Text

Initial Exam 2010-301 Draft Administrative Documents
	ML102870160
Person / Time
Site:	Vogtle
Issue date:	04/12/2010
From:	; NRC/RGN-II
To:	; Southern Nuclear Operating Co
References
	50-424/10-301, 50-425/10-301, ES-401, Rev 9
	Download: ML102870160 (21)
	v • d • e

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAIG A2 G* Total

=

1

=

2 3

=

4

=

5

=

6

=

1

=

2

=

3

=

41* =

Total

1. 1 333 33 3 18 3 3 6 Emergency &

Abnormal Plant 2 E N/A 2 1 NIA 1 9 2 2 4 Evolutions Tier Totals 5 = 5 4 4

= = 27 5 5 10 1 33232323223 28 3 2 5 2.

2 11 1 11 1 1 101 1 10 2 Plant 1 3 Systems Tier Totals 4 4 3 4 3 4 3 4 2 3 4 38 5 3 8.

= = = = = = = = =

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 1 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 KJA 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 +/- I 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 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 (lR) 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* 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.

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 K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EG2.4.31 Reactor Trip Stabilization Recovery 4.2 4.1 Knowledge of annunciators alarms, indications or I1 response procedures OO8AAI .04 Pressurizer Vapor Space Accident! 3 2.8 2.5 Feedwater pumps 009EK2.03 Small Break LOCA /3 3 3.3 Li LI LI LI LI LI LI LI LI LI S/Gs 011 EG2.2.38 Large Break LOCA / 3 3.6 4,5 LI LI LI LI LI LI LI LI LI LI Knowledge of conditions and limitations in the facility license.

01 5AK2.07 RCP Malfunctions /4 2.9 2.9 LI [] [] } ( ) RCP seals 022AK1 .01 Loss of Rx Coolant Makeup / 2 2.8 3.2 J [ Consequences of thermal shock to RCP seals 025AA1 .19 Loss of RHR System / 4 2.6 2.4 LI LI LI LI LI LI LI LI LI Block orifice bypass valve controller and indicators 027AA1.05 Pressurizer Pressure Control System 3.3 3.2 Malfunction / 3 LI LI LI LI LI LI LI LI LI LI Transfer of heaters to backup power supply 038EK1 .04 Steam Gen. Tube Rupture / 3 3.1 3.3 J LI LI LI LI LI LI LI LI LI LI Reflux boiling 054AK1 .01 Loss of Main Feedwater / 4 4.1 4.3 LI LI LI LI LI LI LI LI LI LI MFW line break depressurizes the S/G (similar to a steam line break) 055EG2.4.2 Station Blackout /6 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Page 1 of 2 9/9/2009 8:59 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 056AK3.0l Loss of Off-site Power / 6 3.5 3.9 D E D LI Order and time to initiation of power for the load sequencer 057AA2.05 Loss of Vital AC Inst. Bus /6 3.5 3.8 SIG pressure and level meters 062AA2.02 Loss of Nuclear Svc Water! 4 2.9 3.6 LI The cause of possible SWS loss 065AA2.03 Loss of Instrument Air / 8 2.6 2.9 LI Location and isolation of leaks 077AK3.02 Generator Voltage and Electric Grid 3.6 3.9 Disturbances / 6 LI LI LI LI LI LI LI LI LI LI Actions contained in abnormal operating procedures for voltage and grid disturbances WE04EK2.2 LOCA Outside Containment / 3 3.8 4.0 LI LI LI L] LI LI LI LI [1 LI 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.

WEO5EK3.2 Inadequate Heat Transfer Loss of 3.7 4.1 Normal, abnormal and emergency operating procedures Secondary Heat Sink / 4 associated with (Loss of Secondary Heat Sink).

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ES-401, REV 9 Ti G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: JR Ki K2 1(3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003AK3.1O Dropped Control Rod /1 3.2 4.2 LI LI RIL and PDIL 032AA2.07 Loss of Source Range NI / 7 2.8 3.4 LI Maximum allowable channel disagreement O51AA1.04 Lossof Condenser Vacuum/4 2.5 2.5 LI LI LI [1 LI Rodposition 060AG2.I.25 AccidentalGaseousRadwasteRel./9 3.9 4.2 LI LI Abilityto interpret reference materials such as graphs, monographs and tables which contain performance data.

061 AK2.01 ARM System Alarms! 7 2.5 2.6 Detectors at each ARM system location 068AK3.02 Control Room Evac. / 8 3.7 4.1 J LI System response to turbine trip WE01 EK1 .2 Rediagnosis! 3 3.4 4 [] U LI [] LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection /

Rediagnosis).

WE13EA1.1 Steam Generator Over-pressure /4 3.1 3.3 LI LI LI LI LI LI LI LI LI LI Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE16EKI.1 High Containment Radiation/9 2.7 3.0 LI LI LI LI LI LI LI LI LI LI Components, capacity, and function of emergency systems.

Page 1 of 9/9/2009 8:59 AM

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 003G2.4.35 Reactor Coolant Pump 3.8 4.0 LI [] [] [] LI Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 004G2.l.23 Chemical and Volume Control 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

004K6.31 Chemical and Volume Control 3.1 3.6 Seal injection system and limits on flow range 005K2.03 Residual Heat Removal 2.7 2.8 LI LI LI LI LI LI LI LI LI LI RCS pressure boundary motor-operated valves 005K6.03 Residual Heat Removal 2.5 2.6 LI LI LI LI L] RHR heat exchanger 006K6.02 Emergency Core Cooling 3.4 3.9 J LI LI LI LI Core flood tanks (accumulators) 007K1 .03 Pressurizer Relief/Quench Tank 3.0 3.2 ] LI LI LI LI LI LI LI LI LI LI RCS 007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 LI LI LI LI LI LI LI LI LI LI Quench tank cooling 008K2.02 Component Cooling Water 3.0 3.2 LI LI LI LI LI LI LI LI LI LI CCW pump, including emergency backup 01 OK1 .08 Pressurizer Pressure Control 3.2 3.5 LI fl fl LI LI LI LI LI LI LI PZR LCS 012K1.05 Reactor Protection 3.8 3.9 ESFAS Page 1 of 3 9/9/2009 8:59 AM

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:

RD SRO 01 2K5.01 Reactor Protection 3.3 3.8 J DNB 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022A1 .01 Containment Cooling 3.6 3.7 [] [] [] [ Containment temperature 022A2.03 Containment Cooling 2.6 3.0 [] [] { Fan motor thermal overload/high-speed operation 026A3.02 Containment Spray 3.9 4.2 Verification that cooling water is supplied to the containment spray heat exchanger 039A2.01 Main and Reheat Steam 3.1 3.2 Li Li Flow paths of steam during a LOCA 059A3.02 Main Feedwater 2.9 3.1 Li Li Li Li fl Li Li Li Programmed levels of the S/G 061A1.01 Auxiliary/Emergency Feedwater 3.9 4.2 Li Li Li Li Li Li j Li Li Li Li SIG level 062G2.1 .27 AC Electrical Distribution 3.9 Li Li Li Li Li Li Li Li Li Li Knowledge of system purpose and or function.

063K2.0l DC Electrical Distribution 2.9 3.1 Li Li Li Li LI Li Li Li Li Li Major DC loads 063K4.02 DC Electrical Distribution 2.9 3.2 Li Li Li Li Li Li Li Li Li Li Breaker interlocks, permissives, bypasses and cross-ties.

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064A2.13 Emergency Diesel Generator 2.6 2.8 Consequences of opening auxiliary feeder bus (EDIG sub supply) 073A4.02 Process Radiation Monitoring 3.7 3.7 Radiation monitoring system control panel 073K3.O1 Process Radiation Monitoring 3.6 4.2 Radioactive effluent releases 076K3.02 Service Water 2.5 2.8 D [] [J [( [] [] [] [] Secondary closed cooling water 078K4.O1 Instrument Air 2.7 2.9 Manual/automatic transfers of control El El H 1 03A4.03 Containment 2.7 2.7 LI LI LI El H H H H H l H ESF slave relays Page 3 of 3 9/9/2009 8:59 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 001 K2.05 Control Rod Drive 3.1 3.5 WG sets 002A2.03 Reactor Coolant 4.1 4.3 fl Loss of forced circulation 016K1.08 Non-nuclear Instrumentation 34 3.4 J PZR PCS 028K5.01 Hydrogen Recombiner and Purge 3.4 3.9 Control fl fl Explosive hydrogen concentration 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems 035G2.2.40 Steam Generator 3.4 4.7 Ability to apply technical specifications for a system.

lJ 055K3.01 Condenser Air Removal 2.5 2.7 Main condenser 071 K4.06 Waste Gas Disposal 2.7 3.5 fI Sampling and monitoring of waste gas release tanks 079A4.01 Station Air 2.7 2.7 EJ j Cross-tie valves with lAS 086K6.04 Fire Protection 2.6 2.9 Fire, smoke and heat detectors Page 1 of 1 9/9/2009 8:59 AM

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

RD SRO G2.1.l5 Conduct of operations 2.7 3.4 LI LI LI LI LI LI LI LILILI Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

G2.1.3 Conduct of operations 3.7 3.9 LI LI LI LI LI LI LI LI LI LI II Knowledge of shift or short term relief turnover practices.

G2. 1.37 Conduct of operations 4.3 4.6 LI LI LI LI LI LI LI LI LI LI Knowledge of procedures, guidelines or limitations associated with reactivity management G2.2.12 Equipment Control 3.7 4.1 LI LI LI LI LI LI LI LI LI LI I Knowledge of surveillance procedures.

G2.2.13 Equipment Control 4.1 4.3 LI LI LI LI LI LI LI LI LILI I] Knowledge of tagging and clearance procedures.

G2.2.42 Equipment Control 3.9 4.6 LI LI LI LI LI LI LI LI LI LI Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.13 Radiation Control 34 3.8 LI LI LI LI LI LI LI LI LI LI I Knowledge of radiological safety procedures pertaining to licensed operator duties G23.6 Radiation Control 2.0 3.8 LI LI LI LI LI LI LI LI LI LI (I Ability to aprove release permits G2.4.30 Emergency Procedures/Plans 2.7 4.1 LI LI LI LI LI LI LI LI LI LI l?i Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

G2.4.35 Emergency Procedures/Plans 3.8 4.0 LI LI LI LI LI LI LI LI LI LI II Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 9/9/2009 8:59 AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR KIK2K3K4K5K6AIA2A3A4G TOPIC:

RO SRO 008AA2.28 Pressurizer Vapor Space Accident /3 Safety parameter display system indications O11EG2.4.11 LargeBreakLOCA/3 4.0 4.2 DLI LI LI LH Knowledge of abnormal condition procedures.

025AG2.4.31 Loss of RHR System 14 4.2 4.1 DEED DDE LiD Knowledge of annunciators alarms, indications or response procedures 056AA2.73 Loss of Off-site Power / 6 3.5 3.6 LI EDDEDDD LID PZR heater on/off 065AG2.1 .30 Loss of Instrument Air /8 4.4 4.0 Li DDDDDL1l Ability to locate and operate components, including local controls.

WEO4EA2.1 LOCA Outside Containment /3 3.4 4.3 DEED LHL] LID Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

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

RO SRO 003AG2.l .30 Dropped Control Rod/i 4.4 4.0 DDEEIDL1D Ability to locate and operate components, including local controls.

028AG2.4.20 Pressurizer Level Malfunction / 2 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

068AA2.03 Control Room Evac. / 8 4 4.2 T-hot, T-cold and in-core temperatures WEIOEA2.l Natural Circ. With Seam Void/ 4 3.2 3.9 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-40I-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 003G2.4.41 Reactor Coolant Pump 2.9 4.6 j Knowledge of the emergency action level thresholds and classifications.

007A2.03 Pressurizer Relief/Quench Tank 3.6 3.9 D fl Overpressurization of the PZFI 010G2.1.20 Pressurizer Pressure Control 4.6 4.6 EJ Abilityto execute procedure steps.

026A2.03 Containment Spray 4.1 4.4 LI fl fl Failure of ESF 073A2.02 Process Radiation Monitoring 2.7 3.2 LI Detector failure Page 1 of 1 9/9/2009 8:59 AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 034G2.4.20 Fuel Handling Equipment 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

072A2.03 Area Radiation Monitoring 2.7 2.9 Blown power-supply fuses O79A2O1 Station Air 2.9 3.2 Cross-connection with lAS Page 1 of 1 9/9/2009 8:59AM

ES-401, REV 9 SRO 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 .35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs Gal .40 Conduct of operations 2.8 3.9 J Knowledge of refueling administrative requirements G2.2.19 Equipment Control 2.3 3.4 D Knowledge of maintenance work order requirements.

G2.2.35 Equipment Control 3.6 4.5 Ability to determine Technical Specification Mode of Operation G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.4.27 Emergency Procedures/Plans 3.4 3.9 Knowledge of fire in the plant procedures.

G2.4.39 Emergency Procedures/Plans 3.9 3.8 El El El LI El [l Knowledge of the ROs responsibilities in emergency plan implementation.

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ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 DraJ Facility: Plant Vogtle Date of Examination: 02/22/2010 Examination Level: RO Operating Test Number: 2010-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

R, D, P

Title:

Critical Safety Function Status Tree Evaluation

Description:

Students will be provided a listing of plant parameters. This Conduct of Operations will require manually evaluating each status tree to determine the challenges to each tree and identify the highest priority challenge.

K/A: G2.1.7 (RO 4.4)

Title:

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: random Iv selected)

ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2 ZDraJ-z Facility: Vogtle Date of Examination: 02/22/2010 Exam Level (circle one): RO / SRO-l I SRO-U Operating Test No.: 201 0-301 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. Dropped Rod Recovery in Model (RO/SRO-l) S, M, A A dropped rod will be recovered lAW AOP-1 8003-C, Rod Control Malfunction Section A for Dropped Rods in Mode 1. During the recovery, the rod being retrieved will not move. This will require reconfiguring the rod control system back to its previous state prior to attempting the dropped rod recovery.

K/A: 003M2.01 (RO 3.7 / SRO 3.9)

b. Respond to Failure of PRZR Level Instrument (RO / SRO-I) 5, D, A 2 A PRZR level instrument will fail low requiring entry into AOP-18001 Section D. After to candidate attempts to place letdown back in service, a letdown isolation valve will NOT open requiring Excess Letdown to be placed into service.

K/A: 028AA1 .05 (RO 3.7 / SRO 3.6)

c. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train S, D, A, P 3 A Components Fail to Align (RO / SRO-I)

EN, L During alignment of ECCS to Hot Leg Recirculation, multiple Train A components will fail to align requiring the use of the RNO column.

K/A: 006A4.05 (RO 3.9 / SRO 3.8)

d. Respond To RHR Pump Trip in Mode 4 (RO / SRO-l) 5, N, A, L 4P An RHR pump will trip in Mode 4 requiring entry into AOP-1 801 9, Section A, Loss of RHR Capability in Mode 4. The flow path through the procedure will require the candidate to start an RCP.

K/A: 025G2.4.9 (RO 3.8 / SRO 4.2)

e. Dilute Containment with Service Air in accordance with 19010- S, D, L 5 C, E-l, Loss of Reactor or Secondary Coolant, Step 29. (RO /

SRO-l)

The student will be required to use SOP 13130-1, section 4.4.2 to align service air to containment to dilute the hydrogen.

K/A: 028A4.01 (RO 4.0 / SRO 4.0)

ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2 D ra4

f. Synchronize Main Generator to the Grid. Field amps not S, D, A, P 6 indicated on one phase requires Main Turbine trip. (RO)

After synchronizing the main generator the student must recognize that one phase does not show any current, requiring opening of the generator output breaker to prevent damage to the generator.

K/A: 062A4.07 (RO 3.1)

g. Respond to Fuel Handling Building High Radiation (ROISRO-l) S, D, A 7 High Radiation will occur due to dropped rod in FHB but auto actuation fails, manual system alignment is required.

K/A: O61AA1 .01 (RO 3.6 / SRO 3.6)

h. Transfer Steam Dumps to Steam Pressure Mode (RO I SRO-l) S, N, A, L 4S The student will be required to transfer steam dumps to the steam pressure mode using step 14 of AOP 1 8009-C. The steam dumps will not work, the student must shift the temperature control to the SG ARVs.

K/A: 041A4.08 (RO 3.0/ SRO 3.1)

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

i. Bypass CNMT HI-I Bistables Following Loss of Heat Sink D, E, L, P 7 Bistables must be bypassed using the BTI equipment in order to align a feedwater flow path to the SGs during a loss of secondary heat sink. This will also require knowledge of how / where to obtain multiple BTI keys to bypass 2 trains of equipment (RO / SRO-l)

K/A: 012A4.03 (3.6 / 3.6)

j. Locally Start the TDAFW Pump D, E, L 8 Following a Control Room evacuation, the TDAFW pump is required to be locally started at Shutdown Panel C. Local transfer switches must be manipulated, the T & T valve checked for proper status, and throttling of AFW flow from the local panel is required using available flow indications.

K/A: 068AA1 .02 (RO 4.3 / SRO 4.5)

k. Locally Isolate RCP Seals I ACCW per 19100-C, Attachment E M, E, L, R 6 During a loss of All AC power, the RCP seals are required to be isolated.

Included on Attachment E is opening the breakers to the SG ARVs in preparation for local operation.

K/A: 055G2.4.34 (RO 4.2/ SRO 4.1)

@ 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-l / SRO-U

ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2

..DraJ (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank <91<81<4 (E)mergency or abnormal in-plant > 1 I 1 / 1 (EN)gineered Safety Feature - I - I> 1 (control room system)

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

(R)CA >11>11>1 (S)imulator

ES-301, Rev. 9E Control Roomlln-Plant Systems Outilne Form ES-301-2 Facility: Vogtle Date of Examination: 02/22/2010 Exam Level (circle one): RO I SRO-I / SRO-U Operating Test No.: 201 0-301 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. Dropped Rod Recovery in Model (RO/SRO-l) S, M, A A dropped rod will be recovered lAW AOP-1 8003-c, Rod control Malfunction Section A for Dropped Rods in Mode 1. During the recovery, the rod being retrieved will not move. This will require reconfiguring the rod control system back to its previous state prior to attempting the dropped rod recovery.

K/A: 003AA2.01 (RO 3.7/ SRO 3.9)

b. Respond to Failure of PRZR Level Instrument (RO / SRO-l) S, D, A 2 A PRZR level instrument will fail low requiring entry into AOP-1 8001 Section D. After to candidate attempts to place letdown back in service, a letdown isolation valve will NOT open requiring Excess Letdown to be placed into service.

K/A: 028AA1 .05 (RO 3.7 / SRO 3.6)

c. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train S, D, A, P 3 A Components Fail to Align (RO / SRO-l)

EN, L During alignment of ECCS to Hot Leg Recirculation, multiple Train A components will fail to align requiring the use of the RNO column.

K/A: 006A4.05 (RO 3.9 / SRO 3.8)

d. Respond To RHR Pump Trip in Mode 4 (RO / SRO-l) S, N, A, L 4P An RHR pump will trip in Mode 4 requiring entry into AOP-1 8019, Section A, Loss of RHR capability in Mode 4. The flow path through the procedure will require the candidate to start an RCP.

K/A: 025G2.4.9 (RO 3.8 / SRO 4.2)

e. Dilute Containment with Service Air in accordance with 19010- S, D, L 5 C, E-1, Loss of Reactor or Secondary Coolant, Step 29. (RO /

SRO-l)

The student will be required to use SOP 13130-1, section 4.4.2 to align service air to containment to dilute the hydrogen.

K/A: 028A4.01 (RO 4.0 / SRO 4.0)

f. N/A N/A N/A

ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2

g. Respond to Fuel Handling Building High Radiation (RO/SRO-I) S, D, A 7 High Radiation will occur due to dropped rod in FHB but auto actuation fails, manual system alignment is required.

K/A: 061AA1 .01 (RD 3.6 / SRD 3.6)

h. Transfer Steam Dumps to Steam Pressure Mode (RO I SRO-l) S, N, A, L 4S The student will be required to transfer steam dumps to the steam pressure mode using step 14 of ADP 1 8009-C. The steam dumps will not work, the student must shift the temperature control to the SG ARVs.

K/A: 041A4.08 (RD 3.0 / SRD 3.1)

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

i. Bypass CNMT HI-I Bistables Following Loss of Heat Sink D, F, L, P 7 Bistables must be bypassed using the BTI equipment in order to align a feedwater flow path to the SGs during a loss of secondary heat sink. This will also require knowledge of how/ where to obtain multiple BTI keys to bypass 2 trains of equipment (RD / SRD-l)

K/A; 012A4.03 (3.6/3.6)

j. Locally Start the TDAFW Pump D, F, L 8 Following a Control Room evacuation, the TDAFW pump is required to be locally started at Shutdown Panel C. Local transfer switches must be manipulated, the T & T valve checked for proper status, and throttling of AFW flow from the local panel is required using available flow indications.

K/A: 068AA1 .02 (RD 4.3 / SRD 4.5)

k. Locally Isolate RCP Seals I ACCW per 19100-C, Attachment E M, F, L, R 6 During a loss of All AC power, the RCP seals are required to be isolated.

Included on Attachment E is opening the breakers to the SG ARVs in preparation for local operation.

K/A: 055G2.4.34 (RD 4.2/ SRD 4.1)

Type Codes Criteria for RD I S RD-I I SRD-U (A)Iternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank <91<81<4 (E)mergency or abnormal in-plant ? I I1 I 1 (EN)gineered Safety Feature - I - I> 1 (control room system)

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

(R)CA >1/>1/>1 (S)imulator

ML102870160

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