ML101720553

Draft - Outlines (Folder 2)

ML101720553
Person / Time
Site:	Ginna
Issue date:	04/06/2010
From:	Constellation Energy Nuclear Group
To:	Todd Fish Operations Branch I
HANSELL S
Shared Package
ML092470059	List: IR 05000244/2010301 ML100400205 ML101680575 ML101720347 ML101720553 ML101720560 ML101720564 ML102320373 ML102320386 ML102320393 ML102320408 ML102520045 ML102520054 ML102710006
References
TAC U01766
Download: ML101720553 (31)

Text

ES-401 Written Examination Outline Form ES-401-2 Facility: R.E. Ginna Date of Exam: 06/21/10 SRO-Only Points Tier Group K K G Total A2 G* Total 2 3

• 1.

Emergency 3 3 3 3 18 3 3 6 2 2 2 9 2 2 4 Plant Evaluations Tier 4 4 5 5 27 5 5 10 Totals 2 2 3 2 3 2 2 :3 3 3 3 28 3 2 5 2.

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

3. Generic Knowledge & Abilities 2 3 4 10 2 3 4 7 3 3 2 2 2 2 2 I

Not~ 1. Ensure that at least two topics from every applicabl,e KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one cate1gory in Tier 3 of the SRO-only outline, the Tier Totals in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401 , for guidance regarding elimination of inappropriate KIA statements.

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

5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the FlO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 K/A's

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 1

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA2.23 - Ability to determine and interpret the following as 056/ Loss of Off-site Power they apply to the Loss of 3.9 76 16 Offsite Power: Turbine trip reactor button and indicator EA2.04 - Ability to determine or interpret the following as they apply to a Station 055 I Station Blackout / 6 4.1 77 Blackout: Instruments and controls operable with only de available AA2.06 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water:

026 / Loss of Component The length of time after the 3.1 78 Cooling Water 18 loss of CCW flow to a component before that component may be dam 2.4.34 - Emergency Procedures I Plan:

Knowledge of RO tasks 062/ Loss of Nuclear performed outside the main 4.1

• 79 i Service Water / 4 control room during an emergency and the resultant effects.

2.2.22 - Equipment Control:

E12/ Steam Line Rupture Knowledge of limiting 4.7 80.

Excessive Heat Transfer /4 conditions for operations and limits.

2.4.3 - Emergency 025 / Loss of Residual Heat Procedures / Plan: Ability to 3.9 81 Removal System / 4 identify post-accident instrumentation.

EK1.02 - Knowledge of the operational implications of 009 / Small Break LOCA / 3 X the following concepts as 3.5 39 they apply to the small break LOCA: Use of steam tables 2

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KiA Topic(s)

EK1.04 - Knowledge of the operational implications of the following concepts as 007 / Reactor Trip Stabilization - Recovery /1 x they apply to the reactor trip: 3.6 40 Decrease in reactor power following reactor trip (prompt and su uent EK1.1 - Knowledge of the operational implications of the following concepts as E05/lnadequate Heat they apply to the (Loss of Transfer - Loss of x Secondary Heat Sink) 3.8 41 Secondary Heat Sink / 4 Components, capacity, and function of emergency s.

EK2.2 - Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: Facility's heat removal systems, including E11 / Loss of Emergency Coolant Recirculation / 4 x primary coolant, emergency 3.9 42 coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facil .

EK2.1 - Knowledge of the interrelations between the (LOCA Outside Containment) and the following: Components, and E04 / LOCA Outside Containment /3 x functions of control and 3.5 43 safety systems, including instrumentation, signals, interlocks, failure modes and automatic and man~al features.

AK2.07 - Knowledge of the interrelations between 077 / Generator Voltage Generator Voltage and and Electric Grid x Electric Grid Disturbances 3.6 44 Disturbances and the following: Turbine /

erator control 3

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal PlanI Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function A2 I G I KIA Topic(s) limp. I Q# I AK3.03 - Knowledge of the reasons for the following responses as they apply to 022 / Loss of Reactor the Loss of Reactor Coolant X 3.1 45 Coolant Makeup / 2 Makeup: Performance of lineup to establish excess letdown after determining need AK3.03 - Knowledge of the reasons for the following responses as they apply to 026 / Loss of Component the Loss of Component X 4.0 46 Cooling Water / 8 Cooling Water: Guidance actions contained in EOP for Loss of CCW/nuclear service water AK3.02 - Knowledge of the reasons for the following 040/ Steam Line Rupture /

X responses as they apply to 4.4 47 4

the Steam Line Rupture:

ESFAS initiation AA 1.24 - Ability to operate and / or monitor the following as they apply to the Loss of 056/ Loss of Off-site Power X Offsite Power: Plant 2.9 48 6

computer, to call up in-core temperature monitoring AA1.21 - Ability to operate and / or monitor the following as they apply to the Reactor 015 / 17 / Reactor Coolant X Coolant Pump Malfunctions 4.4 49 Pump Malfunctions / 4 (Loss of RC Flow):

Development of natural circulation How EA1.01 - Ability to operate and monitor the following as 055 / Station Blackout / 6 X they apply to a Station 3.7 50 Blackout: In-core thermocou eratures 4

ES-401 Form ES-401-2 R.E. Giinna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KIA Topic(s)

AA2.17 - Ability to determine and interpret the following as 1057 / Loss of Vilal AC they apply to the Loss of

• Electrical Instrument Bus I Vital AC Instrument Bus: 3.1 51 System and component status, using local or remote controls AA2.12 - Ability to determine 027 I Pressurizer Pressure and interpret the following as Control System Malfunction they apply to the 3.7 52

/3 Pressurizer Pressure Control Malfunctions: PZR level EA2.01 - Ability to determine

• 038/ Steam Generator or interpret the following as 4.1 53 Tube Rupture / 3 they apply to a SGTR: When to isolate one or more 2.1.23 - Conduct of Operations: Ability to perform specific system and 011 / Large Break LOCA / 3 4.3 54 integrated plant procedures during all modes of plant 054/ Loss of Main 4.2 55 Feedwater / 4 008/ Pressurizer Vapor 3.8 56 Space Accident / 3 KIA Category Totals 3 3 3 18/6 5

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#fName Safety Fun KIA Topic(s)

AA2.03 - Ability to determine and interpret the following as 036 / Fuel Handling they apply to the Fuel 4.2 82 Incidents /8 Handling Incidents:

Magnitude of potential radioactive release AA2.12 - Ability to determine and interpret the following as 033/ Loss of Intermediate they apply to the Loss of Range Nuclear Intermediate Range Nuclear 3.1 83 Instrumentation /7 Instrumentation: Maximum allowable channel reement 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I status E03 / LOCA Cooldown and that must be reported to 4.1 84 Depressurization /4 internal organizations or external agencies, such as the state, the NRC, or the transmission system rator.

2.4.6 - Emergency E14/ High Containment Procedures / Plan:

4.7 85 Pressure /5 Knowledge of EOP m on ies.

AK1.01 - Knowledge of the operational implications of the following concepts as 024 / Emergency Boration / X they apply to Emergency 3.4 57 1

Boration: Relationship between boron addition and in T-ave EK2.08 - Knowledge of the interrelations between the 074/lnadequate Core Cooling /4 x following Inadequate Core 2.5 58 Cooling: Sensors and detectors 6

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 AK3.02 - Knowledge of the reasons for the following responses as they apply to 061 / Area Radiation the Area Radiation Monitoring (ARM) System X 3.4 59 Monitoring (ARM) System Alarms / 7 Alarms: Guidance contained in alarm response for ARM EA 1.3 - Ability to operate and / or monitor the following as they apply to the (SI E02 / SI Termination / 3 Termination) Desired 3.8 60 operating results during abnormal and emergency situations.

EA2.2 - Ability to determine and interpret the following as they apply to the (Steam Generator Overpressure)

E13 / Steam Generator Adherence to appropriate 3.0 61 Overpressure / 4 procedures and operation within the limitations in the facility's license and amendments.

2.2.39 - Equipment Control:

Knowledge of less than or 069 / Loss of Containment equal to one hour technical 3.9 62 Integrity / 5 specification action statements for AK3.05 - Knowledge of the reasons for the following responses as they apply to 076 I High Reactor Coolant the High Reactor Coolant X 2.9 63 Activity /9 Activity : Corrective actions as a result of high fission-product radioactivity level in the RCS 2.2.37 - Equipment Control:

E10/ Natural Circulation Ability to determine Steam Void in Vessel operability and I or 3.6 64 RVLlS/4 availability of safety related ment.

7

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#/Name Safety Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s)

AA1.01 - Ability to operate and I or monitor the following 003 I Dropped Control Rod as they apply to the 1

x Dropped Control Rod:

2.9 65 Demand position counter and converter KIA Category Totals 2 2 8

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those 026 Containment predictions, use 4.2 86 Spray procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the Main Feedwater System; and (b) based on those 059 Main Feedwater predictions, use 3.4 87 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Feeding a SG 2.2.38 - Equipment 010 Pressurizer Control: Knowledge of 4.5 88 Pressure Control conditions and limitations in the facil license.

2.4.9 - Emergency Procedures / Plan:

Knowledge of low power 004 Chemical and / shutdown implications 4.2 89 Volume Control in accident (e.g., loss of coolant accident or loss of residual heat removal) ation ies.

9

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 I System #/Name I K1 I K21 K31 K41 K51 K61 A1 I A2 IA31 A41 G KIA Topic(s) I Imp. I Q# I A2.11 - Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those 006 Emergency predictions, use 4.4 90 Core Cooling procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture of ECCS header K1.01 - Knowledge of the physical connections and/or cause-effect 022 Containment X relationships between 3.5 1 Cooling the CCS and the following systems:

K1.02 - Knowledge of the physical connections and/or cause-effect 008 Component Cooling Water X relationships between 3.3 2 the CCWS and the 064 Emergency Diesel Generator x 2.8 3 K2.02 - Knowledge of bus power supplies to 078 Instrument Air x the following Emergency 3.3 4 026 Containment Spray x 3.9 5 076 Service Water x 3.7 6 10

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name IK1 IK21K31K41K51K61A1 I A2 IA3 A4 G KIA Topic(s)

K4.06 - Knowledge of MRSS design feature(s) 039 Main and and/or interlock(s) which X 3.3 7 Reheat Steam provide for the following:

Prevent reverse steam flow on steam line break K4.08 - Knowledge of 013 Engineered ESFAS design feature(s)

Safety Features X and/or interlock(s) which 3.1 8 Actuation provide for the following Redu KS.44 - Knowledge of the operational implications of the 004 Chemical and following concepts as X 3.2 9 Volume Control they apply to the CVCS:

Pressure response in PZR during in-and-out su KS.01 - Knowledge of the operational implications of the OOG Emergency X following concepts as 2.8 10 Core Cooling they apply to ECCS:

Effects of temperatures on water level indications K6.03 - Knowledge of the effect of a loss or 012 Reactor X malfunction of the 3.1 11 Protection following will have on the RPS: Tri ic circuits K6.14 - Knowledge of the effect of a loss or 003 Reactor Coolant malfunction on the X 2.6 12 Pump following will have on the RCPS: Starting uirements A 1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 007 Pressurizer associated with 2.7 13 Relief/Quench Tank operating the PRTS controls including:

Maintaining quench tank 11

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 C System #/Name KIA Topic(s)

A 1.01 - Ability to predict and/or monitor changes in parameters associated 063 DC Electrical with operating the dc Distribution x electrical system controls 2.5 14 including: Battery capacity as it is affected rate A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, 005 Residual Heat control, or mitigate the 2.7 15 Removal consequences of those malfunctions or operations: Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on 010 Pressurizer those predictions, use 3.3 16 Pressure Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures A3.06 - Ability to monitor automatic operation of 059 Main Feedwater 3.2 17 the MFW, including:

Feedwater isolation A3.01 - Ability to monitor automatic operation of 103 Containment the containment system, 3.9 18 including: Containment isolation 12

ES-401 Form ES-401-2 R.E. Ginna 2010 !\IRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A4.04 - Ability to 062 AC Electrical manually operate and/or monitor in the control 2.6 19 Distribution room: Local operation of breakers A4.02 - Ability to manually operate and/or 073 Process monitor in the control Radiation Monitoring 3.7 20 room Radiation monitoring system control I 2.4.34 - Emergency Procedures / Plan:

Knowledge of RO tasks 061 performed outside the Auxiliary/Emergency 4.2 21 main control room during Feedwater an emergency and the resultant operational effects.

2.1.27 - Conduct of Operations: Knowledge 076 Service Water 3.9 22 of system purpose and /

or function.

K3.01 - Knowledge of 013 Engineered the effect that a loss or Safety Features x malfunction of the 4.4 23 Actuation ESFAS will have on the followi : Fuel 2.4.20 - Emergency Procedures / Plan; Knowledge of 010 Pressurizer operational 3.8 24 Pressure Control implications of EOP warnings, cautions, and notes.

A3.01 - Ability to monitor automatic operation of 007 Pressurizer the PRTS, including: 2.7 25 Relief/Quench Tank Components which disch to the PRT 13

ES-401 Form ES-401-2 R.E. Ginna 2010 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 A2.05 - Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on those predictions, use 039 Main and procedures to correct, 3.3 26 Reheat Steam control, or mitigate the consequences of those malfunctions or operations: Increasing steam demand, its relationship to increases in reactor r A4.01 - Ability to manually operate and/or 063 DC Electrical monitor in the control 2.8 27 Distribution room: Major breakers and control 'fuses K5.02 - Knowledge of the operational implications of the 003 Reactor Coolant following concepts as Pump x they apply to the RCPS:

2.8 28 Effects of RCP coastdown on RCS KiA Category Totals 28/5 14

ES-401 Form ES-401-2 R.E. Ginna 2010 Written Examination Outline Plant Systems - Tier 2 Group 2 KJA Topic(s)

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those 068 Liquid predictions, use 2.8 91 Radwaste procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release 2.4.21 - Emergency Procedures I Plan:

Knowledge of the parameters and logic used to assess the status of safety 011 Pressurizer functions, such as 4.6 92 Level Control reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control etc.

A2.19 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those 001 Control Rod predictions, use 4.0 93 Drive procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Axial flux distribution 15

ES-401 Form ES-401-2 R.E. Ginna 2010 Written Examination Outline Plant Systems - Tier 2 Group 2 System #!Name KIA Topic(s)

K5.12 - Knowledge of the operational implications of the 011 Pressurizer following concepts as Level Control x they apply to the PZR 2.7 29 LCS Criteria and purpose of PZR level ram A4.02 - Ability to 015 Nuclear manually operate and/or Instrumentation monitor in the control 3.9 30 I room: NIS indicators A3.01 - Ability to monitor automatic operation of 016 Non-nuclear the NNIS, including:

2.9 31 Instru mentation Automatic selection of NNIS inputs to control K2.05 - Knowledge of 001 Control Rod bus power supplies to Drive x the following: M/G 3.1 32 sets .....

K6.04 - Knowledge of the effect or a loss or malfunction on the 002 Reactor Coolant x following RCS 2.5 33 components: RCS vent valves K4.01 - Knowledge of design feature(s) and/or interlock(s) which 071 Waste Gas Disposal x provide for the following: 2.6 34 Pressure capability of the waste gas decay tank K3.02 - Knowledge of the effect that a loss or 072 Area Radiation malfunction of the ARM 3.1 35 Monitoring system will have on the following: Fuel handling n<u-'"ns 16

ES-401 Form ES-401-2 R.E. Ginna 2010 Written Examination Outline Plant Systems - Tier 2 Group 2 KIA Topic(s)

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; 041 Steam and (b) based on those Dump!Turbine 3.6 36 predictions or mitigate Bypass Control the consequences of those malfunctions or operations: Steam valve stuck 0 K1.06 - Knowledge of the physical connections and/or cause effect 055 Condenser Air Removal x relationships between 2.6 37 the CARS and the following systems: PRM A 1.04 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 086 Fire Protection associated with 2.7 i 38 operating the Fire Protection System controls including: Fire dam Group Point Total:

17

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 1::'.  : ...

I o.l"flllY R.E. Ginna Date: 6/21/2010

r. y KA# Topic RO SRO-Only IR Q# IR Q#

Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew 2.9 66 COmfJfClllclit, overtime limitations, etc.

Ability to coordinate personnel activities 2.1.8 3.4 67 outside the control room.

Knowledge of shift or short-term relief 2.1.3 3.7 75

1. Conduct of turnover pra~tir.p.~.

Operations Ability to interpret referemce materials, 2.1.25 4.2 94 such as graphs, curves tables etc.

Knowledge of new and spent fuel 2.1.42 3.4 100 movement procedures.

Subtotal ..

3 /?~': ... 2 Ability to determine opeirability and / or 2.2.37 3.6 68 availability of safety related equipment.

Ability to determine Technical 2.2.35 3.6 69 Rnp.r.ifir.~tion Mode of OperdLlUII.

Knowledge of the process for 2.2.7 2.9 conduction .1 or infrequent tests

2. EqUipment Ability to interpret control room Control indications to verify the status and 2.2.44 operation of a system, and understand 4.4 95 how operator actions and directives affect plant and i:)yi:)l~' II conditions.

Subtotal .;.:.;,'; ';.

3 r. 1 18

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 I Knowledge of radiation or contamination hazards that may arise 2.3.14 3.4 70 during normal, abnormal, or emergency conditions or activities.

Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to 2.3.13 radiation monitor alarms, containment 3.4 71 entry requirements, fuel handling responsibilities, access to locked high r

radiation areas, aligning filters, etc.

3. Radiation Control Ability to use radiation monitoring systems, such as 'fixed radiation 2.3.5 monitors and alarms, portable survey 2.9 96 instruments, personnel monitoring equipment, etc.

Knowledge of radiation exposure limits 2.3.4 3.7 98 under normal or emergency conditions.

Subtotal f .. " " 2 '.;::;,t.:1'1: 2 Knowledge of events rellated to system operation / status that must be reported 2.4.30 to internal organizations or external 2.7 72 agencies, such as the state, the NRC, or the transmission system operator.

Knowledge of the RO's responsibilities 2.4.39 3.9 73 in emergency plan implementation.

4. Emergency I Procedures /

Knowledge of the emergency action Plan 2.4.41 4.6 97 level thresholds and classifications.

Ability to take actions called for in the facility emergency plan, including 2.4.38 4.4 99 supporting or acting as emergency coordinator if required.

otal ~~t~j< .. 2 ~. 2 Tier 3 Point Total: i""""" ..,..... "",*

10  !~" 7 19

ES-401 Record of RejBcted KIA's Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection KA G3 / 2.3.4 replaced 3/3 This topic is duplicated on the SRO Examination by G3 / 2.3.14 G2 / 2.2.35 replaced Duplicated on 1=10 examination and is more suitable to RO 3/1 by G2 / 2.2.44 examination 028/ K6.01 replaced System is no longer used or referenced by any procedures at the 2/2 by 002 / K6.04 facility 007/ A2.01 replaced Excessive overlap for system. Questions 7 and 47 also test 2/ 1 by 059 / A2.04 same topic.

Reactor Protection has already performed its function in lower 012 /G2.4.9 replaced 2/1 mode, making it impossible to develop a test item to evaluate by 004 / G2.4.9 knowledge of this KA topic for this system 040/ AK3.03 Direct overlap with question 7. Selected this item for removal 1/ 1 replaced by 040 /

because it has the lower KA importance value of the 2 items AK3.02 010/ G2.4.30 For this system, this generic KA will not yield an RO test item.

2/ 1 replaced by 010/

This information is confined to responsibility of SRO.

G2.4.20 G2 / 2.2.15 replaced 3/2 Direct overlap with topic on Operating Examination.

by G2 / 2.2.7 028/ A2.01 replaced System is no longer used or referenced by any procedures at the 2/2 by 001 / A2.19 facility I

20

Administrative Topics Form L-~'-uU -1 II Facility: Ginna Date of Examination: 6/21/10 Examination Level: RO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (3.9) Ability to interpret reference material, such as Conduct of Operations graphs, curves, tables, etc.

M,R JPM: Given a Set of Conditions, Perform a Critical Rod Position Calculation In Accordance With 0 1.2.2, Critical Rod Position Calculation.

2.1.29(4.1) Knowledge of how to conduct system lineups, I Conduct of Operations such as valves, breakers, switches, etc.

N,R JPM: Perform an RHR System Valve and Breaker Position Verification on the Control Board Prior to Mode 3 Entry i 2.2.13(4.1) Knowledge of tagging and clearance Equipment Control procedures.

M,R JPM: Perform the RO Review of a Tagout For V-3968, 4B Condensate Heater Discharge Check Valve.

2.3.15 (2.9) Knowledge of radiation monitoring systems, Radiation Control such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

N,R JPM: Determine Steam Generator Tube Leakage Using Radiation Monitor R-47, Air Ejector Radiation Monitor Low Range Ii Emergency Procedure/Plan N/A CATEGORY NOT SELECTED NOTE: All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (::; 3 for ROs; ::; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank (> 1) (4)

(P}revious 2 exams (~ 1; randomly selected) (0)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Ginna Date of Examination: 6/21/10 Examination Level: SRO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (4.2) Ability to interpret reference material, such as Conduct of Operations graphs, curves, tables, etc.

M,R JPM: Review a Critical Rod Position Calculation 2.1.18 (3.8) Ability to make accurate, clear, and concise Conduct of Operations logs, records, status board, and reports.

M,R JPM: Perform the Shift Manager review of the 0-6.13, DAILY SURVEILLANCE LOG 2.2.37 (4.6) Ability to determine operability and/or availability Equipment Control I of safety related equipment.

D,R I JPM: Perform a Safety Function Determination 2.3.14 (3.8) Knowledge of radiation or contamination Radiation Control hazards that may arise during normal, abnormal, P,S or emergency conditions or activities.

JPM: Respond to a Contaminated Injured Person

, 2.4.41 (4.6) Knowledge of the emergency action level Emergency Plan thresholds and classifications.

M,R JPM: Determine the EAL For an 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 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) (1)

(N)ew or (M)odified from bank (> 1) (3)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Ginna Date of Examination: 6/21/10 Exam Level (circle one): RO Operating Test No.: NRC ntrol Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Code* Safety System I JPM Title Function

a. 064 Emergency Diesel Generator i S,A,D,E,EN 6 Start the Emergency Diesel Generator during a Station Blackout

b. 006 Emergency Core Cooling System S,A,E.EN,N 2 Isolate the Safety Injection Accumulators during inadequate core cooling

c. 003 Reactor Coolant Pump

s. L. M 4P Start a RCP during a plant startup Ii I

I d. APE 068 Control Room Evacuation S,A,E,P 8 Perform the immediate actions for a Control Room Evacuation

e. 010 Pressurizer Pressure Control System I S.P,L 3 Place LTOP in service i

f. 004 Chemical and Volume Control System i S,L, N 1 Perform a Rapid Boration during a plant shutdown I

. g. 026 Containment Spray S,A,E,EN,N 5 Secure Containment Spray following an automatic actuation.

h. 061 Auxiliary I Emergency Feedwater System Place the Standby Auxiliary Feedwater System in service during a loss of S.D,E 4S heat sink I

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

I I II i. 071 Waste Gas Disposal System D,R 9 Release the A Gas Decay Tank APE 067 Plant Fire On Site D,E,R 8

~cure Ventilation System During a Fire I k. 039 Main and Reheat Steam System P,E 4S Locally Operate the ARVs

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

@ 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 1 SRO-II SRO-U (A)lternate path 4-6 (4) 14-6/2-3 (C)ontrol room (D)irect from bank S 9 (4) 1s 8 1s 4 (E)mergency or abnormal in-plant 1 (7) 1 ~ 1 1 ~ 1 (EN)gineered safety feature - I - I ~ 1 (control room system)

(L)ow-Power I Shutdown ~ 1 (3) / ~ 1 I ~ 1 (N)ew or (M)odified from bank including 1(A) ~ 2 (4) I ~ 2 I ~ 1 (P)revious 2 exams s 3 (3) I s 3 I s 2 (randomly selected)

(R)CA ~ 1 (2) I ~ 1 I ~ 1 (S)imulator

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

Facility: Ginna Date of Examination: 6/21/10 Exam Level: SRO(I) I SRO (U) Operating Test No.: NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Code* Safety System 1 JPM Title Function

a. 064 Emergency Diesel Generator S,A,D,E,EN 6 Start the Emergency Diesel Generator during a Station Blackout

b. 006 Emergency Core Cooling System Isolate the Safety Injection Accumulators during inadequate core S,A,E,EN,N 2 cooling I

c. 003 Reactor Coolant Pump S,L,M 4P Start a RCP during a plant startup

d. APE 068 Control Room Evacuation S,A,E,P 8 Perform the immediate actions for a Control Room Evacuation

e. 010 Pressurizer Pressure Control System S,P,L 3 Place LTOP in service

f. 004 Chemical and Volume Control System S,L, N 1 Perform a Rapid Boration during a plant shutdown I

g. 026 Containment Spray S,A, E, EN, N 5 Secure Containment Spray following an automatic actuation.

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

i. 071 Waste Gas Disposal System I D,R 9 Release the A Gas Decay Tank J

• j. APE 067 Plant Fire On Site D,E,R 8 Secure Ventilation System During a Fire i

k. 039 Main and Reheat Steam System P,E I 4S Locally Operate the ARVs

@ 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.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 / 4-6 (4)/2-3 (2)

(C)ontrol room

{D)irect from bank  ::;; 9/ ~ 8 (3)1 ~ 4 (3)

(E)mergency or abnormal in-plant ~ 1 / ';? 1 (6)/ ~ 1 (3)

(EN)gineered safety feature I - 1 ~ 1 (2)(control room system)

(L)ow-Power I Shutdown ';? 1 I ~ 1 (3)/ ~ 1 (1)

(N)ew or (M)odified from bank including 1(A) ~ 21 ';? 2 (4)/ ~ 1 (2)

(P)revious 2 exams ~ 3 I ~ 3 (3)1 ~ 2 (O)(randomly selected) i (R)CA ';? 1 / ';? 1 (2)/ ~ 1 (2)

. {S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 1 Op Test No.: N10-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 49% power (BOl). The plant power was reduced several days ago due to a malfunction on the A MFW Pump . Corrective Maintenance has been

• completed, and the pump is ready to be restarted. RG&E Energy Control Center has requested that the electriic plant be aligned to a 0/100 configuration on circuit 7T to allow the RG&E personm~1 to perform an insulator inspection on the 767 Line.

Per Chemistry direction Normal letdown is at 60 gpm.

Turnover: The following eqUipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement.

Event Malf. Event Type* Event No. No. Description 1 NA N-BOP Shift Electric Plant N-SRO 2 EDS07B C-RO loss of B Instrument Bus C-BOP C{TS)-SRO 3 PZR02D I-RO Pressurizer Pressure (PT-449) fails High I(TS)-SRO 4 TUR05E R-RO Main Turbine High Vibration/EHC control failure TUR09D C-BOP C-SRO 5 FDW09A M-RO Feed Line Hupture Inside Containment M-BOP M-SRO 6 TUR02 NA Main Turbine Failure to Auto Trip 7 RPS07K C-BOP A AFW Pump Fails after start 8 REM- NA TDAFW Pump overspeed trip FDW32 9 OVR- C-RO Standby AFW fails to function FDW42A FDW15B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

- 1

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 2 Op Test No.: N10-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The Plant is at 100% power (EOl). Per the daily work schedule, CROl-7, Swapping Service Water Pumps, is to be performed this shift, swapping to A and D Service Water pumps.

Turnover: The following equipment is Out-Of-Service: The B SI Pump is OOS for Bearing

• Replacement.

Event Malf. No. Event Type* Event No. Description 1 ClG09C N-BOP Swap Service Water PumpsJD Service Water Pump Trip ClG01D C(TS)-SRO 2 CVC10A I-RO VCT level '112 Fails HIGH I-SRO 3 CVC12C C-RO C Charging Pump trips C-SRO 4 TUR16B I-BOP Turbine Impulse Pressure (PT-486) fails High I-SRO 5 A-FDW30 R-RO A MFW Pump Oil Sump HI-lO level/Rapid DownpowerlStuck Rod ROD03* C-BOP G11 C(TS)-SRO 6 SGN04B M-RO SGTR M-BOP M-SRO 7 RPS07A C-RO A SI Pump fails to start in AUTO RPS07C C SI Pump fails to start in AUTO RPS07D

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

- 1

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 3 Op Test No.: N10-1 Examiners: Operators: (SRO)

(BOP)

Initial Conditions: The plant is at 70% power (MOL). The plant was taken to 50% due to a failure of the B MFW Pump. Corrective Maintenance was performed and plant power raised to 70% four days ago. The plant has been holding at this power level to observe the B MFW Pump operating characteristics. The plant power is now to be raised to 100% power using 0-5.2, Load Ascension, Step 6.2.33, Placing Condensate

• Booster Pumps in service.

Turnover: I The following equipment is Out-Ot-Service: The B SI Pump is OOS for Bearing

• Replacement.

Event Malf. No. Event Type* Event No. Description I I 1 NA R-RO Load Ascension/Start Condensate Booster Pumps N-BOP N-SRO 2 GEN02 C-BOP Generator Hydrogen Temperature (Cold Gas) Instrument Fails C-SRO High 3 RCS11F I-RO BLoop Thot RTD fails Low I(TS)-SRO 4 FDW07C C-BOP FRV B Controller Fails Low i C-SRO nd 5 ROD02-F2 C-RO Dropped Rod/2 Dropped >Rod ROD02-B8 C(TS}-SRO 6 RCS03D M-RO Large Break LOCA on BLoop Tcold I

M-BOP M-SRO 7 SIS02A C-RO Failure of A Train SIS in Auto 8 RPS07F C-RO Failure of the B RHR Pump to start in AUTO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 4 Op Test No.: N10-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The Plant is at 100% power (MOL). It is expected that immediately after turnover the crew will swap Condensate Pumps per Maintenance Dept Work Order, and conduct routine Rod Control exercises on Control Bank D.

Turnover: The following equipment is Out-Of-Service: The B AFW Pump is OOS for Bearing Replacement.

Event Malf. No. Event Event No. Type* Description 1 CND04B N-BOP Swap Condensate Pumps (Start B, Secure C)/B Condensate C-SRO Pump Trip 2 ROD13C- N-RO Rod Control Exercise/MRPI Failure K7 C(TS)-SRO 3 PZR03C I-RO Pressurizer Level (LT-428) Fails HIGH I(TS)-SRO 4 HTR02A R-RO Heater Drain Pump A trips/Rapid Downpower C-BOP C-SRO 5 STM04C C-BOP B SG ARV Controller (AOV-3410) fails in AUTO C-SRO 6 STM05A M-RO MSIVs Close STM05B M-BOP M-SRO 7 STM09A NA SG Safeties lift/fail OPEN (1 per SG)

STM09B 8 RPS07M C-BOP TDAFW Pump Steam Supply Valves Fail to Open in AUTO RPS07N 9 FDW11A NA A AFW Pump trips on Start

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

-1

D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 5 Op Test No.: N10-1 Examiners: Operators: (SRO) I (RO)

(BOP)

Initial Conditions: I The plant is at 1 x 10-8 amps (BOL). The plant ran at 100% power for 12 days, and*

, then tripped four days ago due to a MFW Pump failure. The repairs have been made and the plant is ready to be started back up. The crew will be directed to pull rods to the point of adding hE~at (POAH), and start the B MFW Pump, in accordance with 0-1.2, Plant Startup From Hot Shutdown to Full Power Load, Step 6.3.4 and beyond.

Turnover: The following equipment is Out-Of-Service: The B Condensate Pump is OOS for Bearing Replacement.

Event Malt. Event Type* Event No. No. Description 1 NA R-RO Raise power to POAH N-SRO 2 NA N-BOP Testing of the MFW Oil Pumps N-SRO 3 CLG10 C-RO 480VAC Ground/A CCW Pump trips w/B CCW Pump fails to start CLG02A C(TS)-SRO in AUTO A-EDS33 4 NIS05 C-BOP Loss of Compensating VoltClge to Intermediate Range N35.

C(TS)-SRO 5 EDS04D C-BOP Fault on 480V Bus 18/SW Pump D fails to start CLG01D C(TS)-SRO 6 CVC07A C-RO PCV-135 fails Closed C-SRO 7 RCS02D M-RO Loop B Cold Leg Break (1000 gpm)

M-BOP M-SRO 8 RPS05A C-RO Failure of R'eactor to Trip in AUTO and MANUAL RPS05B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

-1