ML102940514

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2010 LaSalle County Station Initial License Examination Outline Submission Examiner Standards Forms
ML102940514
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 09/24/2010
From: Mcneil D
Operations Branch III
To:
References
ES-301-1
Download: ML102940514 (26)
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: LaSalle County Station_________ Date of Examination: 09/13/10-09/24/10 Examination Level: RO SRO Operating Test Number: 2010301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Emergency Response actions of injured person per N,S 2.1.2 4.1/4.4 LAP-950-3, Handling Personnel Injuries.

Determine availability to assume shift work hour Conduct of Operations N,S 2.1.5 2.9/3.9 rules application.

Equipment Control N, S Identify isolation points for a leak in the fire 2.2.41 3.5/3.9 protection header.

Radiation Control Determine brief and protective clothing D, S 2.3.7 3.5/3.6 requirements of an RWP.

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

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: _LaSalle County Station_________ Date of Examination: 09/13/10 - 09/24/10 Examination Level: RO SRO Operating Test Number: 2010301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Reactivation of an SRO License per OP-AA-105-Conduct of Operations D,S 2.1.4 3.3/3.8 102, NRC Active License Maintenance Determine availability to assume shift work hour Conduct of Operations N,S 2.1.5 2.9/3.9 rules application.

Equipment Control Identify isolation points for a leak in the fire N, S 2.2.41 3.5/3.9 protection header and identify any T.S. actions.

Determine brief and protective clothing Radiation Control D, S 2.3.7 3.5/3.6 requirements of an RWP.

Emergency Procedures/Plan N,S Classify a Security Event IAW EP-AA-1005 2.4.29 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: LaSalle County Station ________________ Date of Examination: 09/13/10 - 09/24/10 Exam Level: RO SRO-I SRO-U Operating Test No.: 2010301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Reactor Recirc. System / Downshift RR Pumps /Failure of one RR pump to 1 S,A,D downshift ( 202001, A4.01,3.7/3.7)
b. Reactor Water Level Control/ Loss of TDRFP speed feedback signal/restore to Auto 2 S,N (259002, A4.03, 3.8/3.6)
c. Emergency - High Reactor Pressure/ RPV Depressurization via RT per LGA-RT- 3 S,A, N,L 102/ Subsequent leak (295025, A.2.2.44, 4.2/4.4)
d. Reactor Core Isolation Cooling/ Perform RCIC S/D following spurious init. with 4 S,A,D failure of the injection valve to close ( 217000, A2.01, 3.8/3.7)
e. Rod Position Indication System/RPIS data fault/ substitute rod position (214000, 7 S,N A4.02, 3.8/3.8)
f. Standby Gas Treatment/Manually initiate SBGT in response to irradiated fuel 9 S,N,EN assembly damage ( 261000, A2.12, 3.2/3.4)
g. Fuel Handling / Installation of Control Rod Block IAW LFP-100-1 (234000, A4.02, 8 C,N,L 3.4/3.7
h. AC Electrical Distribution / Loss of 141Y Hard Card - Failure to Bus Tie (295003 S,A,D,L 6 a.1.01, 3.7/3.8)

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

i. DC Electrical System / DC Load shed after Station Blackout (263000, A4.01, 3.3/3.5 D,L,E,R 6
j. Reactor Low Water Level / Fill SBLC tank with alternate source of water for alternate 2 D,E,A,R injection (295031, A1.08, 3.8/3.9)
k. Primary Containment System / Manually isolate a stuck open primary containment 5 D,A,EN,R vacuum breaker (223001, A2.02, 3.9/4.1)

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: LaSalle County Station ________________ Date of Examination: 09/13/10 - 09/24/10 Exam Level: RO SRO-I SRO-U Operating Test No.: 2010301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Reactor Recirc. System / Downshift RR Pumps /Failure of one RR pump to 1 S,A,D downshift ( 202001, A4.01,3.7/3.7)
b. Reactor Water Level Control/ Loss of TDRFP speed feedback signal/restore to Auto 2 S,N (259002, A4.03, 3.8/3.6)
c. Emergency - High Reactor Pressure/ RPV Depressurization via RT per LGA-RT- 3 S,A, N,L 102/ Subsequent leak (295025, A.2.2.44, 4.2/4.4)
d. Reactor Core Isolation Cooling/ Perform RCIC S/D following spurious init. with 4 S,A,D failure of the injection valve to close ( 217000, A2.01, 3.8/3.7
e. Rod Position Indication System/RPIS data fault/ substitute rod position (214000, 7 S,N A4.02, 3.8/3.8)
f. Standby Gas Treatment/Manually initiate SBGT in response to irradiated fuel 9 S,N,EN assembly damage ( 261000, A2.12, 3.2/3.4)
g. Fuel Handling / Installation of Control Rod Block IAW LFP-100-1 (234000, A4.02, 8 C,N,L 3.4/3.7
h. n/a n/a n/a In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. DC Electrical System / DC Load shed after Station Blackout (263000, A4.01, 3.3/3.5 D,L,E,R 6
j. Reactor Low Water Level / Fill SBLC tank with alternate source of water for alternate 2 D,E,A,R injection (295031, A1.08, 3.8/3.9)
k. Primary Containment System / Manually isolate a stuck open primary containment 5 D,A,EN,R vacuum breaker (223001, A2.02, 3.9/4.1)

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

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

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility LaSalle County Station Date of Exam 09/13/2010 Operating Test No 2010301 A E Scenarios P V 1 2 3 4 M P E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION O N T

I T I C T A M A Y S A B S A B S A B S A B L U N P R T O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RX 2 1 1 1 0 RO NOR 2 1 1 1 1 SRO-I 2,3, 4 4 2 I/C 3,5 4.6 8 5,6 SRO-U MAJ 6,7 7 7,8 5 2 2 1 RO-1 RO-2 TS 0 0 2 2 RX 1 1 1 1 0 RO 1 1 1 NOR 2 1 SRO-I 2,3, 4 4 2 I/C 3,5 3,4, 8 5,6 SRO-U 2 2 1 MAJ 6,7 7 7 4 RO-3 0 2 2 TS 0 RX 1 1 1 1 0 RO NOR 2 1 2 1 1 1 SRO-I 1,3, 4 4 2 I/C 4 3,5 7 4,5 SRO-U MAJ 6,7 7 7,8 5 2 2 1 SRO-1 SRO-3 TS 1,3, 4 3 0 2 2 RX 1 2 2 1 1 0 RO NOR 1 1 1 1 1 SRO-I 2,3,4, 3,4, 4 4 2 I/C 1,4 11 5,6 5,6 SRO-U MAJ 6,7 7 7,8 5 2 2 1 SRO-2 SRO-4 TS 2,3,4 2,3,4 6 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility LaSalle County Station Date of Exam 09/13/2010 Operating Test No 2010301 A E Scenarios P V 1 2 3 4 M P E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION O N T

I T I C T A M A Y S A B S A B S A B S A B L U N P R T O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RX 1 1 1 1 0 RO 1 1 1 NOR 2 2 SRO-I 1,3, 4 4 2 I/C 4 6 4,5 SRO-U 2 2 1 MAJ 6,7 7 4 SRO-5 0 2 2 TS 1,3,4 3 RX 1 1 1 1 0 RO 2,3,4 1 1 1 NOR 1

,5,6 SRO-I I/C 1,4 7 8 4 4 2 SRO-U MAJ 2,5 2,3,4 4 2 2 1 SRO-6 SRO-8 TS 3 0 2 2 RX 1 1 1 1 0 RO 1 1 1 NOR 2 1 SRO-I 1,3, 2,3, 4 4 2 I/C 3,4 10 4,5 5,6 SRO-U 2 2 1 MAJ 7 7 7 3 SRO-7 0 2 2 TS 3,4 2 RX 1 1 2 1 1 0 RO 1 1 1 NOR 2 2 2 SRO-I 4 4 2 I/C 35 4 345 6 SRO-U 2 2 1 MAJ 67 7 7 4 SRO-9 TS 56 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

ES-301 Transient and Event Checklist Form ES-301-5

Facility LaSalle County Station Date of Exam 09/13/2010 Operating Test No 2010301 A E Scenarios P V 1 2 3 4 M P E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION O N T

I T I C T A M A Y S A B S A B S A B S A B L U N P R T O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RX 2 1 2 1 1 0 RO 1 1 1 NOR 1 1 SRO-I 3,4, 4 4 2 I/C 3,4 6 5,6 SRO-U 2 2 1 MAJ 7,8 7 3 SRO-10 0 2 2 TS 2,3,4 3 RX 2 1 2 1 1 0 RO 1 1 1 NOR 2 1 SRO-I 4 4 2 I/C 4,6 3,4,5 5 SRO-U 2 2 1 MAJ 7,8 7 3 SRO-11 TS 5,6 2 0 2 2 1 1 0 1 1 1 RO 4 4 2 SRO-I 2 2 1 SRO-U 0 2 2 1 1 0 1 1 1 RO 4 4 2 SRO-I 2 2 1 SRO-U 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

ES-401 3 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Facility: LaSalle Co. Station Date of Exam: 09/13/2010 RO K/A Category Points SRO-Only Points Grou Tier K K K K K K A A A A G p Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • 1 3 3 3 3 4 4 20 4 3 7 1.

Emergency 2 1 1 1 1 2 1 7 1 2 3 Plant Tier Evolutions Total 4 4 4 4 6 5 27 5 5 10 s

1 2 2 2 2 2 3 3 3 2 2 3 26 3 2 5 2.

2 1 1 1 2 1 1 1 1 1 1 1 12 0 1 2 3 Plant Systems Tier Total 3 3 3 4 3 4 4 4 3 3 4 38 4 4 8 s

1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 3 2 3 2 2 1 2 2 Note 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of
the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant specific priority, only those KAs 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 K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As

8. On the following pages, enter the K/A 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 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 10CFR55.43

ES-401 3 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

Function AA2.02 - Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to X 3.4 76 Cooling / 4 LOSS OF SHUTDOWN COOLING :

RHR/shutdown cooling system flow AA2.03 - Ability to determine and/or 295023 Refueling Acc Cooling interpret the following as they apply to X 3.8 77 Mode / 8 REFUELING ACCIDENTS : Airborne contamination levels AA2.06 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site / 8 X PLANT FIRE ON SITE: Need for 2.8 78 pressurizing control room (recirculating mode) 2.1.7 - Conduct of Operations: Ability to evaluate plant performance and make 295038 High Off-site Release X operational judgements based on 4.7 79 Rate / 9 operating characteristics, reactor behavior, and instrument interpretion.

2.2.44 - Equipment Control: Ability to interpret control room indications to 295026 Suppression Pool High verify the status and operation of a X 4.4 80 Water Temp. / 5 system, and understand how operator actions and directives effect plant and system conditions.

2.2.40 - Equipment Control: Ability to 295006 SCRAM / 1 X apply technical specifications for a 4.7 81 system.

EA2.04 - Ability to determine and/or 295031 Reactor Low Water interpret the following as they apply to X 4.8 82 Level / 2 REACTOR LOW WATER LEVEL :

Adequate core cooling AK1.02 - Knowledge of the operational implications of the following concepts 295006 SCRAM / 1 X 3.4 39 as they apply to SCRAM : Shutdown margin AK1.02 - Knowledge of the operational implications of the following concepts 295021 Loss of Shutdown X as they apply to LOSS OF 3.3 40 Cooling / 4 SHUTDOWN COOLING : Thermal stratification EK1.04 - Knowledge of the operational implications of the following concepts 295037 SCRAM Conditions as they apply to SCRAM CONDITION Present and Reactor Power X PRESENT AND REACTOR POWER 3.4 41 Above APRM Downscale or ABOVE APRM DOWNSCALE OR Unknown / 1 UNKNOWN: Hot shutdown boron weight: Plant-Specific AK2.07 - Knowledge of the 295005 Main Turbine interrelations between MAIN TURBINE X 3.6 42 Generator Trip / 3 GENERATOR TRIP and the following:

Reactor pressure control AK2.05 - Knowledge of the interrelations between PARTIAL OR 295019 Partial or Total Loss of X COMPLETE LOSS OF INSTRUMENT 3.4 43 Inst. Air / 8 AIR and the following: Main steam system AK2.07 - Knowledge of the interrelations between GENERATOR 700000 Generator Voltage and X VOLTAGE AND ELECTRIC GRID 3.6 44 Electric Grid Disturbances DISTURBANCES and the following:

Turbine/generator control.

AK3.04 - Knowledge of the reasons for 600000 Plant Fire On-site / 8 X 2.8 45 the following responses as they apply

ES-401 3 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

Function to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site AK3.03 - Knowledge of the reasons for 295016 Control Room the following responses as they apply X 3.5 46 Abandonment / 7 to CONTROL ROOM ABANDONMENT

Disabling control room controls EK3.09 - Knowledge of the reasons for 295025 High Reactor Pressure the following responses as they apply X 3.7 47

/3 to HIGH REACTOR PRESSURE : Low-low set initiation: Plant-Specific AA1.02 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of X PARTIAL OR COMPLETE LOSS OF 3.8 48 DC Pwr / 6 D.C. POWER : Systems necessary to assure safe plant shutdown EA1.04 - Ability to operate and/or 295031 Reactor Low Water monitor the following as they apply to X 4.3 49 Level / 2 REACTOR LOW WATER LEVEL : High pressure core spray: Plant-Specific EA1.14 - Ability to operate and/or 295024 High Drywell Pressure monitor the following as they apply to X 3.4 50

/5 HIGH DRYWELL PRESSURE: Drywell ventilation system EA2.03 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to X 3.7 51 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL : Reactor pressure EA2.03 - Ability to determine and/or 295038 High Off-site Release interpret the following as they apply to X 3.5 52 Rate / 9 HIGH OFF-SITE RELEASE RATE :

Radiation levels AA2.03 - Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow X PARTIAL OR COMPLETE LOSS OF 3.3 53 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION

Actual core flow 2.1.28 - Conduct of Operations:

295023 Refueling Acc Cooling Knowledge of the purpose and function X 4.1 54 Mode / 8 of major system components and controls.

2.4.8 - Emergency Procedures / Plan:

295003 Partial or Complete Knowledge of how abnormal operating X 3.8 55 Loss of AC / 6 procedures are used in conjunction with EOP's.

2.4.3 - Emergency Procedures / Plan:

295026 Suppression Pool High X Ability to identify post-accident 3.7 56 Water Temp. / 5 instrumentation.

EA2.02 - Ability to determine and/or 295028 High Drywell interpret the following as they apply to X 3.8 57 Temperature / 5 HIGH DRYWELL TEMPERATURE :

Reactor pressure 2.4.11 - Emergency Procedures / Plan; 295018 Partial or Total Loss of X Knowledge of abnormal condition 4.0 58 CCW / 8 procedures.

K/A Category Totals: 3 3 3 3 4/4 4/3 Group Point Total: 20/7

ES-401 4 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 1 EAPE # / Name Safety K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

Function AA2.02 - Ability to determine and/or interpret the following as they apply to 295020 Inadvertent Cont.

X INADVERTENT CONTAINMENT 3.4 83 Isolation / 5 & 7 ISOLATION : Drywell/containment temperature 2.4.44 - - Emergency Procedures / Plan:

295017 High Off-site Release X Knowledge of emergency plan 4.4 84 Rate / 9 protective action recommendations.

2.2.25 - Equipment Control: Knowledge 295009 Low Reactor Water of the bases in Technical Specifications X 4.2 85 Level / 2 for limiting conditions for operations and safety limits.

AK1.03 - Knowledge of the operational 295008 High Reactor Water implications of the following concepts as X 3.2 59 Level / 2 they apply to HIGH REACTOR WATER LEVEL : Feed flow/steam flow mismatch AK2.07 - Knowledge of the interrelations between LOSS OF CRD 295022 Loss of CRD Pumps /

X PUMPS and the following: Reactor 3.4 60 1

pressure (SCRAM assist): Plant-Specific AK3.02 - Knowledge of the reasons for the following responses as they apply to 295013 High Suppression Pool X HIGH SUPPRESSION POOL 3.6 61 Temperature / 5 TEMPERATURE : Limiting heat additions AA1.08 - Ability to operate and/or monitor the following as they apply to 295015 Incomplete SCRAM / 1 X INCOMPLETE SCRAM : Process 2.7 62 computer/SPDS/ERIS/CRIDS/GDS:

Plant-Specific EA2.01 - Ability to determine and/or 295032 High Secondary interpret the following as they apply to Containment Area Temperature X HIGH SECONDARY CONTAINMENT 3.8 63

/5 AREA TEMPERATURE : Area temperature 2.4.50 - Emergency Procedures / Plan:

295035 Secondary Ability to verify system alarm setpoints Containment High Differential X 4.2 64 and operate controls identified in the Pressure / 5 alarm response manual.

EA2.03 - Ability to determine and/or 295036 Secondary interpret the following as they apply to Containment High Sump/Area X SECONDARY CONTAINMENT HIGH 3.4 65 Water Level / 5 SUMP/AREA WATER LEVEL : Cause of the high water level K/A Category Totals: 1 1 1 1 2/1 1/2 Group Point Total: 7/3

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System # / Name A2 G K/A Topics Imp Q#

1 2 3 4 5 6 1 3 4 A2.01 - Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b) 262002 UPS (AC/DC) X based on those predictions, use 2.8 86 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under voltage A2.03 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on 211000 SLC X those predictions, use 3.4 87 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. power failures 2.4.6 - Emergency Procedures /

205000 Shutdown Cooling X Plan: Knowledge of EOP 4.7 88 mitigation strategies.

2.2.36 - Equipment Control:

Ability to analyze the effect of 215004 Source Range maintenance activities, such as X 4.2 89 Monitor degraded power sources, on the status of limiting conditions for operations.

A2.03 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based 264000 Emergency on those predictions, use X 3.4 90 Generators procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Operating unloaded, lightly loaded, and highly loaded.

K1.03 - Knowledge of the physical connections and/or cause- effect relationships 259002 Reactor Water X between REACTOR WATER 3.8 1 Level Control LEVEL CONTROL SYSTEM and the following: Reactor water level K1.11 - Knowledge of the physical connections and/or cause- effect relationships between PRIMARY 223002 PCIS/Nuclear X CONTAINMENT ISOLATION 2.9 2 Steam Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Containment atmosphere sampling K2.01 - Knowledge of electrical 215003 IRM X power supplies to the following: 2.5 3 IRM channels/detectors K2.01 - Knowledge of electrical 262001 AC Electrical X power supplies to the following: 3.3 4 Distribution Off-site sources of power

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K3.05 - Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT 261000 SGTS X 3.2 5 SYSTEM will have on following:

Secondary containment radiation/ contamination levels K3.03 - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS 264000 EDGs X (DIESEL/JET) will have on 4.1 6 following: Major loads powered from electrical buses fed by the emergency generator(s)

K4.02 - Knowledge of D.C.

ELECTRICAL DISTRIBUTION design feature(s) and/or 263000 DC Electrical X interlocks which provide for the 3.1 7 Distribution following: Breaker interlocks, permissives, bypasses and cross ties: Plant-Specific K4.10 - Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) design feature(s) and/or interlocks 203000 RHR/LPCI: Injection X which provide for the following: 3.9 8 Mode Dedicated injection system during automatic system initiation (injection valve interlocks)

K5.02 - Knowledge of the operational implications of the following concepts as they apply 205000 Shutdown Cooling X to SHUTDOWN COOLING 2.8 9 SYSTEM (RHR SHUTDOWN COOLING MODE) : Valve operation K5.05 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE 215005 APRM / LPRM X 3.6 10 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

Core flow effects on APRM trip setpoints K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 262002 UPS (AC/DC) X 2.7 11 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) : A.C.

electrical power K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the 212000 RPS X 3.5 12 REACTOR PROTECTION SYSTEM : Nuclear boiler instrumentation A1.07 - Ability to predict and/or monitor changes in parameters associated with operating the 209001 LPCS X LOW PRESSURE CORE 3.0 13 SPRAY SYSTEM controls including: Emergency generator loading

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 211000 SLC X 3.6 14 STANDBY LIQUID CONTROL SYSTEM controls including:

Tank level A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based 215004 Source Range X on those predictions, use 3.4 15 Monitor procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SRM inop condition A2.04 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, 239002 SRVs X use procedures to correct, 4.1 16 control, or mitigate the consequences of those abnormal conditions or operations: ADS actuation A3.01 - Ability to monitor automatic operations of the CCWS including: Setpoints on 400000 Component Cooling X instrument signal levels for 3.0 17 Water normal operations,warnings, and trips that are applicable to the CCWS A3.06 - Ability to monitor automatic operations of the HIGH PRESSURE CORE 209002 HPCS X 2.8 18 SPRAY SYSTEM (HPCS) including: Lights and alarms:

BWR-5,6 K/A A4.02 - Ability to manually 218000 ADS X operate and/or monitor in the 4.2 19 control room: ADS logic initiation A4.05 - Ability to manually operate and/or monitor in the 217000 RCIC X 4.1 20 control room: Reactor water level 2.2.4 Equipment Control:

(multiple-unit license) Ability to explain the variations in control 300000 Instrument Air X board/control room layouts, 3.6 21 systems, instrumentation, and procedural actions between units at a facility.

2.4.45 - Emergency Procedures

/ Plan: Ability to prioritize and 212000 RPS X 4.1 22 interpret the significance of each annunciator or alarm.

A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 259002 Reactor Water X REACTOR WATER LEVEL 3.6 23 Level Control CONTROL SYSTEM controls including: Reactor feedwater flow 2.2.3 - Equipment Control:

(multi-unit license) Knowledge of 263000 DC Electrical X the design, procedural, and 3.8 24 Distribution operational differences between units.

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 A2.01 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based 262001 AC Electrical on those predictions, use X 3.4 25 Distribution procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine/generator trip K6.09 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection following will have on the X 3.4 26 Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : Nuclear boiler instrumentation K/A Category Totals: 2 2 2 2 2 3 3 3/3 2 2 3/2 Group Point Total: 26/5

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System # / Name G K/A Topics Imp Q#

1 2 3 4 5 6 1 2 3 4 A2.02 - Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) 201002 RMCS X based on those predictions, use 3.3 91 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod drift alarm 2.4.20 - Equipment Control:

219000 RHR/LPCI: Knowledge of the operational X 4.3 92 Torus/Pool Cooling Mode implications of EOP warnings, cautions, and notes.

2.2.38 - Equipment Control:

241000 Reactor/Turbine X Knowledge of conditions and 4.5 93 Pressure Regulator limitations in the facility license.

K1.05 - Knowledge of the physical connections and/or cause- effect relationships 256000 Reactor X between REACTOR 3.1 27 Condensate CONDENSATE SYSTEM and the following: CRD hydraulics system K2.01 - Knowledge of electrical 239001 Main and Reheat power supplies to the following:

X 3.2 28 Steam Main steam isolation valve solenoids K3.03 - Knowledge of the effect that a loss or malfunction of the 234000 Fuel Handling X FUEL HANDLING EQUIPMENT 3.1 29 Equipment will have on following: Fuel handling operations K4.02 - Knowledge of RECIRCULATION System design feature(s) and/or 202001 Recirculation X 3.1 30 interlocks which provide for the following: Adequate recirculation pump NPSH K5.02 - Knowledge of the operational implications of the 290002 Reactor Vessel following concepts as they apply X 2.9 31 Internals to REACTOR VESSEL INTERNALS : Fission product poisons K6.02 - Knowledge of the effect that a loss or malfunction of the 286000 Fire Protection X following will have on the FIRE 2.8 32 PROTECTION SYSTEM D. C .

electrical distribution A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 272000 Radiation RADIATION MONITORING X 3.2 33 Monitoring SYSTEM controls including:

Lights, alarms, and indications associated with normal operations

ES-401 5 Form ES-401-1 LaSalle Class 09-1 NRC ILT Exam Written Examination Outline Plant Systems - Tier 2 Group 2 A2.02 - Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) 202002 Recirculation Flow X based on those predictions, use 2.9 34 Control procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of A.C.

A3.03 - Ability to monitor automatic operations of the 215001 Traversing In-core X TRAVERSING IN-CORE 2.5 35 Probe PROBE including: Valve operation: Not-BWR1 A4.01 - Ability to manually 245000 Main Turbine operate and/or monitor in the Generator and Aux. X 2.7 36 control room: Turbine lube oil Systems pumps 2.4.4 - Emergency Procedures /

Plan: Ability to recognize abnormal indications for system 288000 Plant Ventilation X operating parameters which are 4.5 37 entry-level conditions for emergency and abnormal operating procedures.

K4.02 - Knowledge of the effect that a loss or malfunction of the ROD POSITION 214000 RPIS X 2.5 38 INFORMATION SYSTEM will have on following:

Thermocouple 1

K/A Category Totals: 1 1 1 2 1 1 1 / 1 1 1/2 Group Point Total: 12/3 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: LaSalle County Station Exam Date: 09/13/2010 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Knowledge of individual licensed operator responsibilities related to shift staffing, such 2.1.4 as medical requirements, "no-solo" operation, 3.8 94 maintenance of active license status, 10CFR55, etc.

Ability to interpret and execute procedure 2.1.20 4.6 98 steps.

Knowledge of procedures and limitations 2.1.36 3.0 66

1. involved in core alterations.

Conduct Ability to explain and apply all system limits 2.1.32 3.8 67 of Operations and precautions.

Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, 2.1.44 communication with fuel storage facility, 3.9 74 systems operated from the control room in support of fueling operations, and supporting instrumentation.

Subtotal 3 2 Knowledge of the process for making design 2.2.5 3.2 95 or operating changes to the facility.

Ability to recognize system parameters that 2.2.42 are entry-level conditions for Technical 3.9 68

2. Specifications.

Equipment Ability to determine the expected plant Control configuration using design and configuration 2.2.15 3.9 69 control documentation, such as drawings, line-ups, tag-outs, etc.

Subtotal 2 1 2.3.11 Ability to control radiation releases. 4.3 96 Knowledge of Radialogical Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 3.8 100 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, 3.

such as fixed radiation monitors and alarms, Radiation 2.3.15 2.9 70 portable survey instruments, personnel Control monitoring equipment, etc.

Knowledge of radiation exposure limits under 2.3.4 3.2 71 normal or emergency conditions.

Knowledge of radiation or containment hazards that may arise during normal, 2.3.14 3.4 75 abnormal, or emergency conditions or activities.

Subtotal 3 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 97 acting as emergency coordinator if required.

Knowledge of local auxiliary operator tasks

4. 2.4.35 during emergency and the resultant 4.0 99 Emergency operational effects.

Procedures / Knowledge of RO tasks performed outside Plan 2.4.34 the main control room during an emergency 4.2 72 and the resultant operational effects.

Knowledge of the emergency action level 2.4.41 2.9 73 thresholds and classifications.

Subtotal 2 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Note: Western Technical Services BWR Outline software was used to randomly select K/As.

Randomly Question # Tier / Group Reason for Rejection Selected K/A 2.2.36 - Equipment Control: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations was also selected for SRO question #89. 2.2.4 Equipment Control: (multiple-unit Tier 2 / Gr. 1 300000 21 license) Ability to explain the variations in control board/control RO 2.2.36 room layouts, systems, instrumentation, and procedural actions between units at a facility. was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology to replace the original K/A to prevent duplication of the K/A on the exam.

2.4.6 - Emergency Procedures / Plan: Knowledge of EOP mitigation strategies was also selected for SRO question #88.

Tier 1 / Gr. 1 295026 K/A 2.4.3 Emergency Procedures / Plan Ability to identify post-56 RO 2.4.6 accident instrumentation was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology to replace the original K/A to prevent duplication of the K/A on the exam.

EAP 295022 was over-sampled, so a new EAP was randomly Tier 1 / Gr. 2 selected using ES-401 Attachment 1 Systematic Sampling 84 295022 SRO Methodology. The new EAP is 295017, High Off-site release rate. The original Generic K/A is retained, which is 2.2.22.

EAP 295013 was over-sampled, so a new EAP was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology. The new EAP is 295009, Low Reactor Water Level.

Generic 2.2.3 Equipment Control: (multi-unit license) Knowledge Tier 1 / Gr. 2 295013 85 of the design, procedural, and operational differences between SRO 2.2.3 units, is not applicable to SRO questions. Replaced with Generic K/A 2.2.25 Equipment Control: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

System 212000 was over-sampled, so a new system was Tier 2 / Gr. 1 randomly selected using ES-401 Attachment 1 Systematic 87 212000 SRO Sampling Methodology. The new system is 211000, Standby Liquid Control. The original K/A is retained, which is A2.03.

System 262001 was over-sampled, so a new system was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology. The new system is 264000, Emergency Generators (Diesel/Jet).

The originally selected K/A A2.11 does not exist under System Tier 2 / Gr. 1 262001 264000, so K/A 2.03 Ability to (a) predict the impacts of the 90 SRO A2.11 following on the EMERGENCY GENERATORS (DIESEL/JET) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Operating unloaded, lightly loaded, and highly loaded, was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Question # Tier / Group Reason for Rejection Selected K/A 2.4.2 - Emergency Procedures / Plan: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions is not applicable to SRO questions. Replaced Tier 2 / Gr. 2 219000 92 with Generic K/A 2.4.20 Knowledge of the operational SRO 2.4.2 implications of EOP warnings, cautions, and notes, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

2.2.12 - Equipment Control: Knowledge of surveillance procedures, is not applicable to SRO questions. Replaced with Tier 2 / Gr. 2 241000 93 Generic K/A 2.2.38 Knowledge of conditions and limitations in SRO 2.2.12 the facility license, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

Changes after initial submittal A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leaky SRV, was originally selected however it was not possible to create a question that had specific procedural direction provided for a Tier 2 / Gr. 1 239002 15 "Leaky SRV". Replaced with K/A A2.04 - Ability to (a) predict the RO A2.02 impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: ADS actuation, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

A4.04 - Ability to manually operate and/or monitor in the control room: ADS inhibit: Plant Specific. This K/A was rejected due to overlap with the operating portion of the exam. Replaced with Tier 2 / Gr. 1 218000 19 K/A A4.02 - Ability to manually operate and/or monitor in the RO A4.04 control room: ADS logic initiation, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

A2.08 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Opening a disconnect under load was originally selected however it was not possible to create a question that had specific Tier 2 / Gr. 1 262001 25 procedural direction provided for "Opening a disconnect under RO A2.08 load". Replaced with A2.01 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine/generator trip, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

A4.01 - Ability to manually operate and/or monitor in the control room: System pumps. Original K/A overlapped with a simulator Tier 2 / Gr. 2 204000 JPM and required replacement. Replaced with System 245000, 36 RO A4.01 Main Turbine Generator and Auxiliary Systems, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology. Original K/A number was retained, and

ES-401 Record of Rejected K/As Form ES-401-4 is basically the same, A4.01 - Ability to manually operate and/or monitor in the control room: Turbine lube oil pumps 2.4.30 - Emergency Procedures / Plan; Knowledge of events related to system operation / status that must be reported to internal organizations or external agencies, such as the state, the Tier 1 / Gr. 1 295018 NRC, or the transmission system operator was originally selected 58 RO 2.4.30 however it was not possible to create a question on the RO level and tied to a CCW system. Replaced with 2.4.11, Knowledge of abnormal condition procedures which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

AA2.11 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Time limit for use of respirators, was originally selected however it was not possible to create a question which could be supported with specific time limits for respirator use. Time limits specified in support Tier 1 / Gr.1 600000 78 documents were general in nature, using language such as short SRO AA2.11 term, approximately, etc. Replaced with K/A AA2.06 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Need for pressurizing control room (recirculating mode), which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

2.2.22 - Equipment Control: Knowledge of limiting conditions for operations and safety limits was originally selected however it was not possible to create a question which tied an LCO or safety Tier 1 / Gr. 2 295017 84 limit to 295017, High Off-site release rate. Replaced with K/A SRO 2.2.22 2.4.44 Knowledge of emergency plan protective action recommendations which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

A2.01 - Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Rod movement sequence timer malfunctions was originally selected, however it was not possible to create a question Tier 2 / Gr. 2 201002 because the electronic circuitry used in RCMS has integrated 91 SRO A2.01 back-up checks to deal with timer issues. Replaced with A2.02, -

Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Rod drift alarm, which was randomly selected using ES-401 Attachment 1 Systematic Sampling Methodology.

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle County Station Scenario No.: 1 Test No.: 2010301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: S/U IC Turnover:

  • Unit 1 startup is in progress IAW LGP 1-1, step E. 4, Mode Switch to Run.
  • Reactor power is being raised via control rod withdrawal to transfer the Mode Switch to Run.
  • 1 D CD/CB pump and oil pump are OOS for lube oil pump repair.
  • Swap VP per LOP-VP-02.

Event Malf. Event Type* Event No. No. Description Pull Rods for reactor Startup IAW LGP 1-1. One rod will 1 MRD060 C RO uncouple when full out. Rod will be driven full in. (TS) 2 N/A N BOP Swap VP loops IAW LOP-VP-LOP-VP-02.

MRM03 Station Vent Stack WRGM low range pump trip / trip on 3 C BOP 4 restart and unavailable (TS) 4 MNI018 I RO A IRM fails high (TS) 5 cae C BOP TBCCW system low pressure 6 Mcf033 M All FW break outside containment / scram 7 Mrc034 M All RR LOCA on B RR suction 8 cae C BOP 1VP053B fails to isolate

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

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle County Station Scenario No.: 2 Test No.: 2010301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: IC for RR upshift (30%-35% power)

Turnover:

  • Reactor Power is 30%-35%, ready for RR pump upshift per step E.6.4 of LGP 1-1.

Event Malf. No. Event Type* Event No. Description 1 N/A R RO Upshift RR per LOP-RR-05 2 CAE C BOP Earthquake, A VR Exhaust Fan Trip (TS) 3 MNB080 C BOP Earthquake, Spurious RCIC initiation (TS) 4 MRC40 C,R RO B RR FCV fails open / HPU trip button fails (TS) 5 MEE039 C BOP Loss of MCC 133 6 multiple I BOP Spurious VC realignment on spurious high rad 7 MRW010 M All RWCU leak, failure to isolate 8 MES08 C BOP SRV C fails to open on manual ADS

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

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle County Station Scenario No.: 3 Test No.: 2010301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Power Turnover:

  • S/D C Condensate/ Booster Pump IAW LOP-CD-03 Event Malf. No. Event Type* Event No. Description 1 N/A N BOP Swap CD pumps 2 MMS047 R RO Main Turbine #5 Bypass valve fails open (TS) 3 CAE I BOP RCIC Drain Pot Drain Fails Closed (TS) 4 MNI095 I RO LPRM fails downscale (TS) 5 CAE C BOP Steam Seal Evaporator PCV fails closed CAE Turbine Lube Oil TCV fails open / Main Turbine Shaft Bow 6 C RO / Scram MMS056 MRD277,27 ATWS 7 M All 8

MNB106, A MSL steam leak / Fails to isolate 8 M All 109, 113

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

Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle County Station Scenario No.: 4 Test No.: 2010301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Ramping to full power Turnover:

  • Unit 1 at 85% power ramping to full power.
  • LOS-LP-Q1 needs completed from step A.6.
  • A IN Compressor OOS Event Malf. No. Event Type* Event No. Description 1 N/A R RO Ramp to full power 2 N/A N BOP Complete LOS-LP-Q1 3 MRW001 C RO A RT Pump trips 4 CAE C RO A TDRFP lube oil leak 5 MRM009 I BOP A OG Post treat rad high (TS)

R1165 Primary Containment CAM 1PL75J and 1PL15J INOP 6 I SRO R0517 (TS) 7 MNB104 M ALL Main Steam Line Leak in DW before restrictor MMS048- Main Turbine Bypass Valves Fail Closed 8 C BOP 052 9 MRC033 C BOP Primary Containment Bypass Path 10 VMRH16A C BOP RHR Drywell Spray 16A fails closed.

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