ML24016A178

SSES, Units 1 and 2, Final Submittal Forms: 3.2-1, 3.2-2, 3.3-1, 4.1, 4.1-1; and Proctor Log, Handout Summary

ML24016A178
Person / Time
Site:	Susquehanna
Issue date:	07/31/2023
From:	Todd Fish NRC/RGN-I/DORS/OB
To:	NRC/RGN-I/DORS/OB, Talen Energy Susquehanna Steam Electric Station
References
EPID L-2023-OLL-0009
Download: ML24016A178 (1)

Text

Form 3.2-1 Administrative Topics Outline Facility: SSES Units 1 and 2 Date of Examination: _07/31/2023___

Examination Level:

RO SRO Operating Test Number: _LOC-32___

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Calculate RCS Leakage and SRO Determine if Leakage is Less Than TS LCO K/A 2.1.19 R, M Conduct of Operations Implement RPV WIC and Determine Drain Time (NDAP-QA-0350)

K/A 2.2.22 R, M Equipment Control Review Acceptance Criteria of SO-152-004 Quarterly HPCI Valve Exercising K/A 2.2.37 R, N Radiation Control Emergency Plan Activate the Fire Brigade and Manually Initiate Fire Suppression K/A 2.4.26 S, M

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

• Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Form 3.2-1 Administrative Topics Outline Facility: SSES Units 1 and 2 Date of Examination: _07/31/2023___

Examination Level:

RO SRO Operating Test Number: _LOC-32___

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Calculate RCS Leakage and SRO Determine if Leakage is Less Than TS LCO K/A 2.1.19 R, M Conduct of Operations Implement RPV WIC and Determine Drain Time (NDAP-QA-0350)

K/A 2.2.22 R, M Equipment Control Review Acceptance Criteria of SO-152-004 Quarterly HPCI Valve Exercising K/A 2.2.37 R, N Radiation Control Approve an LRW Discharge Permit K/A 2.3.6 R, N Emergency Plan Emergency Event Classification and ENR K/A 2.4.41 R, M

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

• Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: SSES Units 1 and 2 Date of Examination: _July 31, 2023_

Operating Test Number: _LOC-32___

Exam Level:

RO

SRO-I

SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. Quick Recovery of Shutdown Cooling Loop A (Alternate Decay Heat Removal with RHR) (AOP-149-001)

A, EN, L, N, S

4

b. Terminate ADS Emergency Depressurization (OP-183-001)

D, EN, L, S 3

c. Respond to a Stuck Control Rod (During Rod Exercising) (AOP-155-001)

A, N, S 1

d. Vent Unit 1 Drywell Using SGTS (EO-000-103)

EN, N, S 9

e. Circ Water Quick Recovery following an Electrical Transient (OP-142-001)

A, D, S 8

f. Recover RCIC System Turbine Trip with Initiation Signal Present (OP-150-001)

A, D, S 2

g. Inserting APRM Rod Block and Scram Setpoints for Single Loop (OP-178-002)

D, S 7

h. Synchronize the Main Generator in AUTO (OP-198-001)

A, D, S 6

In-Plant Systems

i. Bypass All Unit 2 RCIC Isolation Signals and RCIC High Reactor Water Level Shutdown Signal (ES-250-001)

E, N 2

j. Place RHR in Supp Pool Cooling at Unit 2 RSDP (OP-249-005)

D, E, L, R 5

k. Manual Local Start of A D/G from 0C521A during SBO (EO-100-030)

A, E, M 6

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria 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 (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: SSES Units 1 and 2 Date of Examination: _July 31, 2023_

Operating Test Number: _LOC-32___

Exam Level:

RO SRO-I

SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. Quick Recovery of Shutdown Cooling Loop A (Alternate Decay Heat Removal with RHR) (AOP-149-001)

A, EN, L, N, S

4

b. Terminate ADS Emergency Depressurization (OP-183-001)

D, EN, L, S 3

c. Respond to a Stuck Control Rod (During Rod Exercising) (AOP-155-001)

A, N, S 1

d. Vent Unit 1 Drywell Using SGTS (EO-000-103)

EN, N, S 9

e. Circ Water Quick Recovery following an Electrical Transient (OP-142-001)

A, D, S 8

f. Recover RCIC System Turbine Trip with Initiation Signal Present (OP-150-001)

A, D, S 2

g.

h. Synchronize the Main Generator in AUTO (OP-198-001)

A, D, S 6

In-Plant Systems

i. Bypass All Unit 2 RCIC Isolation Signals and RCIC High Reactor Water Level Shutdown Signal (ES-250-001)

E, N 2

j. Place RHR in Supp Pool Cooling at Unit 2 RSDP (OP-249-005)

D, E, L, R 5

k. Manual Local Start of A D/G from 0C521A during SBO (EO-100-030)

A, E, M 6

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria 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 (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: SSES Units 1 and 2 Date of Examination: _July 31, 2023_

Operating Test Number: _LOC-32___

Exam Level:

RO

SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. Quick Recovery of Shutdown Cooling Loop A (Alternate Decay Heat Removal with RHR) (AOP-149-001)

A, EN, L, N, S

4

b. Terminate ADS Emergency Depressurization (OP-183-001)

D, EN, L, S 3

c.

d.

e. Circ Water Quick Recovery following an Electrical Transient (OP-142-001)

A, D, S 8

f.

g.

h.

In-Plant Systems

i. Bypass All Unit 2 RCIC Isolation Signals and RCIC High Reactor Water Level Shutdown Signal (ES-250-001)

E, N 2

j. Place RHR in Supp Pool Cooling at Unit 2 RSDP (OP-249-005)

D, E, L, R 5

k.

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria 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 (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator

SSES-2023 NRC-S1 Page 1 of 2 Form 3.3-1 Scenario Outline Facility:

SSES Units 1 & 2 Scenario #: SSES-2023 NRC-S1 Scenario Source:

New Op. Test #: LOC 32 Examiners:

Applicants/

Operators:

Initial Conditions:

70% RX Power RHR Pump 1A OOS Circ Water Pump 1C is shutdown Turnover:

Main Condenser Water Box work was in progress and has been completed.

Place Circ Water Pump 1C in service.

Raise RX power to rated w/Recirc flow Critical Tasks:

GEN.CT.01, RPS Failure. Insert control rods using RPS Manual Scram logic or Alternate Rod Insertion (ARI) system.

EPE.CT.24, RPV Flooding (non-ATWS). When RPV Level CANNOT be determined then perform an Emergency Depressurization EPE.CT.26 RPV Flooding (non-ATWS or ATWS). Following Emergency Depressurization, flood to the Main Steam Lines

SSES-2023 NRC-S1 Page 2 of 2 Event No.

Malf. No.

Event Type*

Event Description 1

N/A N - BOP, SRO

[Start an additional Circ Water Pump] Place Circ Water Pump 1C in service.

OP-142-001 2

N/A R - ATC

[Restore RX Power to Rated Power] Raise RX Power to Rated using RX Recirc Flow (1%/min ramp rate).

OP-164-002, GO-100-012 3

NB09U1_PDTC321N 004BTVSP I - BOP TS - SRO

[RPV Narrow Range B Level Instrument fails low] Place instrument in Maintenance Bypass.

ON-LVL-101, AOP-145-001, TS 3.3.2.2 4

MALF_VC14A (Fan A Trips)

MALF_ VC05B (Fan B fails to auto start)

MALF_VC14B (Fan B Trips)

C/MC - BOP TS - SRO

[Control Structure Battery Room Exhaust Fan A trips /

Battery Room Exhaust Fan B fails to automatically start]

Crew will manually start Control Structure Battery Room Exhaust Fan B; then recognize Fan B also trips.

AR-029-C03, AR-030-C03, TRO 3.7.9, TS 3.0.3 5

MALF_TC03 (EHC Malfunction)

C-All

[EHC failure causes an RPV HI Pressure] Crew will monitor RPV pressure and take scram actions.

[EOP Entry] EO-000-102 RPV Control 6

MALF_RP08A (RPS Auto Scram Fail)

MALF_RP09A (ARI Auto Init Fail)

P1C601_HS147103A 1_INSERT (ARI Man Init Fail)

I/MC - ATC

[RPS scram setpoint exceeded (on Hi RPV pressure),

RPS fails to insert an automatic scram signal] Crew will take Immediate Operator Actions. PCOM places the RX Mode switch to SHUTDOWN, inserting a scram signal and causing ALL rods to insert.

OP-AD-300, EO-000-102 RPV Control 7

MALF_CU09 and MALF_CU011 Bottom Head Drain Leak M - ALL

[Drywell Pressure rises following the scram] Crew will monitor/take action for the rising Drywell Pressure.

EO-000-103 PCC 8

P1C601_HSE111S17 A_2 P1C601_HSE111S17 B_2 C - BOP

[RHR Loop A(B) LOCA Override Switch S17A(B) fails in the OFF position] Unable to place Supp Chamber & DW Sprays in service on RHR Loop A(B).

EO-000-103 9

RWL Reference Leg Flashing (fails all RPV Inst Upscale)

I - BOP, ATC

[Drywell Pressure & Temperature cross the Saturation Curve causing RPV Level instrumentation to become invalid] Flood the RPV to the Main Steam Lines

[EOP Contingency] EO-000-114 RPV Flooding

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

SSES-2023 NRC-S2 Page 1 of 2 Form 3.3-1 Scenario Outline Facility:

SSES Units 1 & 2 Scenario #: SSES-2023 NRC-S2 Scenario Source:

New Op. Test #: LOC 32 Examiners:

Applicants/

Operators:

Initial Conditions:

Rated RX Power CRD Pump B in service for predictive maintenance, CRD A in standby Turnover:

ZWO has been established for Fire Door #DR23. Door is located between Unit 1 RHR A and RHR B Pump Rooms. Door is open, a Firewatch has been established.

Swap River Water Makeup Pumps.

Lower RX power to determine if RX Feedpump B vibration is load related.

Critical Tasks:

EPE.CT.08, Primary Containment Control. When Supp Pool level CANNOT be maintained above 17 feet, then scram and isolate HPCI.

EPE.CT.09, Primary Containment Control. When Supp Pool Level CANNOT be maintained above 12 feet, then perform an Emergency Depressurization.

SSES-2023 NRC-S2 Page 2 of 2 Event No.

Malf. No.

Event Type*

Event Description 1

N/A N - BOP, SRO

[Swap River Water Makeup Pumps] Place RWMU Pump D in service, Place RWMU Pump C in standby.

OP-054-001 2

N/A R - ATC

[Lower RX power to 95% rated power] Lower RX power using RX Recirc flow, 1% per minute ramp rate.

OP-164-002, CRC Book 3

1Y236_CB_52_21 C/TS -

SRO

[Loss of power to Standby Liquid Control A Squib Valve, power supply 1Y236 Bkr 21 fails open]

Respond to alarm AR-107-A03.

AR-107-A03, TS 3.1.7 4

MALF_SM05 I - BOP, SRO

[Seismic alarm received in the Control Room].

Classify and validate the alarm at Earthquake Monitoring Panel 0C696.

OP-099-002, ON-NATPHENOM-001 5

MALF_E103 C - ALL TS - SRO

[Loss of Offsite Power to T-20] Restore cooling to the RX Recirc pumps and restart a Control Rod Drive Pump.

ON-SUB-001, TS 3.8.1 (1 Hour action).

6 MALF_RH03 (RHR A Suct Line Break)

MALF_RH04 (RHR C Suct Line Break)

M - ALL

[Suppression Pool leak / RHR Room A Flooded alarm] Crew will enter EOPs, scram the reactor and manually isolate HPCI prior to Supp Pool level reaching 17 ft.

[EOP Entry] EO-000-102 RPV Control, EO-000-103 PPC 7

MALF_MG02 C/MC -

ATC

[Main Generator Output Breaker fails to automatically open following a RX scram and Main Turbine trip] Manual action is required to open the output breaker.

ON-SCRAM-101 8

CN01U1_1P102A_MTFSEIZUR CN01U1_1P102B_MTFSEIZUR CN01U1_1P102C_MTFSEIZUR CN01U1_1P102D_MTFSEIZUR C - ATC

[Two Condensate Pumps trip due to shaft seizer]

Perform quick recovery of the other two Condensate pumps.

OP-144-001 9

MALF_SM05 MALF_RH05 MALF_RH06 MALF_CS01 ANBDP1C601_AR109H01TVFAI L

M - SRO

[Aftershock seismic event] Monitor Supp Pool Level, Emergency Depressurize required before Supp Pool Level reaches 12.

[EOP Contingency] EO-000-112 ED 10 NB03U1_HV141F013LTVFAILS P

C/MC -

BOP

[SRV L fails to OPEN during Emergency Depressurization] Open an additional SRV.

EO-000-112

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

SSES-2023 NRC-S3 Page 1 of 2 Form 3.3-1 Scenario Outline Facility:

SSES Units 1 & 2 Scenario #: SSES-2023 NRC-S3 Scenario Source:

New Op. Test #: LOC 32 Examiners:

Applicants/

Operators:

Initial Conditions:

85% Power Turnover:

Lower RX power to 80% using RX Recirc flow Remove Condensate Pump B from service for Predictive Maintenance testing Critical Tasks:

EPE.CT.21, Level/Power Control. Lower RX Water Level by Stop and Preventing injection with reactor power > 5%.

EPE.CT.22, Level/Power Control. During failure to scram conditions and after lowering level to control power, maintain adequate core cooling by controlling RPV level above -179 inches.

EPE.CT.23, Level/Power Control. During failure to scram conditions, insert control rods using one or more methods contained within EO-113 Table Q-2 to reduce power below the POAH.

SSES-2023 NRC-S3 Page 2 of 2 Event No.

Malf. No.

Event Type*

Event Description 1

N/A R - ATC

[Lower RX power to 80%] Lower RX power using control rods and RX Recirc flow.

GO-100-012 2

NBACU1F1ACC C/TS -

SRO

[ADS Fuse Failure] Respond to alarms AR-110-D02, ADS Out of Service and AR-155-A01, ADS Logic A Power Failure. [Note:

Div. 1 of ADS is INOP (Div. 2 available)].

AR-110-D02, AR-155-A01, TS 3.3.5.1 applies.

3 N/A N - BOP SRO

[Remove Condensate Pump B from service for Predictive Maintenance] Remove pump from service in accordance with OP-144-001.

OP-144-001 4

CUBDU1TSH_G33

_1N600CTVSP C/MC -

BOP

[RWCU temperature switch TSH-G33-1N600C fails upscale, RWCU Inboard isolation valve HV-144F001 fails to isolate]

Isolate RWCU by manually closing the Outboard isolation valve from the Control Room.

HV-144F004.

AR-101-A02, OP-AD-300 4

NBAXU1K26TSVP I/TS -

SRO

[RWCU Fails to Isolate - Tech Spec]

Tech Spec 3.3.6.1 (PCIS Instrumentation), Tech Spec 3.6.1.3 (PCIV), TRM 3.4.1 (Conductivity Recorder INOP).

5 MALF_MS53J MALF_MS54J C - BOP, SRO

[SRV J stuck open] Attempt to close the SRV and Scram the reactor.

ON-SRV-101 6

MALF_RP01 MALF_RP09A MALF_RP09B P1C601_HS147103 A1_2 P1C601_HS147103 B1_2 RD01U1_PV146F0 03_ATFASIS M - ALL

[Electrical ATWS] Crew will take actions in accordance with EO-113, Level Power Control.

[EOP Entry] EO-000-102 RPV Control

[EOP Contingency] EO-000-113 Level Power Control 7

SLAAU1SQUIBATV SP SLABU1SQUIBBTV SP C - BOP

[Initial SBLC Pump started fails to fire Squib valves] Crew will start the standby SBLC pump.

OP-153-001 8

NBCDU1RL96_1_1 A20601TVSP NBCEU1RL96_1_1 A20602TVSP C/MC -

ATC

[RX Recirc Pump B fails to automatically trip on low RPV water level] When the crew lowers RPV level during the ATWS, manual action will be required to trip the RX Recirc pump and further reduce RX power.

OP-AD-300 9

EEBFU1_CCTVSP EEBGU1_CCTVSP C - ATC

[Aux Buses fail to transfer on Main Turbine/Generator Trip; causing a loss of Feedwater] Crew will transfer RPV level control to RCIC and HPCI.

OP-152-001, OP-150-001

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

SSES-2023 NRC-S4 Page 1 of 2 Form 3.3-1 Scenario Outline SPARE SCENARIO Facility:

SSES Units 1 & 2 Scenario #: SSES-2023 NRC-S4 Scenario Source:

New Op. Test #: LOC 32 Examiners:

Applicants/

Operators:

Initial Conditions:

9% RX Power Turnover:

RX startup in progress IAW GO-100-002 HPCI is out of service due to a governor oil leak RWM is bypassed for Reactor Engineering to reload a change to the Startup Sequence Reinitialize RWM in accordance with OP-131-001, Rod Worth Minimizer Continue withdrawing Control Rods to raise RX Power close to but less than 16%

power in preparation to roll the main turbine Critical Tasks:

EPE.CT.04, RPV Control. When RPV level CANNOT be restored and maintained above -179 inches, perform Emergency Depressurization.

EPE.CT.12b, Primary Containment Control. Initiate drywell sprays before RPV Instrument Reference Legs flash resulting in entry of RPV Flooding EOP.

SSES-2023 NRC-S4 Page 2 of 2 Event No.

Malf. No.

Event Type*

Event Description 1

N/A N - ATC, SRO

[Initialize the RWM] Initialize RWM IAW OP-131-001 OP-131-001 2

N/A R - ATC

[Withdraw Control Rods to Raise RX power] Withdraw control rods IAW the Startup Sequence.

OP-156-001, GO-100-002 3

RDBOROD_5827TFDRIF TO C - ATC TS - SRO

[Control Rod drifts out] Insert control rod and hydraulically disarm.

ON-CRD-101, TS 3.1.3 4

MALF_RC03 C - BOP TS - SRO

[Inadvertent RCIC initiation] Verify RPV level and override RCIC injection.

ON-PWR-101, TS 3.5.3 5

MALF_e405 EECEU1_CCTVSP C - ALL

[T-10 Lockout - loss of SUB 10 and Aux Buses 11A & B].

Loss of Aux Buses will cause a loss of both RX Recirc pumps and all Condensate and Feedwater pumps.

Reactor scram, RCIC will be used for RPV level control and SRVs for RPV pressure control.

ON-SUB-001, OP-150-001,

[EOP Entry] EO-000-102 RPV Control 6

EECXU1_52_20109_BKR TF_TYPE MALF_DE03A C/MC -

BOP

[ESS bus 1A fails to transfer to its alternate power source and Diesel Generator A fails to auto start] Manually start DG A from the Control Room to reenergize the 1A ESS Bus.

OP-AD-300 7

RCBAU1FC_E51_1R600 COHILIM Insert C/MC -

ATC

[RCIC Flow Control Valve Fails Low in AUTO] Operate the Flow Controller in MANUAL.

OP-150-001, OP-AD-300 8

MALF_RR03 M - BOP, SRO

[Medium break LOCA occurs]

• RPV water level lowers requiring the crew to Emergency Depressurize and inject with Low Pressure ECCS systems to restore and maintain RPV level above -179

• Crew will line up Supp Chamber and Drywell sprays for Containment Cooling

[EOP Contingency] EO-000-112 ED, EO-000-103, PCC 9

CSASU1K20ATVSP Insert CSASU1K11ATVSP Insert CSASU1K41ATVSP Insert CSASU1K10ATVSP Insert CSASU1K102ATVSP Insert CSATU1K20BTVSP Insert CSATU1K11BTVSP Insert CSATU1K41BTVSP Insert CSATU1K10BTVSP Insert CSATU1K102BTVSP Insert C - ATC

[Both Core Spray loops fail to initiate using the initiation pushbuttons] Crew will a component-by-component startup of Core Spray.

EO-000-102 RPV Control

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

1¶ Form 4.1-BWR Boiling-Water Reactor Examination Outline Facility: Susquehanna K/A Catalog Rev. 3 Rev. 2 Date of Exam:

07/31/2023 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 4

4 3

3 3

20 4

3 7

2 1

1 1

1 1

1 6

1 2

3 Tier Totals 4

5 5

4 4

4 26 5

5 10

2.

Plant Systems 1

2 3

2 2

3 2

2 3

3 2

2 26 3

2 5

2 1

0 1

2 1

1 1

1 0

1 2

11 1

2 0

3 Tier Totals 3

3 3

4 4

3 3

4 3

3 4

37 6

2 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

2 2

1 2

4. Theory Reactor Theory Thermodynamics 6

3 3

Notes: CO =

EM =

Conduct of Operations; EC = Equipment Control; RC = Radiation Control; Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan.

These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan.

ES-4.1-BWR BWR Examination Outline (Susquehanna)

Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

Item E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

1 (295001) (APE 1)

PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X

(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (2.4.18) Knowledge of the specific bases for emergency and abnormal operating procedures (CFR:

41.10 / 43.1 / 45.13) 3.3 1

2 (295003) (APE 3)

PARTIAL OR COMPLETE LOSS OF AC POWER X

(295003AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER: (CFR: 41.5 / 41.10 / 45.6 /

45.13) Manual and automatic bus transfer 3.7 2

3 (295004) (APE 4)

PARTIAL OR COMPLETE LOSS OF DC POWER X

(295004AK3.02) Knowledge of the reasons for the following responses or actions as they apply to (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER: (CFR: 41.5 / 41.10 / 45.6 /

45.13) Ground isolation/fault determination 3.3 3

4 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP X

(295005AK2.03) Knowledge of the relationship between the (APE

5) MAIN TURBINE GENERATOR TRIP and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Recirculation system 3.5 4

5 (295006) (APE 6)

SCRAM X

(295006AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 6) SCRAM: (CFR: 41.5 / 41.7 / 45.7 / 45.8)

Decay heat generation and removal 4

5 6

(295016) (APE 16)

CONTROL ROOM ABANDONMENT X

(295016) (APE 16) CONTROL ROOM ABANDONMENT G2.1.32 Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 / 43.2 / 45.12) 3.8 6

7 (295018) (APE 18)

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW)

X (295018AA2.01) Ability to determine or interpret the following as they apply to (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW): (CFR: 41.10 / 43.5 /

45.13) Component temperatures 3.7 7

8 (295019) (APE 19)

PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X

(295019AK2.11) Knowledge of the relationship between the (APE

19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following systems or components: (CFR: 41.8 / 41.10 / 45.3)

Radwaste 2.5 8

9 (295021) (APE 21)

LOSS OF SHUTDOWN COOLING X

(295021AK2.02) Knowledge of the relationship between the (APE

21) LOSS OF SHUTDOWN COOLING and the following systems or components: (CFR: 41.7 / 45.8) Reactor Water Cleanup 3.2 9

10 (295023) (APE 23)

REFUELING ACCIDENTS X

(295023AK2.04) Knowledge of the relationship between the (APE

23) REFUELING ACCIDENTS and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) RMCS/RCIS 3.2 10 11 (295024) (EPE 1) HIGH DRYWELL PRESSURE X

(295024EK3.01) Knowledge of the reasons for the following responses or actions as they apply to (EPE 1) HIGH DRYWELL PRESSURE: (CFR: 41.5 / 41.10 / 45.6 / 45.13) Drywell spray (Mark I, II) 4.4 11 12 (295025) (EPE 2) HIGH REACTOR PRESSURE X

(295025EK3.03) Knowledge of the reasons for the following responses or actions as they apply to (EPE 2) HIGH REACTOR PRESSURE: (CFR: 41.5 / 41.10 / 45.6 / 45.13) HPCI operation 3.5 12 13 (295026) (EPE 3)

SUPPRESSION POOL HIGH WATER TEMPERATURE X

(295026EA2.01) Ability to determine or interpret the following as they apply to (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13) Suppression pool water temperature 4.1 13

14 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY)

X (295028EK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY): (CFR: 41.5 / 41.7 / 45.7 / 45.8) Reactor water level measurement 3.8 14 15 (295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL X

(295030EA2.01) Ability to determine or interpret the following as they apply to (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13) Suppression pool level 4.1 15 16 (295031) (EPE 8)

REACTOR LOW WATER LEVEL X

(295031) (EPE 8) REACTOR LOW WATER LEVEL (G2.1.8)

CONDUCT OF OPERATIONS Ability to coordinate personnel activities outside the control room (CFR: 41.10 / 43.1 / 45.5 / 45.12

/ 45.13) 3.4 16 17 (295037) (EPE 14)

SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN X

(295037EA1.10) Ability to operate or monitor the following as they apply to (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.5 / 41.7 / 45.5 to 45.8) Systems used for alternate boron injection 3.7 17 18 (295038) (EPE 15)

HIGH OFFSITE RADIOACTIVITY RELEASE RATE X

(295038EA1.10) Ability to operate or monitor the following as they apply to (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.5 / 41.7 / 45.5 to 45.8) SGTS/FRVS 3.9 18 19 (600000) (APE 24)

PLANT FIRE ON SITE X

(600000AA1.05) Ability to operate or monitor the following as they apply to (APE 24) PLANT FIRE ON SITE: (CFR: 41.7 / 45.5 / 45.6)

Plant and control room ventilation systems 3.3 19 20 (700000) (APE 25)

GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X

(700000AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR: 41.5 / 41.7 / 45.7 / 45.8) Over-excitation 3.1 20 21 (295004) (APE 4)

PARTIAL OR COMPLETE LOSS OF DC POWER X

(295004) (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER (G2.2.15) EQUIPMENT CONTROL Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups or, tagouts (reference potential) (CFR: 41.10 / 43.3 /

45.13) 4.3 76 22 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP X

(295005) (APE 5) MAIN TURBINE GENERATOR TRIP (G2.2.22)

EQUIPMENT CONTROL Knowledge of limiting conditions for operation and safety limits (CFR: 41.5 / 43.2 / 45.2) 4.7 77 23 (295016) (APE 16)

CONTROL ROOM ABANDONMENT X

(295016AA2.03) Ability to determine or interpret the following as they apply to (APE 16) CONTROL ROOM ABANDONMENT:

(CFR: 41.10 / 43.5 / 45.13) Reactor Pressure 4.2 78 24 (295018) (APE 18)

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW)

X (295018AA2.03) Ability to determine or interpret the following as they apply to (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW): (CFR: 41.10 / 43.5 /

45.13) Partial or complete loss 3.5 79 25 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY)

X (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) (G2.4.12) EMERGENCY PROCEDURES/PLAN Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 / 45.12) 4.3 80 26 (295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL X

(295030EA2.06) Ability to determine or interpret the following as they apply to (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13) Suppression chamber pressure 3.5 81

27 (295038) (EPE 15)

HIGH OFFSITE RADIOACTIVITY RELEASE RATE X

(295038EA2.05) Ability to determine or interpret the following as they apply to (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.10 / 43.5 / 45.13) Emergency plan implementation 4.5 82 (295027) (EPE 4) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

/ 5 K/A Category Totals:

3 4

4 3

7 6

Group Point Total:

27 ES-4.1-BWR BWR Examination Outline (Susquehanna)

Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

Item E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

28 (295007) (APE 7) HIGH REACTOR PRESSURE X

(295007AK2.05) Knowledge of the relationship between the (APE

7) HIGH REACTOR PRESSURE and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Shutdown cooling system (RHR shutdown cooling mode) 3.7 21 29 (295009) (APE 9) LOW REACTOR WATER LEVEL X

(295009AA2.02) Ability to determine or interpret the following as they apply to (APE 9) LOW REACTOR WATER LEVEL: (CFR:

41.10 / 43.5 / 45.13) Steam flow/feed flow mismatch 3.9 22 30 (295012) (APE 12)

HIGH DRYWELL TEMPERATURE X

(295012AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 12) HIGH DRYWELL TEMPERATURE: (CFR: 41.5 / 41.10 / 45.6 / 45.13) Increased drywell cooling 3.8 23 31 (295020) (APE 20)

INADVERTENT CONTAINMENT ISOLATION & 7 X

(295020) (APE 20) INADVERTENT CONTAINMENT ISOLATION &

7 (G2.1.2) CONDUCT OF OPERATIONS Knowledge of operator responsibilities during any mode of plant operation (CFR: 41.10 /

43.1 / 45.13) 4.1 24 32 (295035) (EPE 12)

SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE X

(295035EA1.01) Ability to operate or monitor the following as they apply to (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: (CFR: 41.5 / 41.7 / 45.5 to 45.8)

Secondary containment ventilation 3.7 25 33 (295036) (EPE 13)

SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL X

(295036EK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 13) SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: (CFR: 41.5 / 41.7 / 45.7 / 45.8)

Radiation releases 3.2 26 34 (295008) (APE 8) HIGH REACTOR WATER LEVEL X

(295008AA2.05) Ability to determine or interpret the following as they apply to (APE 8) HIGH REACTOR WATER LEVEL:

(CFR: 41.10 / 43.5 / 45.13) Swell 3.5 83 35 (295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL X

(295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL EQUIPMENT CONTROL (G2.2.25) Knowledge of the bases in technical specifications for limiting conditions for operation and safety limits (SRO Only) (CFR: 43.2) 4.2 84 36 (295034) (EPE 11)

SECONDARY CONTAINMENT VENTILATION HIGH RADIATION X

(295034) (EPE 11) SECONDARY CONTAINMENT VENTILATION HIGH RADIATION (G2.4.19) EMERGENCY PROCEDURES/

PLAN Knowledge of emergency and abnormal operating procedures layout, symbols, and icons (CFR: 41.10 / 45.13) 4.1 85 (295002) (APE 2) LOSS OF MAIN CONDENSER VACUUM / 3

(295010) (APE 10)

HIGH DRYWELL PRESSURE / 5 (295011) (APE 11)

HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)

/ 5 (295013) (APE 13)

HIGH SUPPRESSION POOL TEMPERATURE.

/ 5 (295014) (APE 14)

INADVERTENT REACTIVITY ADDITION

/ 1 (295017) (APE 17)

ABNORMAL OFFSITE RELEASE RATE / 9 (295022) (APE 22)

LOSS OF CONTROL ROD DRIVE PUMPS / 1 (295032) (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE / 5 (295033) (EPE 10)

HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS / 9 (500000) (EPE 16)

HIGH CONTAINMENT HYDROGEN CONCENTRATION / 5 K/A Category Totals:

1 1

1 1

2 3

Group Point Total:

9

ES-4.1-BWR BWR Examination Outline (Susquehanna)

Plant SystemsTier 2/Group 1 (RO/SRO)

Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR Q#

37 (203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:

INJECTION MODE X

(203000K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2, SF4 RHR/LPCI)

RHR/LPCI: INJECTION MODE:

(CFR: 41.5 / 45.3) Core cooling methods 4.2 27 38 (205000) (SF4 SCS)

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

X (205000K2.02) (SF4 SCS)

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) Knowledge of electrical power supplies to the following:

(CFR: 41.7) Motor-operated valves 3.3 28 39 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X

(206000A2.09) Ability to (a) predict the impacts of the following on the (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:

41.5 / 45.6) Low condensate storage tank level 3.8 29 40 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X

(206000A2.11) Ability to (a) predict the impacts of the following on the (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:

41.5 / 45.6) High/low reactor water level 4.3 30 41 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X

(209001A3.02) Ability to monitor automatic operation of the (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM including:

(CFR: 41.7 / 45.7) Pump start 4.3 31 42 (212000) (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(212000A3.09) Ability to monitor automatic operation of the (SF7 RPS) REACTOR PROTECTION SYSTEM including: (CFR: 41.7 /

45.7) System actuation 4.3 32 43 (212000) (SF7 RPS)

REACTOR PROTECTION SYSTEM X

(212000K6.08) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF7 RPS) REACTOR PROTECTION SYSTEM : (CFR:

41.7 / 45.7) Main turbine generator and auxiliaries systems 3.3 33

44 (215003) (SF7 IRM)

INTERMEDIATE RANGE MONITOR SYSTEM X

(215003K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 IRM) INTERMEDIATE RANGE MONITOR SYSTEM: (CFR:

41.5 / 45.3) Changing detector position 3.3 34 45 (215004) (SF7 SRMS)

SOURCE RANGE MONITOR SYSTEM X

(215004K2.01) (SF7 SRMS)

SOURCE RANGE MONITOR SYSTEM Knowledge of electrical power supplies to the following:

(CFR: 41.7) SRMS channels/detectors 3.3 35 46 (215005) (SF7 PRMS)

AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X

(215005A4.07) Ability to manually operate and/or monitor the (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR in the control room:

(CFR: 41.7 / 45.5 to 45.8) OPRM back panel switches, and indicating lights 3.6 36 47 (215005) (SF7 PRMS)

AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X

(215005K1.17) Knowledge of the physical connections and/or cause and effect relationships between the (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Recirculation flow control system 3.5 37 48 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X

(217000K6.02) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM :

(CFR: 41.7 / 45.7) Instrument air systems 2.6 38 49 (218000) (SF3 ADS)

AUTOMATIC DEPRESSURIZATION SYSTEM X

(218000A1.09) Ability to predict and/or monitor changes in parameters associated with operation of the (SF3 ADS)

AUTOMATIC DEPRESSURIZATION SYSTEM including: (CFR: 41.5 / 45.5) Lights and alarms 3.8 39 50 (223002) (SF5 PCIS)

PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUTOFF X

(223002K2.01) (SF5 PCIS)

PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUTOFF Knowledge of electrical power supplies to the following: (CFR:

41.7) Logic power supplies 3.6 40 51 (223002) (SF5 PCIS)

PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUTOFF X

(223002K4.05) Knowledge of (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUTOFF design features and/or interlocks that provide for the following: (CFR:

41.7) Single failures will not impair the function ability of the system 3.6 41

52 (239002) (SF3 SRV)

SAFETY RELIEF VALVES X

(239002K3.05) Knowledge of the effect that a loss or malfunction of the (SF3 SRV) SAFETY RELIEF VALVES will have on the following systems or system parameters:

(CFR: 41.7 / 45.4) Suppression pool 3.9 42 53 (259002) (SF2 RWLCS)

REACTOR WATER LEVEL CONTROL SYSTEM X

(259002) (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM (G2.1.41) CONDUCT OF OPERATIONS Knowledge of the refueling process (CFR: 41.2 / 41.10

/ 43.6 / 45.13) 2.8 43 54 (259002) (SF2 RWLCS)

REACTOR WATER LEVEL CONTROL SYSTEM X

(259002K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM: (CFR: 41.5 / 45.3)

Moisture carryover/carryunder 3.1 44 55 (261000) (SF9 SGTS)

STANDBY GAS TREATMENT SYSTEM X

(261000K1.02) Knowledge of the physical connections and/or cause and effect relationships between the (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Primary containment system and auxiliaries 3.7 45 56 (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION X

(262001A4.04) Ability to manually operate and/or monitor the (SF6 AC)

AC ELECTRICAL DISTRIBUTION in the control room: (CFR: 41.7 / 45.5 to 45.8) Synchronizing of AC sources 3.9 46 57 (262002) (SF6 UPS)

UNINTERRUPTABLE POWER SUPPLY (AC/DC)

X (262002A3.01) Ability to monitor automatic operation of the (SF6 UPS) UNINTERRUPTABLE POWER SUPPLY (AC/DC) including: (CFR: 41.7 / 45.7)

Transfer of power sources 3.4 47 58 (263000) (SF6 DC) DC ELECTRICAL DISTRIBUTION X

(263000K4.06) Knowledge of (SF6 DC) DC ELECTRICAL DISTRIBUTION design features and/or interlocks that provide for the following: (CFR: 41.7) Divisional separation 3.6 48 59 (264000) (SF6 EGE)

EMERGENCY GENERATORS (DIESEL/JET)

X (264000K3.04) Knowledge of the effect that a loss or malfunction of the (SF6 EGE) EMERGENCY GENERATORS (DIESEL/JET) will have on the following systems or system parameters: (CFR: 41.7 /

45.4) Bus frequency/voltage 3.9 49 60 (300000) (SF8 IA)

INSTRUMENT AIR SYSTEM X

(300000) (SF8 IA) INSTRUMENT AIR SYSTEM (291002K1.13)

SENSORS AND DETECTORS (CFR: 41.7) (PRESSURE) Modes of failure 3.1 50

61 (400000) (SF8 CCS)

COMPONENT COOLING WATER SYSTEM X

(400000A2.06) Ability to (a) predict the impacts of the following on the (SF8 CCS) COMPONENT COOLING WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 /

45.6) Component cooling water system heat exchanger tube leak 3.3 51 62 (510000) (SF4 SWS*)

SERVICE WATER SYSTEM X

(510000A1.03) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4 SWS*)

SERVICE WATER SYSTEM including: (CFR: 41.5 / 45.5) Service water pressures 3.6 52 63 (205000) (SF4 SCS)

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

X (205000) (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

(G2.2.20) EQUIPMENT CONTROL Knowledge of the process for managing troubleshooting activities (CFR: 41.10 / 43.5 /

45.13) 3.8 86 64 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X

(209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM (G2.4.41) EMERGENCY PROCEDURES / PLAN:

Knowledge of the emergency action level thresholds and classifications (CFR: 41.10 / 43.5 /

45.11).

4.6 87 65 (239002) (SF3 SRV)

SAFETY RELIEF VALVES X

(239002A2.01) Ability to (a) predict the impacts of the following on the (SF3 SRV)

SAFETY RELIEF VALVES and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:

41.5 / 45.6) Stuck-open vacuum breakers 3.6 88 66 (400000) (SF8 CCS)

COMPONENT COOLING WATER SYSTEM X

(400000A2.13) Ability to (a) predict the impacts of the following on the (SF8 CCS)

COMPONENT COOLING WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6) Loss of instrument air system 3.3 89

67 (510000) (SF4 SWS*)

SERVICE WATER SYSTEM X

(510000A2.04) Ability to (a) predict the impacts of the following on the (SF4 SWS*)

SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6) Pipe leakage/rupture 3.5 90 (207000) (SF4 IC)

ISOLATION (EMERGENCY)

CONDENSER (209002) (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM (211000) (SF1 SLCS)

STANDBY LIQUID CONTROL SYSTEM K/A Category Totals:

2 3

2 2

3 2

2 6

3 2

4 Group Point Total:

31

ES-4.1-BWR BWR Examination Outline (Susquehanna)

Plant SystemsTier 2/Group 2 (RO/SRO)

Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR Q#

68 (201001) (SF1 CRDH)

CRD HYDRAULIC SYSTEM X

(201001K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF1 CRDH) CRD HYDRAULIC SYSTEM: (CFR: 41.5 / 45.3) Pump operation 3.2 53 69 (201003) (SF1 CRDM)

CONTROL ROD AND DRIVE MECHANISM X

(201003) (SF1 CRDM) CONTROL ROD AND DRIVE MECHANISM (G2.4.2) EMERGENCY PROCEDURES/PLAN Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (CFR:

41.7 / 45.7 / 45.8) 4.5 54 70 (201003) (SF1 CRDM)

CONTROL ROD AND DRIVE MECHANISM X

(201003K4.07) Knowledge of (SF1 CRDM) CONTROL ROD AND DRIVE MECHANISM design features and/or interlocks that provide for the following: (CFR:

41.7) Maintaining the control rod at a given position 3.7 55 71 (202001) (SF1, SF4 RS)

RECIRCULATION SYSTEM X

(202001) (SF1, SF4 RS)

RECIRCULATION SYSTEM (291003K1.01) CONTROLLERS AND POSITIONERS (CFR: 41.7)

Function and operation of flow controller in manual and automatic modes 3.7 56 72 (204000) (SF2 RWCU)

REACTOR WATER CLEANUP SYSTEM X

(204000K3.01) Knowledge of the effect that a loss or malfunction of the (SF2 RWCU) REACTOR WATER CLEANUP SYSTEM will have on the following systems or system parameters: (CFR: 41.7 /

45.4) Reactor water quality 3.5 57 73 (230000) (SF5 RHR SPS) RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE X

(230000A4.04) Ability to manually operate and/or monitor the (SF5 RHR SPS) RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE in the control room:

(CFR: 41.7 / 45.5 to 45.8) Minimum flow valves 3.3 58 74 (239001) (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM X

(239001K1.27) Knowledge of the physical connections and/or cause and effect relationships between the (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Reactor protection system 4.1 59

75 (245000) (SF4 MTGEN)

MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS X

(245000K4.07) Knowledge of (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS design features and/or interlocks that provide for the following: (CFR: 41.7) Generator voltage regulation 3.1 60 76 (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM X

(272000K6.03) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF7, SF9 RMS) RADIATION MONITORING SYSTEM : (CFR:

41.7 / 45.7) AC Power 3.1 61 77 (290002) (SF4 RVI)

REACTOR VESSEL INTERNALS X

(290002A2.06) Ability to (a) predict the impacts of the following on the (SF4 RVI) REACTOR VESSEL INTERNALS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Exceeding safety limits 4.6 62 78 (290003) (SF9 CRV)

CONTROL ROOM VENTILATION X

(290003A1.05) Ability to predict and/or monitor changes in parameters associated with operation of the (SF9 CRV)

CONTROL ROOM VENTILATION including: (CFR: 41.5 / 45.5)

Airborne Radioactivity Levels 3.4 63 79 (201006) (SF7 RWMS)

ROD WORTH MINIMIZER SYSTEM X

(201006A2.04) Ability to (a) predict the impacts of the following on the (SF7 RWMS)

ROD WORTH MINIMIZER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6)

Stuck rod 3.4 91 80 (226001) (SF5 RHR CSS) RHR/LPCI:

CONTAINMENT SPRAY MODE SYSTEM MODE X

(226001A2.05) Ability to (a) predict the impacts of the following on the (SF5 RHR CSS)

RHR/LPCI: CONTAINMENT SPRAY MODE SYSTEM MODE and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR: 41.5 / 45.6) AC electrical failures 3.8 92 81 (234000) (SF8 FH)

FUEL HANDLING X

(234000K2.01) (SF8 FH) FUEL HANDLING Knowledge of electrical power supplies to the following: (CFR: 41.7) Fuel handling equipment power 2.5 93

(201002) (SF1 RMCS)

REACTOR MANUAL CONTROL SYSTEM (201005) (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM (202002) (SF1 RSCTL)

RECIRCULATION FLOW CONTROL SYSTEM (214000) (SF7 RPIS)

ROD POSITION INFORMATION SYSTEM (215001) (SF7 TIP)

TRAVERSING IN CORE PROBE (215002) (SF7 RBMS)

ROD BLOCK MONITOR SYSTEM (216000) (SF7 NBI)

NUCLEAR BOILER INSTRUMENTATION (219000) (SF5 RHR SPC) RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE (223001) (SF5 PCS)

PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES (233000) (SF9 FPCCU)

FUEL POOL COOLING/CLEANUP (239003) (SF9 MSVLCS) MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (241000) (SF3 RTPRS)

REACTOR/TURBINE PRESSURE REGULATING SYSTEM (256000) (SF2 CDS)

CONDENSATE SYSTEM (259001) (SF2 FWS)

FEEDWATER SYSTEM

(268000) (SF9 RW)

RADWASTE SYSTEM (271000) (SF9 OG)

OFFGAS SYSTEM (286000) (SF8 FPS)

FIRE PROTECTION SYSTEM (288000) (SF9 PVS)

PLANT VENTILATION SYSTEMS (290001) (SF5 SC)

SECONDARY CONTAINMENT (510001) (SF8 CWS*)

CIRCULATING WATER SYSTEM K/A Category Totals:

1 1

1 2

1 1

1 3

0 1

2 Group Point Total:

14

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Susquehanna)

Facility:

Susquehanna Date of Exam:

07/31/2023 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Category K/A #

Topic RO SRO-Only Item #

IR Q#

IR Q#

1.

Conduct of Operations G2.1.5 (G2.1.5) CONDUCT OF OPERATIONS Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations (reference potential) (CFR: 41.10 / 43.5 / 45.12) 82 2.9 64 G2.1.32 (G2.1.32) CONDUCT OF OPERATIONS Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 / 43.2 / 45.12) 83 3.8 65 G2.1.7 (G2.1.7) CONDUCT OF OPERATIONS Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation (CFR: 41.5

/ 43.5 / 45.12 / 45.13) 84 4.7 94 G2.1.31 (G2.1.31) CONDUCT OF OPERATIONS Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup (CFR: 41.10 / 45.12) 85 4.3 95 Subtotal N/A 2

N/A 2

2.

Equipment Control G2.2.18 (G2.2.18) EQUIPMENT CONTROL Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments and work prioritization (CFR: 41.10 / 43.5 / 45.13) 86 2.6 66 G2.2.21 (G2.2.21) EQUIPMENT CONTROL Knowledge of pre-and post-maintenance operability requirements (CFR: 41.10 / 43.2) 87 2.9 67 G2.2.13 (G2.2.13) EQUIPMENT CONTROL Knowledge of tagging and clearance procedures (CFR: 41.10 / 43.1 / 45.13) 88 4.3 96 G2.2.45 (G2.2.45) EQUIPMENT CONTROL Ability to determine or interpret technical specifications with action statements of greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (SRO Only) (CFR: 43.2 / 43.5 / 45.3) 89 4.7 97 Subtotal N/A 2

N/A 2

3.

Radiation Control G2.3.5 (G2.3.5) RADIATION CONTROL Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 / 41.12 / 43.4 / 45.9) 90 2.9 68 G2.3.14 (G2.3.14) RADIATION CONTROL Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative normal, abnormal, and emergency procedures, or analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only)

(CFR: 43.4 / 45.10) 91 3.8 98 Subtotal N/A 1

N/A 1

4.

Emergency Procedures / Plan G2.4.26 (G2.4.26) EMERGENCY PROCEDURES/PLAN Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage (CFR: 41.10 / 43.5 / 45.12) 92 3.1 69 G2.4.16 (G2.4.16) EMERGENCY PROCEDURES/PLAN Knowledge of emergency and abnormal operating procedures implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, or severe accident management guidelines (CFR: 41.10 / 43.5 / 45.13) 93 4.4 99

G2.4.38 (G2.4.38) EMERGENCY PROCEDURES/PLAN Ability to take actions required by the facility emergency plan implementing procedures, including supporting or acting as emergency coordinator (CFR: 41.10 /

43.5 / 45.11) 94 4.4 100 Subtotal N/A 1

N/A 2

Tier 3 Point Total N/A 6

N/A 7

Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Susquehanna)

Facility:

Susquehanna Date of Exam:

07/31/2023 Theory (Tier 4) (RO)

Category K/A #

Topic RO Item #

IR Q#

Reactor Theory 292001 (292001K1.02) NEUTRONS (CFR: 41.1) Define prompt and delayed neutrons 95 3.1 70 292005 (292005K1.09) CONTROL RODS (CFR: 41.1) Explain direction of change in the magnitude of CRW for a change in moderator temperature, void fraction, control rod density, and xenon 96 2.6 71 292007 (292007K1.03) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1)

Given a curve of K-effective versus core age, state the reasons for maximum, minimum, and inflection points 97 2.7 72 Subtotal 3

Thermodynamics 293005 (293005K1.05) THERMODYNAMIC CYCLES (CFR: 41.14) State the advantages of moisture separators/reheaters and feedwater heaters for a typical steam cycle 10242A 98 2.8 73 293007 (293007K1.13) HEAT TRANSFER (CFR: 41.14) (CORE THERMAL POWER) Calculate core thermal power using a simplified heat balance 99 2.9 74 293009 (293009K1.06) CORE THERMAL LIMITS (CFR: 41.14) (LHGR) Define LHGR 100 3.8 75 Subtotal 3

Tier 3 Point Total N/A 6

Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection 1/1 (Item 1) 295001.G2.4.32 No procedural guidance for loss of annunciators; randomly reselected G2.4.18 as replacement.

1/1 (Item 6) 295016.G2.1.18 Unable to develop a test item; randomly reselected 2.1.32 as replacement.

1/1 (Item 9) 295021AK2.04 Unable to develop operationally valid test item to this KA; randomly reselected AK2.08 as a replacement.

1/1 (Item 20) 700000AK1.04 No existing procedural guidance for off normal frequency at Susquehanna.

Reselected AK1.02 as a replacement.

1/1 (Item 23) 295016AA2.05 Could not develop operationally valid question; randomly reselected AA2.03 as replacement.

1/2 (Item 29) 295009AA2.03 Could not develop operationally valid question; randomly reselected AA2.02 as replacement.

1/2 (Item 35) 295029G2.2.41 Repeat sampling of use of drawings with item #21 on sample plan; randomly reselected G2.2.25 as a replacement.

2/1 (Item 61) 400000A2.16 No effect on component cooling water systems due to loss of cooling to alternate decay heat removal system; Randomly reselected A2.06 as a replacement.

2/2 (Item 76) 272000K6.04 No effect on RMS Radiation Monitoring at SSES from loss of Plant Process Computer. Randomly reselected K6.03 as a replacement.

2/2 (Item 78) 290003A1.01 No control room indication/procedural guidance for filter differential pressure; randomly reselected A1.05 as a replacement.

2/2 (Item 79) 201004A2.02 SSES does not have Rod Sequence Control System; reselected 201006A2.04 as a replacement.

3 (Item 91)

G2.3.6 Overlap concern with JPM with same K&A, randomly reselected G 2.3.14 as a replacement.

4 (Item 99) 293007K1.12 Could not develop an operationally valid test item with a difficulty greater than 1. Reselected 293007.K1.13 as a replacement.

1/1 (Item 9)

KA Mismatch. Randomly selected new KA 295021AK2.02 as a replacement following NRC review during prep week.

1/1 (Item 19) 600000AA1.07 UNSAT Question. Randomly selected new KA 600000A1.05 as a replacement following NRC review during prep week.

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SSES 2023 ILT EXAM PROVIDED REFERENCES Electrical Prints (E-16 sh. 11 and 12, E-18 sh. 9, E-26 sh.11)

Technical Specification 3.1.3 (redacted)

Technical Specification 3.1.6 (redacted)

Rod Pull Sheet (pages 5 and 6)

Technical Specification 3.6.4.3 (redacted)

Technical Specification 3.7.3 (redacted)

Technical Specification 3.8.1 (redacted)

Technical Specification 3.8.4 (redacted)

Technical Specification 3.8.6 (redacted)

EP-PS-001-23 (Att. JJ; Protective Action Recommendation Determination)