrumentation 3.3 3.7 LI NIS channels, components and interconnections 016K5.01 Non-nuclear Instrumentation 2.7 2.8 Separation of control and protection circuits 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 LI LI LI LI LI 1 LI LI LI LI Radiation monitoring systems 034A4.01 Fuel Handling Equipment 3.3 3.7 LI LI LI 1 LI LI LI LI LI. [i El Radiation levels 035A3.02 Steam Generator 3.7 3.5 LI LI LI LI LI LI LI LI MAD valves LI LI 071 G2.2.40 Waste Gas Disposal 3.4 4.7 LI LI LI LI LI LI LI LI LI LI Ability to apply technical specifications for a system.

072K4.01 Area Radiation Monitoring 3.3 3.6 LI LI LI LI LI LI fl Containment ventilation isolation 079K1.01 Station Air 3.0 3.1 LI LI LI LI LI LI LI LI LI El AS -

086A2.04 Fire Protection 3.3 3.9 LI LI LI LI LI LI LI LI LI LI Failure to actuate the FPS when required, resulting in fire damage Page 1 of 1 03/28/2011 12:45 PM

ES-401, REV 9 T3 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 G2.1.17 Conduct of operations 3.9 4.0 El El El El El El Ability to make accurate, clear and concise verbal reports.

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

G2.1 .41 Conduct of operations 2.8 3.7 LI El El LI El Knowledge of the refueling processes G2.2.12 Equipment Coriol 3.7 4.1 El El El El El El El El El El Knowledge of surveillance procedures.

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

G2.3.13 Radiation Control 3.4 3.8 El El El El El El El El El El Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 El El El El El El El El El El Knowledge of radiation exposure limits under normal and emergency conditions G2.4.32 Emergency Procedures/Plans 3.6 4.0 El El El El El El El El El El Knowledge of operator response to loss of all annunciators.

G2.4.34 Emergency Procedures/Plans 4.2 4.1 El El El 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 G2.4.4 Emergency Procedures/Plans 4.5 4.7 El El El El El El El El El El Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 03/28/2011 12:45 PM

ES-401, REV 9 SRO TIGI 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 008AG2.2.4 Pressurizer Vapor Space Accident 13 3.6 3.6 (multi-unit) Ability to explain the variations in control board layouts, systems instrumentation and procedural actions between units at a facility.

011 EA2.0l Large Break LOCA / 3 4.2 4.7 Actions to be taken based on RCS temperature and pressure saturated and superheated 025AA2.04 Loss of RHR System! 4 3.3 3.6 Location and isolability of leaks 056AG2.4.18 Loss of Off-site Power /6 3.3 4.0 Knowledge of the specific bases foc EOPs.

065AA2.02 Loss of Instrument Air! 8 2.4 2.6 Relationship of flow readings to system operation weO4EG2.4.34 LOCAOutsideContainment/3 4.2 4.1 Knowledge of RO tasks performed outside the main control Li LI Li Li LI El room during an emergency and the resultant operational effects Page 1 of 1 03/28/2011 12:46 PM

ES-401, REV 9 SRO TIG2 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 028AG2.4.18 Pressurizer Level Malfunction! 2 3.3 4.0 E D El LI Knowledge of the specific bases for EOP5.

068AA2.04 Control Room Evac. I 8 3.7 4 El fl j SIG pressure 076AG2.2.39 High Reactor Coolant Activity! 9 3.9 4.5 Knowledge of less than one hour technical specification action statements for systems.

WE1OEA2.2 Natural Circ. With Seam Void! 4 3.4 3.9 El El El El El El El El El El Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Page 1 of 1 03128/2011 12:46 PM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 005G2.2.25 Residual Heat Removal 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

008A2.Ol Component Cooling Water 3.3 3.6 E E ri Loss of CCW pump 010G2.1.7 Pressurizer Pressure Control 4.4 4.7 J Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

026A2.09 Containment Spray 2.5 2.9 Radiation hazard potential of BWST 062G2.2.25 AC Electrical Distribution 3.2 4.2 El El Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Page 1 of 1 03/28/2011 12:47PM

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

RO SRO 028G2.2.40 Hydrogen Recombiner and Purge 3.4 4.7 Ability to apply technical specifications for a system.

Control 055G2.l.19 CondenserAir Removal 3.9 3.8 Ability to use plant computerto evaluate system or component status.

079A2.Ol Station Air 2.9 3.2 Cross-connection with lAS Page 1 of 1 03/28/2011 12:47PM

ES-401, REV 9 SRO 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 SRO G2.l.8 Conduct of operations 3.4 4.1 J E El LI Ability to coordinate personnel activities outside the control room.

G2.2.14 Equipment Control 3.9 4.3 Knowledge of the process for controlling equipment configuration or status G22.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.4 Radiation Control 3.2 3.7 El LI Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 El ri El El El LI ri j Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.35 Emergency Procedures/Plans 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects G2.4.38 Emergency Procedures/Plans 2.4 4.4 El El El El El El LI El El El Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

Page 1 of 1 03/28/2011 12:47 PM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seguoyah Nuclear Station 1 & 2 Date of Examination:01/16-2312012 Exam Level: RO SRO E Operating Test No: 2012-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations 2.1.40 Knowledge of refueling administrative R, N requirements. (2.8/3.9)

Review Completed Refueling Checklist and Implement Technical Specification Requirements.

Conduct of Operations R, N 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.

(4.3/4.6)

Given plant data, review a Shutdown Margin Calculation, find all embedded errors and take all required action.

Equipment Control R, N 2.2.12 Knowledge of surveillance procedures. (3.7/ 4.1)

Review a Manual RCS Leakrate Calculation find all embedded errors and take required actions.

Radiation Control R, D, P 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (3.8)

Pre Job Analysis for Emergent Work in the RCA.

Emergency Procedures/Plan R, N 2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

Given plant data, determine event classification and complete the state notification form.

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)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seguoyah Nuclear Station I & 2 Date of Examination:01/1 6-23/2012 Exam Level: RO SRO El Operating Test No: 2012-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations R, D 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.914.2)

Given plant data, determine Main Turbine maximum acceleration rate, holding time and loading rate.

Conduct of Operations R, M 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.

(4.3/4.6)

Manual Makeup to the Volume Control Tank Equipment Control R, M, P 2.2.12 Knowledge of surveillance procedures. (3.7/4.1)

Given plant data, perform a Manual RCS Leakrate Calculation.

Radiation Control Not selected Emergency Procedures/Plan R, M 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.. (4.0/4.6)

Given plant data, recommend required actions while applying safety Status Tree criteria during a Degraded Core Cooling event.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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 (S 1; randomly selected)

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: SeQuoyah Nuclear Station 1 & 2 Date of Examination: 01/16-23/2012 Exam Level: RO El SRO-I SRO-U Operating Test No: 2012-301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. EPE 007 EA1 .05 (4.0/4.1) Reinstate source range detectors following S, A, D, L 1 a reactor trip.
b. 004 A4.12 (3.8/3.3) Return CVCS Makeup to Automatic S, M 2
c. EPE 011 EA1 .11 (4.2/4.2) Transfer to Hot Leg Recirc S, D, A, EN 3
d. 005 A4.01 (3.6/3.4) Swap RHR Pumps (A Train to B Train) with Level 5, D, L 4P in the Pressurizer
e. 028 A4.03 (3.1/3.3) Place 1 B H2 Analyzer in Service S, M 5
f. 064 A4.01 (4.0/4.3) Perform DIG Load Test on lA-A DIG S, A, M 6
g. APE 061 AAI .01 (3.6/3.6) Respond to a Main Control Room High 5, D 7 Radiation Alarm.
h. APE 026 AA1 .05 (3.1/3.1) Respond to a Leak in the Component S, N, A 8 Cooling Water System.

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

i. APE 028 AA1 .07 (3.3/3.3) Locally Control Charging Flow Using 2-FCV- D, E, R 2 62-93
j. EPE 038 EA1 .16 (4.4/4.3) Manually Control A S/G PORV Locally M, E, A, L 3
k. 033 A2.03 (3.1/3.5) Refill The Spent Fuel Pit During A Spent Fuel Pit D, E, L, R S Low Level Event.

All RO 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 / SRO-I I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9!814 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - / - I 1 (control room system)

(L)ow-Power I Shutdown 1 I I I 1 (N)ew or (M)odifled from bank including 1(A) 2 I 2/ 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA (S)imulator

a. The examinee will reinstate source range detectors following a reactor trip using ES-O.1 Reactor Trip Response. The examinee will determine one channel of Intermediate Range Nuclear Instruments is indicating in excess of the Source Range auto initiation setpoint and transfer to the alternate path to manually reinstate source range detectors. Once the Source Range instruments have been placed in service, the examinee will restore the High Flux at Shutdown alarms.
b. The examinee will shift to Makeup of the CVCS from Manual to Automatic using O-SO-62-7 Boron Concentration Control and Tl-44 Boron Tables.
c. During a plant event, the examinee will realign RHR to cold leg injection and BOTH trains of safety injection to hot leg recirculation flow path using ES-i .4, Transfer to Hot Leg Recirculation. During the transfer FCV-63-172 fa?ls to open. The examinee will transition to the alternate path and realign RHR trains to cold legs.
d. During Mode 5 conditions, the examinee will shift RHR Pumps from A Train to B Train with Level in the Pressurizer using O-SO-74-1 Residual Heat Removal System.
e. The examinee will place the 1 B H2 Analyzer in Service for a post maintenance test using O-SO-43-4 Hydrogen Analyzer.
f. The examinee will Perform DIG Load Test on lA-A DIG using surveillance 1-Sl-OPS-082-007.A, Electrical Power System Diesel Generator lA-A. Once the Diesel is loaded a high crankcase pressure condition will develop, which requires the examinee to transition to the alternate path to shutdown the Diesel.
g. The examinee will respond to a Main Control Room high radiation condition using O-S0-30-2 Section 8.1. The examinee will manually place one train of Emergency Control Room Ventilation in service and isolate the normal Control Room Ventilation
h. The examinee will respond to a leak in the Component Cooling Water System using AOP-M.03. The examinee will manually open the Surge Tank Make-up valve and transition to the alternate path to stop the running CCS pump and manually close the CCS isolation valves to isolate the leak.

I. The examinee will place 2-FCV-62-93 Pressurizer level Control valve in local manual and control charging and seal flow within normal values using 2-SO-62-1, CVCS.

j. During a plant event, the examinee will take local manual control of #1 S/G PORV using EA-1-2 Local Control of S/G PORVS. The examinee will transition to the alternate path to once the examinee discovers there is no control air available to the #1 S/G PORV. Once local manual control is established, the examinee will demonstrate the ability to control steam generator pressure
k. During a Spent Fuel Pit low level event, the examinee will refill the spent fuel pit using EA-78-1, Refilling the Spent Fuel Pit.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Seguoyah Nuclear Station 1 & 2 Date of Examination: 01/16-23/2012 Exam Level: RO SRO-l E SRO-U Operating Test No: 2012-301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. EPE 007 EA1 .05 (4.0/4.1) Reinstate source range detectors following S, A, D, L 1 a reactor trip.
b. Not examined
c. EPE 011 EA1 .1 1 (4.2/4.2) Transfer to Hot Leg Recirc S, D, A, EN 3
d. 005 A4.01 (3.6/3.4) Swap RHR Pumps (A Train to B Train) with Level S, D, L 4P in the Pressurizer
e. 028 A4.03 (3.1/3.3) Place lB H2 Analyzer in Service S, M 5
f. 064 A4.01 (4.0/4.3) Perform DIG Load Test on lA-A DIG 5, A, M 6
g. APE 061 AA1 .01 (3.6/3.6) Respond to a Main Control Room High S, D 7 Radiation Alarm.
h. APE 026 AA1 .05 (3.1/3.1) Respond to a Leak in the Component 5, N, A 8 Cooling Water System.

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

i. APE 028 AA1 .07 (3.3/3.3) Locally Control Charging Flow Using 2-FCV- D, E, R 2 62-93
j. EPE 038 EA1.16 (4.4/4.3) Manually Control A S/G PORV Locally M, E, A, L 3
k. 033 A2.03 (3.1/3.5) Refill The Spent Fuel Pit During A Spent Fuel Pit D, E, L, R 8 Low Level Event.

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-l I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 91<814 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2/ 2 I? I (P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA II1I1 (S)imulator

a. The examinee will reinstate source range detectors following a reactor trip using ES-O. 1 Reactor Trip Response. The examinee will determine one channel of Intermediate Range Nuclear Instruments is indicating in excess of the Source Range auto initiation setpoint and transfer to the alternate path to manually reinstate source range detectors. Once the Source Range instruments have been placed in service, the examinee will restore the High Flux at Shutdown alarms.
b. Not examined.
c. During a plant event, the examinee will realign RHR to cold leg injection and BOTH trains of safety injection to hot leg recirculation flow path using ES-i .4, Transfer to Hot Leg Recirculation. During the transfer FCV-63-i 72 fails to open. The examinee will transition to the alternate path and realign RHR trains to cold legs.
d. During Mode 5 conditions, the examinee will shift RHR Pumps from A Train to B Train with Level in the Pressurizer using O-SO-74-i Residual Heat Removal System.
e. The examinee will place the 1 B H2 Analyzer in Service for a post maintenance test using O-SO-43-4 Hydrogen Analyzer.
f. The examinee will Perform DIG Load Test on iA-A D/G using surveillance 1-Sl-OPS-082-007.A, Electrical Power System Diesel Generator lA-A. Once the Diesel is loaded a high crankcase pressure condition will develop, which requires the examinee to transition to the alternate path to shutdown the Diesel.
g. The examinee will respond to a Main Control Room high radiation condition using O-SO-30-2 Section 8.1. The examinee will manually place one train of Emergency Control Room Ventilation in service and isolate the normal Control Room Ventilation
h. The examinee will respond to a leak in the Component Cooling Water System using AOP-M.03. The examinee will manually open the Surge Tank Make-up valve and transition to the alternate path to stop the running CCS pump and manually close the CCS isolation valves to isolate the leak.
i. The examinee will place 2-FCV-62-93 Pressurizer level Control valve in local manual and control charging and seal flow within normal values using 2-SO-62-1, CVCS.
j. During a plant event, the examinee will take local manual control of #1 S/G PORV using EA-1-2 Local Control of S/G PORVS. The examinee will transition to the alternate path to once the examinee discovers there is no control air available to the #1 S/G PORV. Once local manual control is established, the examinee will demonstrate the ability to control steam generator pressure
k. During a Spent Fuel Pit low level event, the examinee will refill the spent fuel pit using EA-78-1, Refilling the Spent Fuel Pit.

ES-301 Control Room!ln-Plant Systems Outline Form ES-301-2 Facility: Seguoyah Nuclear Station 1 & 2 Date of Examination: 01/16-23/2012 Exam Level: RD SRO-I SRO-U E Operating Test No: 2012-301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code* Safety Function

a. Not examined.
b. Not examined
c. EPE 011 EA1.11 (4.2/4.2) Transfer to Hot Leg Recirc S, M, A, EN 3
d. Not examined
e. Not examined
f. 064 A4.01 (4.0/4.3) Perform DIG Load Test on lA-A D/G 5, A, M 6
g. APE 061 AA1 .01 (3.6/3.6) Respond to a Main Control Room High S, N 7 Radiation Alarm.
h. Not examined In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
i. APE 028 AA1 .07 (3.3/3.3) Locally Control Charging Flow Using 2-FCV- D, E, R 2 62-93
j. Not examined
k. 033 A2.03 (3.1/3.5) Refill The Spent Fuel Pit During A Spent Fuel Pit D, E, L, R 8 Low Level Event.

All RO 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 / SRO-l I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 I 1 / 1 (EN)gineered safety feature - / - / l (control room system)

(L)ow-Power I Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1 (A) 2I 2I 1 (P)revious 2 exams 3I 3 / 2 (randomly selected)

(R)CA (S)imulator

a. Not examined
b. Not examined
c. During a plant event, the examinee will realign RHR to cold leg injection and BOTH trains of safety injection to hot leg recirculation flow path using ES-i .4, Transfer to Hot Leg Recirculation. During the transfer FCV-63-172 fails to open. The examinee will transition to the alternate path and realign RHR trains to cold legs.
d. Not examined
e. Not examined
f. The examinee will Perform DIG Load Test on lA-A D/G using surveillance i-Sl-OPS-082-007.A, Electrical Power System Diesel Generator lA-A. Once the Diesel is loaded a high crankcase pressure condition will develop, which requires the examinee to transition to the alternate path to shutdown the Diesel.
g. The examinee will respond to a Main Control Room high radiation condition using O-SO-30-2 Section 8.1. The examinee will manually place one train of Emergency Control Room Ventilation in service and isolate the normal Control Room Ventilation
h. Not examined
i. The examinee will place 2-FCV-62-93 Pressurizer level Control valve in local manual and control charging and seal flow within normal values using 2-SO-62-1, CVCS.
j. Not examined
k. During a Spent Fuel Pit low level event, the examinee will refill the spent fuel pit using EA-78-i, Refilling the Spent Fuel Pit.
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