exelon nuclear ilt 17-1 nrc exam

ILT 17-1 NRC Exam Scenario 1 Rev. 1

ILT 17-1 NRC Scenario 1 Rev 1 4-03-18 Post Val.Doc Post Val of 18

Exelon Nuclear

ILT 17-1 NRC Exam

Scenario Number: NRC Exam Scenario 1

Revision Number: 1

Date: 4/03/18

Developed By: Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Approved By: Training Department Date



Appendix D Scenario Outline Form ES-D-1

Facility: Clinton Power Station Scenario No.: 1 Operating Test No.: 2018-301 Examiners: ____________________________ Operators: ____________________ ____________________________ ____________________ ____________________________ ____________________ Initial Conditions: • Mode 1 at ~40% power. Power ascension is in progress. • Weather conditions are calm and clear. • Condensate Pump 1A (1CD01PA) is out of service for minor maintenance. Restoration is expected prior to

requiring 4 condensate pump operation. Turnover: • Priorities for the shift are as follows:

• Perform on-line testing of the Emergency Seal Oil Pump IAW CPS 3109.01 Generator Seal Oil (SO) section 8.1.2.3. – First Priority.

• Raise reactor power to ~ 45% IAW CPS 3005.01 Unit Power Changes and the current ReMA. Critical Tasks: • Take actions to reduce the RPV cooldown rate to prevent flooding the MSLs or exceeding the RPV cooldown

rate limitation.

• RPV-1.3 Maintain Reactor Water Level above TAF.

Event No.

Malf. No. Event Type*

Event Description

1 N/A N-BOP Perform On-Line Testing of the Emergency Seal Oil Pump

2 N/A R-ATC Raise Power with flow to ~ 45%

3 S_K603A 4 OPEN SLOW C-ATC ‘A’ RR Flow Control Valve drifts OPEN

4 A05_A01_A0108_3_TVM steady

A05_A01_A0108_5_TVM steady

C-BOP TS-SRO

Failure of DG Fuel Oil Transfer Pump 1A to auto start

5 A01_A01_02_5_TVM=2 C-ATC ‘B’ RWCU pump seal plate temperature high

6 ed_ek20=true C-BOP TS-SRO

Trip of ERAT SVC

7 YP_XMFTB_4063 YPXMALSE_588 100%

RAT_B_Differential

M-All Generator Trip / Turbine Trip / Bypass Valve 1 sticks open / RAT Failure after MSIVs closed

8 YPXMALSE_510 0.1% YP_XMFTB_4101

YFRIPPSS hp10con45fsp=True

C-BOP LOCA - HPCS Pump fails to auto start / RCIC failure / HPCS Injection Valve fails to auto open

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



Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 Operating Test No.: 2018-301 Narrative Summary Event # Description

1. Perform On-Line Testing of the Emergency Seal Oil Pump Following shift turnover, the BOP will perform on-line testing of the Emergency Seal Oil Pump IAW CPS 3109.01 Generator Seal Oil (SO) section 8.1.2.3 On-Line Testing Of Emergency Seal Oil Pump (ESOP) for post-maintenance testing.

2. Raise Power with flow to ~ 45% The crew will raise Reactor power with Recirc Flow IAW CPS 3005.01 Unit Power Changes and the current ReMA.

3. ‘A’ RR Flow Control Valve (FCV) Drifts Open The ‘A’ RR Flow Control Valve slowly drifts open causing reactor power to rise and requires the ATC to perform an emergency shutdown of the ‘A’ RR Hydraulic Power Unit to stop further RR FCV movement. The crew will enter and execute CPS 4008.01 Abnormal Reactor Coolant Flow. The crew will evaluate core thermal limits by demanding a 3D Monicore Case to ensure core thermal limits are within TS limits. The crew will also evaluate RR loop flow mismatch to ensure operation within ITS 3.4.1 Recirculation Loops Operating limits.

4. Failure of DG Fuel Oil Transfer Pump 1A to auto start Annunciators 5060-8C LOW LEVEL DG DAY TANK 1A and 5060-8E TROUBLE DIESEL GEN 1A are received. The BOP will report that the Fuel Oil Transfer Pump (FOTP) failed to auto start. The SRO will direct the BOP to manually start the FOTP. The ATC/BOP will dispatch an operator to DG 1A room to determine the cause of the alarm. The Equipment Operator will report that the alarm is due to low fuel level in the Div 1 DG Day Tank; currently at 45% and lowering/rising based on whether the FOTP running. Annunciators will clear approximately 1 minute after the FOTP has started. The SRO will declare Div 1 DG inoperable and take actions for TS 3.8.1 Action B.

5. ‘B’ RWCU pump seal plate temperature high Annunciator 5000-2E CLEANUP PUMP SEAL GLAND PLATE TEMP HI comes in due to RWCU Recirc Pump B (1G33-C001B) developing excessive seal leak requiring its removal from service. The ATC Operator will dispatch an Equipment operator and coordinate/perform operations per CPS 3303.01 Reactor Water Cleanup (RT) Sections 8.1.3 System/Filter Demin Flow Control and 8.1.4 Removing RWCU Pump from Service.

6. Trip of ERAT SVC Annunciator 5011-8E ERAT SVC TRIP comes in due to a trip of the ERAT Static VAR Compensator for unknown reasons. The ARP will direct the BOP/ATC to dispatch an Equipment Operator to investigate, the BOP to place the ERAT SVC control switch to OFF and to transfer the 1A1 bus to the RAT. The SRO will enter CPS 4200.01 Loss Of AC Power, ensure/make necessary notifications to the Power Team and TSO (Ameren) and will declare the 138KV Offsite Source inoperable and take actions for TS 3.8.1.

7. Generator Trip / Turbine Trip / Bypass Valve 1 sticks open / RAT Failure after MSIVs closed The Main Generator will trip resulting in a Turbine trip and reactor scram. The Steam Bypass Valves will initially open as expected following the Main Turbine trip, but #1 Bypass Valve will remain open causing RPV pressure to decrease. The crew will diagnose the failure of the Bypass Valves to control Reactor pressure and will shut the MSIVs to prevent exceeding the 100°F/hr cooldown rate limitation and to prevent flooding the MSLs with feedwater. Shutting the MSIVs will eliminate the RFPTs as a high pressure injection source. A RAT trip will occur due to a fault when the MSIVs are closed (not related), resulting in a loss of BOP power and eliminating the FW/CD/CB system as a feed source.

8. LOCA - HPCS Pump fails to auto start / RCIC failure / HPCS Injection Valve fails to auto open An unisolable RCS leak occurs in the DW, causing DW pressure to exceed 1.68 psig. The RCIC pump shaft will fail if automatically or manually initiated. The HPCS Pump will fail to automatically start and 1E22F004 HPCS Injection Valve will fail to automatically open, requiring the MCR to manually start the HPCS Pump and open the injection valve for inventory control and to avoid the necessity for performing a blowdown when RPV level reaches TAF.



Operator Actions

Event No.(s): 1 Page 1 of 1

Description: Perform On-Line Testing of the Emergency Seal Oil Pump

Initiation: Following shift turnover and as directed by the SRO.

Cues: None

Time Position Applicant’s Actions or Behavior

General Note on Requirements for “Expected Annunciator Response” – OP-AA-103-102 If this evolution was pre-briefed and “Expected Alarms” were reviewed, the following expectations apply:

• “Expected alarms” will be flagged • When the annunciator comes in the operator will announce “Expected Alarm” • The annunciator response procedure (ARP) need not be entered since it has already been reviewed in the pre-

brief. If a pre-brief was not conducted the operator should perform the following:

• When an annunciator comes in the ARP should be referred to. • The annunciator may then be identified as an “Expected Alarm”, flagged, and from that point on the ARP need not

be referred to. Key Parameter Response: Emergency Seal Oil Pump status lights, Computer Point TO-BC223 changes state Expected Annunciators: 5017-5B Running Emerg Seal Oil Pump, 5017-6A Auto Start Turb Auxiliary Pump/Motor 5018-2A Trouble GC System and at 1PL10J, 5201-3A Running Emerg Seal Oil Pump Automatic Actions: None

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands.

Per CPS 3109.01, Generator Seal Oil, Step 8.1.2.3: • Depresses Gen H2 Emerg Seal Oil Pump Test push-button for at least 5 seconds. • Verifies Gen H2 Emergency Seal Oil Pump starts. • Verifies Comp Pt TO-BC223 shows a NORMAL state. • Verifies annunciators 5017-5B/6A, 5018-2A and 5201-3A energized. • Verifies locally that noise and vibration levels on the ESOP are normal. • Stops the Gen H2 Emergency Seal Oil Pump. • Verifies annunciators and computer point off.

SRO • Acknowledges reports from ATC/BOP. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures.

Terminus: ESOP testing completed.

NOTES:

• Solid bullets are required actions

o Hollow bullets are actions that may or may not be performed



Operator Actions


Description: Raise Power with flow to ~ 45%

Initiation: Following Event 1 and as directed by SRO.

Cues: None


Key Parameter Response: Reactor power, Generator load

Expected Annunciators: None

Automatic Actions: None

ATC Per CPS 3005.01 Unit Power Changes section 8.1: • Raises power with reactor recirc flow. • Monitors the following items listed below:

• RCIS status (LPAP, HPSP, Rod Blocks) • Power (APRM, LPRM, Gen Load) • Actual plant response compared to expected response

• Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.


SRO • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. • Positions himself/herself in proximity of the reactor operator, typically the location from

which EOP actions are directed (OP-AA-300).

Terminus: Clearly observable plant response from change in power level.

NOTES:



Operator Actions


Description: ‘A’ RR Flow Control Valve (FCV) Drifts Open

Initiation: Following Event 2 and upon direction of the Lead Examiner, insert REMOTE 1.

Cues: Rising Reactor Power


Key Parameter Response: Rising Reactor Power, RR ‘A’ FCV position


Automatic Actions: None ATC • Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Notifies the SRO that Reactor Power is rising. o Notifies the SRO that the ‘A’ RR FCV is drifting open. • Arms and depresses the HPU ‘A’ Shutdown Switch. • Verifies the ‘A’ RR FCV stops opening. o Reports RR Loop Flow mismatch. o Verifies operation within CPS 3005.01 Unit Power Changes Figure 1, CPS Stability Control &

Power/Flow Operating Map limits. o Dispatches an Equipment Operator to investigate for abnormalities at the ‘A’ RR HPU. o Monitors RR Pump ‘A’ Seal Parameters.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Notifies the SRO that the ‘A’ RR FCV is drifting open. o Verifies operation within CPS 3005.01 Unit Power Changes Figure 1, CPS Stability Control &

Power/Flow Operating Map limits. o Contacts the Reactor Engineer. o Dispatches an Equipment Operator to investigate for abnormalities at the ‘A’ RR HPU. o Demands a 3D Monicore Case.

SRO • Acknowledges reports from ATC/BOP. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

standards and approved procedures. • Directs actions listed above. • Enters and executes CPS 4008.01 Abnormal Reactor Coolant Flow. • Evaluates ITS 3.4.1 Recirculation Loops Operating and enters ITS 3.4.1 A.1 if loop flow

mismatch exceeds 5% of rated core flow (4.225 x 106 lbm/hr). o Informs RE, SM, and TSO o Contacts Maintenance to investigate. o Conducts a brief.

Terminus: RR ‘A’ FCV motion stopped, CPS 4008.01 Abnormal Reactor Coolant Flow entered. NOTES:



Operator Actions


Description: Failure of DG Fuel Oil Transfer Pump 1A to auto start


Cues: 5060-8C, LOW LEVEL DG DAY TANK 1A and 5060-8E, TROUBLE DIESEL GEN 1A


Key Parameter Response: DG1A Day Tank level lowering. Expected Annunciators: 5060-8C, LOW LEVEL DG DAY TANK 1A and 5060-8E, TROUBLE DIESEL GEN 1A Automatic Actions: DG1A Fuel Oil Transfer Pump (FOTP) starts on Day Tank low level (failure to auto start)

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Dispatches Equipment Operator to investigate.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports issue to SRO. • Refers to the ARP for 5060-8C Low Level DG Day Tank 1A. o Dispatches an Equipment Operator to investigate.

Per CPS 5060-8C Low Level DG Day Tank 1A: • Determines that the DG1A Fuel Oil Transfer Pump (FOTP) failed to autostart:

• Manually starts the DG1A Fuel Oil Transfer Pump (FOTP).

o Secures FOTP when annunciators 5060-8C and 5060-8E clear, or o Allows FOTP to remain running.

SRO • Acknowledges reports from BOP. • Verifies / directs BOP to manually start the DG1A Fuel Oil Transfer Pump (FOTP). • Enters ITS 3.8.1 AC Sources – Operating Required Actions B.1, B.2, B.3.1, B.4 OR B.1,

B.2, B.3.2, B.4. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o Informs Shift Manager. o Conducts a brief. o Contacts Maintenance to investigate.

Terminus: Annunciators 5060-8C and 5060-8E clear with FOTP running or secured and Technical Specification review complete.

NOTES:



Operator Actions


Description: ‘B’ RWCU pump seal plate temperature high


Cues: Annunciator 5000-2E, Cleanup Pump Seal Gland Plate Temp Hi


Key Parameter Response: None

Expected Annunciators: 5000-2E, Cleanup Pump Seal Gland Plate Temp Hi


ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Reports issue to SRO. • Refers to ARP 5000-2E. o Dispatches an Equipment Operator to investigate/support RWCU operation. Per CPS 3303.01, RWCU step 8.1.4 and 8.1.3: • Directs Equipment Operator to remove all Filter demins from service. • Throttles open the F/D bypass valve (1G33-F044) to maintain RT system flow 150 – 300

gpm. • Secures RWCU pump ‘B’. Throttles 1G33-F044) to maintain RT system flow ~ 150 gpm. o Places one F/D in service while monitoring RT system flow. o Shuts the F/D bypass valve (1G33-F044).

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Dispatches an Equipment operator to investigate/support RWCU operation.

SRO • Acknowledges report from BOP. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations


Terminus: RWCU pump 1B has been shutdown IAW CPS 3303.01.

NOTES:



Operator Actions


Description: Trip of ERAT SVC


Cues: Annunciator 5011-8E, ERAT SVC Trip


Key Parameter Response: ERAT SVC Output VARS will go to 0 Expected Annunciators: 5011-8E, ERAT SVC Trip Automatic Actions: ERAT SVC Breakers 0AP103E and 0AP104E will trip.

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Dispatches an Equipment Operator to the ERAT SVC Building to investigate. o Recognizes that the ERAT SVC has tripped and reports condition to the SRO.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands. o Dispatches an Equipment Operator to the ERAT SVC Building to investigate. o Recognizes that the ERAT SVC has tripped and reports condition to the SRO.

Per CPS 5011-8E ERAT SVC Trip: • Places the ERAT SVC control switch to OFF, and then releases. • Verifies ERAT SVC Bkr 0AP103E and 0AP104E is open (green light on, red light off). • Transfers 4160V Bus 1A1 to RAT ‘B’ IAW CPS 3501.01 High Voltage Auxiliary Power

System when directed by the SRO.

Per CPS 3501.01 High Voltage Auxiliary Power System section 8.1.8 Transferring a 6900V or 4160V Bus TO or FROM its Reserve {Main} Source:

• At 1H13-P877-5060, places the 4160V Bus 1A1 Bus Mn Bkr Sync keylock switch to the ON position.

• Verifies 4160V Bus 1A1 voltage 4084 – 4300 VAC. • Verifies 4160V Bus 1A1 synchroscope is steady at ~ the 12 o’clock position. • Closes the Mn Bkr, and prior to releasing the switch to the AUTO position, verifies:

• Closed indication on the Main breaker, and • A load shift is indicated on the bus load meters.

• Places the Reserve Feed Breaker in OPEN, and resets annunciator 5060-1B Auto Trip Breaker.

• At 1H13-P877-5060, places the 4160V Bus 1A1 Bus Mn Bkr Sync keylock switch to the OFF position.




Description: Trip of ERAT SVC


SRO • Acknowledges reports from ATC/BOP.

• Directs actions listed above. • Enters and executes CPS 4200.01 Loss of AC Power. o Notifies CMO Group to perform thermography on Circuit Switcher 4538. o Notifies TSO & Power Team of the loss of the ERAT SVC. • Enters ITS 3.8.1 AC Sources – Operating Required Actions:

o A.1 and A.2 (if ITS Required Actions entered in Event 4 were exited following Div 1 DG day tank level restoration).

o A.1, A.2, D.1 OR A.1, A.2, D.2 (if ITS Required Actions entered in Event 4 were NOT exited following Div 1 DG day tank level restoration).

• Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Informs the Shift Manager. o Conducts a brief. o Contacts Maintenance to investigate.

Terminus: 4060V Bus 1A1 transferred to RAT ‘B’ and Technical Specification review complete.

NOTES:



Operator Actions

Event No.(s): 7, 8 Page 1 of 3

Description: Generator trip / Turbine trip / Bypass Valve 1 sticks open / RAT failure after MSIVs closed / LOCA - HPCS Pump fails to auto start / RCIC failure / HPCS Injection Valve fails to auto open


Cues: Generator Trip and Scram alarms


Key Parameter Response: Turbine / Generator trip. Turbine Bypass Valve (TBV) #1 sticks open. RAT ‘A’ trips on differential overcurrent resulting in a loss of non-class 1E 6.9 / 4.16KV Bus power. DW Pressure exceeds 1.68 psig. Expected Annunciators: Multiple Automatic Actions: Reactor Scram. 4160V Bus 1A1, 1B1, and 1C1 will automatically transfer to the ERAT. Auto start of all divisional ESF Systems (ECCS, DGs, VG, SX). CRVICS Group 2, 7, 8, 10, 11, 12, 15, 16, 17, 19, and 20 isolation.

[CT]

[CT]

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Reports issues to SRO. • Places reactor mode switch in Shutdown when the reactor automatically scrams.

• Carries out Scram Choreography by reporting the following: • Mode Switch in Shutdown, Power is… • Rod status is… • Reactor Power is… and trend • Reactor pressure is… and trend • Reactor level is… and trend • Any EOPs with entry conditions

Per CPS 4100.01, Reactor Scram • Turns Mode Switch to SHUTDOWN

1) Verifies reactor power is lowering 2) Verifies SHUTDOWN CRITERIA met

• IF RPV level is rising with 2 feed pumps operating, THEN Secures/verifies secured 1 feed pump and controls RPV water level Level 3 to Level 8.

• Verifies Turbine and Generator trip when required

• Performs EOP actions as directed by SRO. o Reports EOP entry conditions. • Coordinates with BOP to monitor and control RPV level and pressure. o Diagnoses RPV depressurization (BPV #1 fails to close). o Directs EO to secure the Steam Bypass EHC skid. o [CT] Shuts inboard and/or outboard Main Steam Isolation Valves prior to RPV

Pressure reaching 380#. o Diagnoses the MDRFP trip and loss of CD/CB when the RAT trips. o Attempts to inject with RCIC if directed by the SRO. o Diagnoses the reactor coolant leakage into the DW. o [CT] Manually starts the HPCS pump when the pump fails to automatically start and

before RPV water level reaches -160” WR (TAF).






[CT]

[CT]

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Reports issues to SRO.

• Carries out Scram Choreography by: • Making an Announcement

• Reactor Scram • MDRFP may start • Evacuate the RCIC room • Evacuate the Containment

• Determines Rod status and reports to the CRS

o Verifies needed auto actions (isolations, ECCS systems start, Div 1, 2, and 3 DGs start). o Reports EOP entry conditions. • Performs EOP actions as directed by SRO. o Diagnoses RPV depressurization (BPV #1 fails to close). o Directs EO to secure the Steam Bypass EHC skid. o [CT] Shuts inboard and/or outboard Main Steam Isolation Valves prior to RPV

Pressure reaching 380#. o Diagnoses the MDRFP trip and loss of CD/CB when the RAT trips. o Initiates Recirc Pump Auxiliary Seal Injection Pump Operation per CPS 3304.01 Control

Rod Hydraulic & Control (RD). o Shuts 1B21-F065A & B RPV Inlet Valves (Feedwater Header Isolation Valves). o Attempts to inject with RCIC if directed by the SRO. o Diagnoses the LOCA into the DW. o [CT] Manually starts the HPCS pump when the pump fails to automatically start and

before RPV water level reaches -160” WR (TAF).






[CT]

[CT]

SRO • Acknowledges reports from ATC/BOP. • Ensures operations are conducted IAW Operations expectations, standards and approved

procedures. • Carries out Scram Choreography by performing an Update:

• Entering EOP-1. • Entering Scram Off-Normal. • End of Update.

• Directs entry into EOP-1 RPV Control and verifies performance of the following actions: • Mode Switch to SHUTDOWN • Shutdown criteria verified • Establishes a RPV water level band between Level 3 and Level 8. • Directs ATC / BOP to verify needed automatic actions (isolations, ECCS start, DG start)

• Directs securing the Steam Bypass EHC system. • [CT] Directs closing inboard and/or outboard Main Steam Isolation Valves prior to

RPV Pressure reaching 380#. • Directs entry into CPS 4200.01 Loss of AC Power (RAT failure). o Directs injection with RCIC to maintain RPV water level band. • Directs entry into CPS 4001.01 Reactor Coolant Leakage (LOCA). • Directs (re)entry into EOP-1 RPV Control / entry into EOP-6 Primary Containment Control. • [CT] Directs or verifies manually starting the HPCS pump when the pump fails to

automatically start and before RPV water level reaches -160” WR (TAF). • Directs actions listed above. o Informs Shift Manager. o Contacts Maintenance to investigate. o Conducts a brief.

Terminus: The scenario can be terminated when the MSIVs have been closed to terminate the cooldown and HPCS is maintaining RPV level above TAF.

NOTES:



Simulator Operator Instructions

Initial Setup

1. Fill out plant status and have Turnover Sheet ready for the crew.

2. Verify daily lamp test completed.

3. Simulator key count: ______ keys.

4. Reset to IC-211 (PW 78910) @ 40% Power. If this is the first reset after swapping simulator loads, reset the IC twice.

5. Load the lesson plan for this scenario.

6. Verify the following commands are active: • YP_XMFTB_4101 • YFRIPPSS • HP10CON45FSP • YP_XREMT_739

7. Place simulator in RUN.

8. Turn on and advance recorders.

9. Verify RCIC Flow Controller is set at 620 gpm.

10. Verify the AR/PR server is running and stabilize AR/PR.

11. Verify Rod Drive pressure is in the expected range of 235-265 psid.

12. Provide pull sheets: Step 26 is current - Gang 9D is at Position 30.

13. Make sure Sequence A is selected.

14. Procedures that are expected to be used during this scenario are:

• CPS 3005.01 UNIT POWER CHANGES • CPS 3109.01 GENERATOR SEAL OIL • CPS 3303.01 REACTOR WATER CLEANUP (RT) • CPS 3501.01 HIGH VOLTAGE AUXILIARY POWER SYSTEM • CPS 4001.01 REACTOR COOLANT LEAKAGE • CPS 4008.01 ABNORMAL REACTOR COOLANT FLOW • CPS 4100.01 REACTOR SCRAM • CPS 4200.01 LOSS OF AC POWER • CPS 4401.01 EOP-1 RPV CONTROL • CPS 4402.01 EOP-6 PRIMARY CONTAINMENT CONTROL • CPS 5000.02 ALARM PANEL 5000 ANNUNCIATORS-ROW 2 • CPS 5011.08 ALARM PANEL 5011 ANNUNCIATORS-ROW 8 • CPS 5017.05 ALARM PANEL 5017 ANNUNCIATORS-ROW 5 • CPS 5017.06 ALARM PANEL 5017 ANNUNCIATORS-ROW 6 • CPS 5018.02 ALARM PANEL 5018 ANNUNCIATORS-ROW 2 • CPS 5060.01 ALARM PANEL 5060 ANNUNCIATORS-ROW 1 • CPS 5060.08 ALARM PANEL 5060 ANNUNCIATORS-ROW 8 • CPS 5201 ALARM PANEL 5201 ANNUNCIATORS AT 1PL10J • ITS 3.4 REACTOR COOLANT SYSTEM (LCO 3.4.1) • ITS 3.8 ELECTRICAL POWER SYSTEMS (LCO 3.8.1)

15. Hang OOS tags on:

• Condensate Pump 1A (1CD01PA)



16. Identify T/S issues associated with OOS and turnover: None

17. Operating Equipment: None

18. Marked up copies:

• CPS 3005.01 Unit Power Changes

19. Verify simulator conditions match the turnover.



Event Triggers and Role Play Event # 1. Perform On-Line Testing of the Emergency Seal Oil Pump (Pull up 1PL10J Alarm Panel)

a. Event Trigger - None. b. Role play :

(1) EO (If requested) a) (after ESOP started and when asked for status) – report “1PL10J Annunciator 5201-3A (Running Emerg

Seal Oil Pump) is ON". b) (after ESOP started and when asked for status) – report “noise and vibration levels on the ESOP are

NORMAL". c) (after ESOP stopped and when asked for status) – report “1PL10J Annunciator 5201-3A (Running Emerg

Seal Oil Pump) is OFF". d) Reset 1PL10J alarm and report “1Pl10J alarm is reset”.

2. Raise Power with flow to ~ 45% (Pull up TT06 Trip Panel on PIDs) a. Event Trigger - None. b. Role play

(1) WEC (when contacted about the TT alarm) – report alarm, reset when requested and report alarm is reset.

3. ‘A’ RR Flow Control Valve (FCV) Drifts Open (Pull up FCV A controller) a. Event Trigger - Following Event 2 and when directed by the Lead Examiner, Activate Remote 1 and verify the

following command(s): (1) S_K603A 2 OPEN SLOW. (Recirc Loop Flow Controller B33-K603A).

b. Role play

(1) RE (when contacted about the FCV failure) – “I am on my way to the MCR.”

(2) EO (when dispatched to the RR HPU to investigate) – “The ‘A’ RR HPU looks normal locally. There are no oil leaks on the skid.”

(3) Booth Operator (if FANUC LEDs are checked) – “The LEDs are normal”.

(4) Booth Operator (if the MCR requests the ‘A’ RR HPU restarted) :

a) Release YP_XREMT_676 Start Up (Restart RR HPU A)’ and then report that the ‘A’ RR HPU has been restarted.

4. Failure of DG Fuel Oil Transfer Pump 1A to auto start (Pull up FOTP control switch)

a. Event Trigger - Following Event 3 and when directed by the Lead Examiner, Activate Remote 2 and verify the following command(s): (1) A05_A01_A0108_3_TVM steady. (5060-8C LOW LEVEL DG DAY TANK 1A) (2) A05_A01_A0108_5_TVM steady. (5060-8E TROUBLE DIESEL GEN 1A)

b. Role play (1) EO (if directed to determine source of annunciators) – report, “There is a low fuel level in the Div 1 DG Day

Tank. It is currently at 45% and lowering/rising (based on whether the FOTP running).” (2) WEC (if CPS 9082.01 Offsite Source Power Verification is requested) – report, “I will bring it to the MCR when

I get it ready”.

5. ‘B’ RWCU pump seal plate temperature high a. Event Trigger - Following Event 4 and when directed by the Lead Examiner, Activate Remote 3 and verify the

following command(s): (1) A01_A01_02_5_TMV=2. (Annunciator 5000-2E, Cleanup Pump Seal Gland Plate Temp Hi)

b. Role Play (1) EO (if requested):

a) To check RT pump seal temperatures locally – report, “‘B’ RT pump seal temperature is 285 degrees and rising slowly”.

b) Verify CCW lineup/’A’ RT pump status – report, “CCW is lined up to the RT pumps and the ‘A’ RT pump is at 175 degrees and stable”

c) To check for steam in the RT pump room – report, “there is no steam in the room.” d) To perform local actions to isolate and vent ‘B’ RT pump - respond that you will go to RP to obtain a Hi

Rad Brief.



(2) Chemistry:

a) When informed of RT F/D removal from service – acknowledge the report. b) If/When asked on preference on final F/D alignment – report, “Chemistry has no preference on which F/D

to restore to service. (3) Booth Operator (when requested):

a) To check Div 2 RT Pump Room Temperature indication – report that it reads 86⁰F and stable. b) To remove RT F/D ‘A’ from service, Release - Remove RT F/D ‘A’ from service c) To remove RT F/D ‘B’ from service, Release - Remove RT F/D ‘B’ from service d) To place RT F/D ‘A’ in service, Release - Place RT F/D ‘A’ back in service e) To place RT F/D ‘B’ in service, Release - Place RT F/D ‘B’ back in service

6. Trip of ERAT SVC a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 4 and verify the

following command: (1) ed_ek20=true. (Trip ERAT SVC on overcurrent)

b. Role play

(1) EO (when directed to investigate ERAT SVC trip): “The ERAT SVC Lockout Relays are tripped and the TSC Overcurrent LED is lit. The ERAT SVC Cooling System is operating normally.”

(2) WEC (if asked to make required notifications to the Power Team and TSO of the loss of the ERAT SVC) – “I will make the required notifications”.

(3) Maintenance/Engineering (if requested to investigate failure of the ERAT SVC) – “I will brief and dispatch personnel to investigate”.

7. Generator Trip / Turbine Trip / Bypass Valve 1 sticks open / RAT Failure after MSIVs closed a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 5 and verify the

following command(s): (1) YP_XMFTB_4063. (Generator Trip) (2) YPXMALSE_588 100%. (#1 BPV Fail To Position) (3) A02_A05_02_11_TVM. (5006-2L HPU Trouble) (4) RAT_B_Differential. (RAT B Differential Trip) (5) YPXMALSE_510 0.1%. (RR B Suction Line Leak)

b. Role play:

(1) Maintenance (after 2 minutes from scram announcement) – report to the MCR as IMD.

(2) EO (when directed to secure the Steam Bypass EHC skid) – acknowledge the order and report; “the Steam Bypass EHC skid is secured”.

8. LOCA - HPCS Pump fails to auto start / RCIC failure / HPCS Injection Valve fails to auto open

a. Event Trigger – None b. Role play (If requested):

(1) EO (investigate RCIC pump failure) – Report, “The RCIC pump shaft appears to be damaged”. (2) Maintenance (investigate RCIC pump failure) – Report, “I will brief and dispatch personnel to investigate”.



Turnover

1. The plant is in Mode 1, operating at ~ 40% power. a. CPS 3005.01 Unit Power Changes. Section 5.0 Prerequisites are complete. Steps 8.1.1 – 8.1.8 are

complete. b. Control rods - Step 26 / Gang 9D @ position 30.

2. Status of Tagged Out Equipment

• Condensate Pump 1A (1CD01PA)

3. Today Day Shift

4. Weather Conditions

• Calm and clear.

5. Thermal Limit Problems or concerns

• Power ascension to rated power per CPS 3005.01 Unit Power Changes. • RE and Rod Verifier are available on request.

6. LCO’s in effect

• None

7. Surveillances in progress

• None

8. Previous Shift Evolutions completed

• None

9. Evolutions planned for the shift

• First Priority – Perform on-line testing of the Emergency Seal Oil Pump IAW CPS 3109.01 Generator

Seal Oil (SO) section 8.1.2.3. • Continue with power ascension to 45% IAW CPS 3005.01 Unit Power Changes using RR flow.

10. Risk Levels

• Green • Protected Equipment: None

11. Dose equivalent Iodine 131 is reading 1.5 E-6 µcuries per gram.


ILT 17-1 NRC Scenario 2 Rev 1 4-03-18 Post Val.Doc Post Val Page 1 of 21

Exelon Nuclear

ILT 17-1 NRC Exam


Revision Number: 1

Date: 4/03/18





Facility: Clinton Power Station Scenario No.: 2 Operating Test No.: 2018-301 Examiners: ____________________________ Operators: ____________________ ____________________________ ____________________ ____________________________ ____________________ Initial Conditions: • Mode 1 at ~73% power. • Power ascension to RTP is in progress IAW CPS 3005.01 Unit Power Changes (but on hold for this shift). • Weather conditions are calm and clear. Turnover: • Priorities for the shift are as follows:

• Shift Generator Stator Cooling Pumps IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps (MCR).

• Maintain power at 73% throughout the shift. Critical Tasks: • ATC inserts a manual scram when multiple rods begin drifting. • PC-6.1 Within 10 minutes of exceeding Figure N and containment pressure continuing to rise, enter EOP-3

Emergency RPV Depressurization. (PRA)

Event No.

Malf. No. Event Type* Event Description

1 NA N-BOP Shift Generator Stator Cooling (GC) Pumps

2 A02_A11_S01=2 TS-SRO Failure of the EOC-RPT Bypass Relay (5006-1J)

3 YPRR15AB 0% TS-SRO FW NR Level Transmitter C34N004B failure

4 A04_A01_04_4_TVM R-ATC Loss of IPBD Cooling requires power reduction to < 17,000 amps generator output

5 A02_A05_01_7_TVM=2 C-ATC CRD high temperature

6 A01_A03_02_1_TVM Steady

C-ATC Loss of seal water to the ‘A’ TDRFP

7 GS1GS02CA_SHEAR C-BOP Steam Packing Exhauster Blower Failure

8 A11_A02_03_7_TVM 2 C-BOP Clogged CW Pump 1C TW Supply Strainer

9 A11_A08_S07 Close

LCRPOS for 28-29, 44-17, 20-21, and 48-33

YPXMALSE_511 1%

YPCTHOLE 10%

M-All Loss of IA to Cnmt / Multiple Rod Drifts / Unisolable Lower Plenum Leak / DW Failure / ED on Fig. N

10 YPXMALSE_76 0% YPXMALSE_87 0% YPXMALSE_79 0%

C-BOP 3 ADS SRVs Fail To Open





1. Shift Generator Stator Cooling (GC) Pumps The BOP will shift GC Water Pumps IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps (MCR) to support upcoming maintenance on 1GC01PB.

2. Failure of the EOC-RPT Bypass Relay (5006-1J) Annunciator 5006-1J DIV 1 RPT BYP will be received. The CRS will request IMD to report to the MCR to investigate the alarm. The IMD technicians will report it appears that the Div 1 EOC/RPT Bypass Circuitry is malfunctioning and that it is not an annunciator issue. The SRO will declare Div 1 EOC-RPT Instrumentation inoperable and enter ITS 3.3.4.1 Action B.1 to place one channel in affected function in trip within 6 hours.

3. FW NR Level Transmitter C34N004B failure FW NR Level Transmitter C34N004B fails causing annunciator 5002-3P RX WTR LVL CONT SYS TROUBLE to alarm. The SRO will evaluate and enter ORM 2.2.12 Feedwater System / Main Turbine Trip Action 3.2.12.a Restore channel to an operable status within 7 days.

4. Loss of IPBD Cooling requires power reduction to < 17,000 amps generator output Annunciator 5010-4D TROUBLE ISOL PHASE DUCT COOLERS will alarm. The BOP will dispatch an EO to investigate the alarm locally. The EO will report that the running IPBD cooling fan has tripped. The EO will report that the belt for the standby IPBD Fan failed when the fan auto started. Bus duct temperature is slowly rising but < 187⁰F. Due to the loss of forced cooling, the SRO will direct the ATC to lower Main Generator load to < 17,000 amps.

5. CRD high temperature Annunciator 5006-1G CRD HYDR TEMP HI is received. The ATC operator will dispatch a field operator to the local recorder on 1H22-P007 to determine rod 52-25 is alarming. The ATC operator will note that rod 52-25 is currently at position 48 and IAW CPS 3304.01 Control Rod Hydraulic & Control (RD) perform an extended coupling check. The annunciator will clear for ~ 30 seconds and then alarm again. The ATC operator will then insert rod 52-25 to position 46 which will clear the high temperature condition.

6. Loss of seal water to the ‘A’ TDRFP Annunciator 5002-2A LOW PRESS RFP 1A SEAL WATER will alarm due to local pressure control valve 1TD600A failing closed. The SRO will direct the D-Area operator to swap seal water filters. The MCR will determine that shifting the filters did not corrected the low seal water pressure condition. The ATC will closely monitor reactor water level while removing RFP 1A from service.

7. Steam Packing Exhauster Blower Failure Annunciator 5019-1B HIGH PRESSURE STM PACKING EXH SUCTION is received. The BOP operator will determine that the running SPE blower failed and will start the parallel non-running SPE blower.

8. Clogged CW Pump 1C TW Supply Strainer Annunciator 5041-3G LOW FLOW CW PUMP 1C BRG SEAL WATER comes in due to CW Pump ‘C’ seal water flow less than the setpoint (15 gpm). The BOP operator will dispatch an Equipment Operator to investigate. Seal water flow to Circulating Water (CW) Pump 1C cannot be restored. The BOP/ATC operator(s) will closely monitor main condenser vacuum (may enter Loss of Vacuum off-normal) while securing CW Pump 1C and starting CW Pump 1A.

9. Loss of IA to Cnmt / Multiple Rod Drifts / Unisolable Lower Plenum Leak / DW Failure / ED on Fig. N 1IA005 Cnmt IA Outbd Isol Vlv will fail closed due a failure of the actuator air supply line, causing a loss of IA to the containment. The control rod scram valves will begin to fail open, causing multiple control rods to drift. The ATC will insert a manual scram due to the drifting control rods. When the mode switch is placed in shutdown, an unisolable reactor coolant leak will begin, causing DW pressure to rise. EOP’s 1 and 6 will be entered. The DW will fail, causing containment pressure to rise. The SRO will direct containment sprays to be initiated when containment pressure is in the OK to Spray region of Figure O Containment Spray Initiation Limit. Initiating Containment Spray fails to prevent Containment pressure from exceeding Fig. N Pressure Suppression Pressure, requiring an ED to be performed.

10. 3 ADS SRVs Fail To Open Upon initiation of ADS in event 9, three ADS SRVs (41F, 51G, and 47A) fail to open. The BOP Operator will open three additional safety relief valves to complete the blowdown.



Operator Actions


Description: Shift Generator Stator Cooling (GC) Pumps


Cues: None



• “Expected alarms” will be flagged • When the annunciator comes in the operator will announce “Expected Alarm” • The annunciator response procedure (ARP) need not be entered since it has already been reviewed in the pre-brief.

If a pre-brief was not conducted the operator should perform the following: • When an annunciator comes in the ARP should be referred to. • The annunciator may then be identified as an “Expected Alarm”, flagged, and from that point on the ARP need not be referred to.

Key Parameter Response: GC Pump indicator lights on 1H13-P870-5017

Expected Annunciators: 5017-5A Auto Start Stator Cooling Water Pump (when the stby pump auto start feature is tested)

Automatic Actions: GC Pump 1B will auto start when the when the standby pump auto start feature is tested.

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Performs Plant Announcement.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Performs Plant Announcement.

IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4: • BOP obtains authorization from the Control Room Supervisor to perform critical steps

({CS}) before performing CPS 3110.01 Section 8.2.4. • {CS} Start standby GC Pump 1A (1GC01PA). • {CS} Stop GC Pump 1B (1GC01PB). Allow control switch to spring return to AUTO. • Tests the standby GC pump auto start by:

• Depress the Generator Cooling Water Pump Test push-button. • Verify AUTO START STATOR COOLING WATER (5017-5A) illuminates.

• {CS} Places control switch for the GC Pump 1B (1GC01PB) in the STOP position, AND lets it spring return to AUTO.

SRO • Acknowledges reports from ATC/BOP. • Authorizes BOP to perform the critical steps contained in CPS 3110.01 Section 8.2.4

(denoted by {CS}). • Provides direct oversight of the GC Pump shift. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations


Terminus: GC Pumps shifted and the auto start feature of the standby GC pump has been tested.

NOTES:





Operator Actions


Description: Failure of the EOC-RPT Bypass Relay (5006-1J)


Cues: 5006-1J Div 1 RPT Byp alarm


Key Parameter Response: Div 1 RPT bypass switch position Expected Annunciators: 5006-1J Division 1 Recirculation Pump Trip Bypassed Automatic Actions: None

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Communicates annunciator 5006-1J to the SRO. • Refers to ARP 5006-1J Division 1 Recirculation Pump Trip Bypassed.

Per CPS 5006-1J, Division 1 Recirculation Pump Trip Bypassed: • Verifies Div 1 RPT bypass switch in NORMAL. • Informs SRO to refer to ITS LCO 3.3.4.1, EOC – RPT Instrumentation.



expectations, standards, and approved procedures. • Contacts Maintenance to investigate Div 1 RPT Bypass annunciator. • Evaluates and enters ITS LCO 3.3.4.1 EOC – RPT Instrumentation, RA A.1 & B.1 for

malfunctioning Div 1 EOC – RPT bypass circuitry. o Informs the Shift Manager. o Conducts a brief.

Terminus: Tech Specs evaluated.

NOTES:



Operator Actions


Description: FW NR Level Transmitter C34N004B Failure


Cues: 5002-3P Reactor Water Level Control System Trouble


Key Parameter Response: Reactor Water Level – Narrow Range Expected Annunciators: 5002-3P Reactor Water Level Control System Trouble Automatic Actions: If alarming channel is bad quality then 2 remaining good quality channels will average to produce NR median select output.

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Communicates annunciator 5002-3P to the SRO. • Refers to ARP 5002-3P Reactor Water Level Control System Trouble.

Per CPS 5002-3P, Reactor Water Level Control System Trouble: • Monitors Reactor water level (verifies stable). o Informs SRO to evaluate entering CPS 4002.01, Abnormal RPV Level / Loss of Feedwater

at Power. o Diagnoses failure of the B NR level transmitter (C34N004B).



expectations, standards, and approved procedures. • Evaluates and enters ORM 2.2.12 Feedwater System / Main Turbine Trip, RA 3.2.12.a for

failure of the B NR level transmitter. o Evaluates entering CPS 4002.01, Abnormal RPV Level / Loss of Feedwater at Power. o Contacts Maintenance to investigate failure of the B NR level transmitter (C34N004B). o Informs the Shift Manager. o Conducts a brief.

Terminus: Tech Specs evaluated.

NOTES:



Operator Actions


Description: Loss of IPBD Cooling requires power reduction to < 17,000 amps generator output


Cues: 5010-4D Trouble Isol Phase Duct Coolers


Key Parameter Response: IPBD air flow / IPBD temperature Expected Annunciators: 5010-4D Trouble Isol Phase Duct Coolers Automatic Actions: Standby

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Dispatches Equipment Operator to investigate / check status of alarms and equipment at

1PL113J and 1PL113JA. o Directs the Equipment Operator to promptly start the standby IPBD fan. • When it is determined that no IPBD Cooling Fans (forced cooling) are available, lowers Main

Generator load to < 17,000 amps by reducing power with flow (by closing the RR FCVs) and/or control rod insertion.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Recognizes that operating IPBD fan tripped and standby IPBD fan failed to start. • Reports issue to the SRO. • Refers to the ARP for 5010-4D Trouble Isolated Phase Bus Duct Coolers.

Per 5010-4D Trouble Isolated Phase Bus Duct Coolers: o Dispatches Equipment Operator to investigate / check status of alarms and equipment at

1PL113J and 1PL113JA. o Directs the Equipment Operator to promptly start the standby IPBD fan. • Determines that no IPBD Cooling Fans (forced cooling) are available. o Reports loss of IPBD cooling to SRO. o Refers to CPS 3504.01, Main Power and Unit Auxiliary Transformers Cooling section 8.3.3

Trouble IPBD Cooling System.


expectations, standards, and approved procedures. • When it is determined that no IPBD Cooling Fans (forced cooling) are available, directs the

ATC to lower Main Generator load to < 17,000 amps (~ 57% power) by reducing power with flow and/or rods.

o Contacts Maintenance to investigate loss of IPBD cooling. o Informs the Shift Manager and RE. o Conducts a brief.

Terminus: Clearly observable plant response to the reactivity manipulation (Reducing power with flow to < 17,000 amps).

NOTES:



Operator Actions


Description: CRD high temperature


Cues: Annunciator 5006-1G, CRD Hydr Temp Hi


Key Parameter Response: CRD 52-25 operating temperature

Expected Annunciators: 5006-1G, CRD Hydr Temp Hi

Automatic Actions: None ATC • Reports issue to SRO.

• Refers to ARP. o Directs Equipment Operator to check local recorder to determine which CRD is alarming. • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per 3304.01, Control Rod Hydraulic & Control (RD), 8.3.2 CRD High Operating Temperature: • Determines CRD 52-25 is alarming. • Performs extended coupling check of rod 52-25 (10-15 seconds). • Inserts control rod 52-25 to position 46.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Directs Equipment Operator to check local recorder to determine which CRD is alarming.

SRO • Acknowledges report from ATC. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o Informs Shift Manager. o Contacts Maintenance/RE. o Conducts a brief.

Terminus: Control rod 52-25 inserted to position 46. Annunciator 5006-1G clear.

NOTES:



Operator Actions


Description: Loss of Seal Water to the ‘A’ TDRFP


Cues: 5002-2A Low Press RFP 1A Seal Water


Key Parameter Response: RFP 1A Seal Water pressure Expected Annunciators: 5002-2A Low Press RFP 1A Seal Water Automatic Actions: None

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Reports issue to the SRO. • Refers to ARP CPS 5002.02 Alarm Panel 5052 Annunciators - Row 2.

Per 5002-2A Low Pressure Reactor Feed Pump 1A Seal Water: • Verifies Condensate Booster Pump discharge header pressure > 350 psig. • If supply pressure is satisfactory, swaps seal water inlet filter to the standby filter.

• Directs Equipment Operator to swap seal water inlet filter to the standby filter IAW CPS 3103.01 Feedwater (FW) section 8.3.12 Low Seal Injection Pressure.

• Determines no change to seal water pressure. • If seal pressure is not restored (and conditions permit), removes (isolates) RFP 1A from

service.

Per CPS 3103.01 Feedwater (FW) section 8.3.12 Low Seal Injection Pressure: o Determines that reactor power is within the capacity of a single RFP. • Stops TDRFP ‘A’ per CPS 3103.01 Feedwater (FW) section 8.1.10.

Per CPS 3103.01 Feedwater (FW) section 8.1.10 TDRFP Shutdown: o Discusses with the SRO the need to lockout the RR FCVs.

Per CPS 3302.02P001 and P002 Reactor Recirculation Flow Control Hydraulic Power Unit 1A(1B) section 8.1.6 Shutdown: o Arms and depresses the HPU A and B Shutdown trip push-buttons. o Verifies FCV motion is inhibited as indicated by:

o Annunciators 5003-4B & 4H FCV A & B Motion Inhibit on. o White light above FCV A & B Motion Inhibit Reset push-buttons energized.

Per CPS 3103.01 Feedwater (FW) section 8.1.10 TDRFP Shutdown: • Obtains authorization from the SRO to perform critical steps ({CS}) listed below. • {CS} Removes TDRFP ‘A’ from service using either Auto or Manual method as follows:

• {CS} Auto – Selects TDRFP A “Take Pump Offline” command • Manual:

• {CS} Places TDRFP ‘A’ in either speed setter mode auto, or speed setter mode manual.

• {CS} Reduces off-going turbine speed as necessary, to transfer all flow to the ‘B’ TDRFP.

• {CS} Verifies the ‘A’ TDRFP flow has been transferred to the ‘B’ TDRFP.




Description: Loss of Seal Water to the ‘A’ TDRFP


ATC (cont.)

o Reduces TDRFP ‘A’ speed to minimum speed by placing TDRFP ‘A’ m/a in manual 0% output.

o Places 1FW010A in manual closed. o Places/verifies 1FW010A CLOSED pushbutton in depressed. o {CS} Presses the TDRFP 1A trip push-button and verifies the HP and LP Stop Valves

and the 1FW002A valve closes. o Verifies the Turning Gear 1FW02KA engages when the TDRFP stops. o Resets RR FCVs when directed by SRO per CPS 3302.01 Reactor Recirculation (RR).

Per CPS 3302.01 Reactor Recirculation (RR) section 8.4.1:

o Restores the HPU A and B equipment to normal operation (restarts the RR A and B HPUs.

o Depresses the A and B FCV A/B Motion Inhibit Reset push-buttons.

Per CPS 3103.01 Feedwater (FW) section 8.3.12 Low Seal Injection Pressure: o Directs EO to isolate RFP 1A by shutting:

o 1CB009A RFP 1A Suction Valve o 1FW002A RFP 1A Discharge Valve o 1FW038A Warming Line Isolation Valve


Per CPS 3103.01 Feedwater (FW) section 8.1.10 TDRFP Shutdown (after tripping TDRFP ‘A’): o Opens/verifies open the following drain valves:

o 1TD004A RFPT A High Pressure Stop Valve Before Seat Drain Valve. o 1TD005A RFPT A High Pressure Stop Valve After Seat Drain Valve. o 1TD006A RFPT A Low Pressure Stop Valve Before Seat Drain Valve. o 1TD007A RFPT A Low Pressure Stop Valve After Seat Drain Valve. o 1TD008A RFPT A First Stage Drain Valve.

o Shuts 1B21-F303A RFPT 1A Main Steam Inlet Valve.

SRO • Acknowledges reports from ATC/BOP.

• Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards, and approved procedures.

o Contacts Maintenance to investigate low seal water pressure on RFP 1A. • Authorizes ATC to perform the critical steps contained in CPS 3103.01 Section 8.1.10

TDRFP Shutdown (denoted by {CS}). • Provides direct oversight during shutdown of the ‘A’ TDRFP. • Directs actions listed above. o Informs the Shift Manager. o Conducts a brief.

Terminus: RFP 1A shutdown initiated. Continue with E6, E7, and E8 while waiting for the RFP shutdown to complete.

Notes:




Description: Steam Packing Exhauster Blower Failure


Cues: Annunciator 5019-1B alarms


ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies SRO of unusual/unexpected conditions. o Dispatches Equipment Operator to investigate cause of the SPE Blower trip.

BOP • Reports issue to SRO • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Dispatches Equipment Operator to investigate status of the running SPE Blower. • Refers to the ARP. Per 5019-1B High Pressure SPE Suction: • Monitors SPE Inlet Pressure. • Starts the standby SPE Blower and stops the running SPE Blower.

SRO • Acknowledges report from BOP. o Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o May enter CPS 4004.02, Loss of Vacuum. (Vacuum should not substantially change). o Informs Shift Manager. o Conducts a brief. o Contacts maintenance to investigate.

Terminus: Standby SPE Blower is running.

NOTES:



Operator Actions


Description: Low Flow CW Bearing Seal Water


Cues: Annunciator 5041-3G, Low Flow CW Pump 1C Brg Seal Water



Expected Annunciators: 5041-3G, Low Flow CW Pump 1C Brg Seal Water


o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Performs Plant Announcements. o Dispatches Equipment Operator to investigate CW Pump 1C Bearing Seal Water flow issue. o Monitors CW pump bearing temperatures (computer points CW-BA027, CW-BA028, and

CW-BA029) (may be performed by BOP). o Dispatches Equipment Operator to investigate RPS Inverter ‘A’ Trouble alarm (received when

CW Pump 1A is started). o Directs an Equipment Operator to reset the trouble alarm on RPS Inverter ‘A’.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports issue to SRO. • Refers to ARP 5041-3G. o Performs Plant Announcements. o Dispatches Equipment Operator to investigate CW Pump 1C Bearing Seal Water flow issue. Per 5041-3G, Low Flow CW Pump 1C Brg Seal Water: • Directs Equipment Operator to flush CW Pump 1C TW supply strainer 1TW01MC. o Monitors CW pump bearing temperatures (computer points CW-BA027, CW-BA028, and

CW-BA029) (may be performed by ATC). • Starts standby (1A) CW Pump. • Trips 1C CW Pump.

o Dispatches Equipment Operator to investigate RPS Inverter ‘A’ Trouble alarm (received when CW Pump 1A is started).

o Directs an Equipment Operator to reset the trouble alarm on RPS Inverter ‘A’. o Notifies chemistry of CW pump shift.

SRO • Acknowledges report from BOP. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o May enter CPS 4004.02, Loss of Vacuum. (Vacuum should not substantially change). o Contacts Maintenance to investigate. o Informs Shift Manager. o Conducts a brief.

Terminus: CW Pump 1C has been tripped, CW Pump 1A is started.



Operator Actions


Description: Loss of IA to Cnmt / Multiple Rod Drifts / Unisolable Lower Plenum Leak / DW Failure / ED on Fig. N / 3 ADS SRVs Fail To Open


Cues: 5003-5M Cnmt / DW IA Isol Vlv Closed


Key Parameter Response: Instrument Air Pressure, Control Rod Position Expected Annunciators: 5003-5M Cnmt / DW IA Isol Vlv Closed, 5006-4G Rod Drift Automatic Actions: Scram air header depressurizes – Multiple rod drifts. Inboard MSIVs drift shut (after ~ 20 minutes).

[CT]

[CT] [CT]

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Reports issues to the SRO. • Diagnoses loss of IA to the containment. • Determines that multiple control rods are drifting (multiple drift lights) • [CT] Places the Mode Switch in Shutdown.

• Carries out Scram Choreography by reporting the following: • Mode Switch in shutdown, power is… • Rod Status is… • Reactor Power is … and trend • Reactor pressure is… and trend • Reactor water level is………and trend. • Any EOPs with entry conditions (no values required).


• Verifies reactor power is lowering • Verifies SHUTDOWN CRITERIA met

• IF RPV level is rising with 2 feed pumps operating, THEN Secures/verifies secured 1 feed pump and controls RPV water level Level 3 to Level 8.

• Verifies Turbine and Generator trip when required

• Performs EOP actions as directed by the SRO. o Reports EOP entry conditions. • Coordinates with BOP to monitor and control RPV level and pressure. o Diagnoses reactor coolant leakage into the DW. o Announces rising Drywell Pressure and EOP-6 entry. • _____Time DW Pressure reaches 1.68 psig. • _____Time both RR Pumps are stopped. • Stops both RR pumps within 1 minute of Hi Drywell Pressure (1.68 psig). o Attempts to open bypass valves when directed by the SRO.

Per EOP-3, Emergency RPV Depressurization (will probably be BOP): o [CT] Initiates ADS when directed by SRO. o [CT] Opens other SRVs for a total of seven valves open.

• Operates ECCS/FW Systems as needed to control RPV Water Level, Level 3 to Level 8. (may be performed by BOP)






[CT] [CT]

BOP

• Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Reports issues to SRO.


• Reactor Scram • MDRFP may start • Evacuate the RCIC room • Evacuate the Containment

• Determines Rod status and report to CRS o Performs EOP actions as directed by SRO. o Diagnoses reactor coolant leakage into the DW. o Announces rising Drywell Pressure and EOP-6 entry.

Per EOP-6 Primary Containment Control o Starts Drywell Mixers, as directed. o Starts Containment Spray, as directed.

o Monitors the start of the ECCS Systems on High Drywell Pressure. o Operates ECCS/FW Systems as needed to control RPV Water Level, Level 3 to Level 8.

(may be performed by ATC)

Per EOP-3, Emergency RPV Depressurization (may be performed by ATC): • [CT] Initiates ADS when directed by SRO. • [CT] Opens other SRVs for a total of seven valves open. • Verifies ADS actuation using the following indications:

o SPDS o DCS Display 122 (2H) [Acoustic Monitor Input] o DCS Display 186 (7B) [‘A’ Solenoid Input] o 1H13-P601/P642 Solenoid Indicator Lights o 1H13-P866 Valve Flow Monitor Control Panel o 1H13-P614 ADS Safety Valve Temperature recorder 1B21-R614 o Indirect indication via changes in RPV pressure, RPV level, MSL flows & suppression

pool temperatures.






[CT]

[CT] [CT]


expectations, standards, and approved procedures. • Enters and executes CPS 4004.01 Instrument Air Loss. • [CT] Directs ATC to scram the reactor or concurs with ATC recommendation to scram

the reactor due to multiple drifting control rods.

Enters and executes CPS4100.01 Reactor Scram: • Carries out Scram Choreography by performing an Update:

o Update. o Entering EOP-1. o Entering Scram Off-Normal. o End of Update.

• Directs entry into EOP-1 RPV Control and verifies performance of the following actions: • Mode Switch to SHUTDOWN • Shutdown criteria verified • Establishes a RPV water level band between Level 3 and Level 8 • ATC / BOP verifies automatic actions (isolations, ECCS start, DG start)

• Enters and executes CPS 4001.01 Reactor Coolant Leakage. • Issues Containment Pressure as a critical parameter.

Enters EOP-6, Primary Containment Control, and directs the following: • Starting Mixers. • IAW Fig. O, directs the start of Containment Sprays. • _____Time Figure N exceeded. • _____Time EOP-3 entered • _____Elapsed time between time Fig. N exceeded and EOP-3 entered is ≤ 10 minutes. o Anticipates doing blowdown. Directs ATC to depressurize the RPV rapidly using main

turbine bypass valves (bypass valves fail shut).

Enters EOP-3, Emergency RPV Depressurization, when Figure N is exceeded. • [CT] Directs initiation of ADS. • [CT] Directs opening other SRVs for a total of seven valves open.

• Directs actions listed above. o Informs Shift Manager. o Conducts a brief.

Terminus: ADS initiated, 7 ADS valves open, RPV water level being controlled in prescribed band and upon direction of Lead Examiner. NOTES:




Initial Setup






6. Verify the following commands are active: • YPXMALSE_76 (FV = 0). (B21F041F ADS Valve Failure) • YPXMALSE_87 (FV = 0). (B21F051G ADS Valve Failure) • YPXMALSE_79 (FV = 0). (B21F047A ADS Valve Failure)






12. Provide pull sheets: Step 29 is current - Gang 10A is at Position 8.



• CPS 3005.01 UNIT POWER CHANGES • CPS 3103.01 FEEDWATR (FW) • CPS 3110.01 GENERATOR STATOR COOLING (GC) • CPS 3302.01 REACTOR RECIRCULATION (RR) • CPS 3302.02 P001 REACTOR RECIRCULATION HYDRAULIC POWER UNIT 1A • CPS 3302.02 P002 REACTOR RECIRCULATION HYDRAULIC POWER UNIT 1B • CPS 3304.01 CONTROL ROD HYDRAULIC & CONTROL (RD) • CPS 3504.01 MAIN POWER AND UNIT AUXILIARY TRANSFORMERS COOLING • CPS 4001.01 REACTOR COOLANT LEAKAGE • CPS 4002.01 ABNORMAL RPV LEVEL / LOSS OF FEEDWATER AT POWER • CPS 4004.01 INSTRUMENT AIR LOSS • CPS 4004.02 LOSS OF VACUUM • CPS 4008.01 ABNORMAL REACTOR COOLANT FLOW • CPS 4100.01 REACTOR SCRAM • CPS 4200.01 LOSS OF AC POWER • CPS 4401.01 EOP-1 RPV CONTROL • CPS 4407.01 EOP-3 EMERGENCY RPV DEPRESSURIZATION (BLOWDOWN) • CPS 4402.01 EOP-6 PRIMARY CONTAINMENT CONTROL • CPS 5002.02 ALARM PANEL 5002 ANNUNCIATORS-ROW 2 • CPS 5002.03 ALARM PANEL 5002 ANNUNCIATORS-ROW 3 • CPS 5003.05 ALARM PANEL 5003 ANNUNCIATORS-ROW 5 • CPS 5006.01 ALARM PANEL 5006 ANNUNCIATORS-ROW 1 • CPS 5006.04 ALARM PANEL 5006 ANNUNCIATORS-ROW 4 • CPS 5010.04 ALARM PANEL 5010 ANNUNCIATORS-ROW 4 • CPS 5017.05 ALARM PANEL 5017 ANNUNCIATORS-ROW 5 • CPS 5019.01 ALARM PANEL 5019 ANNUNCIATORS-ROW 1 • CPS 5041.03 ALARM PANEL 5041 ANNUNCIATORS-ROW 3 • ITS 3.3 INSTRUMENTATION (LCO 3.3.4.1)



• ORM 2.2 INSTRUMENTATION (ORM 2.2.12)

15. Hang OOS tags on: None








Event Triggers and Role Play Event # 1. Shift Generator Stator Cooling Pumps (Pull up 1PL10J trouble alarms)

a. Event Trigger - Following shift turnover and as directed by the SRO. b. Role play :

(1) EO (If requested)

a) (when asked to check local panel alarms on 1PL10J ) – acknowledge 1PL10J alarms and provide reports.

b) (when asked to perform prestart checks for GC Pump A) – “Prestart checks are complete for GC Pump A. I’m standing by for pump start”.

c) (when asked to check for GC Pump A locally) – “GC Pump A is running normally.”

2. Failure of the EOC-RPT Bypass Relay (5006-1J) a. Event Trigger - Following Event 1 and when directed by the Lead Examiner, Activate Remote 1 and verify the

following command(s): (1) A02_A11_S01=2. (Div 1 RPT Bypass Switch to BYPASS)

b. Role play

(1) Maintenance (If requested) a) Report to MCR. b) (when asked to investigate annunciator) – exit MCR horseshoe; return ~ one minute later and report,

“It appears that the Div 1 EOC – RPT Bypass Circuitry is malfunctioning and it is not an annunciator issue”.

3. FW NR Level Transmitter C34N004B Failure a. Event Trigger - Following Event 2 and when directed by the Lead Examiner, Activate Remote 2 and verify the

following command(s): (1) YPRR15AB 0%. (Level Transmitter C34N004B fails low)

b. Role play

(1) Maintenance (If requested) a) Report to MCR. b) (when asked to investigate annunciator) – exit MCR horseshoe; return ~ one minute later and report,

“It appears that the Level Transmitter C34N004B is malfunctioning and it is not an annunciator issue”.

4. Loss of IPBD Cooling requires power reduction to < 17,000 amps generator output

a. Event Trigger - Following Event 3 and when directed by the Lead Examiner, Activate Remote 3 and verify the following command(s): (1) A04_A01_04_4_TVM. (5010-4D Trouble Isol Phase Duct Coolers)

b. Role play

(1) EO (If requested)

a) (when asked to check local panels 1PL113J and 1PL113JA ) – report that “The running Isophase Bus Duct Cooling Fan is TRIPPED” and the standby Isophase Bus Duct Cooling Fan failed to start.

b) (when directed to start the standby IPBD Fan) – wait ~ one minute and report that “The standby fan immediately tripped when the fan was taken to START”.

c) Report IPBD temperature as 110⁰F and rising at ~ 1⁰F/min (before lowering power) and 115 ⁰F and steady when < 17000 amps.

(2) Maintenance (when contacted) – respond as “dispatching personnel to investigate”.



5. CRD high temperature (Pull up OD-7 page) a. Event Trigger – Following Event 4 and when directed by the Lead Examiner, Activate Remote 4 and verify the

following command(s): (1) A02_A05_01_7_TVM=2 (Annunciator 5006-1G CRD Hydr Temp Hi).

b. Role play:

(1) Field Operator (if requested):

a) Report, “CRD 52-25 is alarming at 255°F and rising slowly. All other CRD temperatures appear to be normal”.

b) During coupling check and alarm clears report, “rod 52-25 is 248°F and steady”.

c) After rod 52-25 has been repositioned to position 46, report “CRD 52-25 temperature is 240°F and slowly lowering.

6. Loss of Seal Water to the ‘A’ TDRFP a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 5 and verify the

following command(s): (1) A01_A03_02_1_TVM Steady. (5002-2A Low Press RFP 1A Seal Water)

b. Role play (If requested)

(1) EO (when asked to swap RFP 1A seal water filters) – wait ~ one minute and report that “The RFP 1A seal water inlet filter has been swapped to the STANDBY filter”.

(2) EO (when asked status of local pressure control valve 1TD600A) – report, “1TD600A is operating normally”.

(3) EO (when directed to isolate RFP 1A) – acknowledge the order.

(4) EO (if directed to perform pre-start checks of the A and B RR HPUs before restarting them) – “The A and B RR HPU pre-start checks have been performed sat.”

(5) EO (when directed to restart A and B RR HPUs) – release A and B RR HPU Startup and report, “A and B RR HPU are running”.

(6) Maintenance (when contacted) – respond as “dispatching personnel to investigate”.

7. Steam Packing Exhauster Blower Failure a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 6 and verify the

following command(s): (1) GS1GS02CA_SHEAR. (GS02CA Shaft Shear)


(1) EO (when directed to investigate SPE Blower failure): “The breaker for SPE Blower 1B1 is closed. SPE Inlet Pressure indicates 0 inches of water.”

(2) EO (when directed to report status of Vacuum Breaker Loop Seal) – wait 1 minute and report, “Vacuum Breaker Loop Seal is filled”.

(3) EO (when directed to verify RFP Seal Tank Level) – wait 1 minute and report, “RFP Seal Tank Level is controlling at 10 IN WC”.



8. Clogged CW Pump 1C TW Supply Strainer

a. Event Trigger - Following Event 7 and when directed by the Lead Examiner, Activate Remote 7 and verify the following command(s): (1) A11_A02_03_7_TVM2. (Annunciator 5041-3G, Low Flow CW Pump 1C Brg Seal Water)

b. Role play

(1) EO (when directed to): a) Check CW Pump 1C Seal Water Flow locally – report “CW Pump 1C Seal Water flow is 0

gpm locally.” b) Check CW Pump 1A and/or 1B Seal Water Flow locally – report “Seal water flow is

normal”. c) Flush the CW Pump 1C TW Supply Strainer 1TW 01MC using 1TW605C Strainer Flush

Valve – report “I have completed flushing 1TW01MC. CW Pump 1C Seal Water flow is still 0 gpm locally.”

d) Check operation of the Filtered Water Pumps – report “Filtered Water Pumps are operating normally.”

e) Stop CW Pump Discharge Header – SI Injection {Carrier Water] by performing 3209.01 section 8.2.2 – acknowledge the order.

f) Stop CW Pump Suction Bay – NaOCL Injection by performing 3209.01 section 8.2.1 – acknowledge the order.

g) Verify CW Pump 1C Discharge Valve limit switch position locally – report “1CW001C is closed.”

h) Verify CW Pump 1C shaft has stopped rotating – report “CW Pump 1C shaft is not rotating.”

i) Align [SI] and NaOCl Injection to CW Pump 1A – acknowledge the order. j) Check RPS Solenoid Inverter ‘A’ trouble – “RPS ‘A’ has a “Loss of Sync” LED lit. RPS ‘A’

AC Output Frequency is 60 Hz and AC Voltage is 120 VAC. k) Reset RPS Solenoid Inverter ‘A’ trouble – acknowledge report and then release

YP_XREMT_35 = RESET in the simulator lesson plan.

9. Loss of IA to Cnmt / Multiple Rod Drifts / Unisolable Lower Plenum Leak / DW Failure / ED on Fig. N a. Event Trigger - Following Event 8 and when directed by the Lead Examiner, Activate Remote 8 and verify the

following command(s): (1) A11_A08_S07 Close. (CNMT IA Outbd Isol Vlv 1IA005) (2) LCRPOS for 28-29, 44-17, 20-21, and 48-33. (Selected Rods Drift) (3) YPXMALSE_511 2%. (Plenum Leak) (4) YPCTHOLE 10%. (Hole Between DW and CNMT)

b. Role play

(1) EO (if requested to investigate Steam Bypass EHC skid) – report, “both pump breakers are tripped on overcurrent”. If directed to reset breakers, report “neither breaker will reset”.


10. 3 ADS SRVs Fail To Open

a. Event Trigger – None (1) YPXMALSE_76 (FV = 0). (B21F041F ADS Valve Failure) (2) YPXMALSE_87 (FV = 0). (B21F051G ADS Valve Failure) (3) YPXMALSE_79 (FV = 0). (B21F047A ADS Valve Failure)

b. Role play – None



Turnover


complete. b. Control rods - Step 29 / Gang 10A @ position 8.


• None

3. Today Day Shift


• Calm and clear.


• Power ascension to RTP is in progress IAW CPS 3005.01 Unit Power Changes (but on hold for this shift).

• RE and Rod Verifier are available on request.


• None


• None


• None


• First Priority – Shift Generator Stator Cooling Pumps IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps (MCR).

• Maintain power at 73% throughout shift.

10. Risk Levels




ILT 17-1 NRC Scenario 3 Rev 1 4-03-18 Post Val.Doc Page 1 of 18

Exelon Nuclear

ILT 17-1 NRC Exam


Revision Number: 1

Date: 4/03/18





Facility: Clinton Power Station Scenario No.: 3 Operating Test No.: 2018-301 Examiners: ____________________________ Operators: ____________________ ____________________________ ____________________ ____________________________ ____________________ Initial Conditions: • Mode 1 Rx Power at 78%. • Thunderstorms are expected in the area within the next hour. Turnover: • Perform CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test. • On the previous shift, the Drywell was vented per CPS 3316.01 Containment Combustible Gas Control (HG)

to support performance of CPS 9064.01. • Maintain Rx Power at 78%. Critical Tasks: • SC-1.1 ATC inserts a manual Scram before area temperature reaches max safe in any one area. • RPV-6.2 BOP Inhibits ADS within 105 seconds of RPV level reaching Level 1 (-145.5” Wide Range). • RPV-6.3 BOP terminates and prevents injection from HPCS before RPV level reaches Level 2 (-45.5” Wide

Range). • RPV-6.3 BOP terminates and prevents injection from LPCS and LPCI before RPV level reaches Level 1 (-

145.5” Wide Range).

Event No.


1 N/A N-BOP Drywell Vacuum Breaker Test

2 A05_A02_A0203_5_TVM Steady

C-BOP

TS-SRO

RCIC Suppression Pool Level Transmitter Failure - High

3 ROD0429TFIA3 C-ATC

TS-SRO

Rod drifts outward

4 YPXMALSE_612 I-BOP Turbine Oil Temperature Controller Failure

5 YPXMALSE_528

YPXMALSE_529

C-ATC TS-SRO

RR Pump ‘A’ Seal Failure / Emergency Loop Shutdown and Isolation

6 N/A R-ATC Exit the Controlled Entry Region

7 YARITPLA_1 0.2% XPXMALSE_253

M-All Unisolable leak in RCIC/4 stuck rods will not insert/2nd area exceeds Max Safe/EOP-3 with a low power ATWS

8 YP_XMFTB_4094 C-All Trip of MDRFP





1. Drywell Vacuum Breaker Test Following shift turnover, the SRO will direct the BOP Operator to perform CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.

2. RCIC Suppression Pool Level Transmitter Failure - High Annunciator 5063-3E Suppression Pool Water Level High is received. The crew will recognize that the RCIC suction source failed to automatically shift to the Suppression Pool. The SRO will direct the BOP to transfer RCIC suction to the Suppression Pool IAW CPS 3310.01 Reactor Core Isolation Cooling (RI) section 8.1.9.2 Shifting RCIC Suction to Suppression Pool. The SRO will enter ITS LCO 3.3.5.2 RCIC System Instrumentation A.1, D.1. and (D.2.1 or D.2.2).

3. Rod drifts outward Annunciator ROD DRIFT (5006-4G) comes in due to rod 04-29 drifting outward. The ATC Operator will take the Immediate Actions and applicable Subsequent Actions as directed by the SRO for an Inadvertent Rod Movement per CPS 4007.02 Inadvertent Rod Movement. Rod 04-29 will drift outward until individually scrammed at the Hydraulic Control Unit (HCU). Technical Specification LCO 3.1.3 Actions C.1 and C.2 will be evaluated requiring full insertion of the inoperable control rod in 3 hours and disarming the associated CRD in 4 hours. Technical Specification LCO 3.1.6 Actions A.1 will also be evaluated and found not to apply.

4. Turbine Oil Temperature Controller Failure Annunciator 5018-3A High Temp Turb Gen Lube Oil will be received due to a failure of the auto portion of the Turbine Oil Cooling Water Controller. The BOP will take manual control of the controller and coordinate with the ATC to restore turbine oil temperature to the normal control band.

5. RR Pump ‘A’ Seal Failure / Emergency Loop Shutdown and Isolation The inner and outer seals will partially fail on the ‘A’ RR Pump. Annunciators 5003-4E RECIRC PMP A OUTER SEAL LEAKAGE HI is received, followed by 5003-1K RECIRC PMP MTR A OR B TEMP HI due to rising seal temperatures. CPS 3302.01 Reactor Recirculation (RR), section 8.3.3 Rising Temperature on RR Seals requires the MCR crew to perform an Emergency Loop Shutdown and Isolation of the ‘A’ RR Loop per CPS 3302.01 Reactor Recirculation (RR), sections 8.2.3 RR Loop – Emergency Shutdown and 8.2.4 Idle RR Loop - Isolating. Additionally, the SRO will enter CPS 4008.01 Abnormal Reactor Coolant Flow and ITS 3.4.1 Required Action C.1 Satisfy the requirements of the LCO within 24 hours.

6. Exit the Controlled Entry Region Due to the RR Pump ‘A’ Emergency Loop Shutdown and using CPS 3005.01 Unit Power Changes (Figure 1: Stability Control & Power/Flow Operating Map), the crew will identify a forced entry into the CONTROLLED ENTRY REGION (below the MELLA Limit). The SRO will direct the ATC to promptly exit the CONTROLLED ENTRY REGION via reverse rod sequence or CRAM RODS.

7. Unisolable leak in RCIC/4 stuck rods will not insert/2nd area exceeds Max Safe/EOP-3 with a low power ATWS Annunciator 5065-6F Sec. Cnmt. Area High Temp will be received. The BOP will monitor secondary containment temperatures and will report rising temperatures in the RCIC Pump Room (1TR-CM326 points 8 and 9). When temperatures exceed max normal values, EOP-8 Secondary Containment Control and CPS 4001.01 Reactor Coolant Leakage will be entered. The SRO will direct the RCIC Steam supply to be isolated, but 1E51-F063 RHR & RCIC Stm Supp Inbd Isol Valve will fail to close. Due to the inability to isolate the leak into the RCIC pump room, the SRO will direct the reactor to be scrammed before temperatures in the RCIC Pump Room exceed max safe values. Four control rods will fail to insert requiring entry into EOP-1 RPV Control and then transitioning into EOP-1A ATWS RPV Control. After the reactor is scrammed, the leak into the secondary containment will worsen, causing two areas to exceed max safe values, requiring blowdown per EOP-3 Emergency RPV Depressurization.

8. Trip of MDRFP Per EOP-3 Emergency RPV Depressurization, the SRO will direct RPV injection to be terminated and prevented. Three minutes after starting, the MDRFP will trip. The BOP will initiate ADS and verify that 7 ADS valves open. The operating crew will monitor RPV pressure, and recommence RPV injection with CD/CB IAW CPS 4411.03 Injection/Flooding Sources when RPV pressure reaches 138 psig. The scenario is terminated when reactor power is below 5% and reactor water level is being maintained between -162” and Level 8 (+52”).



Operator Actions


Description: Drywell Vacuum Breaker Test


Cues: None






be referred to. Key Parameter Response: 1HG010A-D and 1HG11A-D indicating lights





Per CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test, tests 1HG010A-D & 1HG011A-D: • Verifies that Drywell Vacuum Relief Valves indicate the expected position of closed. • Tests one valve at a time (required in MODE 1). • During testing verifies each vacuum breaker fully opens (Red light on – green light off) and

then fully recloses (Green light on – red light off). o Report completion of test to the SRO.

SRO • Acknowledges reports from BOP. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

standards and approved procedures.

Terminus: Drywell Vacuum Relief Valve testing complete.

NOTES:





Operator Actions


Description: RCIC Suppression Pool Level Transmitter Failure - High


Cues: 5063-3E Suppression Pool Water Level High


Key Parameter Response: Suppression Pool Water Level Expected Annunciators: 5063-3E Suppression Pool Water Level High Automatic Actions: 1E51-F031, RCIC Suppr Pool Suction Valve OPENS, 1E51-F010, RCIC Suction From RCIC Storage Tank Valve CLOSES (Both automatic actions fail to occur)

ATC • Monitors reactor to ensure operations remain within established bands.


BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports issue to the SRO. • Refers to the ARP for 5063-3E Suppression Pool Water Level High. o Determines that automatic actions to transfer Reactor Core Isolation Cooling (RCIC) suction to

the suppression pool (SP) failed to occur. o MOV Test Prep Switch (RCIC Div 1) may be taken to TEST prior to the operation of 1E51-

F031 & 1E51-F010 motor-operated valves. • When directed, transfers RCIC suction to the SP IAW CPS 3310.01 Reactor Core Isolation

Cooling (RI) section 8.1.9.2 Shifting RCIC Suction to Suppression Pool. • Verifies shut 1E51-F022, RCIC Pmp First Test Valve To Stor Tank. • Verifies shut 1E51-F059, RCIC Pmp Second Test Valve To Stor Tank. • Opens 1E51-F031, RCIC Suppr Pool Suction Valve. • Verifies 1E51-F010, RCIC Storage Tank Suction Valve shuts.

o If Test Prep Switch (RCIC Div 1) was placed in TEST, it should be taken back to NORMAL at the completion of the evolution.


expectations, standards, and approved procedures. o Determines that automatic actions to transfer RCIC suction to the suppression pool failed to

occur. • Evaluates and enters ITS 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System

Instrumentation, RA A.1, D.1, AND D.2.1 or D.2.2 for one or more channels inoperable • Directs BOP to transfer RCIC suction to the SP IAW CPS 3310.01 Reactor Core Isolation

Cooling (RI) section 8.1.9.2 Shifting RCIC Suction to Suppression Pool. o Contacts Maintenance to investigate failure of RCIC suction shift to SP. o Informs the Shift Manager. o Conducts a brief.

o If MOV Test Prep Switch (RCIC Div 1) was placed in TEST, enters ORM 2.5.2 Action 3.5.2. o When MOV Test Prep Switch (RCIC Div 1) is taken back to NORMAL at the completion of the

evolution, exits ORM 2.5.2 Action 3.5.2.

Terminus: RCIC suction shifted to the SP. ITS 3.3.5.2 evaluated.

NOTES:



Operator Actions


Description: Rod drifts outward


Cues: Annunciator 5006-4G, Rod Drift


Key Parameter Response: None Expected Annunciators: 5006-4G, Rod Drift Automatic Actions: None



• Reports issue to SRO. • Monitors reactor to ensure operations remain within established bands.

Per CPS 4007.02, Inadvertent Rod Movement Immediate Actions: • Selects Control Rod 04-29 and fully inserts 04-29 by depressing the In Timer Skip button on

P680. Subsequent actions: • Once Control Rod 04-29 reaches the fully inserted position (00), releases the In Timer Skip

button. • Observes 04-29 rod withdrawal recommences. • Reinserts rod 04-29 with the In Timer Skip button. o Evaluates thermal limits.


• Dispatches an Equipment Operator to the HCU for rod 04-29. • Directs an Equipment Operator to individually scram control rod 04-29. o Evaluates MSL rad monitor values. o Evaluates OG Rad levels.

SRO • Acknowledges reports from ATC/BOP. • Enters Inadvertent Rod Movement, CPS 4007.02. o Establishes critical parameter to monitor for multiple rod drifts. • Directs actions listed above. • Evaluates and enters Technical Specification LCO 3.1.3 action C.1 and C.2. • Evaluates and enters Technical Specification LCO 3.1.5 action A.1 or A.2. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o Informs Shift Manager. o Directs hydraulic isolation of the HCU for control rod 04-29. o Evaluates thermal limits. o Conducts a brief. o Contacts RE for guidance prior to recommencing power ascension.

Terminus: Rod 04-29 is fully inserted, individually scrammed and ITS 3.1.3 & 3.1.5 evaluated.

NOTES:



Operator Actions


Description: Turbine Oil Temperature Controller Failure


Cues: 5018-3A, High Temp Turb Gen Lube Oil


Key Parameter Response: Turbine Lube Oil temperature will rise. Expected Annunciators: 5018-3A, High Temp Turb Gen Lube Oil, 5002-2C High Temp RFPT 1A Brg, 5002-2G High Temp RFPT 1B Brg Automatic Actions: None

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Reports PPC alarm on Bearing Oil from TO Cooler temp. o Dispatches Equipment Operator to investigate. o Checks for excessive temperatures across the turbine bearings. o Monitors turbine bearing vibrations. o Monitors turbine lube oil temperature.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports issue to SRO. • Refers to the ARP for 5018-3A High Temp Turb-Gen Lube Oil. o Dispatches an Equipment Operator to investigate.

Per CPS 5018-3A, High Temp Turb-Gen Lube Oil: • Determines that the Turbine Oil Temperature Controller has failed:

• Places the TURB OIL CLG WTR Controller in MANUAL. • Adjusts (open/close) TCV controller as needed to maintain turbine oil outlet

temperature 110°F to 120°F. o Checks for excessive temperatures across the turbine bearings.

SRO • Acknowledges reports from BOP. • Verifies / directs BOP to take manual control of the TURB OIL CLG WTR Controller to

stabilize turbine oil temperature. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations


Terminus: Turbine Oil Cooling Water Controller in manual and turbine oil temperature stabilized.

NOTES:



Operator Actions


Description: RR Pump ‘A’ Seal Failure / Emergency Loop Shutdown and Isolation


Cues: Annunciator, 5003-4E Recirc Pmp A Outer Seal Leakage Hi, 5003-1K Recirc Pmp Mtr A or B Temp Hi


Key Parameter Response: Rising RR Pump “A” upper seal pressure, then slightly lowering seal pressure in both cavities. Expected Annunciators: 5003-4E Recirc Pmp A Outer Seal Leakage Hi, 5003-1K Recirc Pmp Mtr A or B Temp Hi Automatic Actions: None



• Reports issue to SRO. • Refers to ARPs 5003-4E and 5003-1K.

Per 5003-4E Recirc Pmp A Outer Seal Leakage Hi: • Determines seal condition from DCS seal pressure display (failure of the inner (lower) seal and

partial failure of the outer (upper) seal). o Refers to CPS 3302.01 Reactor Recirculation section 8.3 RR Pump Seal Problems –

Response Actions. Per 3302.01H001 RR Loop/Pump Shutdown and Isolation HARD CARD: • Determines Emergency Loop Shutdown is required due to high RR seal temperatures. • Lowers RPV water level setpoint to ~ 31 inches. • Trips RR Pump 1A by opening any of the following breakers:

o Bkr 3A, 4A or 5A • Shuts 1B33-F067A, RX Recirc Pump 1A Disch Block Valve. Per CPS 4008.01 Abnormal Reactor Coolant Flow: o Monitors RR Pump seal pressure for signs of degradation. o Checks operation on the Power to Flow map. o Determines operation in Controlled Entry Region. o Determines flow transient has resulted in entry into the OPRM Enable Region by observing

the status of annunciator 5006-3D.


o Makes plant announcement. o Determines operation in Controlled Entry Region. o Demands an official 3D Monicore Case.




Description: RR Pump ‘A’ Seal Failure / Emergency Loop Shutdown and Isolation


SRO • Acknowledges report from ATC. • Determines that an Emergency Loop Shutdown of RR Pump 1A is required due to high seal

temperatures (3302.01 step 8.3.1.6) and directs the ATC to perform an emergency loop shutdown of RR Pump 1A.

• Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

• Reviews and enters Tech Spec 3.4.1 B.1 and C.1. • Enters and executes CPS 4100.02 Core Stability Control and directs ATC to scram the

reactor if the restricted zone is entered or if core instabilities are observed. • Enters and executes 4008.01 Abnormal Reactor Coolant Flow. o Informs Shift Manager. o Conducts a brief.

Terminus: RR Pump 1A secured and ITS 3.4.1 evaluated.

NOTES:



Operator Actions


Description: Exit the Controlled Entry Region

Initiation: After securing RR Pump 1A and as directed by the SRO.

Cues: None


Key Parameter Response: Reactor Power, Rod Drive Parameters (flows, dP), Control Rods move as expected

Expected Annunciators: None Automatic Actions: None

ATC • Per CPS 3304.02 Rod Control and Information System (RC&IS), NF-CL-721-1002 Control

Rod Move Sheets, and CPS 3005.01 Unit Power Changes section 8.2: • Reduces reactor power by inserting control rods to exit the Controlled Entry Region

(~ 40%). o Reduces reactor power to < 58% using control rod insertion when directed by SRO

• Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.


SRO • Directs actions listed above • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. • Directs lowering power to exit the Controlled Entry Region using reverse rod sequence or

CRAM Rods within 15 minutes after plant is stable to be in compliance within 2 hours IAW CPS 1005.09M002.

• Positions himself/herself in proximity of the reactor operator, typically the location from which EOP actions are directed (OP-AA-300)

o Notifies Shift Manager o Notifies TSO o Conducts a brief.

Terminus: Clearly observable plant response from change in power level.

Notes:



Operator Actions


Description: Unisolable leak in RCIC/4 stuck rods will not insert/2nd area exceeds Max Safe/EOP-3 with a low power ATWS/Trip of MDRFP

Initiation: Following Event 6 and when directed by the Lead Examiner, activate Remote 5.

Cues: Annunciator 5065-6F Sec. Cnmt. Area High Temp and 5065-5F Sec Cnmt Area High High Temp


Key Parameter Response: Multiple points on 1TR-CM326 and 1TR-CM327 above max safe values of EOP-8 Table T Expected Annunciators: 5065-6F Sec Cnmt Area High Temp, 5004-3F SPDS CSF Alarm Automatic Actions: None

[CT]


EOP-8 Actions o Reports EOP-8 entry on Hi Secondary Containment temperature. o Makes plant announcement to evacuate affected areas.

ATWS Actions • [CT] Initiates a manual reactor scram when directed by the SRO. • Places mode switch in Shutdown • Determines Shutdown Criteria is NOT met (4 control rods will remain at position 48). • Arms and depresses MANUAL SCRAM push-buttons and initiates ARI. • Verifies reactor power is lowering. • Carries out ATWS Scram Choreography by reporting the following:

• Mode Switch in Shutdown, Power is… • Rod status is <Shutdown Criteria is not met>… • Reactor Power is… and trend • Reactor pressure is… and trend • Reactor level is… and trend • Manual Scram and ARI have been initiated • Any EOPs with entry conditions

o Reports Reactor power < IRM Range 7. • Stabilizes RPV pressure <1065 psig. • Lowers RPV pressure to reduce the driving head behind the leak. o Monitors for re-criticality when reducing RPV pressure.

MDRFP Trip Actions o Reports trip of the MDRFP. o Uses CD/CB/TDRFPs to control RPV level -162” to Level 8 or to band prescribed by SRO.

EOP-3 Blowdown Actions o Verifies suppression pool level is above 8 feet.






[CT]

[CT]

[CT]

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Performs EOP actions as directed by SRO.

EOP-8 Actions o Reports EOP-8 entry on Hi Secondary Containment temperature. o Makes plant announcement to evacuate affected areas. • When directed by the SRO, attempts to isolate RCIC steam lines. • Diagnoses and reports failure of 1E51-F063 RHR & RCIC Stm Supp Inbd Isol Valve to close

to the SRO. o Announces Group 1 Isolation of the Main Steam Lines.

ATWS Actions • Performs ATWS scram choreography actions.

• Announces: - Reactor Scram with Failure to Scram - Motor Driven Reactor Feed Pump may start - Evacuate the RCIC room - Evacuate the Containment

• Determines rod status and reports “Shutdown Criteria is not met” to SRO. • Verifies Manual Scram / ARI have been initiated.

• [CT] Terminates and prevents injection of HPCS before RPV level reaches Level 2 (-45.5” Wide Range), when directed by SRO.

• [CT] BOP terminates and prevents injection from LPCS and LPCI before RPV level reaches Level 1 (-145.5” Wide Range), when directed by SRO.

• [CT] Inhibits ADS within 105 seconds of RPV level reaching Level 1 (-145.5” Wide Range), when directed by SRO.

• Starts Hydrogen Mixing Compressors and Igniters.

MDRFP Trip Actions o Reports trip of the MDRFP.

EOP-3 Blowdown Actions o Verifies suppression pool level is above 8 feet. • Terminates and prevents injection from HPCS, LPCS, and LPCI systems • When directed by the SRO, initiates ADS. o Reports 7 SRVs are open. o Initiates Suppression Pool Cooling when directed by the SRO.






[CT]

[CT]

[CT]

[CT]

SRO • Acknowledges reports from ATC/BOP. • Directs actions listed above. • Ensures operations are conducted IAW Operations expectations, standards and approved

procedures. • Directs EOP actions as entry conditions are met.

EOP-8 Actions • Directs RCIC to be isolated. o Diagnoses failure of RCIC to isolate. o Directs evacuating affected areas of Secondary Containment. • [CT] Directs a scram to be inserted prior to exceeding EOP-8 Table T Maximum safe

temperature. o Directs ATC to monitor for re-criticality when lowering RPV pressure. o Notifies Radiation Protection (RP) Department. ATWS Actions • Directs / Verifies:

• Mode switch to SHUTDOWN • Arm and Depress MANUAL SCRAM and ARI pushbuttons

• Carries out ATWS Scram Choreography by performing the following: • Update: • Entering EOP-1 and 8 • Transitioning to EOP-1A • Entering the Scram Off-Normal • End of Update

• [CT] BOP to inhibit ADS within 105 seconds of RPV level reaching Level 1 (-145.5” Wide Range).

• [CT] BOP to terminate and prevent injection of HPCS before RPV level reaches Level 2 (-45.5” Wide Range).

• [CT] BOP to terminate and prevent injection from LPCS and LPCI before RPV level reaches Level 1 (-145.5” Wide Range).

• Control RPV water level between -162” (TAF) and Level 8 (52”). • Exits EOP-1A power leg and controls power per CPS 4100.01 Reactor Scram. o Directs lowering RPV pressure to reduce the driving head of the leak.

EOP-3/MDRFP Trip Actions • Enters EOP-3, Emergency RPV Depressurization, when two areas are above max safe. • Directs initiation of ADS when two EOP-8 Table T areas reach Max Safe temperatures. • Directs reinjection with CD/CB when RPV pressure reaches 150 psig per Table J of EOP-

1A. o Notifies ATC that injecting too fast may damage the core. o Directs ATC to use CD/CB to control RPV level -162” to Level 8. o Informs Shift Manager. o Conducts a brief.

Terminus: The scenario can be terminated when a blowdown has been initiated, RPV level is being maintained between -162” and Level 8 and when directed by the lead examiner.




Initial Setup






6. Verify the following commands are active: • ROD2437TFIA4 • ROD2829TFIA4 • ROD3625TFIA4 • ROD4037TFIA4 • YVRIMVLK_10 • YARIMVFS_9









• CPS 1005.09M002 EOP / OFF-NORMAL PERFORMANCE AID MATRIX • CPS 3005.01 UNIT POWER CHANGES • CPS 3302.01 REACTOR RECIRCULATION (RR) • CPS 3304.02 ROD CONTROL AND INFORMATION SYSTEM (RC&IS) • CPS 3310.01 REACTOR CORE ISOLATION COOLING (RI) • CPS 4001.01 REACTOR COOLANT LEAKAGE • CPS 4001.02 AUTOMATIC ISOLATION • CPS 4007.02 INADVERTENT ROD MOVEMENT • CPS 4008.01 ABNORMAL REACTOR COOLANT FLOW • CPS 4100.01 REACTOR SCRAM • CPS 4100.02 CORE STABILITY CONTROL • CPS 4411.10H001 SLC INITIATION HARD CARD • CPS 4401.01 EOP-1 RPV CONTROL • CPS 4404.01 EOP-1A ATWS RPV CONTROL • CPS 4406.01 EOP-8 SECONDARY CONTAINMENT CONTROL • CPS 4407.01 EOP-3 EMERGENCY RPV DEPRESSURIZATION (BLOWDOWN) • CPS 5002.02 ALARM PANEL 5002 ANNUNCIATORS-ROW 2 • CPS 5003.01 ALARM PANEL 5003 ANNUNCIATORS-ROW 1 • CPS 5003.04 ALARM PANEL 5003 ANNUNCIATORS-ROW 4 • CPS 5004.03 ALARM PANEL 5004 ANNUNCIATORS-ROW 3 • CPS 5006.03 ALARM PANEL 5006 ANNUNCIATORS-ROW 3 • CPS 5006.04 ALARM PANEL 5006 ANNUNCIATORS-ROW 4 • CPS 5018.03 ALARM PANEL 5018 ANNUNCIATORS-ROW 3 • CPS 5063.03 ALARM PANEL 5063 ANNUNCIATORS-ROW 3



• CPS 5065.05 ALARM PANEL 5065 ANNUNCIATORS-ROW 5 • CPS 5065.06 ALARM PANEL 5065 ANNUNCIATORS-ROW 6 • CPS 9064.01 DRYWELL POST-LOCA VACUUM BREAKER VERIFICATION TEST • ITS 3.1 REACTIVITY CONTROL SYSTEMS (LCOs 3.1.3 and 3.1.5) • ITS 3.3 INSTRUMENTATION (LCO 3.3.5.2) • ITS 3.4 REACTOR COOLANT SYSTEM (LCO 3.4.1)





• CPS 3005.01 Unit Power Changes • CPS 9064.01 DRYWELL POST-LOCA VACUUM BREAKER VERIFICATION TEST




Event Triggers and Role Play Event # 1. Drywell Vacuum Breaker Test

a. Event Trigger - None. b. Role play: Provide verifier to MCR (if requested).

2. RCIC Suppression Pool Level Transmitter Failure - High a. Event Trigger - Following Event 1 and when directed by the Lead Examiner, Activate Remote 1 and verify the

following command(s): (1) A05_A02_A0203_5_TVM Steady. (5063-3E Suppression Pool Water Level High)


(1) Maintenance (when directed to investigate failure of RCIC suction to transfer) – report “The IMD shop will not be able to complete repairs for ~ 2 days. We recommend shifting RCIC suction to the Suppression Pool”.

(2) IMD / WEC / Booth (when asked what E51-N636A and 636E are reading) – report “1E51-N636A is reading -8.50” and the trip 1 LED is lit. 1E51-N636E is reading normally with no trip LEDs lit.”

(3) EO (when directed to support RCIC suction shift) – report “I have been briefed and I’m standing by to manually close 1E51-F010 or 31 at your direction”.

3. Rod drifts outward a. Event Trigger – Following Event 2 and when directed by the Lead Examiner, Activate Remote 2 and verify the

following command(s): (1) ROD0429TFIA3. (Rod 04-29 will drift from its position).

b. Role play

(1) No problem lights at the RGDC or RACC

(2) EO (If requested): report “no indications of problem at the HCU”. If directed to hydraulically isolate the HCU, report “1C11-F101 and 1C11-F102 are SHUT”.

(3) RE (If scram times are requested) report “no rods are slow”. If asked for direction (after rod 20-37 has been scrammed) respond “raise power from here with flow”.

(4) Booth Operator (when directed to scram rod 04-29) - Release ‘Single Rod Scram 04-29 and report it completed. When asked, “Accumulator N2 pressure is 1200 psig” after rod is scrammed.

4. Turbine Oil Temperature Controller Failure

a. Event Trigger - Following Event 3 and when directed by the Lead Examiner, Activate Remote 3 and verify the following command(s): (1) YPXMALSE_612. (Oil Temp Controller Fail)

b. Role play (1) EO (if directed to check Turbine Oil Cooler Temperature Control Valve) – “The Turbine Oil Cooler

Temperature Control Valve: a) is shut (if controller is still in AUTO) OR b) looks normal locally (if controller is in MANUAL).”

5. RR Pump ‘A’ Seal Failure / Emergency Loop Shutdown and Isolation (Pull up computer points) a. Event Trigger - Following Event 4 and when directed by the Lead Examiner, Activate Remote 4 and verify the

following command(s): (1) YPXMALSE_528. (RR Pump A Seal A1 Failure). (2) YPXMALSE_529. (RR Pump A Seal A2 Failure).

b. Role play

(1) RE (when contacted about the RR ‘A’ Seal Failure) – “I am on my way to the MCR.”

(2) Booth Operator (if the MCR requests status of B33-R601 Recorder Points) – report the value of computer points RRBA008 and RRBA009 as B33-R601 Recorder Points 8 & 9 respectively.



6. Exit the Controlled Entry Region a. Event Trigger - None

b. Role play

(1) If RE and/or Rod Verifier are requested – report to the MCR as the RE and/or Rod Verifier. (2) If Chief Examiner requires additional power reduction, enter MCR as RE and recommend lowering power an

additional 5% to provide additional margin to the Controlled Entry Region.

7. Unisolable leak in RCIC/4 stuck rods will not insert/2nd area exceeds Max Safe/EOP-3 with a low power ATWS a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 5 and verify the

following command(s): (1) YARITPLA_1 0.2%. (RCIC Drain Pot Leak) (2) YPXMALSE_253. (MS Line A Rupture In Tunnel)

b. Role play: (1) Work Control Supervisor (if requested):

a) RCIC ATM’s read 10 times higher than on the last 9000.01 reading. b) Release Remove QS Relay from ATWS Actions lesson plan. When complete, report that the QS

relay has been removed. (2) Equipment Operator (if requested):

a) Check conditions in the RCIC Pump Room – wait one minute and report, “There is heavy steam in the RCIC Pump room.”

b) Check the breaker for 1E51-F063, wait one minute and report, “The breakers for 1E51-F063 are shut. No problems noted.” If requested, report “the thermal overload button has been depressed”.

c) Release Bypass RD Suction Filter from the ATWS Actions lesson plan. When complete, report that 1C11-F116 & 117 are open.

(3) IMD (if requested): a) Release Defeat VP-WO Interlocks from the ATWS Actions lesson plan. When complete, report that

4410.00C006 Defeating VP/WO Interlocks sections 3.1 – 3.6 is complete.

8. Trip of MDRFP

a. Event Trigger - Three minutes after RFP 1C starts, verify the following command(s): (1) YP_XMFTB_4094. (MDRFP Trip)

b. Role Play (1) Equipment Operator (if requested):

a) Check condition of MDRFP breaker/motor – wait one minute and report, “The MDRFP breaker tripped on phase A overcurrent. No obvious damage to the motor.”

(2) Work Control Supervisor (If requested): a) Report to the MCR to monitor secondary containment temperatures on 1TR-CM326 and 1TR-CM327

on 1H13-P678 Standby Information Panel. Report ONLY information specifically asked for by the SRO.



Turnover


complete. b. Control rods - Step 30 / Gang 10A @ position 32.


• None

3. Today Day Shift


• Calm and clear.


• Maintain Rx Power at 78%. • RE and Rod Verifier are available on request.


• None


• None


• The Drywell was vented per CPS 3316.01 Containment Combustible Gas Control (HG) to support

performance of CPS 9064.01.


• First Priority – Perform CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test. • Maintain Rx Power at 78%.

10. Risk Levels





Exelon Nuclear

ILT 17-1 NRC Exam


Revision Number: 1

Date: 4/03/18





Facility: Clinton Power Station Scenario No.: 4 Operating Test No.: 2018-301 Examiners: ____________________________ Operators: ____________________ ____________________________ ____________________ ____________________________ ____________________ Initial Conditions: • Mode 1 at ~90% power. Power reduction is scheduled in preparation for surveillance testing. • Thunderstorms are expected in the area within the next hour. • Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB) is OOS for maintenance. Not expected back

this shift. • RCIC Surveillance CPS 9054.01 was completed last shift. RHR B is currently in Suppression Pool Cooling to

support the RCIC surveillance and is no longer required. Turnover: • Priorities for the shift are as follows:

• Secure Suppression Pool Cooling per CPS 3312.01 Residual Heat Removal (RHR) Section 8.1.10 – First Priority. NOTE: RHR HX MC layup is being deferred.

• Lower Reactor Power to 85% using rods. Critical Tasks: • Shuts Safety Relief Valves (SRVs) before Suppression Pool temperature reaches 110⁰F. • TSA-1 Initiate ADS (7 SRVs) within 17.5 minutes of blowdown being required (Rx Level at TAF). • RPV-1.2 Maximize injection to restore water level above -160” (TAF).

Event No.


1 N/A N-BOP Secure from Suppression Pool Cooling

2 A05_A02_A0108_3_TVM = 2 A05_A02_A15DS53_1 = Off A05_A02_A15DS54_1 = Off A05_A02_A15DS55_1 = Off A05_A02_A0107_4_TVM = 2

TS-SRO HPCS Water Leg Pump trip

3 CD01PB C-ATC Condensate Pump ‘B’ Trips

4 N/A R-ATC Lower Power using rods

5 YPXMALSE_83 to 50 C-BOP TS-SRO

Inadvertent opening of LLS SRV F047F

6 YPXMALSE_525 C-BOP Packing Leak on 1B33F060A (RR ‘A’ FCV)

7 YP_XMFTB_4964 YP_XMFTB_4092

YP_RR23A YP_RR23B

C-ATC TDRFP ‘A’ trips and FCVs ‘A’ & ‘B’ fail to runback with Auto Scram failure

8 YPXMALSE_511 YAFWL83

YP_XMFTB_4960

M-All Feedwater Leak /RPV Leak to TAF/RCIC trips on start-no reset

9 YP_XMFTB_4948 RH17CON02FSPI=Fail Low C-BOP

RHR ‘B’ Fails To Auto Start RHR ‘B’ Injection Valve 1E12F042B Fails to Auto Open at 472 psig RPV pressure





1. Secure from Suppression Pool Cooling The BOP Operator will secure Suppression Pool Cooling per CPS 3312.01 Residual Heat Removal (RHR) Section 8.1.10 Suppression Pool Cooling - Shutdown.

2. HPCS Water Leg Pump trip Annunciator HPCS WATER LEG PUMP AUTO TRIP (5062-8C) comes in due to the HPCS Water Leg Pump trip. The BOP Operator will dispatch a field operator to investigate. Upon the report of a breaker trip, the BOP operator will direct the field operator to pull the HPCS Pump Breaker control power fuses per CPS 3309.01 High Pressure Core Spray (HPCS) Precaution 4.3. Technical Specification LCO 3.5.1 Actions B.1 and B.2 will be evaluated requiring verification by administrative means that the RCIC system is operable when required AND the HPCS system is restored to operable status within 14 days.

3. Condensate Pump ‘B’ Trips Annunciator 5014-2B Low Pressure Cond Pumps Disch Header comes in due to a trip of the ‘B’ Condensate Pump. The ATC will start the standby Condensate Pump per the ARP. The crew will enter and execute CPS 4002.01 Abnormal RPV Level / Loss of Feedwater At Power to stabilize RPV level. The crew will dispatch an Equipment Operator and/or Maintenance personnel to determine the cause of the trip.

4. Lower reactor power using rods SRO directs the ATC to lower reactor power to ~ 85% at 100 Mwe/hr using rods to support upcoming surveillance testing IAW CPS 3005.01 Unit Power Changes.

5. Inadvertent opening of LLS SRV F047F Annunciators 5066-5B ADS OR SAFETY RELIEF VALVE LEAKING and 5067-8L SRV MONITORING SYSTEM TROUBLE come in due to SRV 1B21-F047F failing ~ 50 % open. The BOP operator will diagnose and determine the problem is with 1B21-F047F. The SRO will direct the BOP operator to sound the containment evacuation alarm and coordinate with the ATC and attempt to close the SRV IAW CPS 4009.01 Inadvertent Opening Safety/Relief Valve. The SRO will enter and execute CPS 4005.01 Loss of Feedwater Heating and direct the ATC to restore and maintain reactor power at or below the original power level. SRV 1B21-F047F will shut when the first fuse is removed for the second solenoid at 1H13-P661/P662. The SRO will evaluate and enter ITS LCO 3.6.1.6 Action A.1 restore LLS valve to operable status within 14 days.

6. Packing Leak on 1B33F060A (RR ‘A’ FCV) A packing leak will develop on the inner packing ring of 1B33F060A RR ‘A’ FCV, causing annunciator 5064-7D LD System Vlv Stem Leakage High Leak Rate to alarm. The ARP directs the BOP to CPS 3315.02 Leak Detection (LD), section 8.2.3 Determining Leakage From Valve Stem Leak Detection. The BOP will determine that the recorder point for 1B33F060A is alarming on 1E31-R612. The SRO will direct the BOP to close the associated solenoid valve for 1B33-F060A (1B33-F308A on MCR backpanel 1H13-P855). When this is accomplished, the leakage from the packing will stop.

7. TDRFP ‘A’ trips and FCVs ‘A’ & ‘B’ fail to runback with Auto Scram failure The ‘A’ Turbine Driven Reactor Feed Pump (TDRFP) trips with a failure of the ‘A’ & ‘B’ Reactor Recirculation Flow Control Valves (FCVs) to runback. The crew enters CPS 4002.01 Abnormal RPV Level/Loss of Feedwater at Power. The ‘B’ TDRFP will pump at maximum capacity and Reactor Pressure Vessel (RPV) level will slowly lower. The ATC will initiate a reactor scram as level is approaching 12” and prior to 8.9” (level 3). Although the ATC is expected to scram the reactor prior to Level 3 (8.9”), an Automatic Scram failure will allow the SRO time to direct the action if required.

8. Feedwater Leak /RPV Leak to TAF/RCIC trips on start-no reset An unisolable feedwater header leak in conjunction with an RPV leak in the lower plenum develops. The RCIC turbine will trip when started (automatically or manually) and cannot be reset. This failure completes a loss of all major high pressure feed sources. Reactor Pressure Vessel (RPV) water level will lower until it reaches Top of Active Fuel (TAF). At that time the CRS will enter EOP-3, blowdown, recover and restore RPV level per EOP-3.

9. RHR ‘B’ Fails To Auto Start / RHR ‘B’ Injection Valve 1E12F042B Fails to Auto Open at 472 psig RPV pressure The RHR ‘B’ Pump will fail to auto start when DW pressure reaches 1.68 psig and will have to be manually started (critical task). In addition, 1E12-F042B RHR ‘B’ Injection Valve will fail to automatically open at 472 psig RPV pressure, requiring the injection valve to be manually opened to recover RPV level above TAF.



Operator Actions


Description: Secure from Suppression Pool Cooling


Cues: None






be referred to. Key Parameter Response: None




BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands o MOV Test Prep Switches (SSW Sys Div 2 and RHR B) may be taken to TEST prior to the

operation of RHR and SSW motor-operated valves.

Per CPS 3312.01, Residual Heat Removal, Step 8.1.10: o Verifies that Suppression Pool Cooling is NOT needed to support operation of Feedwater

Leakage Control System (FWLCS). • Shuts 1E12-F024B, RHR B Test Valve To Suppr Pool. • Stops RHR Pump B, 1E12-C002B. • Opens 1E12-F048B, RHR B Hx Bypass Valve. • Secures SX flow through the RHR HX.

• Shuts 1E12-F068B, RHR B Hx SSW Outlet Valve. • Shuts 1E12-F014B, SSW Inlet RHR B Hx Vlv. • Opens 1SX082B, RHR B HX MU Cond Inlet Vlv to re-establish the normal MC RHR HX

float. o Verifies the secured RHR loop is in STANDBY per CPS 3312.01 section 8.1.1.

EVALUATOR CUE: If attempted, inform candidate that the RHR B loop has been verified “in STANDBY”.

o Verifies/Places the SX loop in STANDBY per CPS 3211.01, Shutdown Service Water.

EVALUATOR CUE: If attempted, inform candidate that the SX B loop has been verified “in STANDBY”.

o If MOV Test Prep Switches (SSW Sys Div 2 and RHR B) were placed in TEST, they should be taken back to NORMAL at the completion of the evolution.



Operator Actions


SRO • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations


o If MOV Test Prep Switches (SSW Sys Div 2 and RHR B) were placed in TEST, enters ORM 2.5.2 Action 3.5.2.

o When Test Prep Switches (SSW Sys Div 2 and RHR B) are taken back to NORMAL at the completion of the evolution, exits ORM 2.5.2 Action 3.5.2.

Terminus: Suppression Pool Cooling secured.

NOTES:





Operator Actions


Description: HPCS Water Leg Pump trip


Cues: Annunciators, 5062-8C HPCS Water Leg Pump Auto Trip and 5062-7D HPCS Water Leg Pump Discharge Pressure

Low



Expected Annunciators: 5062-8C HPCS Water Leg Pump Auto Trip, 5062-7D HPCS Water Leg Pump Discharge Pressure Low


ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Performs Plant Announcements. o Dispatches an Equipment Operator to investigate. o Dispatches an Equipment Operator to remove HPCS pump control power fuses (5062-7B

will alarm and green breaker indicating light will go dark).

BOP • Reports issue to SRO. o Monitors reactor to ensure operations remain within established bands. • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Refers to the ARPs. o Performs Plant Announcements. Per ARP Procedure CPS 5062-8C: o Dispatches an Equipment Operator to investigate. • Informs the SRO of HPCS WLP status and to refer to ITS 3.5.1. Per HPCS CPS 3309.01 precaution 4.3: o Dispatches an Equipment Operator to remove HPCS pump control power fuses (5062-7B

will alarm and green breaker indicating light will go dark).


expectations, standards and approved procedures. • Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2. o Informs Shift Manager. o Conducts a brief. o Contacts Maintenance to investigate.

Terminus: HPCS control power fuses removed and ITS 3.5.1 evaluated.

NOTES:



Operator Actions


Description: Condensate Pump ‘B’ Trips



Key Parameter Response: Lowering RFP Suction Pressure & RPV Level Expected Annunciators: 5014-2B, Low Press Cond Pumps Disch Header Automatic Actions: None


Per 4002.01, Abnormal RPV Level/Loss Of Feedwater At Power o Determines CD Pump ‘B’ has tripped. o Determines Main Condenser Hotwell Level is normal. • Starts the Standby CD Pump (CD Pump ‘A’). • Monitors and reports RPV Level trend and value. o Dispatches Equipment Operator to monitor CD Pump ‘A’ operation and investigate trip of

CD Pump ‘B’.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports annunciator 5014-2B Low Pressure Condensate Pumps Discharge Header to SRO. • Refers to the ARP for 5014-2B. o Determines Main Condenser Hotwell Level is normal. o Dispatches Equipment Operator to monitor CD Pump ‘A’ operation and investigate trip of

CD Pump ‘B’.

SRO • Acknowledges reports from ATC/BOP. o Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

standards and approved procedures. • Enters and executes CPS 4002.01, Abnormal RPV Level/Loss Of Feedwater At Power. o Issues RPV level as a critical parameter and directs ATC to scram the reactor if RPV level

reaches 12” and cannot be recovered. o Informs the Shift Manager. o Conducts a brief.

Terminus: Standby CD pump has been started. RPV Level is restored and stable.

NOTES:



Operator Actions


Description: Lower reactor power using rods

Initiation: Following Event 3 and as directed by the SRO.

Cues: Shift Manager phone call (on Lead Examiner request)

Key Parameter Response: Reactor Power Expected Annunciators: None Automatic Actions: None



Per CPS 3304.02 Rod Control and Information System (RC&IS), NF-CL-721-1002 Control Rod Move Sheets, and CPS 3005.01 Unit Power Changes section 8.2: o Make plant announcement for Power Reduction. • Reduces reactor power using control rod insertion when directed by SRO. o Verifies Power to flow map / Thermal limits – 3D Case

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Make plant announcement for Power Reduction. o Verifies Power to Flow map / Thermal limits – 3D Case

SRO • Acknowledges reports from ATC/BOP. • Directs actions listed above. • Stays in a position of oversight. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. o Verifies Power to Flow map / Thermal limits – 3D Case. o Informs Shift Manager.

Terminus: Clearly observable plant response from change in power level (Reducing power with control rods ~ 5%).

NOTES:



Operator Actions


Description: Inadvertent opening of LLS SRV F047F


Cues: Annunciators 5067-8L, SRV Monitoring System Trouble and 5066-5B, ADS Or Safety Relief Valve Lifting


Key Parameter Response: Reactor Power, RPV Level

Expected Annunciators: 5067-8L, SRV Monitoring System Trouble and 5066-5B, ADS Or Safety Relief Valve Lifting


ATC o Reports issue to SRO. • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per CPS 4005.01 Loss Of Feedwater Heating • Reduces RR flow with FCV(s) as necessary to restore and maintain power at or below the

original power level.

o Reports 1B21-F047F is shut.

[CT]

BOP o Reports issue to SRO. • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands.

Per CPS 4009.01 Inadvertent Opening Safety/Relief Valves: • Sounds the containment evacuation alarm. • (Attempts) to SHUT open SRV (F047F) by placing control switch to OPEN, and then back to

OFF (from 1H13-P601 or P642 control switches as necessary). • [CT] Removes fuses for the “A” and “B” solenoids (for F047F) at panels 1H13-

P661/P662, using Table 1 for fuse location before Suppression Pool temperature reaches 110⁰F.

o Reports 1B21-F047F is shut.

[CT]

SRO • Acknowledges report from ATC/BOP. • Directs actions listed above. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards and approved procedures. • Enters CPS 4009.01 Inadvertent Opening Safety/Relief Valves and CPS 4005.01 Loss Of

Feedwater Heating. • [CT] Directs Removing fuses for the “A” and “B” solenoids (for F047F) at panels

1H13-P661/P662, using Table 1 for fuse location before Suppression Pool temperature reaches 110⁰F.

o Reviews OP-CL-108-104-1001 ITS LCO/ORM OR/ODCM OR Evaluations And Guidance For Safety Function Determination and determines that per section 2.11 Safety Relief Valves Case 6 (One keylock switch in both Divisions in OFF for one SRV required by LCO 3.6.1.6, Low-Low Set Valves) LCO 3.6.1.6 Action A.1 must be entered.

• Evaluates and enters Technical Specification LCO 3.6.1.6 Action A.1. o May review ITS 3.4.4 Safety/Relief Valves (S/RVs) to verify LCO actions are NOT required. o Informs Shift Manager. o Conducts a brief.

Terminus: SRV F047F is SHUT and ITS 3.6.1.6 evaluated.

NOTES:



Operator Actions


Description: Packing Leak on 1B33F060A (RR ‘A’ FCV)


Cues: Annunciator 5064-7D, LD System Vlv Stem Leakage High Leak Rate


Key Parameter Response: 1E31-R612, VLV STEM LEAKAGE RECORDER on 1H13-P855

Expected Annunciators: 5064-7D, LD System Vlv Stem Leakage High Leak Rate

Automatic Actions: None ATC • Monitors reactor to ensure operations remain within established bands


BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands • Reports issue to the SRO. • Refers to the ARP for 5064-7D Leak Detection System Valve Stem Leakage High Leak Rate.

Per 5064-7D Leak Detection System Valve Stem Leakage High Leak Rate: • Determines which valve packing is leaking using 1E31-R612, VLV STEM LEAKAGE

RECORDER on 1H13-P855 per CPS 3315.02, Leak Detection (LD) • Refers to section 8.2.3 Determining Leakage From Valve Stem Leak Detection. • Determines that the alarm is due to packing leakage on 1B33-F060A. o Verifies that less than 6 valve stem leakage solenoid valve switches are in close. • Closes 1B33-F308A (solenoid valve for 1B33-F060A) on P855.

o Informs SRO to refer to ITS LCO 3.4.5 RCS Operational Leakage. o Initiates a Work Request to have the leaking valve repaired.


expectations, standards, and approved procedures. • When it is determined that annunciator is due to packing leakage on 1B33-F060A, directs the

BOP to close 1B33-F308A (solenoid valve for 1B33-F060A) on P855. o Evaluates entering ITS LCO 3.4.5 RCS Operational Leakage (LCO limit is NOT exceeded

during this event). o Evaluates entering CPS 4001.01 Reactor Coolant Leakage. o Informs the Shift Manager. o Conducts a brief.

Terminus: Packing leak on 1B33-F060A is isolated.

NOTES:



Operator Actions

Event No.(s): 7, 8, 9 Page 1 of 3

Description: TDRFP ‘A’ trips and FCVs ‘A’ & ‘B’ fail to runback with Auto Scram failure / Feedwater Leak / RPV Leak to TAF / RCIC trips on start-no reset RHR B Pump Fails To Auto Start / RHR ‘B’ Injection Valve 1E12F042B

Fails to Auto Open at 472 psig RPV pressure Initiation: Following Event 6 and upon direction of the Lead Examiner, insert REMOTE 5.

Cues: (TDRFP Trip) Annunciator 5002-1C Tripped RFPT 1A Turbine, (FCVs Fail To Runback) Annunciators 5003-1D/1E FCV A/B Partial Closure Due To RFP Trip, (FW Leak) Annunciators 5013-3A Trouble VT System Local Panel 1PL74JA and 5013-4E High-High Level Flr/Equip Drn Tank – Turb Bldg; report from Security of hot and humid conditions in the Turbine Building


Key Parameter Response: Trip of ‘A’ Turbine Driven Reactor Feed Pump (TDRFP), Failure of ‘A’ & ‘B’ Reactor Recirculation Flow Control Valves (FCVs) to runback. Rising Main Steam Line Area Turbine Building Temperatures. Rising DW Pressure (multiple points).

Expected Annunciators: Multiple annunciators on 1H13-P601

Automatic Actions: Group 1 isolation. RR FCVs lockout at 1.08 psig; ECCS and DGs actuate at 1.68 psig DW Pressure

[CT]

[CT]

ATC • Monitors reactor to ensure operations remain within established bands o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Reports issues to the SRO. • Places mode switch in Shutdown due to lowering RPV level. • Carries out Scram Choreography by reporting.

− Mode Switch in Shutdown, Power is… − Rod status is… − Reactor Power is… and trend − Reactor pressure is… and trend − Reactor level is… and trend − Any EOPs with entry conditions

EOP-1 Actions • Reports EOP-1 Entry Condition on low RPV Water Level. • Reports RPV level and pressure. • Performs EOP actions as directed by the SRO. o Diagnoses the feedwater leak. o Dispatches an Equipment Operator to investigate feedwater leak. o Secures CD/CB/FW as directed by the SRO. o Coordinates with BOP operator to monitor and control RPV level and pressure. o Starts both trains of SLC, as directed.

EOP-6 Actions o Reports Drywell Pressure rising. • Reports EOP-6 Entry Condition on High Drywell Pressure, High Drywell Temperature, and

High SP Level. • Secures RR Pumps A and B within one minute of DW Pressure reaching 1.68 psig. o Identifies the failure of RHR ‘B’ Pump to auto start and manually starts pump. EOP-3 Actions o When directed, initiates ADS to Blowdown the reactor or verifies that ADS auto initiates at

Level 1. o [CT] Initiates ADS (7 SRVs) within 17.5 minutes of blowdown being required (Rx Level

at TAF). o [CT] Maximizes injection to restore water level above -160” (TAF).

o Verifies LPCS, RHR A and C auto start/inject. o Manually starts RHR B and opens 1E12-F042B.



Operator Actions



Fails to Auto Open at 472 psig RPV pressure Time Position Applicant’s Actions or Behavior

[CT]

[CT]

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands o Reports issues to the SRO. • Carries out Scram Choreography by:

• Making an Announcement − Reactor Scram − Motor Driven Reactor Feed Pump may start − Evacuate the RCIC room − Evacuate the Containment

• Determines Rod status and reports shutdown criteria met to the SRO.

o Reports Group 1 isolation of the main steam lines.

EOP-1 Actions o Dispatches an Equipment Operator to investigate feedwater leak. o Starts both trains of SLC, as directed. o Dispatches an Equipment Operator to reset RCIC.

EOP-6 Actions o Reports Drywell Pressure rising. o Starts Drywell Mixers, as directed. o Starts Containment Spray, as directed. o Secures Containment Spray when RPV water level is ≤ -100 inches WR. • Monitors the start of the ECCS Systems on High Drywell Pressure. • Identifies the failure of RHR ‘B’ Pump to auto start and manually starts pump. EOP-3 Actions o [CT] Initiates ADS (7 SRVs) within 17.5 minutes of blowdown being required (Rx Level

at TAF). o [CT] Maximizes injection to restore water level above -160” (TAF).

o Verifies LPCS, RHR A and C auto start/inject. o Manually starts RHR B and opens 1E12-F042B.

o When level has been restored above TAF, operates ECCS Systems as needed to control RPV Water Level between Level 3 and Level 8.





Fails to Auto Open at 472 psig RPV pressure Time Position Applicant’s Actions or Behavior

[CT]

[CT]


expectations, standards, and approved procedures. • Enters and executes CPS 4002.01 Abnormal RPV Level/Loss of Feedwater at Power. • Enters and executes CPS 4001.01 Reactor Coolant Leakage Off-Normal. • Directs/verifies mode switch in Shutdown (Failure to Auto Scram).

CPS 4100.01 Reactor Scram: • Carries out Scram Choreography by performing an Update:

• Update • Entering EOP-1 and EOP-6 • Entering the Scram Off-Normal • End of Update

EOP-1 Actions • Directs/verifies:

• Control of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs. • Control of RPV Level, Level 3 to Level 8 by using Preferred Injection Systems. o Starting both trains of SLC.

EOP-6 Actions • Directs starting Mixers. o IAW Fig. O directs the start of Containment Sprays (dependent on RPV Level). • If Containment Sprays are running, directs stopping Containment Sprays when RPV level

reaches -100” and lowering. o May direct the isolation of RT and/or RR.

EOP-3 Actions • _____Time -160” WR (TAF) reached. • [CT] Directs Initiating ADS (7 SRVs) within 17.5 minutes of blowdown being required

(Rx Level at TAF). • _____Time 7 SRVs open. • [CT] Directs maximizing injection to restore water level above -160” (TAF).

• Verifies LPCS, RHR A and C auto start/inject. • Verifies RHR B manually started and 1E12-F042B open.

Terminus: 7 SRVs open. RPV level restored above -160” WR (TAF).

NOTES:




Initial Setup






6. Verify the following commands are active: • YP_XMFTB_4948 • RH17CON02FSPI Fail Low






12. Provide pull sheets: Step 30 is current - Gang 10B is at Position 22 AND Gang 10C is at Position 16.



• CPS 3005.01 UNIT POWER CHANGES • CPS 3304.02 ROD CONTROL AND INFORMATION SYSTEM (RC&IS) • CPS 3309.01 HIGH PRESSURE CORE SPRAY (HPCS) • CPS 3312.01 RESIDUAL HEAT REMOVAL (RHR) • CPS 3315.02 LEAK DETECTION (LD) • CPS 4001.01 REACTOR COOLANT LEAKAGE • CPS 4002.01 ABNORMAL RPV LEVEL / LOSS OF FEEDWATER AT POWER • CPS 4005.01 LOSS OF FEEDWATER HEATING • CPS 4009.01 INADVERTENT OPENING SAFETY / RELIEF VALVES • CPS 4100.01 REACTOR SCRAM • CPS 4401.01 EOP-1 RPV CONTROL • CPS 4407.01 EOP-3 EMERGENCY RPV DEPRESSURIZATION (BLOWDOWN) • CPS 4402.01 EOP-6 PRIMARY CONTAINMENT CONTROL • CPS 5002.01 ALARM PANEL 5002 ANNUNCIATORS-ROW 1 • CPS 5003.01 ALARM PANEL 5003 ANNUNCIATORS-ROW 1 • CPS 5013.03 ALARM PANEL 5013 ANNUNCIATORS-ROW 3 • CPS 5013.04 ALARM PANEL 5013 ANNUNCIATORS-ROW 4 • CPS 5014.02 ALARM PANEL 5014 ANNUNCIATORS-ROW 2 • CPS 5062.07 ALARM PANEL 5062 ANNUNCIATORS-ROW 7 • CPS 5062.08 ALARM PANEL 5062 ANNUNCIATORS-ROW 8 • CPS 5064.07 ALARM PANEL 5064 ANNUNCIATORS-ROW 7 • CPS 5066.05 ALARM PANEL 5066 ANNUNCIATORS-ROW 5 • CPS 5067.08 ALARM PANEL 5067 ANNUNCIATORS-ROW 8 • ITS 3.4 REACTOR COOLANT SYSTEMS (LCO 3.4.4, 3.4.5) • ITS 3.5 ECCS AND RCIC SYSTEM (LCO 3.5.1) • ITS 3.6 CONTAINMENT SYSTEMS (LCO 3.6.1.6)



• OP-CL-108-104-1001 ITS LCO/ORM OR/ODCM OR EVALUATIONS AND GUIDANCE FOR SAFETY FUNCTION DETERMINATION

15. Hang OOS tags on:

• Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB)








Event Triggers and Role Play Event # 1. Secure from Suppression Pool Cooling

a. Event Trigger – None b. Role play – None

2. HPCS Water Leg Pump trip a. Event Trigger – Following Event 1 and when directed by the Lead Examiner, Activate Remote 1 and verify the

following command(s): (1) A05_A02_A0108_3_TVM = 2. (Annunciator 5062-8C HPCS Water Leg Pump Auto Trip) (2) A05_A02_A15DS53_1 = Off (HPCS water leg pump Green Lite ON) (3) A05_A02_A15DS54_1 = Off (HPCS water leg pump Amber Lite ON) (4) A05_A02_A15DS55_1 = Off (HPCS water leg pump Red Lite OFF) (5) A05_A02_A0107_4_TVM = 2 (Annunciator 5062-7D HPCS Water Leg Pump Discharge Pressure Low)

b. Role play

(1) EO (when directed to investigate): report “The HPCS WLP motor breaker is tripped. No abnormalities noted at the pump.”

(2) EO (if requested): report “The HPCS WLP motor breaker will not reset.” (3) Maintenance (if requested): respond “Dispatching personnel to investigate.” (4) Work Control Supervisor:

a) (If ATM 1E22-N650 is checked): 1E22-N650 is reading 6 psig. b) (If requested by SRO): RCIC is operable by administrative means.

(5) Booth Operator (when directed to remove HPCS motor breaker control power fuses): a) Release – ‘Remove HPCS Pump Fuses’, and then report, “The HPCS Pump control power fuses have

been removed.”

3. Condensate Pump ‘B’ Trips a. Event Trigger – Following Event 2 and when directed by the Lead Examiner, Activate Remote 2 and verify the

following command(s): (1) CD01PB. (CD Pump CD01PB Motor Failure)


(1) EO (when asked to investigate trip of 1CD01PB, 1B condensate pump) – report “The breaker for the 1CB01PB is tripped, no abnormalities noted at the pump”.

4. Lower reactor power using rods

a. Event Trigger – None b. Role play – None

(1) Shift Manager (if requested by Lead Examiner): “Commence power reduction for surveillance testing as briefed at shift turnover.”

5. Inadvertent opening of a LLS SRV a. Event Trigger – Following Event 4 and when directed by the Lead Examiner, Activate Remote 3 and verify the

following command(s): (1) YPXMALSE_83 to 50 (F047F MS Relief Failure)

b. Role play

(1) Booth Operator (if requested by BOP to cycle the Div 2 SRV switches or remove SRV solenoid fuses): report “There is no extra operators available to perform that/those action(s)”.



6. Packing Leak on 1B33F060A (RR ‘A’ FCV) a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 4 and verify the

following command(s): (1) YPXMALSE_525. (RR01A-F060A FCV Inner Pkg Leak) (2) Role play – None.

7. TDRFP ‘A’ trips and FCVs ‘A’ & ‘B’ fail to runback with Auto Scram failure a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 5 and verify the

following command(s): (1) YP_XMFTB_4964. (RP02 – Auto Scram Failure) (2) YP_XMFTB_4092. (TDRFP A Trip) (3) YP_RR23A. (Fail FCV A In Current Position) (4) YP_RR23B. (Fail FCV B In Current Position)

b. Role play:


8. Feedwater Leak /RPV Leak to TAF/RCIC trips on start-no reset

a. Event Trigger – Two minutes after the RMS has been placed in S/D, verify the following command(s): (1) YPXMALSE_511. (Lower Plenum Leak) (2) YAFWL83. (Feedwater Header Leak To Turbine Bldg Sump) (3) YP_XMFTB_4960. (RCIC Turbine Tripped – when manually or automatically started)

b. Role play :

(1) Booth Operator (30 seconds after activating remote): make an emergency call to the MCR (3329) as a security guard and report “The Turbine Building 800” level is becoming extremely hot and humid”.

(2) EO (when directed to investigate 1PL74JA): report “MCR annunciator due to High Turbine Building Ventilation Supply Air Temperature”.

(3) EO (when directed to investigate Turbine Building): report “The Turbine Building basement has a large amount of steaming water on the floor”.

(4) EO (when directed to investigate RCIC trip): report “The RCIC overspeed trip linkage is tripped”. If directed to reset the overspeed trip linkage, report that the linkage will NOT reset.

(5) ROC (when directed to investigate Floor / Equip Drain Tank status): acknowledge the order and report that you will investigate.

9. RHR ‘B’ Fails To Auto Start / RHR ‘B’ Injection Valve 1E12F042B Fails to Auto Open at 472 psig RPV pressure a. Event Trigger - None:

(1) YP_XMFTB_4948. (RHR B Fail To Auto Start) (2) RH17CON02FSPI Fail Low. (E12F042B Auto-Open Failure)

b. Role play - None



Turnover


complete. b. Control rods - Step 30 / Gang 10B @ position 22 AND Gang 10C @ position 16.


• Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB) is OOS for maintenance. Not expected

back this shift.

3. Today Day Shift


• Thunderstorms are expected in the area within the next hour.


• Power reduction is scheduled in preparation for surveillance testing. • RE and Rod Verifier are available on request.


• None


• None


• CPS 9054.01 RCIC System Operability Check – Completed SAT.


• First Priority – Secure Suppression Pool Cooling per CPS 3312.01 Residual Heat Removal (RHR)

Section 8.1.10 – First Priority. NOTE: RHR HX MC layup is being deferred. • Lower Reactor Power to 85% using rods.

10. Risk Levels





Exelon Nuclear

ILT 17-1 NRC Exam


Revision Number: 1

Date: 4/03/18





Facility: Clinton Power Station Scenario No.: 5 Operating Test No.: 2018-301 Examiners: ____________________________ Operators: ____________________ ____________________________ ____________________ ____________________________ ____________________ Initial Conditions: • Mode 1 at ~10% power. • Weather conditions are calm and clear. • Section 8.3 LPCS Operability/WLP Double Check Valve Test of CPS 9052.01 LPCS/RHR A PUMPS &

LPCS/RHR A Water Leg Pump Operability is in progress. An extra equipment operator is briefed, staged and ready to provide field support. LPCS is inop per ITS LCO 3.5.1 due to 1E21-F012 being open.

Turnover: • CPS 3002.01 Heatup and Pressurization is complete. • CPS 3004.01 Turbine Startup and Generator Synchronization is in progress. Section 5.0 Prerequisites are

complete. Steps 8.1.1 – 8.1.5 are complete. • On Step 8. Gang 4A is at position 24. • Priorities for the shift are as follows:

• Complete the LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability starting at step 8.3.11.

• Continue with power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. The RE has requested single rod, single notch rod motion.

• After reaching 15% power, perform Turbine Roll IAW Step 8.1.8 of CPS 3004.01. Critical Tasks: • Starts the standby Service Air Compressor before 5006-2H Rod Out Block or 5006-4G Rod Drift annunciators

are received. • PC-3.1, SCRAMs the reactor before suppression pool level lowers to less than 15’ 1”. • PC-3.3, Enters EOP-3 prior to suppression pool level reaching 15’1” and performs an emergency

depressurization. If the suppression pool level lowers to less than 15’1” after the announcement is made to enter EOP-3, but before the blowdown is initiated, then this critical task is considered to be met.

Event No.


1 N/A N-BOP LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability

2 NA R-ATC Raise power with rods to 15%.

3 Rod2025TFIA4 C-ATC Control Rod difficult to withdraw

4 ROD2025TFIA5 C-ATC

TS-SRO Uncoupled Rod

5 ROD4413TFIA6 TS-SRO CRD HCU Accumulator Trouble (Rod 44-13)

6 SA01B1SA1CFO SA01B0SA1CFTC C-BOP #1 SA Compressor trips with failure of Standby

Compressor to Auto Start

7 A05_A02_A0706_3_TVM C-BOP CRD Pump High Seal Leakage / Pump Shift

8 YPXMALSE_665 100% YPXMALSE_666 100% M-All Suppression Pool leak into the LPCS Room/RHR

‘A’ Pump Room

9 A05_A02_A09S38_2=ON A05_A02_A16DS60_1=OFF A05_A02_A16DS61_1=OFF

C-All 1E21F001 LPCS Suppr Pool Suction Valve fails to close





1. LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability The SRO directs BOP to complete the LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability starting at step 8.3.11. The BOP Operator will exercise the 1E21-F012 LPCS Test Valve to Suppr Pool, verify the 1E21-F011 LPCS Pump Min Flow Valve opens and stop the LPCS Pump (1E21-C001). Additionally, the BOP will verify closure of the 1E21-F303 and 1E12-F003 check valves and reposition the LPCS MOV TEST PREP and LPCS OUT OF SERVICE switches prior to field restoration.

2. Raise power with rods to 15% The crew will continue the power ascension to 15% by withdrawing control rods in accordance with CPS 3004.01 Turbine Startup and Generator Synchronization.

3. Control Rod difficult to withdraw Control Rod 20-25 will not withdraw when using normal drive differential pressure. The crew will perform actions for a difficult to withdraw control rod IAW CPS 3304.01 Control Rod Hydraulic & Control (RD) Section 8.3.4 Control Rod Difficult to Withdraw. When drive dP is increased to 300 psid, the control rod withdrawal will be successful, allowing the power ascension to continue.

4. Uncoupled rod When the first in-sequence control rod (20-25) reaches position 48, the ATC will perform a coupling check IAW CPS 3304.02 Rod Control And Information System (RC&IS) section 8.1.10 Coupling Check by applying a continuous withdraw to the rod at position 48. Annunciator 5006-5G Rod Overtravel will be received, indicating that the control rod has become uncoupled from its drive mechanism. The operating crew will attempt to recouple the control rod IAW the annunciator response procedure. The SRO will evaluate and enter ITS 3.1.3 Condition C until the control rod is successfully recoupled.

5. CRD HCU Accumulator Trouble (Rod 44-13) Annunciator ACCUMULATOR TROUBLE (5006-1H) is received. The ATC will determine which accumulator is alarming by depressing the ACCUM FAULT button. The ATC will then acknowledge the accumulator fault to clear the annunciator so another fault will cause an alarm. An Equipment Operator (EO) will be dispatched into the containment to determine the cause of the alarm (high level or low pressure). The EO will report that the accumulator for rod 44-13 is at 1540 psig. IAW 5006-1H, the SRO will declare the accumulator inoperable and will enter TS 3.1.5 Action A.1 or A.2. The SRO will consult with the RE to determine the number of control rods that are slow (0). The ATC/BOP will direct the Equipment Operator (EO) to recharge the accumulator for control rod 44-13.

6. #1 SA Compressor trips with failure of Standby Compressor to Auto Start Annunciator 5041-1A AUTO TRIP PUMP/MOTOR is received due to a trip of the #1 Service Air Compressor (1SA01C). The SRO will enter CPS 4004.01 Instrument Air Loss and direct the BOP to start the standby Service Air Compressor (0SA01C). If the crew fails to manually start 0SA01C, the air compressor will fail to automatically start to restore air pressure.

7. CRD Pump High Seal Leakage / Pump Shift Annunciator 5068-6C, CRD Pump C001B Seal Leakage High is received. The BOP operator will dispatch an Equipment Operator to determine the status of the B CRD Pump Seals. The Equipment Operator will report that the ‘B’ CRD Pump seals are spraying water on the floor around the pump. The BOP operator will shift to the ‘A’ CRD Pump per CPS 3304.01 Control Rod Hydraulic & Control (RD) section 8.1.2 Shifting Drive Water Pumps and then shutting 1C11-F017 Cross Connect Valve to isolate the seal leak.

8. Suppression Pool leak into the LPCS Room/RHR ‘A’ Pump Room IMD technicians (performing restoration activities for CPS 9052.01 in the LPCS Pump Room) report a Suppression Pool Leak (due to a leak in the LPCS Pump Suction piping) including cross-flooding into the RHR ‘A’ Pump Room. The crew will determine that the leak is isolable, but efforts at closing 1E21-F001 LPCS Suppr Pool Suction Valve will fail (breaker trips on overcurrent when the control switch is taken to close). The SRO will determine that Suppression Pool level cannot be maintained above 15’1” requiring the reactor to be scrammed and an Emergency Depressurization performed.

9. 1E21-F001 LPCS Suppr Pool Suction Valve fails to close When the BOP attempts to close 1E21-F001 to isolate the suction piping leak in event 8, the breaker will trip resulting in loss of indicating lights and the inability to operate the valve from the MCR.



Operator Actions


Description: LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability


Cues: None






be referred to. Key Parameter Response: LPCS Pump Amps, LPCS Pump Flow Expected Annunciators: None Automatic Actions: None



CPS 9052.01, LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability Commencing at Step 8.3.11 Exercising 1E21-F012 LPCS Test Valve To Suppr Pool: • Verifies 1E21-F012, LPCS Test Valve To Suppr Pool Open. • Shuts 1E21-F012, LPCS Test Valve To Suppr Pool. • Verifies 1E21-F011, LPCS Pump Min Flow Recirc Valve opens. • Stops LPCS Pump, 1E21-C001. • Places LPCS MOV TEST PREP switch in NORM.

• Verifies LPCS MOVS IN TEST status light deenergizes. • Reports LPCS MOV TEST PREP switch status to SRO.

• Returns LPCS OUT OF SERVICE switch to NORM. • Verifies LPCS OUT OF SERVICE status light deenergizes. • Verifies LPCS OUT OF SERVICE annunciator (5063-8H) is clear.

• Verifies close exercise of 1E21-F003, LPCS Pump Disch Check Valve by observing LPCS PUMP DISCHARGE PRESS ABNORMAL 5063-3G is cleared.




Description: LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability




• Exits ORM 2.5.2. o Exits LCO ITS 3.5.1 A.1.

Terminus: LPCS pump secured, LPCS MOV TEST PREP switch in NORM and LPCS OUT OF SERVICE switch in NORM. NOTES:





Operator Actions


Description: Raise power with rods to 15% / Control Rod Difficult To Withdraw / Uncoupled Rod

Initiation: Following Event 1 and upon direction of the SRO

Cues: Annunciator 5006-5G Rod Overtravel, Control Rod 20-25 fails to move when withdraw signal is applied.


Key Parameter Response: Reactor power, Rod drive parameters (flow, dP), control rod position, Bypass Valve Position, rod uncoupled light on P680 OCM for control rod 20-25,

Expected Annunciators: 5005-2K SRM Period, 5006-5G Rod Overtravel



Reactivity Maneuver

Per CPS 3004.01 Turbine Startup and Generator Synchronization, NF-CL-721-F-2 Control Rod Move Sheets and CPS 3304.02 RCIS: • Withdraws control rods (beginning with 20-25 from position 24 per the control rod

sequence to raise power. • Monitors nuclear instruments during rod movement. o Monitors the Power to Flow Map during power ascension. • Performs a Coupling Check for any control rod(s) withdrawn to position 48.

Control Rod Difficult To Withdraw

• Determines control rod 20-25 will not withdraw with normal drive water differential pressure.

• Informs SRO that 20-25 will not withdraw using normal drive water differential pressure.

Per CPS 3304.01, Control Rod Hydraulic & Control (RD), Section 8.3.4: • Increases Drive Water Diff Press in ~ 50 psid increments to a maximum of 500 psid by

throttling closed on C11-F003, CRD Press Control Valve to achieve the desired differential pressure (if BOP attempts to perform, evaluator shall provide a cue to ATC to perform the drive differential pressure adjustment).

• Attempts to withdraw rod 20-25 using normal notch withdrawal. o Logs Drive Water Flow and Drive Water Diff Press. o Returns Drive Water Diff Press to normal (235 – 265 psid) using C11-F003 (will probably

be performed by BOP).

Uncoupled Rod

Per CPS 3304.02 Rod Control And Information System, section 8.1.10 Coupling Check: • After 20-25 is withdrawn to position 48, applies a continuous withdraw signal to verify rod

coupling. • Observes 5006-3G Rod Overtravel is received. • Observes red full-out light for 20-25 goes out. • Determines control rod 20-25 is uncoupled by pressing the ROD UNCOUPLED button

on the P680 OCM. • Informs SRO that 20-25 is uncoupled and to refer to ITS 3.1.3.




Description: Raise power with rods to 15% / Control Rod Difficult To Withdraw / Uncoupled Rod


ATC (cont.)

Per CPS 3304.02 Rod Control And Information System, section 8.2.6:

• Verifies that the INDIVID DRIVE light is energized on the OCM. If not, selects individual drive by depressing DRIVE MODE push-button.

• Inserts the drive 1 or 2 notches (position 46 or 44) in an attempt to recouple the rod. • Fully withdraws the drive. • Performs the coupling check and determines that the rod is recoupled. o Initiates an Issue Report and contacts the Reactor Engineer regarding the uncoupled rod

event.


Reactivity Maneuver o Monitors the Power to Flow Map during power ascension.

Control Rod Difficult To Withdraw

Evaluator NOTE - If BOP attempts to adjust drive water differential pressure, cue the BOP to allow ATC to perform the drive water differential pressure adjustment.

o Throttles C11-F003 to restore drive water differential pressure to normal (235 – 265 psid) after control rod is successfully withdrawn (may be performed by ATC).

o Logs Drive Water Flow and Drive Water Diff Press.

Uncoupled Rod o Initiates an Issue Report and contacts the Reactor Engineer regarding the uncoupled rod

event.


expectations, standards and approved procedures. o Informs Shift Manager. o Conducts a brief.

Reactivity Maneuver • Directs ATC to raise power to 15%. • Maintains oversight during control rod movement; positioned in proximity to the ATC (typically

from the SRO desk).

Control Rod Difficult To Withdraw • Verifies / directs ATC to perform CPS 3304.01 Control Rod Hydraulic and Control (RD)

section 8.3.4 Control Rod Difficult To Withdraw.

Uncoupled Rod • Verifies / directs ATC to attempt to recouple rod 20-25. • Enters ITS 3.1.3 Action C.1 and C.2 to fully insert control rod 20-25 within 3 hours and disarm

20-25 within 4 hours. • Exits ITS 3.1.3 Action C.1 and C.2 when 20-25 is successfully recoupled. o Directs continuing startup.

Terminus: Clearly observable plant response from change in power level, successful withdrawal of control rod 20-25, rod drive dP restored to normal (235 – 265 psid) and control rod 20-25 recoupled and returned to position 48.

NOTES:



Operator Actions


Description: CRD HCU Accumulator Trouble

Initiation: Following Event 4 and upon direction of the Lead Examiner, insert REMOTE 1

Cues: Annunciator, 5006-1H Accumulator Trouble


Key Parameter Response: Control rod 44-13 accumulator pressure

Expected Annunciators: 5006-1H Accumulator Trouble

Automatic Actions: None ATC • Reports issue to SRO.

• Refers to ARP 5006-1H. • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per 5006-1H Accumulator Trouble:

• Depresses ACCUM FAULT button to determine which HCU is alarming. • Determines and reports the accumulator fault is on rod 44-13. • Depresses the ACKN ACCUM FAULT button to clear alarm 5006-1H. o Dispatches an Equipment Operator to the containment to check CRD HCU accumulator

pressure for control rod 44-13. o Directs the Equipment Operator to recharge the HCU for control rod 44-13.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Dispatches an Equipment Operator to the containment to check CRD HCU accumulator

pressure for control rod 44-13. o Monitors CRD system parameters on P601 (charging water header pressure, pump status,

etc.) o Directs the Equipment Operator to recharge the HCU for control rod 44-13.


expectations, standards and approved procedures. • Reviews TS 3.1.5 when the Equipment Operator reports that the accumulator for control rod

44-13 is at 1540 psig. Enters ITS 3.1.5 Action A.1 or A.2. o Contacts the Reactor Engineer to determine how many control rods are slow (0). Reviews

TS 3.1.4 to determine no additional actions required by Tech Specs. o Informs Shift Manager. o Conducts a brief.

Terminus: Technical Specifications evaluated.

NOTES:



Operator Actions


Description: Service Air Compressor (SAC) trip / failure of the standby SAC to auto start Initiation: Following Event 5 and upon direction of the Lead Examiner, insert REMOTE 2.

Cues: Annunciator 5041-1A, Auto Trip Pump/Motor


Key Parameter Response: SA header pressure decreases, 1SA01C amber trip light energized

Expected Annunciators: 5041-1A Auto Trip Pump/Motor


ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Dispatches Equipment Operator to investigate.

Per CPS 4004.01 Instrument Air Loss: o IF air pressure lowers to 60 psig and cannot be restored, or SDV level increases resulting in

a rod block, or any control rod begins to drift, THEN turn mode switch to SHUTDOWN (CRITICAL TASK FAILURE).

[CT]

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Determines that 1SA01C has tripped. • Reports issue to SRO. • Refers to the ARP for 5041-1A.

Per 5041-1A AUTO TRIP SERVICE AIR COMPRESSOR and CPS 4004.01 Instrument Air Loss: • [CT] Starts the standby Service Air Compressor before 5006-2H Rod Out Block or

5006-4G Rod Drift annunciators are received. • Monitors SA Header Pressure. o Dispatches Equipment Operator to investigate cause of trip.

[CT]

SRO • Acknowledges report from BOP. • Ensures operations are conducted within the bounds of Tech Specs and IAW Operations

expectations, standards, and approved procedures. • Enters and executes CPS 4004.01 Instrument Air Loss. • [CT] Directs/verifies start the standby Service Air Compressor before 5006-2H Rod

Out Block or 5006-4G Rod Drift annunciators are received. • Directs actions listed above. o Informs Shift Manager. o Contacts Maintenance to investigate. o Conducts a brief.

Terminus: 0SA01C running and maintaining SA header pressure.

Notes:



Operator Actions


Description: CRD Pump High Seal Leakage / Pump Shift

Initiation: Following Event 6 and upon direction of the Lead Examiner, insert Remote 3.

Cues: Annunciator 5068-6C CRD Pump C001B Seal Leakage High


Key Parameter Response: None. Expected Annunciators: 5068-6C CRD Pump C001B Seal Leakage High Automatic Actions: None


o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Dispatches an Equipment Operator to investigate seal leakage alarm on CRD Pump ‘B’. o Notifies Radiation Protection of the potential spill. o Communicates annunciator 5068-6C to the SRO.

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. o Communicates annunciator 5068-6C to the SRO. • Refers to ARP 5068-6C CRD Pump C001B Seal Leakage High.

Per CPS 5068-6C, CRD Pump C001B Seal Leakage High: • Swaps running CRD Pumps per CPS 3304.01 Control Rod Hydraulic and Control (RD).

Per CPS 3304.01 Control Rod Hydraulic and Control (RD), 8.1.2 Shifting Drive Water Pumps: • Directs an Equipment Operator to perform prestart local actions. • Directs the Equipment Operator to shut/verify shut 1C11-F014A Pump A Stop Chk Discharge

Valve. • Starts standby CRD Aux Oil Pump & allows AOP to run for 1 minute. • Directs the Equipment Operator to verify oil pressure is ≥ 3 psig. • Starts the standby CRD Pump A, 1C11-C001A. • Verifies CRD Pump is running and Aux Oil Pump has auto stopped. • Directs the Equipment Operator to verify gear increaser oil pressure is between 20 and 30

psig. • Directs the Equipment Operator to slowly open 1C11-F014A, Pump A Stop Chk Discharge

Valve. • Directs the Equipment Operator to slowly throttle close 1C11-F014B until:

1) On-coming pump A amperage increases to > off-going pump’s amperage. 2) 1C11-F014B reaches ≤ 25% open.

• Stops the off-going CRD Pump B, 1C11-C001B • Directs the Equipment Operator to fully shut the off-going CRD Pump B discharge valve 1C11-

F014B. • Directs the Equipment Operator to perform post startup local actions. • Directs Equipment Operator to close 1C11-F017, Cross Connect valve. o Notifies Radiation Protection of the potential spill.




Description: CRD Pump High Seal Leakage / Pump Shift



expectations, standards, and approved procedures. • Enters and executes CPS 4979.06 Radioactive Spill. o Informs the Shift Manager. o Conducts a brief. o Contacts Maintenance to investigate.

Terminus: CRD Pumps shifted and 1C11-F017 Cross-connect Valve is shut.

Notes:



Operator Actions


Description: Suppression Pool leak into the LPCS Room & RHR ‘A’ Pump Room / 1E21-F001 LPCS Suppr Pool Suction Valve fails to close

Initiation: Following Event 7 and upon direction of the Lead Examiner, insert Remote 4.

Cues:


Key Parameter Response: Suppression pool level. Expected Annunciators: 5064-7C ECCS Floor Drain Sump High Leak Rate, 5013-5D High-High Level Floor/Equipment Drain Sump – Auxiliary Building, 5065-5G Sec Cnmt Area Max Safe Oper Water Level, 5013-6D High-High Level Floor/Equipment Drain Sump – Fuel Building Automatic Actions: First sump pump auto starts on sump high level and the backup pump will auto start on Hi-Hi sump level.

[CT]

[CCT]

ATC • Monitors reactor to ensure operations remain within established bands. o Monitors control room panels, notifies the SRO of unusual/unexpected conditions. • Reports issues to SRO. • Diagnoses rising LPCS room sump levels and RHR ‘A’ room sump levels using PPC. o Evacuates affected areas of Secondary Containment. • Observes and reports entry condition for EOP-8 Secondary Containment Control on Floor

Drain Sump above Max Normal. • Observes and reports entry condition for EOP-6 on Suppression Pool Low Level. o Dispatches an Equipment Operator to investigate leakage into the LPCS & RHR ‘A’ Pump

Rooms. • [CT] SCRAMs the reactor before suppression pool level lowers to less than 15’ 1”.

• Carries out Scram Choreography by reporting the following: • Mode Switch in shutdown, power is… • Rod Status is… • Reactor Power is … and trend • Reactor pressure is… and trend • Reactor water level is………and trend. • Any EOPs with entry conditions (no values required).


• Verifies reactor power is lowering • Verifies SHUTDOWN CRITERIA met

• IF RPV level is rising with 2 feed pumps operating, THEN secures/verifies secured 1 feed pump and controls RPV water level Level 3 to Level 8.

• Verifies and stabilizes Turbine and Generator trip when required. • Stabilize Reactor pressure 800 to 1065 psig or per directed band. • Performs EOP actions as directed by the SRO. o [CCT] Rapidly depressurizes the RPV (anticipates blowdown) by opening all Turbine

Bypass Valves when directed by the SRO (may be performed by BOP).






[CT]

BOP • Monitors control room panels, notifies the SRO of unusual/unexpected conditions. o Monitors reactor to ensure operations remain within established bands. • Reports issues to SRO. o Reports EOP entry conditions. • Perform EOP actions as directed by SRO. o Evacuates affected areas of Secondary Containment. o Dispatches an Equipment Operator to investigate leakage into the LPCS & RHR ‘A’ Pump

Rooms.

o Reports to the SRO that the LPCS leak is between 1E21-F001 LPCS Suppr Pool Suction Valve and the LPCS Pump (isolable).

• As directed by SRO, attempts to isolate the LPCS suction line by closing 1E21-F001 LPCS Suppr Pool Suction Valve.

• Recognizes failure of the 1E21-F001 to close and reports failure to the SRO.

• As directed by SRO, holds SP Level above 15’ 1”: • by filling the SP IAW CPS 3220.01 / CPS 3318.01 • by dumping upper pools IAW CPS 4411.03


Reactor Scram MDRFP may start Evacuate the RCIC room Evacuate the Containment

• Determines Rod status and reports to the CRS

• [CT] Initiates ADS when directed by the SRO. • Verifies 7 ADS valves open






[CT]

[CCT]

[CT]


expectations, standards, and approved procedures.

Enters and executes CPS 4304.01 Flooding. o Dispatches area operators to locate and isolate source of flooding. o Notifies ROC and RP of flooding source and magnitude. • Determines that the flooding source is from the suppression pool into the LPCS & RHR ‘A’

Pump Rooms and cannot be isolated (after failure of 1E21-F001 to close). • Reviews 4304.01 Table 2: Suppression Pool Leak / ECCS Room Equalization Levels and

determines that final suppression pool level will be below 15’1”.

Enters and executes EOP-8 Secondary Containment Control: • Directs BOP to shut 1E21-F001 LPCS Suppression Pool Suction Valve.

Enters and executes EOP-6 Primary Containment Control: • Directs BOP to hold Suppression Pool Level above 15'1" using normal suppression pool

makeup methods (SM per 3220.01, SF per 3318.01) • Determines that SP Level cannot be maintained above 15'1" • Directs BOP to dump the upper containment pools. • [CT] Directs scramming the reactor before suppression pool level lowers to less than

15’ 1”.

Carries out Scram Choreography by performing an Update: • Update • Entering EOP- 6 and 8. • Entering Scram Off-Normal. • End of Update.

Enters and executes EOP-1 RPV Control and directs/verifies performance of the following: • Mode Switch to SHUTDOWN • Shutdown criteria verified • Establishes an RPV water level band between Level 3 and Level 8. • Establishes an RPV pressure band below 1065 psig. o [CCT] Anticipates doing blowdown. Directs ATC to depressurize the RPV rapidly by

fully opening the main turbine bypass valves.

Enters and executes EOP-3 Emergency RPV Depressurization (Blowdown) prior to suppression pool level reaching 15’1” and directs the following: • Sounds the containment evacuation alarm. • Verifies that Suppression Pool Level is above 8 ft. • [CT] Initiates ADS.

o Informs the Shift Manager. o Conducts a brief.

Terminus: ADS initiated, RPV level maintained per EOP-1.

NOTES:




Initial Setup



3. Simulator key count: ______ keys (one key in LPCS Test Prep Switch).



6. Verify the following commands are active: • ROD2025TFIA4








14. Make sure Individual Drive Mode is selected on the OCM.


• CPS 3002.01 HEATUP AND PRESSURIZATION • CPS 3004.01 TURBINE STARTUP AND GENERATOR SYNCHRONIZATION • CPS 3304.01 CONTROL ROD HYDRAULIC & CONTROL (RD) • CPS 3304.02 ROD CONTROL AND INFORMATION SYSTEM (RC&IS) • CPS 4004.01 INSTRUMENT AIR LOSS • CPS 4100.01 REACTOR SCRAM • CPS 4304.01 FLOODING • CPS 4401.01 EOP-1 RPV CONTROL • CPS 4402.01 EOP-6 PRIMARY CONTAINMENT CONTROL • CPS 4406.01 EOP-8 SECONDARY CONTAINMENT CONTROL • CPS 4979.06 RADIOACTIVE SPILL • CPS 5005.02 ALARM PANEL 5005 ANNUNCIATORS-ROW 2 • CPS 5006.01 ALARM PANEL 5006 ANNUNCIATORS-ROW 1 • CPS 5006.05 ALARM PANEL 5006 ANNUNCIATORS-ROW 5 • CPS 5013.05 ALARM PANEL 5013 ANNUNCIATORS-ROW 5 • CPS 5013.06 ALARM PANEL 5013 ANNUNCIATORS-ROW 6 • CPS 5041.01 ALARM PANEL 5041 ANNUNCIATORS-ROW 1 • CPS 5063.03 ALARM PANEL 5063 ANNUNCIATORS-ROW 3 • CPS 5063.08 ALARM PANEL 5063 ANNUNCIATORS-ROW 8 • CPS 5064.07 ALARM PANEL 5064 ANNUNCIATORS-ROW 7 • CPS 5065.05 ALARM PANEL 5065 ANNUNCIATORS-ROW 5 • CPS 5068.06 ALARM PANEL 5068 ANNUNCIATORS-ROW 6 • CPS 9052.01 LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability • CPS 9052.01D001 LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability Data Sheet • ITS (3.1) REACTIVITY CONTROL SYSTEMS (LCOs 3.1.3, 3.1.4, 3.1.5)







• CPS 3004.01 Turbine Startup and Generator Synchronization • CPS 9052.01 LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability • CPS 9052.01D001 LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability Data Sheet




Event Triggers and Role Play Event # 1. LPCS Operability IAW CPS 9052.01 – LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability

a. Event Trigger – None. b. Role play :

(1) Provide Extra Operator for Independent Verifications (if requested). (2) EO (If requested)

a) Report “On station and standing by to support performance CPS 9052.01.” b) (When directed to perform step 8.3.14) – report “Step 8.3.14 Verify closure of 1E21-F303, LPCS Suppr

Pool Rtn Chk Valve is complete – SAT. I will be up in the MCR in about an hour to sign off the step.” (3) IMD (If requested)

a) (When directed to perform step 8.3.19) – acknowledge order, and report “I will come up to the MCR to sign off the step, once field work is complete.”

2. Raise Power with flow to ~ 15% a. Event Trigger – None b. Role play

(1) Booth Operator – (when RE and/or Rod Verifier requested) – report to the MCR as the RE and/or Rod Verifier.

3. Control Rod Difficult To Withdraw a. Event Trigger – None b. Role play

(1) System Engineer (if asked about the performance / maintenance history of control rod 20-25) – “The seals for rod 20-25 were NOT replaced during the last outage. There are no previous problems noted in the history file for 20-25.”

4. Uncoupled Rod

a. Event Trigger – None b. Role play

(1) Booth Operator - When control rod 20-25 is inserted from position 48, verify Delete ROD2025TFIA5 is inserted (Delete Rod 20-25 Malfunction).

5. CRD HCU Accumulator Trouble

a. Event Trigger - Following Event 4 and when directed by the Lead Examiner, insert Remote 1 and verify the following command(s): (1) ROD4413TFIA6. (Rod 44-13 Accumulator Trouble)

b. Role play: (1) EO (when asked to check accumulator for rod 44-13): “The accumulator pressure for control rod 44-13 is 1540

psig.” (2) EO (when directed to recharge accumulator for control rod 44-13): “Recharge accumulator for control rod 44-

13”.

a) Release – ‘Recharge 44-13 Accumulator’, wait 5 minutes and then report “the accumulator for control rod 44-13 has been recharged to 1,750 psig”.

b) RE (when asked how many slow control rods exist): “There are no (zero) slow control rods”.



6. #1 SA Compressor trips with failure of Standby Compressor to Auto Start a. Event Trigger – Following Event 5 and when directed by the Lead Examiner, insert Remote 2 and verify the following

command(s): (1) SA01B1SA1CFO. (SA Compr 0 Bkr Tripped) (2) SA01B0SA1CFTC. (SA Compr Bkr Fails To Close)

b. Role play (If requested):

(1) Maintenance (investigate loss of service air pressure or failure of compressor to start) – Report, “I will brief and dispatch personnel to investigate”.

(2) EO (investigate trip of 1SA01C) – Report, “The breaker for 1SA01C is tripped on overcurrent. There are no abnormalities locally. 0SA01C is operating normally.”

(3) EO (if directed to support shifting standby Service Air Compressors – acknowledge the order and report, “I’m on my way up to get a brief”.

7. CRD Pump High Seal Leakage / Pump Shift a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, insert Remote 3 and verify the following

command(s): (1) A05_A02_A0706_3_TVM Steady. (Annunciator 5068-6C ON)

b. Role play

(1) EO a) When dispatched to Control Rod Drive Pump ‘B’ – wait 1 minute and report, “The ‘B’ RD Pump seal is

leaking and spraying water on the floor around the pump. b) When directed to support shifting Control Rod Drive Pumps:

(1) 3304.01 step 8.1.2.1 – wait one minute and report, “The shaft driven oil pump and gear increaser have been primed for CRD Pump ‘A’.”

(2) 3304.01 step 8.1.2.3 – “1C11-R017AI and 1C11-R017BI are closed.” (3) 3304.01 step 8.1.2.4 – when requested to close/verify closed 1C11-F014A, release Shut

1C11-F014A, wait one minute and then report, “1C11-F014A is shut.” (4) 3304.01 step 8.1.2.7 – “CRD Pump ‘A’ Oil pressure is greater than 3 psig.” (5) 3304.04 step 8.1.2.8 – “I’m standing clear of CRD Pump A.” (6) 3304.01 step 8.1.2.9.3 – “CRD Pump ‘A’ Gear increaser oil pressure is 25 psig.” (7) 3304.01 step 8.1.2.10 – “I’ll monitor gear increaser and CRD Pump Oil Cooler outlet

temperature and adjust 1WT600A and 1WT601A as necessary.” (8) 3304.01 step 8.1.2.11 – when requested to open 1C11-F014A, release Open 1C11-F014A,

wait one minute and then report, “1C11-F014A is open.” (9) 3304.01 step 8.1.2.12 – when requested to slowly throttle close 1C11-F014B, release Shut

1C11-F014B, wait one minute and then report, “1C11-F014B is throttled to < 25% open.” (10) 3304.01 step 8.1.2.14 – “1C11-F014B is fully closed.” (11) 3304.01 step 8.1.2.15 – “1C11-R017AI and 1C11-R017BI are open.” (12) 3304.01 step 8.1.2.16 – “I will monitor CRD Pump ‘A’ Gear Increaser and Oil Cooler

temperatures every two hours for the next 24 hours.”

(13) When directed to shut 1C11-F017 Cross Connect Valve (5068-6C Operator Action 2) – from the Summary Page, delete A05_A02_A0706_3_TVM Steady and then report, “1C11-F017 Cross Connect Valve is shut and seal leakage has stopped”.

(2) RP (when informed of CRD Pump ‘B’ seal leak) – “We will dispatch a tech to perform contamination surveys.”



8. Suppression Pool leak into the LPCS Room/RHR ‘A’ Pump Room

a. Event Trigger - Following Event 7 and when directed by the Lead Examiner, insert Remote 4 and verify the following command(s): (1) YPMALSE_665. (LPCS Suction Line Rupture) (2) YPMALSE_666. (RHR A SP Suction Leak)


(1) EO (when directed to investigate leakage into the LPCS Pump Room) – “There is a large leak in the LPCS Pump suction pipe between 1E21-F001 and the LPCS Pump. The leak appears to be isolable. The room is becoming uninhabitable and I am leaving.”

(2) EO (when directed to remove LPCS and RHR A Pump breaker control power fuses) – acknowledge the order. (3) Maintenance (after 2 minutes from scram announcement) – report to the MCR as IMD.

9. 1E21-F001 LPCS Suppr Pool Suction Valve fails to close

a. Event Trigger - When BOP attempts to close 1E21-F001 verify the following command(s): (1) A05_A02_A09S38_2=ON. (LP Pwr Loss/Ovld Any Vlv PB Lite) (2) A05_A02_A16DS60_1=OFF. (E21AF001 Grn Lite) (3) A05_A02_A16DS61_1=OFF. (E21AF001 Red Lite)


(1) EO (when directed to check the breaker for 1E21-F001) – “The breaker for 1E21-F001 is tripped and will not reset.”



Turnover

1. The plant is in Mode 1, operating at ~ 10% power. a. CPS 3002.01 Heatup and Pressurization is complete. b. CPS 3004.01 Turbine Startup and Generator Synchronization is in progress. Section 5.0 Prerequisites are

complete. Steps 8.1.1 – 8.1.5 are complete. RR flow control valves are locked out IAW CPS 3302.01 Reactor Recirculation (RR) precaution 4.5.

c. Control rods - Step 8 / Gang 4A @ position 24.


• None

3. Today Day Shift


• Calm and clear.


• Power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. • The RE has requested single rod, single notch rod motion. • RE and Rod Verifier are available on request.


• LPCS is inop per ITS LCO 3.5.1 due to 1E21-F012 being open (entered at 0500 on the previous shift). • ORM 2.5.2 Action 3.5.2 due to LPCS MOV TEST PREP switch being in TEST (entered at 0500 on the

previous shift).


• None


• None


• First Priority – Complete Section 8.3 LPCS Operability/WLP Double Check Valve Test of CPS 9052.01 LPCS/RHR A PUMPS & LPCS/RHR A Water Leg Pump Operability is in progress. An extra equipment operator is briefed, staged and ready to provide field support.

• Continue with power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. • After reaching 15% power, perform Turbine Roll IAW Step 8.1.8 of CPS 3004.01.

10. Risk Levels



exelon nuclear ilt 17-1 nrc exam

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