ML101650240

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Initial Exam 2010-301 Draft Administrative Documents (Section 1)
ML101650240
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/07/2010
From:
NRC/RGN-II
To:
Southern Nuclear Operating Co
References
50-348/10-301, 50-364/10-301
Download: ML101650240 (19)
v • d • e


Text

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

FARLEY Date of Exam: 2010 RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G*

Total I

2 3

4 5

6 I

2 3

4 Total 1.

i 3

3 3

3 3

3 18 3

3 6

Emergency &

2 E T 2

2 1

9 2

2 4

Abnormal Plant

N/A N/A

Evolutions TierTotals 5

4 5

5 4

27 5

5 10 Plant

+/-+/-+/-+/-

Systems Tier Totals 4

4 4

4 3

3 2

3 4

38 3

5 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

2 3

2 1

2 2

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 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 +/- 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.

Systemslevolutions 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 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 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

  • 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.

8.

On the following pages, enter the KIA 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. 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 1 Rev. 9 PWR Examination Outline Form ES-401*2 Facility: FARLEY Date of Exam: 2010 RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

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

2 2

1 9

2 2

4 Abnormal Plant N/A N/A Evolutions Tier Totals 4

5 4

5 5

4 27 5

5 10 1

3 3

3 3

2 2

3 2

2 2

3 28 I

2 I

3 I

5 I

2.

1 1

1 1

1 1

1 1

0 1

1 10 1

2 Plant 2

3 Systems Tier Totals 4

4 4

4 3

3 4

3 2

3 4

38 3

5 8

3. Generic Knowledge and Abilities 1

2 3

4 10 I

1 I

2 I

3 I

4 I

7 I

Categories 3

2 3

2 1

2 2

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 ofthe 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 ES-401, Attachment 2, for guidance regarding the 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 KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

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

7.
  • The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system.
8.

On the following pages, enter the KIA 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; iffuel 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. 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 pointtotals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

Breakers, relays and disconnects Probable PZR steam space leakage paths other than PORV or code safety Ability to perform specific system and integrated plant procedures during all modes of plant operation.

RCP indicators and controls RCP thermal barrier cooling CRDM high-temperature alarm system Expansion of liquids as temperature increases Operating switches for normal charging header isolation valves Plant conditions from survey of control room indications Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Actions contained in EOP for loss of offsite and onsite power ES-401, REV 9 RO SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

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

FORM ES-401-2 007EK2.02 Reactor Trip

- Stabilization

- Recovery 2.6 2.8

/1 008AA2.26 PressurizerVaporSpaceAccident/3 3.1 3.4 LI LI LI LI LI LI LI LI 009EG2.l.23 Small Break LOCA/3 4.3 4.4 015AK2.10 RCP Malfunctions/4 2.8 2.8 022AK3.06 Loss of Rx Coolant Makeup / 2 3.2 3.3 fl 026AA1.04 Loss of Component Cooling Water / 8 2.7 2.8 027AK1.02 Pressurizer Pressure Control System 2.8 3.1 LI LI LI LI LI LI LI LI LI MaIfunction / 3 029EA1.06 ATWS / 1 3.2 3.1 LI LI LI LI LI LI LI LI LI LI 038EA2.07 Steam Gen. Tube Rupture / 3 4.4 4.8 LI LI LI LI LI LI LI LI LI LI 054AG2.l.7 Loss of Main Feedwater/4 4.4 LI LI LI LI LI LI LI LI LI LI 055EK3.02 Station Blackout! 6 4.3 4.6 LILILILILILILILILILI Page 1 of 2 5/6/2009 9:57 AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO 007EK2.02 Reactor Trip - Stabilization - Recovery 2.6 2.8 0 ~ 0 0 0 0 0 0 0 0 0

/ 1 008AA2.26 Pressurizer Vapor Space Accident / 3 3.1 3.4 DO 009EG2.1.23 Small Break LOCA / 3 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~

015AK2.10 RCP Malfunctions / 4 2.8 2.8 0 ~ 0 0 0 0 0 0 DO 022AK3.06 Loss of Rx Coolant Makeup / 2 3.2 3.3 0 0 ~ 0 0 0 0 0 0 0 0 026AA1.04 Loss of Component Cooling Water /8 2.7 2.8 0 0 0 0 0 0 ~ DOD 027AK1.02 Pressurizer Pressure Control System 2.8 3.1

~ 0 0 0 0 0 0 0 0 0 0 Malfunction / 3 029EA1.06 ATWS/1 3.2 3.1 0 0 0 0 0 0 ~ 0 0 0 0 038EA2.07 Steam Gen. Tube Rupture / 3 4.4 4.8 0 0 0 0 0 0 0 ~ 0 0 0 054AG2.1.7 Loss of Main Feedwater / 4 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~

055EK3.02 Station Blackoutl6 4.3 4.6 0 0 ~ 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC:

Breakers, relays and disconnects Probable PZR steam space leakage paths other than PORV or code safety Ability to perform specific system and integrated plant procedures during all modes of plant operation.

RCP indicators and RCP thermal barrier cooling CRDM high-temperature alarm system Expansion as temperature increases Operating switches for normal charging header isolation valves Plant conditions from survey control room Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Actions contained in EOP for loss of offsite and onsite power 5/6/2009 9:57 AM

NAME I SAFETY FUNCTION:

Loss of Vital AC Inst. Bus I 6 Loss of Instrument Air / 8 Generator Voltage and Electric Grid Disturbances / 6 LOCA Outside Containment / 3 Inadequate Heat Transfer

- Loss of Secondary Heat Sink /4 Loss of Emergency Coolant Recirc. / 4 Steam Line Rupture

- Excessive Heat Transfer / 4 ES-401, REV 9 KA 057AG2.4.49 065AK3.04 077AA1.02 WEO4EA2.2 WEO5EK1.1 WE11EK1.3 WE12EK2.l T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

3 3.2 Cross-over to backup air supplies 3.8 3.7 Turbine! generator controls 3.6 4.2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.8 4.1 Components, capacity, and function of emergency systems.

3.6 4.0 Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recir).

3.4 3.7 J

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Page 2 of 2 5/6/2009 9:57 AM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 057AG2.4.49 Loss of Vital AC Inst. Bus / 6 4.6 4.4 D D D D D D D D D D ~

065AK3.04 Loss of Instrument Air / 8 3

3.2 D D ~

D 077AA1.02 Generator Voltage and Electric Grid Disturbances / 6 3.8 3.7 DDDDDD~DDDD WE04EA2.2 LOCA Outside Containment /3 3.6 4.2 DDDDDDD~DDD WE05EK1.1 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 3.8 4.1

~DDDDDDDDDD WE11 EK1.3 Loss of Emergency Coolant Recirc. / 4 3.6 4.0

~ D D DDDDDDD WE12EK2.1 Steam Line Rupture-Excessive Heat 3.4 3.7 D ~ D D D D D D D D D Transfer / 4 Page 2 of 2 FORM ES-401-2 TOPIC:

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Cross-over to backup air Turbine / generator controls Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Components, capacity, emergency systems.

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recir).

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

5/6/2009 9:57 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 T-ave./ref. deviation meter Guidance contained in EOP for loss of source-range nuclear instrumentation Rod position Radioactive-gas monitors The possible location of a radioactive-gas leak with the assistance of PEO, health physics and chemistry person nel Loss of containment integrity Core flood tank isolation valve controls and indicators Ability to recognize system parameters that are entry-level conditions for Technical Specifications Components, capacity, and function of emergency systems.

KA NAME / SAFETY FUNCTION:

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

RO SRQ OO1AK2.06 Continuous Rod Withdrawal / 1 3

3.1 032AK3.02 Loss of Source Range NI / 7 3.7 4.1 O51AA1.04 Loss of Condenser Vacuum /4 2.5 2.5 El El El El El El 059AK2.02 Accidental Liquid RadWaste Rel. /9 2.7 2.7 060AA2.02 Accidental Gaseous Radwaste Rel. / 9 3.1 4

[] [ [ [ El El El El El El 069AA2.Ol Loss of CTMT Integrity / 5 3.7 4.3 El El El El El El El El El El 074EA1.28 Inacl. Core Cooling / 4 3.7 3.9 El El El El El El El El El El weOl EG2.2.42 Rediagnosis / 3 3.9 4.6 El El El El El El El El El El WEO8EK1.1 RCS Overcooling

- PTS / 4 3.5 3.8 ElElElElElElElElElEl Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 T1 G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 001AK2.06 Continuous Rod Withdrawal / 1 3

3.1 0 ~ 0 0 0 0 0 0 0 0 0 032AK3.02 Loss of Source Range NI / 7 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 051AA1.04 Loss of Condenser Vacuum /4 2.5 2.5 0 0 0 0 0

~ 0 0 0 0 059AK2.02 Accidental Liquid RadWaste ReI. /9 2.7 2.7 0 ~ 0 0 0 0 0 0 0 0 060AA2.02 Accidental Gaseous Radwaste ReI. / 9 3.1 4

0000 oo~ooo 069AA2.01 Loss of CTMT Integrity / 5 3.7 4.3 0 0 0 0 0 0 ~ 0 0 0 074EA1.28 Inad. Core Cooling / 4 3.7 3.9 0 0 0 0 0 ~ 0 0 0 0 we01 EG2.2.42 Rediagnosis / 3 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

WE08EK1.1 RCS Overcooling - PTS / 4 3.5 3.8

~ 0 0 0000000 Page 1 of 1 FORM ES-401-2 TOPIC:

T-ave./ref. deviation meter Guidance contained in EOP for loss of source-range nuclear instrumentation Rod position Radioactive-gas monitors The possible location of a radioactive-gas leak with the assistance of PEO, health physics and chemistry personnel Loss of containment integrity Core flood tank isolation valve controls and indicators Ability to recognize system parameters that are entry-level conditions for Technical Specifications Components, capacity, and function of emergency systems.

5/6/2009 9:57 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 003A2.03 Reactor Coolant Pump 2.7 3.1 El Problems associated with RCP motors, including faulty motors and current, winding and bearing temperature problems 004G2.4.21 Chemical and Volume Control 4.0 4.6 El El El El El El El El fl El Knowledge of the parameters and logic used to assess the status of safety functions 004K1.04 Chemical and Volume Control 3.4 3.8 El El El RCPS, including seal injection flows 005A1.07 Residual Heat Removal 2.5 3.1 Determination of test acceptability by comparison of recorded valve response times with Tech-Spec requirements 005K4.03 Residual Heat Removal 2.9 3.2 RHR heat exchanger bypass flow control 006K6.13 Emergency Core Cooling 2.8 3.1 Pumps 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 El El El El El El El El El El Method of forming a steam bubble in the PZR 008K3.0l Component Cooling Water 3.4 3.5 El El El El El El El El El El Loads cooled by CCWS 008K4.09 Component Cooling Water 2.7 2.9 El El El El El El El El El El The standby feature for the CCW pumps 01 OK1.03 Pressurizer Pressure Control 3.6 3.7 El El El El El El El El El El RCS 012K2.0l Reactor Protection 3.3 3.7 El El El El El El El El El El RPS channels, components and interconnections Page 1 of 3 5/6/2009 9:57 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003A2.03 Reactor Coolant Pump 004G2.4.21 Chemical and Volume Control 004K1.04 Chemical and Volume Control OOSA 1.07 Residual Heat Removal 00SK4.03 Residual Removal 006K6.13 Emergency Cooling 007KS.02 Pressurizer Relief/Quench Tank 00BK3.01 Component Water 00BK4.09 Component Cooling Water 010K1.03 Pressurizer PreSsure Control 012K2.01 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.7 3.1 DDDDDD~DDD 4.0 4.6 0 0 0 0 0 ~

3.4 3.B

~

0 0 0 0 0 0 0 0 0 2.S 3.1 0 0 0 0 0 ~ 0 0 0 0 2.9 3.2 0 0 0 ~ 0 0 0 0 0 0 0 2.B 3.1 DDDDD~DDDDD 3.1 3.4 DDDD~DDDDDD 3.4 3.S DD~DDDDDDDD 2.7 2.9 DDD~DDDDDDD 3.6 3.7

~DDDDDDDDDD 3.3 3.7 0 ~ 0 0 0 0 o

Page 1 of 3 FORM ES-401-2 TOPIC:

Problems associated with RCP motors, including faulty motors and current, winding and bearing temperature problems Knowledge of the parameters and logic used to assess the status of safety functions RCPS, including seal injection flows Determination of test acceptability by comparison of recorded valve response times with Tech-Spec requirements RHR heat eXChanger bypass control Pumps Method of forming a steam bubble in the PZR Loads cooled by CCWS The "standby" feature for the CCW pumps RCS RPS channels, components and interconnections S/6/2009 9:S7 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:

RD SRO 012K6.03 Reactor Protection 3.1 3.5 Trip logic circuits 013K2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control 01 3K5.01 Engineered Safety Features Actuation 2.8 3.2 Definitions of safety train and ESF channel 022A1.01 Containment Cooling 3.6 3.7 Containment temperature 026K1.01 Containment Spray 4.2 4.2 ECCS 039K4.05 Main and Reheat Steam 3.7 3.7 Automatic isolation of steam line 059A2.04 Main Feedwater 2.9 3.4 Feeding a dry S/G 059G2.1.19 Main Feedwater 3.9 3.8 El Ability to use plant computer to evaluate system or component status.

061 G2.2.37 Auxiliary/Emergency Feedwater 3.6 4.6 El El El El El El El El El El Ability to determine operability and/or availability of safety related equipment 062A1.01 AC Electrical Distribution 3.4 3.8 El El El El El El El El El El Significance of D/G load limits 063A3.0l DC Electrical Distribution 2.7 3.1 El El El El El El El El El Meters, annunciators, dials, recorders and indicating lights Page 2 of 3 5/6/2009 9:57 AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 012K6.03 Reactor Protection 3.1 3.S 0 0 0 0 0 ~ 0 0 0 0 0 Engineered Features Actuation 3.6 3.8 0 ~ 0 0 0 0 0 o

013KS.01 Engineered Safety Features Actuation 2.8 3.2 0 0 0 0 ~ 0 0 0 0 0 0 022A1.01 Containment 3.6 3.7 000 oo~oooo 026K1.01 Containment Spray 4.2 4.2

~ 0 0 0 0 0 0 0 0 0 0 039K4.0S Main and Reheat Steam 3.7 3.7 0 0 0 ~ 0 0 0 0 0 0 0 Main Feedwater 2.9 3.4 0 0000

~ooo

.19 Main Feedwater 3.9 3.8 0 ooooooo~

061 G2.2.37 Auxiliary/Emergency Feedwater 3.6 4.6 0 0 0 0 0 0 0 oo~

062A1.01 AC Electrical Distribution 3.4 3.8 0 0 0 0 0 0 ~ 0 0 0 0 063A3.01 DC Electrical Distribution 2.7 3.1 0 0 0 0 0 0

~oo Page 2 of 3 FORM ES-401-2 TOPIC:

Trip logic circuits ESFAS/safeguards equipment control Definitions of safety train and ESF channel Containment temperature ECCS Automatic isolation of steam line Feeding a dry S/G Ability to use plant computer to evaluate system or component status.

Ability to determine operability and/or availability of safety related equipment Significance of D/G load limits Meters, annunciators, dials, recorders and indicating lights S/6/2009 9:S7 AM

T2G1 PWR EXAMINATION OUTLINE IR Ki K2 k3 K4 k5 K6 Al A2 A3 A4 G

SRO DLLL1 4.2 DEEDED ED EL1EE 2.7

4.1 TOPIC

Synchroscope Radioactive effluent releases Emergency heat loads Emergency air compressor ESF slave relays Loss of containment integrity under refueling operations.

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

RO 064A4.03 Emergency Diesel Generator 3.2 073K3.O1 Process Radiation Monitoring 3.6 076A3.02 Service Water 3.7 078K2.02 Instrument Air 3.3 103A4.03 Containment 2.7 103K3.03 Containment 3.7 FORM ES-401-2 Page 3 of 3 5/6/2009 9:57 AM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 064A4.03 Emergency Diesel Generator 3.2 3.3 0 0 0 0 0 0 0 0 0 ~ 0 Synchroscope 073K3.01 Process Radiation Monitoring 3.6 4.2 0 0 ~ 0000 DO Radioactive effluent releases 076A3.02 Service Water 3.7 3.7 0 0 0 0 0 0 0 0 ~ 0 0 Emergency heat loads 078K2.02 Instrument Air 3.3 3.5 0 ~ 0 0 0 0 0 0 DO Emergency air compressor 103A4.03 Containment 2.7 2.7 0 0 0 0 0 0 0 0 ~ 0 ESF slave relays 103K3.03 Containment 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 Loss of containment integrity under refueling operations.

Page 3 of 3 5/6/2009 9:57 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:

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

RO SRO 001 K2.02 Control Rod Drive 3.6 3.7 El El El El El El El El El El One-line diagram of power supply to trip breakers 011 K5.05 Pressurizer Level Control 2.8 3.1 El El El El El El El El El El Interrelation of indicated charging flow rate with volume of water required to bring PZR level back to programmed level hot/cold 027K1.01 ContainmentlodineRemoval 3.4 3.7

[] [

[] El El El El CSS 035K3.02 Steam Generator 4.0 4.3 El El El El El El El El El El ECCS 041 K4.14 Steam Dump/Turbine Bypass Control 2.5 2.8 El El El El El El El El El El Operation of loss-of-load bistable taps upon turbine load loss 045A1.05 Main Turbine Generator 3.8 4.1 El El El El El El El El El El Expected response of primary plant parameters (temperature and pressure) following T/G trip 068K6.10 Liquid Radwaste 2.5 2.9 El fl El El El El El El El El Radiation monitors 071 A4.01 Waste Gas Disposal 2.7 2.2 El El El El El El El El El El Valve to put the holdup tank into service; indications of valve positions and tank pressure 072G2.l.27 Area Radiation Monitoring 3.9 El El El El El El El El El El Knowledge of system purpose and or function.

075A2.03 Circulating Water 2.5 2.7 El El El El El El El ] El El El Safety features and relationship between condenser vacuum, turbine trip and steam dump Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 001K2.02 Control Rod Drive 3.6 3.7 0 ~ 0 0 0 0 0 00 011 K5.05 Pressurizer Level Control 2.8 3.1 0 0 0 0 ~ 0 0 0 0 0 027K1.01 Containment Iodine Removal 3.4 3.7

~ 0 0 0 0 0 0 0 0 0 0 035K3.02 Steam Generator 4.0 4.3 0 0 ~ 0 0 0 0 0 0 0 0 041K4.14 Steam DumplTurbine Bypass Control 2.5 2.8 0 0 0 ~ 000000

.05 Main 3.8 4.1 0 0 0 oo~oo o 068K6.10 Liquid Radwaste 2.5 2.9 0 0 0 0 ~ 0 0 0 0 0 071A4.01 Waste Gas Disposal 2.7 2.2 0 0 0 0 0 0 0 0 0 ~ 0 072G2.1.27 Area Monitoring 3.9 4

oooooooooo~

075A2.03 Circulating Water 2.5 2.7 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

One-line diagram of power supply to trip breakers Interrelation of indicated charging flow rate with volume of water required to bring PZR level back to programmed level hot/cold CSS ECCS Operation of loss-of-Ioad bistable taps upon turbine load loss Expected response of primary plant parameters (temperature and pressure) following T/G trip Radiation monitors Valve to put the holdup tank into service; indications of valve positions and tank pressure Knowledge of system purpose and or function.

Safety features and relationship between condenser vacuum, turbine trip and steam dump 5/6/2009 9:57 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:

IR Kl K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

3.9 4.0 El LI El El El El jrz LI LI Ability to make accurate, clear and concise verbal reports.

LI LI El El El El El El LI LI Ability to identify and interpret diverse indications to validate the response of another indication 2.9 4.5 El LI El LI Ability to direct personnel activities inside the control room.

3.8 3.9 fl (multi-unit license) Knowledge of the design, procedural and operational differences between units.

3.1 4.2 El Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 3.8 4.3 Ability to control radiation releases.

3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions 4.0 4.6 Knowledge of crew roles and responsibilities during EOP usage.

RO SRO G2.1.17 G2.l.45 G2.l.9 G2.2.3 G2.2.36 G2.3.l 1 G2.3.13 G2.3.4 G2.4.13 Conduct of operations Conduct of operations Conduct of operations Equipment Control Equipment Control Radiation Control Radiation Control Radiation Control Emergency Procedures/Plans G2.4.16 Emergency Procedures/Plans 3.5 4.4 El LI LI fl LI LI LI El El LI Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.17 Conduct of operations G2.1.45 Conduct of operations G2.1.9 Conduct of operations G2.2.3 Equipment Control G2.2.36 Equipment Control G2.3.11 Radiation Control G2.3.13 Radiation Control G2.3.4 Radiation Control G2.4.13 Emergency Procedures/Plans G2.4.16 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.0 0 0 0 0 0 0 0 DD~

4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~

2.9 4.5 0 0 0 0 0 0 0 0 0 ~

3.8 3.9 DDDDDDDDD~

3.1 4.2 0 0 0 0 0 0 0 0 0 0 ~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

3.2 3.7 0 0 0 0 0 0 DDD~

4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.5 4.4 0 DDDDDDDD~

Page 1 of 1 FORM ES-401-2 TOPIC:

Ability to make accurate, clear and concise verbal reports.

Ability to identify and interpret diverse indications to validate the response of another indication Ability to direct personnel activities inside the control room.

(multi-unit license) Knowledge of the design, procedural and operational differences between units.

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Ability to control radiation releases.

Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of crew roles and responsibilities during EOP usage.

Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

5/6/2009 9:57 AM

SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 4.6 El El El El El ElElEl iElEl ES-401, REV 9 KA 007EA2.02 FORM ES-401-2 NAME I SAFETY FUNCTION:

TOPIC:

RO Reactor Trip

- Stabilization Recovery 4.3 Proper actions to be taken f the automatic safety func I 1 Dons have not taken place 008AA2.l 5 Pressurizer Vapor Space Accident / 3 3.9 4.2 El El El El El El El El El El ESF control board, valve controls and indicators 022AG2.4.50 Loss of Rx Coolant Makeup! 2 4.2 4.0 El El El El El El El El El El Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

027AA2.l7 Pressurizer Pressure Control System 3.1 3.3 El El El El El El El El El El Allowable RCS temperature difference vs. reactor power Malfunction / 3 065AG2.4.47 Loss of Instrument Air / 8 4.2 4.2 El El El El El El El El El El Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

well EG2.l.28 Loss of Emergency Coolant Recirc. / 4 4.1 4.1 El El El El El El El El El El Knowledge of the purpose and function of major system components and controls.

Page 1 of 1 5/6/2009 9:57AM ES-401, REV 9 SRO T1 G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EA2.02 Reactor Trip - Stabilization - Recovery 4.3 4.6 0 0 0 0 0 0 0 ~ 0

/ 1 o

00BAA2.15 Pressurizer Space Accident / 3 3.9 4.2 0 0 DDDD~DDD 022AG2.4.50 Loss of Rx Coolant Makeup / 2 027AA2.17 Pressurizer Pressure Control Malfunction / 3 065AG2.4.47 Loss of Instrument Air / B 4.2 4.0 0 0 0 0 DDDDD~

3.1 3.3 0 0 0 DDD~DDD 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

we11EG2.1 Loss of Emergency Coolant Recirc. / 4 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-2 TOPIC:

Proper actions to be taken if the automatic safety func-tions have not taken place ESF control board, valve controls and indicators Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Allowable RCS temperature,tt"o'"n,'" vs. reactor power Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Knowledge of the purpose and function of major system components and controls.

5/6/2009 9:57 AM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

KA NAME / SAFETY FUNCTION:

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

RO SRO 024AG2.4.20 Emergency Boration I 1 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

060AA2.03 Accidental Gaseous Radwaste Rel. I 9 3.2 3.9 D

The steps necessary to isolate a given radioactive-gas leak, using P&lDs weO3EG2.4.35 LOCA Cooldown

- Depress. /4 3.8 4.0 j

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects WE1OEA2.2 Natural Circ. With Seam Void! 4 3.4 3.9 L1LE1DE1 Page 1 of 5/6/2009 9:57AM ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 024AG2.4.20 Emergency Boration / 1 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

060AA2.03 Accidental Gaseous Radwaste ReI. / 9 3.2 3.9 0 ooooo~ DO we03EG2.4.35 LOCA Cooldown - Depress. / 4 3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~

WE10EA2.2 Natural Circ. With Seam Void! 4 3.4 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of operational implications of EOP warnings, cautions and notes.

The steps necessary to isolate a given leak, using P&IDs Knowledge local auxiliary operator tasks emergency and the resultant operational effects Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

5/6/2009 9:57 AM

SRO T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.3 4.0 4.5 4.6 2.5 2.7 3.9 4.2 3.9 4.6 FORM ES-401-2 TOPIC:

Knowledge of the specific bases for EOPs.

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Fan motor over-current Failure of spray pump Ability to recognize system parameters that are entry-level conditions for Technical Specifications ES-401, REV 9 KA NAME / SAFETY FUNCTION:

005G2.4.18 Residual Heat Removal 007G2.4.2 Pressurizer RelieflQuench Tank 022A2.01 Containment Cooling 026A2.04 Containment Spray 078G2.2.42 Instrument Air Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

005G2.4.18 Residual Heat Removal 007G2.4.2 Pressurizer Relief/Quench Tank 022A2.01 Containment Cooling 026A2.04 Containment Spray 078G2.2.42 Instrument Air SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 4.0 0 0 0 0 ooooo~

4.5 4.6 0 0 0000 2.5 2.7 0 0 0 ooo~ooo 3.9 4.2 0 0 oooo~ooo 3.9 4.6 0 0 0 0 0 oooo~

Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of the specific bases for EOPs.

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Fan motor over-current Failure spray pump Ability to recognize system parameters that are entry-level conditions for Technical Specifications 5/6/2009 9:57 AM

ES-401, REV 9 KA 01 4A2.04 015G2.4.9 Nuclear Instrumentation SRO T2G2 PWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 3.8 4.2 3.9 4.6 NAME / SAFETY FUNCTION:

Rod Position Indication 027G2.2.42 Containment Iodine Removal TOPIC:

Misaligned rod FORM ES-401-2 Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Ability to recognize system parameters that are entry level conditions for Technical Specifications Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

014A2.04 Rod Position Indication 015G2.4.9 Nuclear Instrumentation 027G2.2.42 Containment Iodine Removal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.9 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.2 DOD DDDDDD~

3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-2 TOPIC:

Misaligned rod Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Ability to recognize system parameters that are entry-level conditions for Technical Specifications 5/6/2009 9:57 AM

SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 4.6 4.3 3.1 4.2 3.6 4.6 3.8 4.3 3.2 3.7 4.5 4.6 3.8 4.3 FORM ES-401-2 ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.31 Conduct of operations G2.2.36 Equipment Control G2.2.37 Equipment Control G2.3.l 1 Radiation Control G2.3.12 Radiation Control G2.4.2 Emergency Procedures/Plans G2.4.20 Emergency Procedures/Plans TOPIC:

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Ability to determine operability and/or availability of safety related equipment Ability to control radiation releases Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Knowledge of operational implications of EOP warnings, cautions and notes.

Page 1 of 1 5/6/2009 9:57 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.31 Conduct of operations G2.2.36 Equipment Control G2.2.37 Equipment Control G2.3.11 Radiation Control G2.3.12 Radiation Control G2.4.2 Emergency Procedures/Plans G2.4.20 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.1 4.2 0 0 000000 3.6 4.6 DOD DDDDDD~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~

4.5 4.6 0 DDDDDDDD~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-2 TOPIC:

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Ability to determine operability and/or availability of safety related equipment Ability to control radiation releases Knowledge of radiological safety principles pertaining to licensed operator duties Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Knowledge of operational implications of EOP warnings, cautions and notes.

5/6/2009 9:57 AM

Es-3o1 Administrative Topics Outline Form ES-301-1 DRAFT OPERATING OUTLINE SUBMITTAL FaciNty: Farley Nuclear Plant Date of Examination: March 8, 2010 Examination Level: SRO + RO Operating Test Number:

FA2010301 Administrative Topic Type Describe activity to be performed Code (see Note)

Given a set of plant conditions with fuel movement in progress, determine if refueling operations can continue, and if not, the reason(s) that prohibit refueling from continuing. UOP-4.1 P&Ls and TS and TRM requirements.

G2.1.40 (2.8/3.9)

G2.1.36 (3.0/4.1)

G2.1.32 (3.8/4.0)

Conduct of Operations N / R Develop a set of conditions that will have RHR flow <3000 RO GPM AND audible count rate in the control room is not audible, N32 is broke. There will be a set of other conditions which allow for refueling to continue like the equipment hatch is open, gamma metrics is broke; one train of PRF is operating, etc.

1 plan to do this in the classroom and use pictures of the NIs that will show that one is not working and the selector switch is selected to that NI and a list of conditions.

Given a set of plant conditions with fuel movement in progress, determine if refueling operations can continue, and if not, the reason(s) that prohibit refueling from continuing.

Conduct of Operations G2.1.40 (2.8/3.9)

G2.1.36 (3.0/4.1)

SRO N / R G2.1.35 (2.2/3.9)

G2.1.32 (3.8/4.0)

This will be like the JPM above only added to the JPM will be to list the Tech Specs or TRM requirements that cover the conditions given and the REQUIRED ACTIONS and COMPLETION TIMES in order to restart the fuel movement.

TS_3,9.2,_3.9.4 Conduct of Operations D / R Conduct A Safety Shutdown Assessment and Determine SRO ONLY Time to Saturation.

G2.1.25 (3.9/4.2)

This JPM will have the candidate evaluate plant conditions, use a table to determine time to boiling and then fill out UOP 4.0, figure la. This is only performed by the SRO only job function_at_Farley.

Perform a Shutdown Margin Calculation in modes I & 2 Equipment Control for a stuck rod (STP-29.5)

SRO + RO D / R 001A4.1 1 (3.5/4.1) APEOO5 AK1.05 (3.3/4.1)

One Bank D rod is 30 steps below the other seven Bank D rods.

Determine the 5DM and that an emergency boration is_required.

Farley OCT 2010 NRC ADM1N exam outline Page 1 of2 ES-301 Administrative Topics Outline Form ES-301-1 DRAFT OPERATING OUTLINE SUBMITTAL Facility: Farley Nuclear Plant Examination Level: SRO + RO Administrative Topic (see Note)

Conduct of Operations RO Conduct of Operations SRO portion Conduct of Operations SRO ONLY Equipment Control SRO + RO Type Code

  • N/R N/R D/R D/R Date of Examination: March 8, 2010 Operating Test Number: FA2010301 Describe activity to be performed Given a set of plant conditions with fuel movement in progress, determine if refueling operations can continue, and if not, the reason(s) that prohibit refueling from continuing. UOP-4.1 P&Ls and TS and TRM requirements.

G2.1.40 (2.8/3.9)

G2.1.36 (3.0/4.1)

G2.1.32 (3.8/4.0)

Develop a set of conditions that will have RHR flow <3000 GPM AND audible count rate in the control room is not audible, N-32 is broke. There will be a set of other conditions which allow for refueling to continue like the equipment hatch is open, gamma metrics is broke; one train of PRF is operating, etc. I plan to do this in the classroom and use pictures of the Nl's that will show that one is not working and the selector switch is selected to that NI and a list of conditions.

Given a set of plant conditions with fuel movement in progress, determine if refueling operations can continue, and if not, the reason(s) that prohibit refueling from continuing.

G2.1.40 (2.8/3.9)

G2.1.36 (3.0/4.1)

~.1.35 (2.2/3.9)

G2.1.32 (3.8/4.0)

This will be like the JPM above only added to the JPM will be to list the Tech Specs or TRM requirements that cover the conditions given and the REQUIRED ACTIONS and COMPLETION TIMES in order to restart the fuel movement.

TS 3.9.2, 3.9.4 Conduct A Safety Shutdown Assessment and Determine Time to Saturation.

G2.1.25 (3.9/4.2)

This JPM will have the candidate evaluate plant conditions, use a table to determine time to boiling and then fill out UOP-4.0, figure 1a. This is only performed by the SRO only job function at Farley.

Perform a Shutdown Margin Calculation in modes 1 & 2 for a stuck rod (STP-29.5) 001A4.11 (3.5/4.1) APE005 AK1.05 (3.3/4.1)

One Bank D rod is 30 steps below the other seven Bank D rods.

Determine the SDM and that an emergency boration is required.

Farley OCT 2010 NRC ADMIN exam outline Page 1 of2

ES-301 Administrative Topics Outline Form ES-301-1 DRAFT OPERATING OUTLINE SUBMITTAL Radiation Control M / R Calculate the Maximum Permissible Stay Time within SRO + RO Emergency Dose Limits.

This JPM has the candidate assess a job where two workers will be assigned a task during an emergency event to save a valuable piece of equipment. There will be three stages to the task in which the dose rate is given and time required to complete the task is given. The year to date dose rates will be given and the task will be to determine if either of the workers will exceed their dose limits of ElP14. Information required to be known is that EDLs do not take into account current dose, admin limits and NRC limits do not apply and the EIP-14 limits must be applied properly.

Emergency Plan

M I S Monitor the Critical Safety Function Status Trees SRO + RO manually (CSF-O.O)

G2.4.14 (SRO 4.5) G2.4.21 (SRO 4.6)

The simulator will be used requiring the candidate to determine the appropriate CSF that applies. Plans are to set up a yellow path on FRP-H.5, an Orange path on FRP-Z.1, a red path on P.1 that is not valid due to a loss of power, and a manual determination of CSF-O as to which FRP is applicable based on the setup.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes) [112]

(N)ew or (M)odified from bank (> 1) [313]

(P)revious 2 exams (< 1; randomly selected) [010]

Farley OCT 2010 NRC ADMN exam outline Page 2 of 2

£:S-301 Radiation Control SRO + RO Emergency Plan -

SRO + RO Administrative Topics Outline Form ES-301-1 DRAFT OPERATING OUTLINE SUBMITTAL M/R MIS Calculate the Maximum Permissible Stay Time within Emergency Dose Limits.

This JPM has the candidate assess a job where two workers will be assigned a task during an emergency event to save a valuable piece of equipment. There will be three stages to the task in which the dose rate is given and time required to complete the task is given, The year to date dose rates will be given and the task will be to determine if either of the workers will exceed their dose limits of EIP-14, Information required to be known is that EDLs do not take into account current dose, admin limits and NRC limits do not apply and the EIP-14 limits must be applied properly, Monitor the Critical Safety Function Status Trees manually (CSF-O.O)

G2.4.14 (SRO 4.5) G2.4.21 (SRO 4.6)

The simulator will be used requiring the candidate to determine the appropriate CSF that applies, Plans are to set up a yellow path on FRP-H,5, an Orange path on FRP-Z, 1, a red path on P.1 that is not valid due to a loss of power, and a manual determination of CSF-O as to which FRP is applicable based on the setup,

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; ~ 4 for SROs & RO retakes) [1/2]

(N)ew or (M)odified from bank (:: 1) [3/3]

(P)revious 2 exams << 1; randomly selected) [0/0]

Farley OCT 2010 NRC ADMIN exam outline Page 2 of2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL Facility:

Farley Nuclear Plant Date of Examination:

March 8, 2010 Exam Level (both): RO SRO-Operating Test No.: FA2010301 Control Room Systems (8 for RO; 7 for SRO-i)

System / JPM Title Type Code*

Safety Function

a. Perform an emergency boration. CRO-65C v024AA2.02 3.9/4.4 024AA2.01 3.8/4.1 S, M, A, L The unit will have entered ESP-0.1. One rod will be stuck out and the candidate will have to determine to emergency borate. The Bat pump will have degraded head and will not deliver the proper flow.

The Attachment at the end of the procedure will have to be accomplished to align the RWST to the chg pump suction. The setup will have charging flow low and letdown secured so the candidate will have to increase charging flow and place letdown 0/S and get proper flow.

b. CRO-327A Align PRF System For A Large Break LOCA 5, D, L 2

OIIEK3.12 RO-4.4 SRO-4.6 The PRF system is operating during a LB LOCA and one train has to be secured. This is an action required by EEP-1.0.

c. CR0- 333E Perform Required Actions for transfer to simultaneous S,, L, M hot and cold leg recirculation\\Z006A4.07 SRO 44 This JPM transfers from cold leg recirc to simultaneous hot and cold leg recirculation lAW ESP-1.4. The alternate path has RHR TO RCS HOT LEGS ISO Q1/2E1 1M0V8889 will not open so the RNO column will have to be used.

Modify to have the B Train chg pump will not start. The alternate path will align B train HHSI for cold leg recirculation. This will leave one train of LHSI to the cold legs and one train of HHSI to the hot. This will be evaluated in the final step to make sure the alignment is correct.

d. Perform required actions in response to RCP Seal Failures. CRO-047A RIAAPE015AA1.22 4.0/4.2 S, D, A V003A202 3.7/3.9 This RCP seal failure has seal flow> 8 gpm and a reactor trip will have to be initiated by the CR0 LAW AOP-4. 1, Abnormal RCP seal leakage.
e. CRO-133A Start Up The Containment Cooling System 5, D, P, V 5

vO22A401 3.6/3.6

-022A4.03 3.2/3.2 On the 2007 This JPM is a mode 5 JPM to start up the ctmt cooling system and NRC exam start the dome recirc fans.

f.

CRO-359E Start 1C DG From The EPB And Align To Supply iF 5, M,,

4160V Bus O55EA1.02 4.3/4.4

-055EA1.06 4.1/4.6 O55EA2.03 3.9/4.7 This JPM starts the 1 C DG per AOP-5.0 and aligns it to unit 1 41 60v bus. Unit 2 A Train is de-energized and the Unit 1 A Train SW pumps will not be available. The IC DG will have to be shutdown lAW attachment or EPB Plaque due to no SW flow.

Farley March 2010 NRC JPM exam Page 1 of 3 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL

~

ility:

Farley Nuclear Plant Date of Examination:

March 8, 2010 m Level (both): RO SRO-I Operating Test No.: FA2010301 Control Room Systems (8 for RO; 7 for SRO-i)

System / JPM Title Type Code*

Safety

a. Perform an emergency boration. CRO-65C v1)24AA2.02 3.9/4.4 024AA2.01 3.8/4.1 The unit will have entered ESP-O.i. One rod will be stuck out and the candidate will have to determine to emergency borate. The Bat pump will have degraded head and will not deliver the proper flow.

The Attachment at the end of the procedure will have to be accomplished to align the RWST to the chg pump suction. The setup will have charging flow low and letdown secured so the candidate will have to increase charging flow and place letdown OIS and get proper flow.

b. CRO-327 A Align PRF System For A Large Break LOCA 011 EK3.12 RO-4.4 SRO-4.6 The PRF system is operating during a LB LOCA and one train has to be secured. This is an action required by EEP-1.0.
c. CRO-333E Perform Required Actions for transfer to simultaneous hot and cold leg recirculation'1)06A4.07 SRO 4.4 This JPM transfers from cold leg recirc to simultaneous hot and cold leg recirculation lAW ESP-1.4. The alternate path has RHR TO RCS HOT LEGS ISO Q1/2E11MOV8889 will not open so the RNO column will have to be used.

Modify to have the B Train chg pump will not start. The alternate path will align B train HHSI for cold leg recirculation. This will leave one train of LHSI to the cold legs and one train of HHSI to the hot. This will be evaluated in the final step to make sure the alignment is correct.

d. Perform required actions in response to RCP Seal Failures. CRO-047A

-1<iAAPE015AA1.224.0/4.2 1>03A2.023.7/3.9 This RCP seal failure has seal flow> 8 gpm and a reactor trip will have to be initiated by the CRO lAW AOP-4.1, Abnormal RCP seal leakage.

e. CRO-133A Start Up The Containment Cooling System v022A4.01 3.6/3.6

--'022A4.03 3.2/3.2 This JPM is a mode 5 JPM to start up the ctmt cooling system and start the dome recirc fans.

f. CRO-359E Start 1 C DG From The EPB And Align To Supply 1 F 4160V Bus

-1)55EA1.02 4.3/4.4

/055EA1.06 4.1/4.6 IvC55EA2.03 3.9/4.7 This JPM starts the 1C DG per AOP-5.0 and aligns it to unit 1 4160v bus. Unit 2 A Train is de-energized and the Unit 1 A Train SW pumps will not be available. The 1 C DG will have to be shutdown lAW attachment or EPB Plaque due to no SW flow.

Farley March 2010 NRC JPM exam v

S, M,A, L S,D,L S,~, L, M S,D,A v

S,D,P,~

On the 2007 NRC exam S,M,~

Function 1 v' Page 1 of3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL Facility:

Farley Nuclear Plant Exam Level (both): RO SRO-l

g. CR0-NEW Perform Corrective Actions In Response To a CCW

/

4 8 pump trip S, D, A, L O08A2.01 3.3/3.6 b26AA1.02 3.2/3.3 This is a new JPM written for the upcoming LOCT JPM exam.

It will be a bank JPM in December. Based on the fact that it will be used at our site I decided to classify it as a bank JPM.

This is a mode 5 JPM that has the operator respond to a CCW pump trip. AOP-9 is used to secure the charging pump and the RHR pump and transition to AOP-12.

h. CRO-316A Place one train of Control room air conditioning and C, D the same train CREFs in service after an LOSP without a Phase A 2 RO actuation.

ONLY 01 3A4 01 L48--

TJPM is to be accomplished in the trolro)After an LOSP Qpv w/o a phase A signal the control room air conditFers will not auto

start. The operator will manually start the A/C units per SOP-.56.0.

This involves operating thermostats in the control room and selecting jjJ) o the AC unit to be run. Set up that B train was running and the SS has directed the operator to place the A Train A/C i/s. This will entail 7

removing B Train from service also. Sections 4.3 and 4.6 This is my best guess:

a, b, c, d, and g are approx. 10-15 mm JPMs.

e, f and h are approx 20 minute JPIVIs with h being done in the CR as a simulate for 4 RO candidates.

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

System I JPM Title Type Safety Code*

Function

i. SO 386 Conduct a Waste Gas release 071A4.26 (3.l/3.9)v D, R 9/

This is a normal waste gas decay tank release.

j. S0-314A Operate the TDAFW pump locally without D,, L, E 4s control power 061A2.03 3.1/3.4 This will involve resetting the trip throttle valve, setting up the proper steam valve alignment on the TDAFW pump and then controlling the speed with the Trip throttle valve. This is a new Appendix for a loss of all AC to control the TDAFW pump manually.

7

k. S0-347A Place The Swing Battery Charger In Service D

6 058AA1.02 3.1/3.1 VO58AA1.03 3.1/3.3 This is a Unit 2 only JPM due to the fact that we installed a new battery charger in the system and it is different from unit 1 1 C Battery charger.

The 3 in plants are all approximately 20-30 minutes in length. Two can be decreased in length depending on how much of the procedure is required to be done.

I can remove all extraneous steps prior to the major actions taken to decrease the length.

I tried to keep in mind having the candidates do more than push a button or operate a valve.

Date of Examination:

March 8, 2010 Oieratinci Test No.: FA2010301

.7 cc JJ //

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j}

6 Farley March 2010 NRC JPM exam Page 2 of 3 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL Date of Examination:

March 8, 2010 o eratin Test No.: FA2010301

g. CRO-NEW Perform Corrective Actions In Response To a CCW pump trip v608A2.01 3.3/3.6 v026AA 1.02 3.2/3.3 This is a new JPM written for the upcoming LOCT JPM exam. It will be a bank JPM in December. Based on the fact that it will be

,/

S, D,A, L

'8 used at our site I decided to classify it as a bank JPM.

'1 This is a mode 5 JPM that has the operator respond to a CCW

\\{)t'\\ I

(\\\\{\\\\j\\Jy pump trip. AOP-9 is used to secure the charging pump and the

)'?, y/

~~~R~H~R~pu~m~p=a~n~d~t~ra~n~s~it~io~n~t~07A~0~P_-~1~2~' ____ ~

__ ~~~

__ ~

__ -r __ ~~

__ -4 __ ~~~~~/v

h. CRO-316A Place one train of Control room air conditioning and C, D the same train CREFs in service after an LOSP without a Phase A actuation.

.~

013A4.01 4.5L4~8--~)

~.-----

_._-.-.... -.... -.. -.~.-

Tfli§'JpMistobe accomplished in the~ntrol ro~;;~~YAfter an LOSP w/o a phase A signal the control room alrConarfioners will not auto start. The operator will manually start the AlC units per SOP-56.0.

This involves operating thermostats in the control room and selecting the AC unit to be run. Set up that B train was running and the SS has directed the operator to place the A Train A/C ils. This will entail removin B Train from service also. Sections 4.3 and 4.6 This is my best guess:

a, b, c, d, and g are approx. 10-15 min JPMs.

e, f and hare approx 20 minute JPMs with h being done in the CR as a simulate for 4 RO candidates.

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

System / JPM Title Type Safety Code*

Function

i. SO - 386 Conduct a Waste Gas release 071A4.26 (3.1/3.9)v""

D,R 9/

This is a normal waste gas decay tank release.

j. SO-314A Operate the TDAFW pump locally without D,~,L,E 4sv control power 061A2.03 3.1/3.4 This will involve resetting the trip throttle valve, setting up the proper steam valve alignment on the TDAFW pump and then controlling the speed with the Trip throttle valve. This is a new Appendix for a loss of all AC to control the TDAFW pump manually.
y. SO-347A Place The Swing Battery Charger In Service D

6 058AA1.02 3.1/3.1 vQ58AA1.033.1/3.3 0.-/

This is a Unit 2 only JPM due to the fact that we installed a new battery charger in the system and it is different from unit 1 1 C Battery charger.

The 3 in plants are all approximately 20-30 minutes in length. Two can be decreased in length depending on how much of the procedure is required to be done. I can remove all extraneous steps prior to the major actions taken to decrease the length. I tried to keep in mind having the candidates do more than push a button or operate a valve.

Farley March 2010 NRC JPM exam Page 2 of3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL All control room (and in-plant) systems must be different and serve different safety functions; in plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO! SRO-i [ACTUAL]

(A)lternate path 4-6 / 4-6 / 2-3 [616]

(C)ontrol room

[110]

(D)irect from bank

< 9 I < S I < 4

[817]

(E)mergency or abnormal in-plant

> 1 I> 1

[111]

(L)ow-Power I Shutdown

> 1 I> 1

[616]

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

> 2 I> 2

[313]

(P)previous 2 exams

< 3 I < 3 / < 2 (randomly selected) [Ill]

(R)CA

>1/>1

[111]

(S)imulator

[717]

Farley March 2010 NRC JPM exam Page 3 of 3 ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 DRAFT OPERATING OUTLINE SUBMITTAL 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 ROI SRO-i [ACTUAL]

(A)lternate path 4-6/4-6/2-3 [6/6]

(C)ontrol room

[1/0]

(D)irect from bank

.:::9/.:::8/.:::4 [8/7]

(E)mergency or abnormal in-plant

> 1 / > 1

[1/1]

(L)ow-Power I Shutdown

~ 11 ~ 1

[6/6]

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

~2/~2

[3/3]

(P)previous 2 exams

.::: 31.::: 3/.::: 2 (randomly selected) [1/1]

(R)CA

~ 11 ~ 1

[1/1]

(S)imulator

[7/7]

Farley March 2010 NRC JPM exam Page 3 of3

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