ML21350A045

2A-2 Final Exam Surry 2021-301(2 Yr Delay)

ML21350A045
Person / Time
Site:	Surry
Issue date:	12/16/2021
From:	NRC/RGN-II
To:	Dominion Generation
References
50-280/21-301, 50-281/21-301 50-280/OL-21, 50-281/OL-21
Download: ML21350A045 (755)

Text

ML21350A045 Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO 2021-3 Facility: Surry Power Station Scenario No.: 3 Op-Test No.: 2021-301 Examiners: _______________________ Operators: __ _________________

Initial Conditions: Unit 1 100% MOL. 1-SD-P-1B degraded requiring ramp down to 84%.

• Containment Smoke and heat detectors are non-functional due local fire panel failure. TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Turnover: The Team will pre-brief ramp to 84% power in accordance with 1-OP-TM-005 prior to Simulator entry, and commence the ramp following turnover.

Event Event Type* Event No. Description R - RO/SRO Upon assuming the Unit, the Team will commence a Ramp down to 84% power at 1 N - BOP the normal rate per 1-OP-TM-005 (.5%/ min).

I - BOP 2 I - SRO Power Range Channel 1, N41, fails LOW. AP-53.00/AP-4.00.

TS-SRO 3 C - BOP A CN pump trips on overcurrent, C CN pump fails to auto start. (CT-1) AP-21.00.

C - SRO C - RO/SRO 4 TS - SRO Presurizer Pressure Master Pressure Controller Fails Low. AP-53.00/AP-31.00.

C - BOP/RO 5 C - SRO Momentary Loss of Vital Bus I. (1-AP-10.01)

N-BOP/SRO Steam break on MS Header in Turbine Building; Upon reactor trip, TDAFW pump 6/7 M - All steam supply line ruptures, causing 3 faulted SG condition. Steam header break isolated by MSTVs. E-0, E-2, ECA-2.1. (CT-2 and CT-3).

Failures for BOP to identify/correct in E-0 Attachments. 1-CH-MOV-1381, auto close 8 fail. 1-VS-MOD-103B auto close fail. MDAFW pumps fail to auto start.

C - BOP

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

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO 2021-3 LIST OF CRITICAL TASKS CT # EVENT DESCRIPTION MET ()

CT-1 CN pump The BOP must start the standby Condensate pump trip prior to SG level causing an auto or manual reactor trip.

CT-2 3 Faulted Restore at least one MDAFW pump prior to SG WR SGs level lowering to FR-H.1 Feed and Bleed criteria (12%). Failing to do this would significantly complicate the scenario by challenging heat sink.

CT-3 3 Faulted Lower AFW flowrate to 60 gpm to each SG if RCS SGs cooldown rate is > 100°F/hour to prevent entry into FR-P.1. Failing to do this could cause an entry into FR-P.1 which is not needed.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO 2021-3 Event 1: Unit 1 Ramp to 84% power IAW 1-OP-TM-005. (R- SRO/RO. N - BOP).

This Event is a ramp down in power using control rods, CVCS blender (boration), and turbine controls to lower reactor power to 84%.

Verifiable Action(s):

1) RO will manipulate control rods to control delta flux and/or Tave.

2) RO will manipulate CVCS control to establish a normal boration to assist in Tave control.

3) BOP will manipulate Turbine Controls to establish power decrease.

Event 2: Power Range Channel 1 (N41) Fails LOW. (I - BOP, I - SRO, TS - SRO).

After the Team has ramped down in power at the normal rate, and the Evaluating Team is ready, the failure of N41 in the LOW direction is initiated. The Team will address the failure IAW AP-53.00 and AP-4.00.

Verifiable Actions(s):

1) BOP: Stop turbine ramp by placing in HOLD.

2) BOP: Will perform Attachment 1 of AP-4.00 to place N44 in TRIP.

Technical Specifications:

1) TS Table 3.7-1, Item 2, Operator Action 2, Place Failed Channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, Inoperable channel may be bypassed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing, Either Thermal Power restricted to 75% of rated power and Neutron Flux trip setpoint reduced to 85% of Rated Power within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />; OR the Quadrant Power Tilt monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. QPT shall be monitored using the in-core detectors.

2) TS-3.12.D, Quadrant Power Tilt. If the reactor is operating above 75% power with one ex-core nuclear channel out of service, the QPT shall be determined once per day, or a change in power level > 10%, or 30 inches of control rod motion.

Event 3: Trip of Running A CN pump with Failure of auto start of C CN pump. (C -

BOP, C - SRO).

When the evaluating Team is ready, the malfunction for the trip of a running condensate pump will be initiated. The BOP will identify the trip of one of the running CN pumps and feed flow less steam flow on all SGs. BOP will perform the Immediate Actions of AP-21.00 and start the non-running condensate pump. The Team will complete AP-21.00 actions.

Verifiable Action(s):

1) BOP: Perform Immediate Actions of AP-21.00, Loss of Feedwater, and start a second Condensate pump.

Critical Task:

CT-1: The BOP must start the standby Condensate pump prior to SG level dropping low enough to cause an auto or manual reactor trip.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO 2021-3 Event #4: Pressurizer Pressure MPC Fails LOW. (C - RO, C - SRO, TS - SRO)

When the Evaluating Team is ready, the failure of Pressurizer Pressure Master Pressure Controller 1-RC-PC-1444J (LOW) is implemented. This failure results in Master Pressure output lowering to minimum, causing all heaters to turn on, and preventing spray valves from opening.

Pressurizer pressure will rise until the operator takes manual control of either the Master Pressure controller or spray controllers to lower pressure. If the operator fails to take corrective action in a timely manner, the Pressurizer PORV 1-RC-PCV-1455C will cycle open and close around its setpoint.

Verifiable Actions:

1) RO: Place Master Pressure controller in Manual and raise demand to open the PRZR spray valves; or place both spray valves in Manual and raise demand to open them. Restore pressure to normal band.

Technical Specifications:

1) TS 3.1.A.6.a, Relief Valves. With one or both PORVs inoperable but capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) and maintain power to the associated block valve(s). Otherwise, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce Reactor Coolant System average temperature to < 350°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Event 5: Momentary loss of Vital Bus I. (C - BOP/RO/SRO, TS - SRO, N-BOP/SRO)

When Evaluating Team is ready, the next event will be initiated. This event is a momentary loss of Vital Bus I. The loss is due to a trip of the Inverter output breaker on fault, followed by the Static switch closing (2 sec later) to power Vital bus I.

Verifiable Action(s):

1) BOP: Return Normal Letdown to service IAW 1-OP-CH-020.

2) RO: Close Letdown Isolation valves, 1-CH-LCV-1460A and 1-CH-LCV-1460B.

3) RO: Open 1-RM-TV-100, and 1-RM-TV-100C

4) RO/BOP: Open 1-IA-TV-100, and 1-IA-TV-101A.

5) RO/BOP: Reset NI-41 Dropped rod signal.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO 2021-3 Event #6/7: Steam break on Header followed by 3 Faulted SGs in SFGDs. (M -All)

When the evaluating Team is ready, the Major event will be initiated. This event is a steam break on the MS header in the Turbine Building, followed three (3) faulted SGs in Unit 1 SFGDs.

The MSTVs close to isolate the Steam Break in the Turbine Building. During the transient the MDAFW pumps will not start following auto/manual initiation of SI, and only the B MDAFW pump will manually start. The Team progresses through E-0, E-2, and then a transition to ECA-2.1 is made. The Team will identify a cooldown rate in excess of 100°F/hour and throttle AFW to

~ 60 gpm. This will result in a transition to FR-H.1, then a return to ECA-2.1.

Verifiable Actions:

1) RO: Trip the reactor and perform E-0 Immediate Actions.

2) BOP: Perform E-0 Attachments 1, 2, and 3. Identify and correct failure of the A FRV failing to close on the SI, 1-CH-MOV-1381 auto close, and 1-VS-MOD-103B failing to auto close. Also manually starts the MDAFW pump, 1-FW-P-3B.

Critical Task:

1) CT-2: Restore at least one MDAFW pump prior to SG WR level lowering to FR-H.1 Feed and Bleed criteria (12%). This would take approximately 12 minutes with no operator action.

Failing to do this would significantly complicate the scenario by challenging heat sink.

2) CT-3: Lower AFW flowrate to 60 gpm to each SG if RCS cooldown rate is > 100°F/hour to prevent entry into FR-P.1. Failing to do this could cause an entry into FR-P.1 which is not needed.

The scenario may be terminated when the Evaluation Team is ready and after return to ECA-2.1 from FR-H.1.

Scenario Recapitulation Total Malfunctions: 9 Abnormal Events: 6: AP-53.00 (two), AP-4.00, AP-10.01, AP-31.00, AP-21.00, Major Transients: 2 (MSL Rupture, 3 Faulted SGs)

EOPs Entered: 2 (E-0, E-2)

EOP Contingencies: 2 (ECA-2.1, FR-H.1)

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO 2021-3 Initial Conditions: Unit 1 100% MOL. 1-SD-P-1B degraded requiring ramp down to 84%.

Turnover: The Team will pre-brief ramp to 84% power in accordance with 1-OP-TM-005 prior to Simulator entry, and commence the ramp following turnover.

Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

o Containment Smoke and heat detectors are non-functional due local fire panel failure (2 days ago).

TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days.

Turnover:

The Team will pre-brief ramp to 84% power in accordance with 1-OP-TM-005 prior to Simulator entry, and commence the ramp following turnover.

Another shift will perform the actual Heater Drain pump swap, and subsequent ramp up to 100%.

Scenario Objectives.

A. Given the Unit at 100% Power, commence a ramp to 84% in accordance with 1-OP-TM-005, Unit Ramping Operations.

B. Given the failure of N-41, Channel I Power Range Channel in the low direction, respond to the failure in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Controls and 1-AP-4.00, Nuclear Instrumentation Malfunction.

C. Given the momentary loss of VB I, stabilize the plant iaw 1-AP-10.01, LOSS OF VB I.

D. Given the failure of the of Pressurizer Pressure Master Pressure Controller 1-RC-PC-1444J (LOW); respond in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Controls and 1-AP-31.00, Increasing or Decreasing RCS Pressure, to regain control of RCVS pressure prior to automatic opening of a PRZR PORV..

E. Given an overcurrent trip of the A CN pump and the failure of the C CN pump to start, respond in accordance with 1-AP-21.00, Loss of Main Feedwater Flow, to restore feedflow to normal.

F. Given a steam break in Unit 1 Turbine Building, automatic steam line isolation, reactor trip, and a subsequent fault on the TDAFW steam supply line, respond in accordance with 1-E-0,

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO 2021-3 Reactor Trip or Safety Injection, 1-E-2, Faulted Steam Generator Isolation, and 1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

G. Given the failure of 1-CH-MOV-1381, Seal Return Isolation MOV, and 1-VS-MOD-103B, MCR Isolation Damper, to reposition on the Safety Injection signal, utilize E-0, Attachments 1 and 3 to identify and correct the condition

SHIFT TURNOVER INFORMATION OPERATING PLAN:

Unit 1 is at 100% power with RCS boron concentration of 795 ppm.

During the last shift, 1-SD-P-1B, B High Pressure Drain Pump has started to degrade based on elevated vibration levels. The Team will ramp the unit to 84% based on 1-OP-TM-005 to

~84% power. All systems and crossties are operable with the following exception:

• Unit 1 and 2 Containment Temperature to the MCR Fire Panel are non-functional. In accordance with TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors, are in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to commence a Ramp to 84% power in accordance with 1-OP-TM-005, Unit Ramping Operations, using the Ramp Plan provided, upon relieving the watch. The SM has directed a 0.5%/min ramp rate to be used for the ramp. Performance of 1-OP-TM-005 has been authorized and has been PSA analyzed for current plant conditions. Another operator will operate the MSRs IAW 1-OP-TM-007, MSR Operation During or Following power reductions.

The next shift will perform the Heater Drain pump swap and subsequent ramp up to 100%.

The previous shift performed two 30 gallon dilutions for temperature control.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 9 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready Time Position Applicants Action or Behavior 1-OP-TM-005, Unit Ramping Operations Team Team will pre-brief Initial Conditions, Precautions and Limitations, and procedure prior to entering simulator.

The team will be provided with a copy of 1-OP-TM-005, Unit Ramping (Marked up to Section 5.2); 1-OP-CH-007, Blender Operations; and a Reactivity plan.

SRO 1-OP-TM-005, Unit Ramping Operations Section 5.1 will be completed (signed off), but will be reviewed by the team prior to entering the simulator. Section 5.2 begins on page 12 of this guide.

SRO 1-OP-TM-005, Unit Ramping Operations 5.1 Preparations for Turbine Ramp Down 5.1.1 Review all lighted annunciator windows for adverse conditions that could impact the performance of this procedure.

Will be initialed as complete. - No annunciators Lit.

5.1.2 Review the Tagout File for tagouts that could impact this procedure.

Will be initialed as complete. - MCR FP Panel Tagged out, OC-18 performed by Unit 2 BOP.

5.1.3 Review the Plant Status Log for conditions that could impact this procedure.

Will be initialed as complete. - No items in the plant status log.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 10 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready SRO 1-OP-TM-005, Unit Ramping Operations Note prior to Step 5.1.4: Rod height adjustments should be used to maintain Delta Flux as recommended by Reactor Engineering. Boration or dilution should be used to account for power defect and Xenon changes to maintain reference temperature.

5.1.4 Check or align letdown orifices for anticipated power change IAW 1-OP-CH-006, Shifting or Increasing/Decreasing Letdown Flow.

Will be initialed as complete.

5.1.5 For scheduled power level changes greater than 10%, verify that a reactivity plan has been provided by Reactor Engineering. Otherwise, direct the STA to notify Reactor Engineering and request recommendations for control of core parameters.

• Delta Flux control

• Recommendations for Rod height and/or RCS Boron adjustments

• Expected Xenon transient Will be initialed as complete. The team will be given a reactivity plan.

5.1.6 TM Have an Electrician remove the seal-in contacts from the MSR STM SUP valves IAW Attachment 5, Moisture Separator MOV Seal-in Contact Defeat.

Will be initialed as complete.

5.1.7 Enter the Temporary Modification as a Procedurally Controlled Modification (PCTM) in the Unit 1 Temporary Modification Log.

Will be initialed as complete.

Caution prior to Step 5.1.8: Energizing additional PRZR heaters may cause a change in RCS average temperature due to a difference in boron concentration between the PRZR and the RCS.

5.1.8 Return PRZR Backup Heaters to the MANUAL ON position IAW 1-OP-RC-019, Pressurizer Heater Operation.

Will be initialed as complete.

5.1.9 Record the Target Power Level, the Current Power Level, and the Percent Power Change below. IF the Target Power Level is unknown, THEN enter N/A for this step.

Current Power Level _____100%_________

Minus Target Power Level - _____84%________

Equals Percent Power Change = ____16%_________

Will be initialed as complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 11 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready Note prior to Step 5.1.10: If a shift turnover is required while Subsection 5.2 is in progress, Steps 5.1.10, 5.1.11 and 5.1.12, as applicable, must be performed for the relieving shift. Multiple signoffs are provided for this purpose.

5.1.10 Check that the Shift Manager (who is the designated Test Coordinator) or his designee has reviewed the Detailed Pre-Job Briefing Checklist and Responsibilities in Attachment 1 (page 3 of 5) and conducted a Detailed Pre-Job Briefing with all personnel performing the unit ramp.

Will be initialed as complete.

5.1.11 Check that the Senior Operations Manager or Operations Manager on Call has reviewed the Management Expectations Briefing Checklist in Attachment 1( page 2 of 5) and briefed the Operations Department and support personnel on management expectations. This step may be marked N/A if the ramp is required due to an emergent issue and a Senior Operation Manager or Operations Manager On Call is not available in a timely manner.

Will be initialed as complete.

5.1.12 The pre-job brief shall include the items in Attachment 2, Pre-job Brief Expectations for Reactivity Control.

Will be initialed as complete.

5.1.13 Determine the specific rate of Reactor Power change and the methods which will be used to achieve this rate of change.

Rate of Power Change _____0.5% per minute_________

Minus Target Power Level - ___Turbine, Boration, Rods____

Will be filled in, and initialed as complete.

5.1.14 Notify Energy Supply (MOC), Chemistry, and the Polishing Building that the power change is imminent.

Will be initialed as complete. Team will re-perform these steps prior to entering simulator.

The Team will commence with Section 5.2. Several steps may be completed prior to entering the simulator (i.e., marked N/A).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 12 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready SRO/RO 1-OP-TM-005, Unit Ramping Operation 5.2 Power Reduction Between 100% and 50% Reactor Power Caution prior to Step 5.2.1: To maintain positive control of the Reactor, control rods shall be moved in a deliberate, carefully controlled manner while the response of the Reactor is closely monitored.

Note prior to step 5.2.1: Steps in this subsection may be performed out of sequence with permission from Shift Supervision.

5.2.1 Initiate Attachment 4, Reactivity Control and Monitoring During Ramp.

Another operator will perform Attachment 4, 1-OP-TM-005. This step can be signed off.

Crew performs step and initials step completion.

Notes prior to Step 5.2.2:

• The ramp rate may be changed, or stopped as required to control Plant parameters.

• Normal ramp rate is obtained using Position 6 on the LOAD RATE %

PER MIN thumbwheel. A change in the ramp rate thumbwheel to position 8, or position 1, or stopping and starting the ramp, may be necessary to control plant parameters.

• If the power reduction is stopped during the ramp down, IMP OUT may be used to assist in stabilizing the Turbine.

5.2.2 Check or place Turbine in IMP IN or IMP OUT as determined by Shift Supervision.

Crew places Turbine in IMP IN or IMP OUT (normally use IMP IN) 5.2.3 Commence the power reduction at the ramp rate specified by Shift Supervision.

Crew places Turbine to GO and commences ramp rate at 0.5%/min.

Note prior to step 5.2.4: During power reduction, the Valve Position Limiter should be maintained approximately 2 to 3 percent avobe the steady state power level. The Turbine control valves should not run up against the Valve Position Limiter.

5.2.4 Lower the Valve Position Limiter and maintain the Limiter as close as reasonably possible above the actual turbine load during power reduction.

Crew operates Valve Position Limiter and signs off the step.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 13 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready SRO/RO 1-OP-TM-005, Unit Ramping Operation Note prior to step 5.2.5: Alternate indications of Reactor Power, such as Core T, First Stage Pressure, Condensate and Feedwater performance parameters, and Electrical output, should be reviewed and compared during power reduction.

BOP 5.2.5 Borate, dilute or use control rods as required to maintain Ø in band.

Observe the expected response on FR-I-113, BA - PRI WTR FLOW, and Y1C-113, BA SUP BATCH INTEGRATOR.

Crew will use 1-OP-CH-007, BLENDER OPERATIONS, for the necessary Boration during the ramp.

NOTE: 1-OP-CH-007, 5.3, Boration is found at the end of this section.

Caution prior to step 5.2.6: The Turbine will momentarily (1.5 seconds) shift to MANUAL when placing in IMP IN. To minimize Governor valve oscillations, the GV Tracking Meter should read as close to zero as possible before transferring to IMP IN.

Note: Minor fluctuations in GV Tracking is normal. GV Tracking is working as designed.

5.2.6 IF the Turbine control is in IMP OUT, THEN perform the following substeps WHEN Reactor power is approximately 90 - 91%. IF the Turbine control is in IMP IN, THEN enter N/A to the following substeps.

a. Stabilize the unit..

b. Check the GV Tracking Meter as close to zero as possible.

c. Place the Turbine in IMP IN.

d. Recommence the load reduction.

Crew performs step and initials step completion. (Anticipate step is N/A) 5.2.7 Operate MSRs IAW 1-OP-TM-007, MSR Operation During or Following Power Reductions, as the Turbine load lowers.

Another operator will be briefed and perform this function.

5.2.8 IF the 2nd Point Extraction can NOT continue to supply the Auxiliary Steam Heater, THEN check that 1-AS-PCV-100, Auxiliary Steam Header PCV, is controlling Auxiliary Steam Header pressure between 160 psib and 180 psig. Enter N/A if the Auxiliary Steam Header is being supplied from an alternate source.

Crew performs step and initials step completion Note: steps 5.2.9 thru step 5.2.13 deal primarily with actions at 60 % power (which is below the power limit specified to ramp to.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 14 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready 5.2.14 Continue the power ramp to 84 percent (approximate) power.

Evaluators Note: No further actions are expected for this event.

-- END EVENT 1 --

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 15 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 16 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 17 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 18 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 19 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 1 Page 20 of 90 Event

Description:

1-OP-TM-005, Unit Ramping Operations, Ramp Down to 84% Power Cue: Following Turnover, and Evaluators Ready

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 21 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

Time Position Applicants Action or Behavior N41 Fail Low Team Diagnose this failure using the following alarms and indications:

Annunciator 1G-E4, NIS PWR RNG CH AVG FLUX DEVIATION Annunciator 1G-H1, NIS DROPPED ROD FLUX DECREASE > 5% PER 2 SECS N41 indication on Benchboard and NI Drawer Fail Low.

0-AP-53.00, Loss of Vital Instrumentation/Controls.

RO Perform Immediate Actions of AP-53.00:

[1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL.

[2] PLACE AFFECTED CONTROL(S)/ COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION NOTE: Crew may go straight to AP-4.00 (this is not incorrect).

Reports to SRO: Immediate Actions of AP-53.00 complete, N41 failed LOW.

0-AP-53.00 SRO The SRO will lead a transient brief. During the brief, the failure of N41 will be discussed.

The RO/BOP will report Annunciators received related to the event, and Critical Parameters affected.

STA will have no input for the brief.

0-AP-53.00 SRO 3. CHECK REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Report reactor power is less than 100%, and provides current reactor power indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 22 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

0-AP-53.00 SRO Notes prior to Step 4.

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

4. DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

• NI Malfunction, 1-AP-4.00 SRO Transitions to AP-4.00.

1-AP-4.00, Nuclear Instrument Malfunction SRO SRO will conduct focus brief, changes to parameters or Unit status will be discussed.

RO/BOP will provide input for Unit Status change.

STA will have no input for the brief.

SRO will continue 1-AP-4.00 1-AP-4.00, Nuclear Instrument Malfunction SRO NOTE Prior to STEP 1: Attachments 6, 7, and 8 show one-line diagrams of Nuclear Instrumentation.

BOP Acknowledges Note.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 1 CHECK NI MALFUNCTION - POWER RANGE FAILURE.

BOP Reports Yes, N41 Failed.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 2. STABILIZE UNIT CONDITIONS BOP RO reports that Unit conditions are stable.

Note: The crew may decide to continue the ramp in order to better control the plant. This is acceptable provide the crew maintains control of RCS temperature and Delta Flux.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 23 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 3. CHECK N FAILED.

BOP RO reports that NO, N-41 has Failed.

3RNO. GO TO STEP 6 1-AP-4.00, Nuclear Instrument Malfunction.

SRO

6. CHECK N FAILED BOP Reports NO, N41 has failed. GOES TO STEP 8.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 8. CHECK POWER RANGE CHANNELS - ONLY ONE FAILED BOP Reports Yes, only N41 Failed.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO NOTE Prior to Step 9: Performance of Attachment 1 to place the failed Power Range Channel in trip requires I&C assistance for N-41, N-42, or N-43.

BOP Acknowledges NOTE.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 9. INITIATE ATTACHMENT 1 TO PLACE FAILED CHANNEL IN TRIP WITHIN 72 HOURS Directs BOP to perform 1-AP-4.00, Attachment 1, Part 1, 2, and 3.

Note: Attachment 1 actions are on pages 25 - 27.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 10. CHECK NI MALFUNCTION - INTERMEDIATE RANGE FAILURE RO Reports No, Power Range Failure SRO GOES to Step 19 1-AP-4.00, Nuclear Instrument Malfunction.

SRO 19. CHECK NI MALFUNCTION - SOURCE RANGE FAILURE RO Reports No, Power Range Failure SRO Goes to Step 38

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 24 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

1-AP-4.00, Nuclear Instrument Malfunction.

SRO 38. NOTIFY THE FOLLOWING

• Instrument Shop

• OM on call SRO Notifies Shift Manager of Unit status, procedures used, and Tech Spec Requirements. Requests that the Shift Manager notify I&C and the OMOC.

--- END OF EVENT 2 ---

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 25 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE BOP 1. Record the following indications for the failed Power Range Channel:

• Power Level

• Delta Flux

• Upper Detector Current

• Lower Dectector Current Applicant records indications.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE BOP 2. Perform the following at the NIS panel within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• Comparator and Rate Drawer

a. Select the failed channel on the COMPARATOR CHANNEL DEFEAT switch. (N-41)

b. Check annunciator 1G-E4, NIS PWR RANGE CH AVG FLUX DEVIATION - NOT LIT. Annunciator will be NOT LIT.

• Miscellaneous Control and Indication Panel

a. Select the failed channel on the ROD STOP BYPASS switch. (N-41).

b. Check annunciator 1G-G1, NIS PWR RNG HI FLUX ROD STOP -

NOT LIT. Annunciator will be NOT LIT.

c. Select the failed channel on the UPPER SECTION defeat switch.

(N-41).

d. IF Reactor power greater than 50%, THEN check annunciator 1G-C4, UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT < 50% -

NOT LIT. (annunciator will remain LIT if any Power Range channel less than 50%)

e. Select the failed channel on the LOWER SECTION defeat switch.

(N-41).

f. IF Reactor power greater than 50%, THEN check annunciator 1G-D4, LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT < 50% -

NOT LIT. (annunciator will remain LIT if any Power Range channel less than 50%)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 26 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE BOP NOTE Prior to Step 3: Annunciator NIS PWR RNG HI STPT (1E-E5, 1E-F5, 1E-G5, or 1E-H5) for the channel being placed in trip, NIS PWR RNG LOSS OF DET VOLT (1G-C3), and NIS DROPPED ROD FLUX DECREASE > 5%

PER 2 SEC (1G-H1) will alarm when the instrument power fuses are pulled If Reactor power is less than 10%, annunciator NIS PWR RNG LO STPT HI FLUX (1E-D5) will alarm when the instrument power fuses are pulled.

Acknowledges NOTE.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE BOP Notifies RO prior to Removing Instrument Fuses (a. Below)

BOP 3. Place the failed Power Range channel in trip IAW the following:

a. At the Power Range drawer, remove the INSTRUMENT POWER fuses. (N-41).

b. At the Power Range drawer, put the POWER RANGE TEST switch in the TEST position. (N-41).

c. Check annunciator 1G-H1, NIS DROPPED ROD FLUX DECREASE

> 5% PER 2 SEC - LIT. Annunciator will be LIT.

d. Check annunciator 1G-C3, NIS PWR RNG LOSS OF DET VOLT -

LIT.

Annunciator will be LIT.

e. IF Reactor power less than 10%, THEN check annunciator 1E-D5, NIS PWR RNG LO STPT HI FLUX - LIT. Annunciator will not be NOT LIT.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE BOP 4. Remove the following PCS points for the failed channel from scan:

• N-41, N0041A and N0042A

• N-42, N0043A and N0044A

• N-43, N0045A and N0046A

• N-44, N0047A and N0048A The BOP will remove these points from scan.

Only N-41 points (in BOLD Above) will be taken off scan.

Note: Only the Shift Manager Computer has the rights to take PCS points out of scan.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE SRO 5. Notify I&C to initiate 0-ICM-ZZ-001, Placing Technical Specifications Channel in Trip to place OTDT and OPDT for the failed Power Range channel in TRIP and check the associated annunciators LIT.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: Page 27 of 90 Event

Description:

Power Range N41 Fails Low.

Cue: By Examiner.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE

6. IF Reactor power is greater than 75%, THEN do either a OR b below.

a. Determine the core quadrant balance using the incore movable detectors when any of the following occur:

• Twelve hours have passed since the last core quadrant balance was performed.

• A change in Reactor power level greater than 10%.

• Control Rod movement of greater than 30 inches. (48 steps)

OR

b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, reduce Reactor power to less than or equal to 75% of rated power, and within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, reduce the High Flux trip setpoint to less than or equal to 85% of rated power.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE

7. IF Reactor power is less than or equal to 75%, and will remain there, THEN within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, reduce the High Flux trip setpoint to less than or equal to 85%

power.

1-AP-4.00, Attachment 1: ONE POWER RANGE CHANNEL INOPERABLE

8. Refer to Tech Spec Table 3.7-1, Item 2, 5, 6, and 20.

9. Refer to Tech Spec 3.12.D.

SRO Consults Tech Specs and identifies:

1) TS Table 3.7-1, Item 2 Nuclear Flux Power Range, Operator Action 2, Place Failed Channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, Inoperable channel may be bypassed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing, Either Thermal Power restricted to 75% of rated power and Neutron Flux trip setpoint reduced to 85% of Rated Power within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />; OR the Quadrant Power Tilt monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. QPT shall be monitored using the in-core detectors.

2) TS Table 3.7-1, Item 5 OTDT, Operator Action 6, Place Failed channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Inoperable channel may be bypassed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing. If the conditions are not satisfied in the time permitted, be in at least Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3) TS Table 3.7-1, Item 6 OPDT, Operator Action 6 (same as above).

4) TS-3.12.D, Quadrant Power Tilt. If the reactor is operating above 75%

power with one ex-core nuclear channel out of service, the QPT shall be determined once per day, or a change in power level > 10%, or 30 inches of control rod motion BOP will return Attachment to SRO and report Parts 1-4 are complete.

Return to AP-4.00 step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 3 Page 28 of 90 Event

Description:

Loss of 1-CN-P-1A w/flr of 1-CN-P-1C to auto start..

Cue: By Examiner.

Time Position Applicants Action or Behavior Trip A CN Pump, C CN pump Fails to auto start Team Diagnose the failure based on the following alarms and indications:

• Annunciator 1K-D4, 4KV BKR AUTO TRIP.

• Feedflow less than Steam flow on all SGs.

• SG NR level lowering on all three SGs 1-AP-21.00 BOP Perform Immediate Actions of 1-AP-21.00.

[1] CHECK MAIN FEED PUMP STATUS:

a) Check Reactor Power - GREATER THAN 80%

b) Check Main Feed Pumps - TWO RUNNING Identify power > 80% AND two Main Feed pumps running.

1-AP-21.00 BOP [2] START AN ADDITIONAL CONDENSATE PUMP Identify 1-CN-P-1C, C CN Pump, failed to auto start.

Start 1-CN-P-1C.

CT-1: The BOP must start the standby Condensate pump prior to SG level dropping low enough to cause an auto or manual reactor trip.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 3 Page 29 of 90 Event

Description:

Loss of 1-CN-P-1A w/flr of 1-CN-P-1C to auto start..

Cue: By Examiner.

1-AP-21.00 BOP [3] REDUCE TURBINE LOAD TO MATCH STEAM FLOW WITH FEED FLOW Use Valve Position Limiter OR Reduce Turbine load using Turbine Manual Monitor Feed flow/Steam flow mismatch and determine load reduction is not necessary.

Report Immediate Actions of AP-21.00 are complete and SG levels are trending to program level.

1-AP-21.00 SRO Conduct Transient Brief, describe event that occurred, procedure used, procedure used to continue further actions.

RO/BOP will provide alarms received during the event and Critical Parameters.

STA will provide no input.

SRO will finalize the Transient Brief, direct the RO to contact the Unit 1 Turbine Building Operator and the Service Building Operator to perform local checks on the C CN pump (post start), A CN pump (indications of cause for tripping) and status of A CN pump breaker. SRO will then continue with AP-21.00.

NOTE: Team may use 1K-D4 ARP to place the A CN pump in PTL; common alarm for a number of loads; allows alarm to be received if other loads subsequently trip.

1-AP-21.00 SRO 4. CHECK CONDENSATE POLISHING BLDG BYPASS - REQUIRED Main Feed Pump Suction Pressure - LESS THAN 400 PSIG BOP Reports No, Feed Pump suction >400 psig (will report actual indicated pressure)

SRO Goes to Step 6 1-AP-21.00 SRO 6. ENERGIZE ALL PRZR HEATERS RO Reports all pressurizer heaters energized.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 3 Page 30 of 90 Event

Description:

Loss of 1-CN-P-1A w/flr of 1-CN-P-1C to auto start..

Cue: By Examiner.

1-AP-21.00 SRO 7. CHECK STEAM DUMP OPERATION - REDUCING TAVE/TREF MISMATCH BASED ON DEMAND SIGNAL BOP Reports Yes, steam dumps operating properly.

1-AP-21.00 SRO NOTE Prior to Step 8: Depending on initial plant conditions, rod insertion or boration may be used to stabilize RCS temperature and maintain Flux in band.

RO Acknowledges NOTE.

SRO 8. CHECK CONTROL RODS - INSERTING IF NECESSARY RO Reports No, not necessary 1-AP-21.00 SRO 9. CHECK ANNUNCIATOR 1E-E3, FLUX DEVIATION - NOT LIT RO Reports Yes, Not Lit.

1-AP-21.00 SRO 10. CHECK ALL SG FLOWS - STEAM FLOW IS LESS THAN OR EQUAL TO FEED FLOW BOP Reports Yes, Steam Flow is equal to Feed Flow.

1-AP-21.00 SRO 11. CHECK ALL SG LEVELS - AT OR TRENDING TO PROGRAMMED LEVEL BOP Reports Yes, all SGs are ~ 44%.

1-AP-21.00 SRO 12. CHECK TAVE - MATCHED WITH TREF RO Reports Yes, (will provide actual Tave/Tref mismatch.)

1-AP-21.00 SRO 13. CHECK FEED HEADER TO STEAM HEADER P - AT LEAST 50 PSID BOP Yes, (will provide actual P indicated.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 3 Page 31 of 90 Event

Description:

Loss of 1-CN-P-1A w/flr of 1-CN-P-1C to auto start..

Cue: By Examiner.

1-AP-21.00 SRO 14. CHECK AMPs ON EACH MOTOR OF THE RUNNING MAIN FEED PUMP(s) - LESS THAN 420 AMPS BOP Reports Yes, (provides actual MFP amps indicated.)

1-AP-21.00 SRO NOTE: The polishing building should be returned to service as soon as reasonably achievable to minimize iron transport and prevent entry in an Action Level.

BOP

15. CHECK OPERATION OF MAIN FEED PUMP(s)

• Recirc valve position (Closed)

• Discharge MOV position (Open)

• Pump amps (Normal, may provide actual MFP Amp indication.)

1-AP-21.00 SRO 16. CHECK REACTOR POWER CHANGE - LESS THAN 15% IN ONE HOUR RO Reports Yes, (will provide indicated reactor power.)

1-AP-21.00 SRO 17. NOTIFY THE FOLLOWING:

OMOC Maintenance Foreman SRO notifies Shift Manage of Plant Status, Completion of AP-21.00, Report results of local investigation of B CN pump and breaker, and requests OMOC and Maintenance Foreman be notified of the event.

Evaluator Note: The crew may stop the ramp at this time, if they havent already. They may use 1-OP-CH-007, BLENDER OPS to stabilize the plant through dilutions.

---End EVENT #3---

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Event No.: 4 Page 32 of 90 Event

Description:

PRZR Master Pressure Controller fails LOW (0-AP-53.00)

Cue: When initiated by Team Time Position Applicants Action or Behavior 0-AP-53.00 RO Diagnoses Failure based on the following indications:

• Master pressure controller output lowering from approximately 35% to 0%.

• PRZR Spray Valves, 1-RC-PCV-1455A, and 1-RC-PCV-1455B remain closed.

• All Pressurizer Heater Banks energize.

• Annunciator 1C-F8, PRZR HI PRESS (5 min) 0-AP-53.00 RO Performs the Immediate Actions of AP-53.00

[1] Checks redundant indications of pressurizer pressure - NORMAL

[2] Places the Master Pressure Controller in MANUAL and raises output to ~ 30%.

Announces completion of Immediate Actions of AP-53.00.

0-AP-53.00 SRO Conducts brief using Brief Placard. RO Will report Critical parameters. BOP will report Critical Parameters. STA will state Nothing to add.

0-AP-53.00 SRO *3. VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Reports reactor power approximately 84% using PCS indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Event No.: 4 Page 33 of 90 Event

Description:

PRZR Master Pressure Controller fails LOW (0-AP-53.00)

Cue: When initiated by Team 0-AP-53.00 SRO CAUTION: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

NOTES before Step 4

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

0-AP-53.00 SRO *4. DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

RO

• PRZR Pressure Control, Step 5 0-AP-53.00 SRO NOTE: RCS pressure reduction will cause a slight decrease in RCS Tave due to negative reactivity from the moderator pressure coefficient.

SRO 5. CHECK PRZR SPRAY VALVE CONTROLLERS - NORMAL RO Reports PRZR Spray Valve Controller Normal.

0-AP-53.00 SRO 6. GO TO 1-AP-31.00, INCREASING OR DECREASING RCS PRESSURE Transitions to 1-AP-31.00.

1-AP-31.00 SRO [1] CHECK PRZR PORVS - CLOSED RO Checks PRZR PORVs closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Event No.: 4 Page 34 of 90 Event

Description:

PRZR Master Pressure Controller fails LOW (0-AP-53.00)

Cue: When initiated by Team SRO SRO will hold a brief on entry to AP-31.00. SRO will direct RO to maintain RCS pressure at 2235 psig +/- band, and pressure to be monitored by RO at a specific frequency.

1-AP-31.00 SRO CAUTION: A Safety Injection may occur if the unit is not tripped prior to RCS pressure decreasing below 2100 psig.

2. CHECK RCS PRESSURE - LOWERING RO Reports No, RCS pressure initially rising.

1-AP-31.00 Step 2RNO IF procedure was entered due to rising RCS pressure, THEN GO TO Step 12.

GOES TO Step 12 1-AP-31.00 SRO

12. CHECK RCS PRESSURE - RISING.

RO Reports No, pressure is currently stable (reports value and trend).

Goes to Step 17.

1-AP-31.00 SRO 17. CHECK MASTER CONTROLLER - IN MANUAL RO Reports, Yes, MASTER PRESSURE CONTROLLER IS IN MANUAL.

1-AP-31.00 SRO 18. DECLARE 1-RC-PCV-1455C INOPERABLE.

Declares 1-RC-PCV-1455C is INOPERABLE.

1-AP-31.00 SRO 19. CHECK PRZR PORVS - EITHER INOPERABLE.

• 1-RC-PCV-1455C

• 1-RC-PCV-1456 RO Reports, Yes, 1-RC-PCV-1455C is inoperable.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Event No.: 4 Page 35 of 90 Event

Description:

PRZR Master Pressure Controller fails LOW (0-AP-53.00)

Cue: When initiated by Team 1-AP-31.00 SRO

20. CLOSE BLOCK VALVE FOR INOPERABLE PORV RO

• 1-RC-MOV-1536 if 1-RC-PCV-1455C INOPERABLE.

• 1-RC-MOV-1535 if 1-RC-PCV-1456 INOPERABLE.

Note: The SRO may determine that this action stops the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> clock.

1-AP-31.00 SRO 21. CHECK PRZR PORVS - EITHER INCAPABLE OF BEING MANUALLY CYCLED.

RO Reports NO, both PORVs are capable of being manually cycled.

Goes to RNO, THEN goes to Step 23 1-AP-31.00 SRO 23. NOTIFY THE FOLLOWING:

• OMOC

• STA

• I&C Contacts the above named individuals 1-AP-31.00 SRO 24. REFER TO TECH SPECS:

• 3.1.A.5 - Not applicable for this event.

• 3.1.A.6. A, Relief Valves - With one or both PORVs inoperable but capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) and maintain power to the associated block valve(s).

Otherwise, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce Reactor Coolant System average temperature to < 350°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• 3.1.C - Not applicable for this event.

1-AP-31.00 SRO 25. REVIEW APPLICABILITY:

• VPAP-2802

• EAL MATRIX SU6.1 STA The STA will report that he has reviewed these documents and discussed the results with the Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Event No.: 4 Page 36 of 90 Event

Description:

PRZR Master Pressure Controller fails LOW (0-AP-53.00)

Cue: When initiated by Team 1-AP-31.00 SRO

26. RESTORE PRESSURE CONTROL SYSTEM(S) TO NORMAL Maintains Pressurizer Pressure Control Systems in MANUAL.

---END OF EVENT 4---

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 37 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

Time Position Applicants Action or Behavior Momentary Loss of Vital Bus I Team Diagnose this failure using the following alarms and indications:

Annunciator 1E-A2/A3/A4, RC LOOP 1A/1B/1C LO FLOW CH-1.

Annunciator 1E-B2, RC LOOP 1A LO FLOW CH-2 Annunciator 1E-F6, PRZR LO LVL CH-1 Annunciator 1E-F4, RX TRIP CH-1 PRZR LO PRESS Annunciator 1E-F7, PRZR LO PRESS SI CH-1 Annunciator 1F-E7, STM GEN 1A LO-LO LVL CH-1 Momentary loss of Vital Bus I on Vertical Board Team enters 1-AP-10.01, LOSS OF VITAL BUS I.

Note: At Chief Examiners discretion an operator will contact MCR and report that a Security officer bumped UPS 1A-1 while on rounds. He heard what sounded like breakers operating.

1-AP-10.01 SRO Conducts Transient Brief of 1-AP-10.01 1-AP-10.01 SRO 1. CHECK UNIT AT POWER RO RO reports that Yes Unit 1 is at power.

1-AP-10.01 SRO 2. CHECK LETDOWN STATUS a) Check 1-CH-TV-1204A-CLOSED or DEENERGIZED.

b) Close Letdown Isolation valves; 1-CH-LCV-1460A and 1-CH-LCV-1460B.

c) Manually control charging flow to minimize PRZR rate of fill.

RO/BOP RO CLOSES 1-CH-LCV-1460A and 1-CH-LCV-1460B and reduces Charging flow.

1-AP-10.01 SRO 3. CHECK CONDENSER VACUUM STATUS a) Check for Vacuum lowering or 1-SV-TV-103 Closed or deenergized.

BOP BOP reports NO and team GOES to step 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 38 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

1-AP-10.01 SRO 4. CHECK CTMT IA STATUS a) Check 1-IA-TV-100A DEENERGIZED (NO goes to RNO).

RNO: Check open or open 1-IA-TV-100.

RO/BOP RO opens 1-IA-TV-100.

1-AP-10.01 SRO 5. CHECK SI ACTUATED.

NO goes to step 7.

1-AP-10.01 SRO 7. CHECK PRZR PRESSURE CONTROL SYSTEM a) Check PRZR heaters - DEENERGIZED (NO)

RNO: GO TO STEP 8.

1-AP-10.01 SRO 8. CHECK RCP COOLING STATUS a) Check 1-CC-TV-140B - DEENERGIZED (NO opens 1-CC-TV-140B)

RO opens 1-CC-TV-140B.

1-AP-10.01 SRO 9. CHECK CTMP PARTICULATE/GAS RM STATUS.

a) Check 1-RM-TV-100A OR 1-RM-TV-100C DEENERGIZED (NO GOES TO STEP 10) 1-AP-10.01 SRO 10.CHECK CTMT VACUUM PUMP STATUS a) Check 1-CV-TV-150A or 1-CV-TV-150C DEENERGIZED (NO GOES TO STEP 11) 1-AP-10.01 SRO 11. CHECK CTMT SUMP PUMP STATUS a) Check 1-DA-TV-100 - DEENERGIZED (NO GOES TO STEP 12) 1-AP-10.01 SRO 12. CHECK PDTT PUMP STATUS a) Check 1-DG-TV-108A - DEENERGIZED (NO GOES TO STEP 13)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 39 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

1-AP-10.01 SRO 13. REFER TO ATTACHMENT 1 FOR A LIST OF MAJOR COMPONENT FAILURES.

Team may or not refer to the Attachment at this time because power is restored.

1-AP-10.01 SRO 14. Direct STA to initiate 0-NSP-CM-001, PLANT COMPUTER SYSTEM (PCS)

OPERABILITY.

Not necessary to do at this time since power is restored.

1-AP-10.01 SRO NOTES before step 15

• A de-energized AC Vital Bus shall be re-energized within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR the unit must be placed in Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• Vital Bus 1-IA voltage can be read on PCS (ERF if not removed)

Computer point V1VB002A.

• All Vital Bus voltages can be read on Group Review 25.

• Loss of Vital Bus 1-IA de-energizes ICCM Train A.

RO Acknowledges the Notes.

1-AP-10.01 SRO 15. CHECK BOTH SECTION OF VITAL BUS DE-ENERGIZED.

Per 15 RNO team will go to step 17 because the bus is restored.

1-AP-10.01 NOTE: Shift Supervision must determine the appropriateness of the following steps depending on initial plant condition when Vital Bus was lost.

SRO 17. CHECK EXCESS LETDOWN IN SERVICE.

RO answers NO, team directed to GO TO STEP 20.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 40 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

1-AP-10.01 SRO 20. RETURN NORMAL LETDOWN TO SERVICE IAW 1-OP-CH-020.

RO/BOP BOP directed to perform 1-OP-CH-020.

Note: 1-OP-CH-020 is at the end of this section. The BOP will probably be assigned to do this.

1-AP-10.01 SRO 21. CHECK RCP SEAL LEAKOFF TEMPERATURE - LESS THAN 235oF.

RO answers YES and team proceeds to step 22.

1-AP-10.01 SRO 22. OPEN CC WATER THERMAL BARRIER RETURN TVs.

This step was already done, team proceeds to next step.

1-AP-10.01 SRO 23. RETURN CTMT PARTICULATE GAS RADIATION MONITOR TO SERVICE.

a) OPEN CTMT GAS and Particulate Radiation Monitoring Trip valves:

• 1-RM-TV-100A

• 1-RM-TV-100B

• 1-RM-TV-100C b) Start the Radiation Monitor Pump.

c) Notify HP that the radiation monitor has been returned to service.

RO/BOP Operator opens 1-RM-TV-100A, 100C, and starts Radiation Monitor pump.

1-AP-10.01 SRO 24. RESTORE CTMT IA COMPRESSOR TO SERVICE:

RO/BOP a) Open 1-IA-TV-100 (opened previously at step 4) b) Open 1-IA-TV-101A (opens 1-IA-TV-101A) c) Open or check open 1-IA-TV-101B (Checks open) d) Start 1-IA-C-4A or 1-IA-C-4B (Checks that one is running) e) Place IA compressor NOT started in AUTO (One comp should be in auto) f) Locally close 1-IA-446, 447. (Should already be closed)

Team proceeds to next step.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 41 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

1-AP-10.01 SRO 25. RETURN AIR EJECTOR RADIATION MONITOR TO SERVICE.

Air Ejector Rad monitor is in service.

1-AP-10.01 SRO 26. Return the following pumps to service:

RO/BOP

• CTMT Sump Pumps; 1-DA-P-4A and 1-DA-P-4B.

• CTMT Vacuum Pumps; 1-CV-P-1A and 1-CV-P-1B.

• Primary Drain Xfer pumps; 1-DG-P-1A and 1-DG-P-1B.

No expected operator action since power was momentarily lost. Pumps will remain in pre-event condition (one pump in AUTO, the other pump in OFF)

Remaining steps in AP-10.01 are mostly administrative or require other operator support. At Chief Examiners discretion proceed to the next event.

1-AP-10.01 SRO 27. Restore SG Blowdown IAW 1-OP-BD-001, STEAM GENERATOR BLOWDOWN SYSTEM OPERATIONS.

This should be done by another operator.

1-AP-10.01 SRO 28. OPEN MS LINE TRAP TVs:

RO/BOP

• 1-MS-TV-109.

Operator opens 1-MS-TV-109.

1-AP-10.01 SRO 29. ALIGN AREA VENTILATION IAW SHIFT SUPERVISION DIRECTION:

• Fuel Building.

• Decon Building.

Operators assigned to restore ventilation as necessary.

1-AP-10.01 SRO 30. RESET NI-41 DROPPED ROD SIGNAL BY PLACING POWER RANGE TEST SWITCH TO RESET.

RO/BOP RO places power range test switch to reset.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 42 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

1-AP-10.01 SRO 31. RESET CTMT ISOLATION TVs:

• 1-SS-TV-102

• 1-DA-TV-100A

• 1-DG-TV-108A

• 1-VG-TV-109A

• 1-SI-TV-101A

• 1-SS-TV-100A

• 1-SS-TV-101A

• 1-SS-TV-102A

• 1-SS-TV-106A Another operator will be assigned this.

1-AP-10.01 SRO 32. NOTIFY THE FOLLOWING

• OMOC

• Manager Operations

---END OF EVENT 5---

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 43 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 44 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 45 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 5 Page 46 of 90 Event

Description:

Momentary Loss of Vital Bus I Cue: Cue by Evaluator.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 47 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

Time Position Applicants Action or Behavior Team Diagnose the failure based upon the following alarms and indications:

Annunciator 1H-G5, STM GEN 1A LVL ERROR Annunciator 1H-G6, STM GEN 1B LVL ERROR Annunciator 1H-G7, STM GEN 1C LVL ERROR Annunciator 1H-A4, T AVG < > T REF DEVIATION Annunciator 1F-F4,(G4), STM GEN 1A CH3 (CH4) HI STM LINE FLOW Annunciator 1F-F5 (G5), STM GEN 1B CH3 (CH4) HI STM LINE FLOW Annunciator 1F-F6 (G6), STM GEN 1C CH3 (CH4) HI STM LINE FLOW All SG NR Level indications rising SRO Direct RO to trip the reactor and perform the Immediate Actions of 1-E-0.

1-E-0, Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Presses reactor trip button.

b) Check the following:

All Rods On Bottom light - LIT Identifies All Rods on Bottom LIT on CERPI Screen.

Reactor trip and bypass breakers - OPEN Identifies Reactor Trip and Bypass breakers Open on Benchboard Mimic.

Neutron flux - LOWERING Identifies PR NI N41, N42, and N41 indications at ~0%; and IR indicators N35/N36 Lowering.

Reports to SRO Reactor Tripped.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 48 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-0, Reactor Trip or Safety Injection RO [2] CHECK TURBINE TRIP:

a) Manually trip the turbine Presses both Turbine Trip pushbuttons - simultaneously.

b) Check all turbine stop valves - CLOSED Identifies Turbine SVs closed using indication lights on Turbine Control section.

c) Isolate reheaters by closing MSR steam supply SOV 1-MS-SOV-104 Places 1-MS-SOV-104 control switch in close.

d) Check generator output breakers - OPEN (Time Delayed)

Identifies Main generator output breakers open.

Reports to SRO Turbine is Tripped.

1-E-0, Reactor Trip or Safety Injection RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED Identifies H and J buses are energized by checking Voltage indicated on

1. 1 and #3 EDG control panels.

Reports Both AC Emergency Buses energized.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 49 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-0, Reactor Trip or Safety Injection RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

LHSI pumps - RUNNING Identifies A/B LHSI pumps running using breaker and amp indications.

SI annunciators - LIT A-F-3 (SI Initiated Train A)

A-F-4 (SI Initiated Train B)

Identifies both Annunciators LIT.

b) Manually initiate SI Presses Manual SI buttons, Train A and Train B.

Reports E-0 Immediate Actions are complete, Have SI flow to the core.

1-E-0, Reactor Trip or Safety Injection SRO Hands out Continuous Action Pages for E-0 to RO and BOP, provides Attachments 1, 2, and 3 to BOP.

Leads a Transient Brief to describe the Plant Status, and asks RO/BOP if any items identified during the E-0 Immediate Actions would have higher priority than continuing with E-0. RO/BOP may identify MSTVs close following reactor trip and safety injection. STA will have no input for the brief.

SRO closes the Transient Brief and continues E-0 with the RO.

1-E-0, Reactor Trip or Safety Injection SRO 5. INITIATE ATTACHMENT 1 Directs BOP to perform E-0 Attachment 1, 2, and 3.

CT-2: Restore at least one MDAFW pump prior to SG WR level lowering to FR-H.1 Feed and Bleed criteria (12%). Failing to do this would significantly complicate the scenario by challenging heat sink E-0 Attachments and components BOP will identify and reposition begin at section 8 of this scenario guide.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 50 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-0, Reactor Trip or Safety Injection SRO *6. CHECK RCS AVERAGE TEMPERATURE STABLE AT 547°F OR RO TRENDING TO 547°F Report NO, RCS Temperature lowering (and provide current Tave value).

SRO Goes to Step 6 RNO IF temperature less than 547°F AND lowering, THEN do the following:

a) Stop dumping steam.

RO Reports Yes, Steam Dumps are closed.

SRO b) IF cooldown continues, THEN control total feed flow. Maintain total feed flow greater than 350 gpm [450 gpm] until narrow range level greater than 12% [18%] in at least one SG.

RO Identify RCS Tave Lowering.

SRO Direct RO to throttle AFW to all SGs to ~120 gpm.

RO Throttle AFW to the SGs to ~120 gpm per SG and report when complete.

SRO c) IF Cooldown continues, THEN close MSTVs.

RO Reports MSTVs are closed. May report that all three SGs appear to be faulted.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 51 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-0, Reactor Trip or Safety Injection SRO 7. CHECK PRZR PORVs AND SPRAY VALVES:

a) PRZR PORVs - CLOSED RO Reports Yes, PRZR PORVs closed.

SRO b) PRZR spray controls Demand at Zero OR Controlling pressure (previous to Rx Trip, RO controlling pressure manually).

RO Reports Yes, Demand at zero.

SRO c) PORV block valves - AT LEAST ONE OPEN RO Reports Yes, one block valve open.

1-E-0, Reactor Trip or Safety Injection SRO NOTE Prior to Step 8: Seal injection flow should be maintained to all RCPs.

RO Acknowledges NOTE.

SRO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Reports Yes, 3 running and flowing to the RCS. May report 2 running depending upon BOP speed of progression through E-0, Attachment 1.

SRO b) RCS subcooling - LESS THAN 30°F [85°F]

RO Reports No, subcooling is (provides actual subcooling value.)

SRO Step 8 RNO: Goes to Step 9.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 52 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-0, Reactor Trip or Safety Injection SRO

9. CHECK IF SGs ARE NOT FAULTED:

Check pressures in all SGs:

STABLE OR RISING AND GREATER THAN 100 PSIG RO Reports No, SG pressures are (current value) and lowering.

SRO Step 9 RNO: IF any SG pressure lowering in an uncontrolled manner OR is completely depressurized, THEN GO TO 1-E-2, FAULTED STEAM SRO GENERATOR ISOLATION.

SRO Announces transition to E-2; RO/BOP acknowledge transition.

1-E-2, Faulted SG Isolation SRO SRO conducts a focus brief, identifies that all three SGs as faulted, and asks if RO has identified any condition that would prevent continuing with E-2 to a transition to ECA-2.1.

RO Report No, agree on continuing with E-2.

SRO SRO closes Focus Brief and continues with E-2.

1-E-2, Faulted SG Isolation SRO CAUTIONS Prior to Step 1:

• At least one SG must be maintained available for RCS cooldown.

• Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

RO Acknowledges CAUTIONS.

SRO 1. CHECK MSTV AND BYPASS VALVE ON AFFECTED SG(s) - CLOSED RO Reports Yes, MSTVs and bypass valves closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 6 Page 53 of 90 Event

Description:

Main Steam Break in Turbine Building, Reactor Trip W/ SI.

Cue: by Evaluator.

1-E-2, Faulted SG Isolation SRO 2. CHECK IF ANY SG SECONDARY SIDE IS INTACT:

Check pressures in all SGs - ANY STABLE OR RISING RO Reports No, All SG pressures are (provides current pressure) and lowering.

SRO Step 7 RNO: IF all SG pressures lowering in an uncontrolled manner, THEN GO TO 1-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.

SRO Announces transition to ECA-2.1.

RO/BOP acknowledge transition.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 7 Page 54 of 90 Event

Description:

Three Faulted SGs in Safeguards.

Cue: by Evaluator.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

SRO SRO conducts Focus brief to update on Plant Status, and handout Continuous Action Pages for ECA-2.1. SRO will ask team members if any conditions have been identified that precludes continuing with ECA-2.1.

RO/BOP Report that no conditions have been identified.

SRO Continues with ECA-2.1.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO CAUTION Prior to Step 1: If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.

1. CHECK SECONDARY PRESSURE BOUNDARY:

• MSTVs and bypass valves - CLOSED RO Report Yes, closed.

• SG PORVs - CLOSED Report Yes, Closed.

• Main Steam line NRVs - CLOSED (1-MS-NRV-101A / B / C)

RO Report No, Open SRO will direct RO to Close the NRVs RO RO will close NRVs and report when they completed stroking closed.

• TD AFW pump steam supply valves - CLOSED Report No, Safeguards inaccessible.

• Feed REG valves - CLOSED Report Yes, Closed

• SG FW bypass flow valves - CLOSED Report Yes, Closed

• SG FW isolation MOVs - CLOSED Report No, Open

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 7 Page 55 of 90 Event

Description:

Three Faulted SGs in Safeguards.

Cue: by Evaluator.

SRO SRO will direct RO to Close the FW isolation MOVs.

RO RO will close FW isolation MOVs and report when they completed stroking closed.

• SG blowdown TVs - CLOSED Report Yes, Closed.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO CAUTION Prior to Step 2: A minimum of 60 gpm [100 gpm] feed flow must be maintained to each SG with a narrow range level less than 12% [18%].

RO Acknowledges CAUTION.

SRO NOTE prior to Step 2: Shutdown Margin should be monitored during RCS cooldown.

STA Acknowledge NOTE.

SRO

2. CONTROL FEED FLOW TO MINIMIZE RCS COOLDOWN:

a) Check cooldown rate in RCS cold legs - LESS THAN 100°F/hr RO Reports No, Cooldown rate is (provides current value.)

STA will agree with Cooldown Rate determined by RO.

SRO Step 2 RNO: Lower feed flow to 60 gpm [100 gpm] to each SG. GO TO Step 2c.

Directs RO to throttle flow to ~ 60 gpm to each SG.

When AFW is throttled less than a total of 350 gpm, STA will report that a RED Path on the Heat Sink Status Tree is indicated.

SRO Will announce transition to FR-H.1. RO/BOP will acknowledge transition.

BOP will suspend E-0 Attachments.

SRO will read CAUTION Prior to STEP 1, FR-H.1:

If total feed flow is less than 350 gpm [450 gpm] due to operator action, this procedure should NOT be performed.

SRO will announce Transition back to ECA-2.1. RO/BOP will acknowledge transition.

CT-3: Lower AFW flowrate to 60 gpm to each SG if RCS cooldown rate is >

100°F/hour to prevent entry into FR-P.1. Failing to do this could cause an entry into FR-P.1 which is not needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 7 Page 56 of 90 Event

Description:

Three Faulted SGs in Safeguards.

Cue: by Evaluator.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO NOTE Prior to Step 3: Seal injection flow should be maintained to all RCPs.

RO Acknowledges NOTE.

SRO 3. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Reports Yes, (identifies number of CH pumps running).

Note: based on speed of BOP progression through Attachment 1 of 1-E-0, 3 or 2 CH pumps may be running at this time.

SRO b) RCS subcooling - LESS THAN 30°F [85°F].

RO Reports No, (identifies actual subcooling).

SRO GOES to Step 4.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO CAUTION Prior to Step 4: If any PRZR PORV opens because of high PRZR pressure, the PORV must be checked closed or isolated after pressure lowers to less than 2335 psig.

RO Acknowledges CAUTION.

SRO 4. CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE RO Reports Yes, power available to both Block Valves.

SRO b) PRZR PORVs - CLOSED RO Reports Yes, both PRZR PORVs closed.

SRO c) PRZR PORV block valves - AT LEAST ONE OPEN RO Reports Yes, One block valve open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 7 Page 57 of 90 Event

Description:

Three Faulted SGs in Safeguards.

Cue: by Evaluator.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO 5. CHECK SECONDARY RADIATION:

a) Initiate periodic activity sampling of all SGs IAW Attachment 1.

SRO Confers with Shift Manager to initiate periodic sampling.

SRO b) Check unisolated secondary radiation monitors:

RO/Unit 2 Main steamline - Report Yes, Main Steam Radiation Normal.

RO TD AFW pump exhaust - Reports Yes, TDAFW Radiation normal.

Unit 2 Condenser air ejector - Reports Yes, Condenser A/E Radiation normal.

SRO c) Secondary Radiation - NORMAL RO Reports Yes, Secondary Radiation Normal.

1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators SRO CAUTION Prior to Step 6: RCS pressure should be monitored. If RCS pressure lowers in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.

RO Acknowledges CAUTION SRO 6. CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO Report Yes, (identifies number of LHSI pumps running) with suction aligned to RWST.

SRO b) Check RCS pressure:

1) Pressure - GREATER THAN 250 PSIG [400 PSIG]

2) Pressure - STABLE OR RISING RO Reports Yes, RCS pressure is (gives actual pressure)

Reports No, RCS pressure lowering.

SRO 6. b) RNO GO TO Step 7.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No.: 7 Page 58 of 90 Event

Description:

Three Faulted SGs in Safeguards.

Cue: by Evaluator.

Scenario Termination based on Evaluator Cue, SI Re-initiation, and Cooldown rate has been controlled.

---END OF EVENT 7---

---END OF SCENARIO #3---

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 3 Event No. 8 Page 59 of 90 E-O Attachments 1, 2, and 3. FOLDOUT PAGES FOR REFERENCED PROCEDURES

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Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 78 of 90 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -378 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Enter/Verify the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Delete in Type (Auto or Manual)

NI1001 POWER RANGE 5 0 1 0 -1 A CHNL N41 FAILURE CN1503 Disable CN-P-1C 0 0 3 FALSE TRUE M Autostart CN0101 MAIN CN PUMP 5 0 3 FALSE TRUE M CN-P-1A TRIPS: OVR-CURREN RC1501 PRZR PRESS 5 60 5 0 -1 M CONTROLLER FAILURE EL2001 LOSS OF 120V AC 5 0 7 FALSE TRUE 2 M VITAL BUS I EL2002 LOSS OF 120V AC 5 0 7 FALSE TRUE 2 M VITAL BUS IA V2KA8 K-A-8 UPS SYSTEM 2 0 7 ON OFF M 1A TROUBLE MS0101 'A' MAIN STM LINE 5 180 9 0 20 M RUPTURE AT HEADER MS02 STM SUP LINE TO 20 0 9 FALSE TRUE M STM HDR AFW PP RUPTURES MS0401 'A' MAIN STM LINE 20 600 9 0 2.0 M RUPTURE BEFORE TRIP VV MS0402 'B' MAIN STM LINE 20 600 9 0 2.0 M RUPTURE BEFORE TRIP VV MS0403 'C' MAIN STM LINE 20 600 9 0 2.0 M RUPTURE BEFORE TRIP VV FP0301 FPS FACP07 0 0 30 FALSE TRUE M ALARM HORN FAILURE FP0302 FPS PC SPEAKER 0 0 30 FALSE TRUE M FAILURE CH59 Disable CH-MOV-381 0 0 30 FALSE TRUE M AUTO Closure VS2002 DISABLE VS-MOD- 0 0 30 FALSE TRUE M 103B AUTO CLOSE FW48 DISABLE AFWP3A 0 0 30 FALSE TRUE M AUTO START

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 79 of 90 SIMULATOR OPERATORS GUIDE FW49 DISABLE AFWP3B 0 0 30 FALSE TRUE M AUTO START Enter/Verify the following EVENT TRIGGERS:

TRIGGER TYPE DESCRIPTION 1

Manual N41 Fails LOW A CN Pump Trip on Overcurrent/C CN Pump Fail to Auto 3 Manual Start 5 Manual 1-RC-PT-1444 Fail High 7 Manual Momentary loss of Vital Bus I Steam Break in Turbine Building, followed by TDAFW Pump 9 Manual Steam Supply Pipe Break In SFGDS 30 Manual FP0301 FPS FACP07 ALARM HORN FAILURE 30 Manual FP0302 FPS PC SPEAKER FAILURE 30 Manual CH59 Disable CH-MOV-381 AUTO Closure 30 Manual VS2002 DISABLE VS-MOD-103B AUTO CLOSE 30 Manual FW48/49 DISABLE FW-P-3A/3B AUTO START

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 80 of 90 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Verify All pink magnets collected from previous scenarios.

Verify vertical board PCS monitor on ALARM SCREEN.

Reset ICCMs.

Verify all calcalc points are displayed on PCS: U9103, U9104, U9105V.

Verify Component Switch Flags; 1-VS-F-58A and 1-VS-F-58B switches (AUTO AFTER STOP).

Verify Brass Caps properly placed (Hi-Hi CLS, MSTVs, CH-MOV-1350, CW and SW MOVs, CTMT Hogger suction, CNDSR Vacuum breaker).

Radiation Monitors all clear.

Verify SG PORVs set for 1035 psig.

Verify D bank rod height at 229 steps and Bank Overlap Counter at 612.

Advance Charts.

Place blue magnets above switches 1-MS-MOV-100A/B/C/D.

Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset).

Verify SYNC keys in proper place.

Verify MOL reactivity plans and benchboard Reactivity Placard is current.

Reset Blender Integrators for Boric Acid to 100 and PG to 1000.

Verify Stop Watches are available for RO and BOP.

Verify Simulator Session In Progress light is turned ON.

Verify no persons are logged onto network computer to ensure no procedures displayed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 81 of 90 SIMULATOR OPERATORS GUIDE Verify PCS time matches Sim time.

Spot check all ARPs are clean, verify the following Procedures are available in the procedure drawers.

E-0 E-2 ECA-2.1 0-AP-53.00 1-OP-CH-020 1-AP-4.00 1-AP-21.00 1-AP-31.00 1-FR-H.1 1-OP-TM-005 1-OPT-RP-001 1-AP-10.01 1-OPT-RX-001 0-OP-ZZ-002 Verify Reactivity Placard is current.

Verify Flux target matces PCS.

Verify ALL PINK MAGNETS are accounted for.

Reset Blender Integrators for Boric Acid to 100 and PG 1000.

ARPs to verify clean:

Event 2 Event 3 Event 4 Event 5 1G-E4 1K-D4 1C-G8 1E-A2 1G-H1 1E-B2 1E-F6 1E-F7 1F-E7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 82 of 90 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

TEAM 1 TEAM 2 TEAM 3 SRO RO BOP Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 83 of 90 SIMULATOR OPERATORS GUIDE OPERATING PLAN:

Unit 1 is at 100% power with RCS boron concentration of 795 ppm.

During the last shift, 1-SD-P-1B, B High Pressure Drain Pump has started to degrade based on elevated vibration levels. The Team will ramp the unit to 84% based on 1-OP-TM-005. All systems and crossties are operable with the following exception:

• Unit 1 and 2 Containment Temperature to the MCR Fire Panel are non-functional. In accordance with TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors, are in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to commence a Ramp to 84% power in accordance with 1-OP-TM-005, Unit Ramping Operations, using the Ramp Plan provided, upon relieving the watch. The SM has directed a 0.5%/min ramp rate to be used for the ramp. Performance of 1-OP-TM-005 has been authorized and has been PSA analyzed for current plant conditions. Another operator will operate the MSRs IAW 1-OP-TM-007, MSR Operation During or Following power reductions.

The next shift will perform the Heater Drain pump swap and subsequent ramp up to 100%.

The previous shift performed two 30 gallon dilutions for temperature control.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 84 of 90 SIMULATOR OPERATORS GUIDE EVENT 1 Ramp down in power from 100% to 84% IAW 1-OP-TM-005, Unit Ramping Operations The Team will pre-brief the Unit Ramp prior to entering the Simulator. The Team will be provided a Copy of 1-OP-TM-005, Unit Ramping Operations, signed off to Section 5.1 for the power reduction. Following the pre-brief, the Team will enter the Simulator and walk down the control boards. When the Team and the Evaluators are ready, the Simulator will be placed in run.

Shift Manager:

• If contacted, acknowledge start of Ramp to 84%.

• If asked: I&C is standing by to adjust IRPIs as necessary.

I&C:

• If contacted: Standing by to adjust IRPIs as necessary.

System Operator/MOC

• If contacted: acknowledge Surry Unit 1 starting ramp to 84% at normal rate.

Field Operators:

• If contacted as Unit 1 Turbine Building: monitoring Lube oil temperatures during ramp.

• If contacted as Polishing Building Operator: There are 6 Beds in service; D/P ~27 psig.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 85 of 90 SIMULATOR OPERATORS GUIDE EVENT 2 PR Channel N-41 Fail Low When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

• If contacted, acknowledge N-41 failure.

• If contacted, will notify I&C of the failure, will notify the OMOC.

• When notified: acknowledge but do not imply agreement with Tech Spec requirements as identified by the SRO.

• If contacted, will take responsibility for writing the CR.

• If asked: will notify Reactor Engineering of need to perform flux map.

• If asked: SM will confer with the OMOC concerning continuing the ramp.

STA:

• If contacted, acknowledge Tech Spec requirements for the failure, but do not imply agreement with requirements identified by the SRO.

• If the team has a transient brief: The STA will have no input for the brief.

• If asked: will notify Reactor Engineering of need to perform flux map.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 86 of 90 SIMULATOR OPERATORS GUIDE EVENT 3 1-CN-P-1A trip/Failure of 1-CN-P-1C to auto start When cued by examiner, implement Trigger #3.

CT-1: The BOP must start the standby Condensate pump prior to SG level dropping low enough to cause an auto or manual reactor trip.

Operations Supervisor/Management:

• If contacted, Acknowledge failure.

• If contacted: Take responsibility for submitting CR.

• If contacted: Will notify Maintenance and OMOC of the failure.

Maintenance/ Work Week Coordinator:

If contacted, will acknowledge the failure, contact Maintenance to commence investigation.

STA:

• If contacted, Acknowledge the failure

• If the team has a transient brief: Will have no input for a transient brief.

Field Operators:

When contacted to check status of CN Pumps: Wait three (3) minutes and report 1-CN-P-1C conditions normal after start; 1-CN-P-1A exhibits no obvious cause for the trip.

When contacted to check status of 1-EP-BKR-15B4: Wait 3 minutes and report breaker 15A4 has timed overcurrent drop on A phase.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 87 of 90 SIMULATOR OPERATORS GUIDE EVENT 4 Master PRZR Pressure Controller, 1-RC-PC-144J Fails Low.

When cued by examiner, implement Trigger #5.

Operations Supervisor/Management:

• If contacted, acknowledge the failure of the Master Pressurizer Controller.

• If asked: will contact I&C and OMOC of the failure.

• If contacted: acknowledge Tech Specs requirement related to the failure, but do not imply agreement.

• If contacted: will take responsibility for submitting CR.

• If asked: SM will confer with the OMOC concerning continuing the ramp with Pressurizer Pressure control in manual.

STA:

• If contacted, acknowledge the failure of the Master Pressurizer Controller.

• If contacted: acknowledge Tech Specs requirement related to the failure, but do not imply agreement.

• If the team has a transient brief: The STA will have no input for the brief.

Maintenance/ Work Week Coordinator:

• If contacted, will acknowledge the failure, contact I&C to commence investigation of the failed controller.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 88 of 90 SIMULATOR OPERATORS GUIDE EVENT 5 Momentary loss of Vital Bus I When cued by examiner, implement Trigger #7.

Operations Supervisor/Management:

• If contacted, acknowledge the failure of Vital Bus I.

• If contacted, will notify I&C of the failure, will notify the OMOC.

• If contacted: will take responsibility for submitting CR.

STA:

• If contacted, acknowledge the failure.

• If the team has a transient brief: The STA will have no input for the brief.

I&C:

• If requested: will prepare for placing the channel in trip.

Maintenance/ Work Week Coordinator:

• If contacted, will notify Electrical Maintenance of the failure to commence investigation.

Field Operator

• If contacted to investigate, Report back after 3 minutes that you spoke with a security guard who thinks he may have bumped up against UPS 1A-1. The Static switch is carrying VBI, no other problems noted.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 89 of 90 SIMULATOR OPERATORS GUIDE EVENT 6 Steam Header Break in TB When cued by examiner, implement Trigger #9.

CT-2: Restore at least one MDAFW pump prior to SG WR level lowering to FR-H.1 Feed and Bleed criteria (12%). Failing to do this would significantly complicate the scenario by challenging heat sink.

Operations Supervisor/Management:

• If contacted: Acknowledge Reactor Trip and SI; agree to notify the OMOC.

• If contacted to close 1-CH-223: Acknowledge order (this will take approx. 45 min)

STA:

• If the team has a transient brief: The STA will have no input for the brief.

• If asked: Annunciator 1E-F3 (Hi Steam Flow SI) came in and cleared quickly.

Unit Two:

• If asked, RWST cross-ties on Unit 2 are closed.

• If asked, Simulate manually opening Unit 2 RWST cross-tie valves.

• If asked, External MCR D/P indicators indicate the same as indicated pressure on Unit 2 Vent Panel.

• If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

• When: BOP reaches Page 6 of E-0, Attachment 3, you will take responsibility for the Attachment at this point.

• If asked: Unit 1 main steam and condenser A/E radiation is normal.

Field Operators: (Wait 4 minutes from direction to check Safeguards and report of conditions.)

• If contacted, SFGDs steam side is inaccessible; steam is blowing out of the steam side louvers.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-3 Scenario No.: 3 Page 90 of 90 SIMULATOR OPERATORS GUIDE EVENT 7 3 Faulted SG in SFGDs CT-3: Lower AFW flowrate to 60 gpm to each SG if RCS cooldown rate is > 100°F/hour to prevent entry into FR-P.1. Failing to do this could cause an entry into FR-P.1 which is not needed.

STA:

• If the team has a transient brief: The STA will have no input for the brief.

• When Team has throttled to < 350 gpm: Notify SRO of Red Path on Heat Sink Status Tree.

Unit Two:

• If asked, RWST cross-ties on Unit 2 are closed.

• If asked, Simulate manually opening Unit 2 RWST cross-tie valves.

• If asked, External MCR D/P indicators indicate the same as indicated pressure on Unit 2 Vent Panel.

• If requested, Chilled Water flows have been adjusted per caution prior to Step 10 of E-0, Attachment 3.

Field Operators: (Wait 4 minutes from direction to check Safeguards and report of conditions.)

• If contacted, SFGDs steam side is inaccessible; steam is blowing out of the steam side louvers.

Role play as other individuals as needed.

Scenario Termination based on Evaluator Cue, SI Re-initiation, and Cooldown rate has been controlled.

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Facility: Surry Power Station Scenario No.: 4 Op-Test No.: 2021-301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 at 13% power, with plant startup in progress; BOL. Unit 2 at 100% power. All systems and crossties are operable with the following exceptions:

• Unit 1 startup is in progress per 1-GOP-1.8 and 1-OP-TM-001.

• Containment Smoke and heat detectors are non-functional due local fire panel failure (2 days ago). TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Turnover: The Crew will be provided a copy of 1-GOP-1.8 and 1-OP-TM-001 and a ramp plan to place Unit 1 online.

Event Event Type* Event No. Description N BOP/SRO 1N R SRO/RO Place Unit 1 MFRVs in AUTO and ramp up IAW 1-GOP-1.8/1-OP-TM-001.

2N I-BOP/SRO 1-CC-RM-105 fails with failure of vent valve auto closure. ARP 0-RM-TS-SRO L5/M5.

3N C-RO/SRO Normal Charging Flow Controller 1-CH-FC-1122C fails high. 0-AP-53.00.

4N C-BOP/SRO Trip of running EH pump with failure of standby pump auto start. ARP TS-D2. (CT-1) 5 C-RO/SRO A CH SW pump trip with failure of B CH SW pump auto start. ARP 1D-TS-SRO G5.

6N C-RO/SRO Dropped Rod. 0-AP-1.00, 1-E-0, 1-ES-0.1.

7 M-ALL SBLOCA, with auto start failure of both LHSI pumps. 1-AP-16.00, 1-E-0.

(CT-2) 8 M-ALL LBLOCA, with A and B CS pump auto start failure, failure of CS Discharge MOVs to auto open. A CS pump lockout. 1-FR-Z.1, 1-E-0.

(CT-3)

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

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 LIST OF CRITICAL TASKS CT # EVENT DESCRIPTION MET ()

4, Start standby EH fluid pump prior to turbine control valves failing closed. (~8 1/2 minutes, 6 minutes from the first CT-1 Annunciator, with no operator action). Failure to respond to this event will result in an unnecessary turbine/reactor trip.

CT-2 7, Start at least one LHSI pump prior to exiting 1-E-0 to restore function. Failure to do this, prior to exiting 1-E-0, will create a challenge to Core Cooling during the subsequent LBLOCA.

CT-3 8, Establish B train of Containment Spray flow within 15 minutes of Containment Pressure reaching 23 psia to prevent unnecessary EAL escalation. Because of the failure of the Containment Spray pumps to start, there is a loss of that function. Failure to establish one train of CS Pump flow within 15 minutes will result in a potential loss of the Containment barrier (per the EAL Matrices). That, paired with the Loss of RCS barrier, will require escalation from an Alert to a Site Area Emergency.

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Event 1: Place Unit On-Line and Ramp Up in Power. (R - RO/SRO, N- BOP/SRO)

The Team will pre-brief 1-GOP-1.8, Unit Startup, HSD to Max Allowable Power (step 5.6.27), and 1-OP-TM-001 (Section 5.8), Turbine-Generator Startup to 20% - 25%

Turbine Power prior to Simulator entry. A reactivity plan will be provided for the Team use during the pre-brief and in the Simulator for the Ramp up in power. The Team will place the Main Feedwater Regulating Valves in AUTO, close the Feedwater bypass HCVs, and commence a ramp up in power. To allow the team time to set up PCS trends, a surrogate operator will be responsible for feed water control until the team relieves the watch; the BOP will then assume SG level control and the surrogate will leave the simulator floor.

Verifiable Action(s):

1) RO: Manipulate rod control and CVCS Blender to control Tave and Flux during the power escalation.

2) BOP: Place Main FRVs in AUTO.

3) BOP: Manually close Main Feed Bypass HCVs during power escalation.

Event 2: 1-CC-RI-105, CC RM, fail high without associated auto action. (I - BOP/SRO, TS

- SRO)

After the Team has raised power, stable control of SG NR level with FRVs in auto has been achieved, and the Evaluation Team is ready, the malfunction is initiated. This failure causes 1-CC-RI-105 Alert and High alarms to actuate with the failure of HCV-CC-100, CC Surge TK VNT Isol VV, to auto close. The BOP will respond to the RM alarm and take action IAW with RM Annunciator Response Procedure.

Verifiable Action(s):

1) BOP: Close HCV-CC-100, CC Surge Tank vent valve.

Technical Specifications (1):

1) Tech Spec 3.13.E, Whenever the component cooling water radiation monitor is inoperable, the surge tank vent valve shall remain closed. (This Tech Spec also satisfies Tech Spec Table 3.7-5.)

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Event 3: Charging flow controller 1-CH-FT-1122C Fail High. (C - RO/SRO)

When the Evaluation Team is ready, the malfunction will be actuated. The malfunction will cause The Charging flow transmitter to Fail High. This will cause charging flow to lower, resulting in Letdown perturbations based on reduced cooling in the Regen Heat Exchanger. Also, Pressurizer level will lower. The RO is expected to diagnose the failure based on alarms and indications received and take manual control of CH flow.

Verifiable Action(s):

1) RO: Take manual control of CH flow.

2) RO: Control Charging flow within the designated PRZR Level band.

Event 4: Running EH pump trips, standby EH pump fails to auto start. (C - BOP/SRO)

This failure causes the running EH pump to trip with the backup pump failing to auto trip.

Approximately 2 minutes after the EH pump trip, Annunciator TS-D2 will come in for Low EH fluid pressure. The BOP will perform the ARP, diagnose the failure based on alarms and EH pump status, and start 1-EH-P-MP2.

Verifiable Action(s):

1) BOP: Start 1-EH-P-MP2.

Critical Task(s):

CT-1: Start standby EH fluid pump prior to automatic OR manual reactor/turbine trip.

(~8 1/2 minutes, 6 minutes from the first Annunciator, with no operator action). Failure to respond to this event will result in turbine control valves failing closed and an unnecessary turbine/reactor trip.

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Event 5: Trip of the running CH pump SW pump, with failure of the redundant pump to auto start. (C - RO/SRO, TS - SRO)

This failure causes the running CH pump SW pump (1-SW-P-10A) to trip, and the redundant pump fails to auto start on low pressure. The Team should respond by implementing ARP 1D-G5, SW OR CC PPS DISCH TO CHG PUMPS LO PRESS, start 1-SW-P-10B, and verify CH Pump SW flow restored.

Verifiable Action(s):

1) RO: Start 1-SW-P-10B.

Technical Specifications (1):

1) Tech Spec 3.0.1, Place the Unit in HSD in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, CSD in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, in effect.

Technical Requirements Manual (1):

1) TRM 3.7.9, Appendix R Alternate Shutdown Equipment and MRule(a)(4) Fire Risk Equipment, Table 3.7.9-1, 1-SW-P-10A. With 1-SW-P-10A nonfunctional:

-A.2, Implement App R hourly fire watch in Unit 1 ESR, Unit 1 and 2 Turbine Buildings Basement North Wall, MER 3 within 14 days.

-A.3, Restore instrument to functional status within 60 days.

NOTE: 1-SW-P-10B will remain FUNCTIONAL because it is still capable of performing its design function per the TRM definition: to provide cooling support for the Charging Pump seals and lube oil coolers.

Event #6: Dropped Control Rod. (C - RO/SRO)

This Event will cause a lowering rector power, lowering RCS temperature and pressure, and result in annunciator 1G-H2, RPI Rod Bottom < 20 Steps. With reactor power below 25%, 0-AP-1.00 will direct 1-E-0 entry. That team may take conservative action and go to 1-E-0 directly. The team will transition to 1-ES-0.1 to stabilize the unit at HSD.

Verifiable Action(s):

1) RO: Perform immediate action steps of 1-E-0.

2) BOP: Throttle AFW flow to all S/Gs.

Event #7: SBLOCA with failure of LHSI pumps to auto start. (M - ALL)

The RO will diagnose the RCS leakage due to the alarms and indications received, and perform the Immediate Actions of 1-AP-16.00. When leakage is determined to be greater than the capacity of a single CH pump, The RO will manually initiate Safety

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Injection and return to 1-E-0. The BOP will start at least one LHSI pump IAW 1-E-0 Attachments 1 and 2.

Verifiable Action(s):

1) RO: Manually initiates Safety Injection and re-performs immediate action steps of 1-E-0.

2) BOP: Manually starts at least one LHSI pump.

Critical Task(s):

CT-2: Start at least one LHSI pump before transition to 1-FR-C.1 is required. Because of the failure of the LHSI pumps to auto start, there is a total loss of available high volume RCS makeup. Failure to do this in a timely manner will create a challenge to Core Cooling during the subsequent LBLOCA.

Event #8: LBLOCA with no running Containment Spray pumps. (M - All)

This Event will cause a sudden drop in RCS pressure, multiple Containment radiation alarms, and a rise in Containment pressure. Hi CLS and Hi Hi CLS will actuate, but the A CS pump breaker will lockout, the B CS pump will fail to auto start, and the CS Pump discharge MOVs will fail to auto open. Orange path criteria will be met for Containment and the Team will transition to 1-FR-Z.1. The Team is expected to align CS flow using the B CS pump and return to 1-E-1.

Verifiable Action(s):

1) RO: Start B Containment Spray (CS) pump.

2) RO: Open B CS Pump Discharge MOVs.

3) RO: Stop all RCPs.

4) BOP: Close CH pump miniflow Recirc MOVs.

Critical Task(s)

CT-3: Establish B train of Containment Spray flow within 15 minutes of Containment Pressure reaching 23 psia to prevent unnecessary EAL escalation. Because of the failure of the Containment Spray pumps to start, there is a loss of that function. Failure to establish one train of CS Pump flow within 15 minutes will result in a potential loss of the Containment barrier (per the EAL Matrices). That, paired with the Loss of RCS barrier, will require escalation from an Alert to a Site Area Emergency.

The Scenario is terminated when the Team restores Containment Spray or Evaluator discretion.

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Scenario Recapitulation Total Malfunctions: 7 Abnormal Events: 5, ARP 1-RM-L5/-M5, 0-AP-53.00, ARP TS-D2, ARP 1D-G5, 0-AP-1.00.

Major Transients: 2 EOPs Entered: 2 (E-0, ES-0.1, E-1)

EOP Contingencies: 1 (FR-Z.1)

Appendix D Scenario Outline Form ES-D-2 NRC EXAM - SCENARIO #4 Initial Conditions: Unit 1 at 13% power, with plant startup in progress; BOL. Unit 2 at 100% power. All systems and crossties are operable with the following exceptions:

Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

o Unit 1 startup is in progress per 1-GOP-1.8 and 1-OP-TM-001.

o Containment Smoke and heat detectors are non-functional due local fire panel failure (2 days ago).

TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Turnover The Team will pre-brief placing unit 1 Main Feedwater Regulating Valves in AUTO and continuing the power escalation in accordance with 1-GOP-1.8 and 1-OP-TM-001 and a ramp plan prior to Simulator entry, and commence following turnover. The performance of this procedure has been analyzed based on the current plant configurations and the PSA indicates green.

Scenario Objectives:

A. Given Station Operating Procedures and an approved ramp plan, perform a Unit 1 power escalation.

B. Given a failure of Component Cooling Radiation Monitoring, respond in accordance with ARPs 0-RM-L5 and -M5.

C. Given a failure of the Normal Charging Flow Controller, respond in accordance with 0-AP-53.00, Loss of Vital Instrumentation / Controls.

D. Given a loss of the running EH pump with auto start failure of the standby pump, respond in accordance with ARP TS-D2.

E. Given a loss of the running Charging SW pump with auto start failure of the standby pump, respond in accordance with ARP 1D-G5.

F. Given a dropped rod below 25% reactor power, respond in accordance with 0-AP-1.00, Rod Control Malfunction, and 1-E-0, Reactor Trip or Safety Injection.

G. Given a small break loss of Reactor Coolant, respond in accordance with 1-AP-16.00, excessive RCS leakage, and 1-E-0, Reactor Trip or Safety Injection.

H. Given a large break loss of Reactor Coolant with a loss of both Containment Spray pumps, respond in accordance with 1-FR-Z.1, Response to Containment High Pressure.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 online at 13% reactor power with the following parameters:

• RCS boron concentration of 1413 ppm.

• Steam Dumps are in AUTO in Tave mode.

• Pimp is 8%.

• RCS Tave is 550°F; Tref is 549°F.

• Rod Control is in MANUAL.

• A surrogate operator is controlling S/G levels at 40% +/- 4%, using the main feedwater bypass HCVs until the team relieves the watch. At that time, the team will assume feed control and the surrogate will leave the simulator.

Unit startup is in progress, with reactor power being held at 13% for turnover.

All systems and crossties are operable with the following exception:

• Containment Smoke and heat detectors are non-functional due local fire panel failure (2 days ago). TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to place unit 1 main feedwater regulating valves in AUTO and commence power escalation in accordance with 1-GOP-1.8 (starting at step 5.6.27), 1-OP-TM-001 and a ramp plan upon relieving the watch. From there, continue the power escalation to 20-25% turbine power. Performance of these startup procedures have been authorized and have been PSA analyzed for current plant conditions.

The last shift performed dilutions as necessary to support unit startup, with PG currently in the blender piping.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 10 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Time Position Applicants Action or Behavior 1-GOP-1.8 Team Team will pre-brief Initial Conditions, Precautions and Limitations, and procedure prior to entering simulator.

1-GOP-1.8 NOTE: 1-OP-CH-021 (Alternate Dilution Using Blender) procedure steps are contained at the end of this section.

SURROGA When the team has relieved the watch, turnover feed control TE responsibilities over to the BOP and leave the simulator floor.

NOTES prior to step 5.6.27:

• Steam Flow / Feed Flow indications do not have to be matched to be considered stable.

• All three MFRVs should be placed in Auto at the same time to ease the transition to Auto feed control.

BOP 5.6.27 WHEN Feedwater temperature is greater than 260°F (PCS points T0418A, T0438A, T0458A) with stable Steam Flow / Feed Flow, THEN perform the following:

a. Check that the MFRVs are closed.

b. Place the MFRVs in Auto.

c. WHEN MFRV demand exceeds approximately 9%, THEN slowly close the MFRV Bypass HCVs as the MFRVs come open.

RO/BOP NOTE: When the Steam Dumps are fully closed, Tave will lower as Turbine power is raised.

5.6.28 IF the Steam Header Pressure controller is in Auto, THEN as Turbine power level is raised, perform the following. Enter N/A if controller in Manual.

a. Check that the Steam Dumps modulate closed.

b. WHEN the Steam Dumps are closed, THEN place the Steam Header Pressure controller in Manual.

NOTE: Step 5.6.28 will already be initialed as complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 11 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Time Position Applicants Action or Behavior 1-GOP-1.8 RO/BOP 5.6.29 IF the Steam Header Pressure controller is in Manual, THEN as Turbine power level continues to rise, reduce the STM DUMP VVS DEMAND signal to zero while maintaining Reactor power constant. Enter N/A if controller was operated in Auto.

RO/BOP NOTE: Step 5.6.29 will already be initialed with N/A 5.6.30 Place the STM DUMP MODE SEL switch in the TAVG position as follows.

a. Check STM HDR pressure controller demand at zero.

b. Place STM DUMP CNTRL switch to OFF/RESET.

c. Place STM DUMP MODE SEL switch to RESET and spring return to TAVG.

d. Check annunciator 1H-D7, STM DUMP PERM, is NOT LIT.

e. Place STM DUMP CNTRL switch to ON.

NOTE: Step 5.6.30 will already be initialed as complete.

NOTE: Annunciators 1H-A3/-B3/-C3 (LOOP A/B/C HI/LO TAVG) may alarm during the ramp and are expected.

NOTE: Annunciator 0-BR-D2 (OVHD GAS COMPR STDBY START) may come in during the ramp and is expected; Unit 2 will perform the ARP is directed.

END OF GOP ACTIONS OP-TM-001 ACTIONS BEGIN NEXT PAGE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 12 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Time Position Applicants Action or Behavior 1-OP-TM-001 SRO CAUTIONS prior to Step 5.8.1:

• Constant communication between the Reactor Operators on the S/G Level Controls, the Control Rods, Steam Dumps, and the Turbine must be maintained to prevent temperature or level transients.

• Rapid Loading of the Turbine - Generator may cause a Steam Generator High Level Trip.

NOTES prior to Step 5.8.1:

• Shift Supervision may authorize entry or exit from this subsection at any step or substep based upon existing plant conditions. N/A must be entered for the specific steps or substeps in the subsection that were not performed as a result of the authorized exit or entry.

• Ramping the Turbine at 1%/min until the Steam Dumps are closed will aid in the transition to auto feed control. Once the Steam Dumps are closed the normal ramp rate is Position 6.

• In the OPER AUTO mode, Turbine loading may be stopped by depressing the HOLD pushbutton and may be restarted by depressing the GO pushbutton.

1-OP-TM-001 SRO/BOP 5.8.1 With the OPER AUTO mode selected, set the desired load in the SETTER and depress the GO pushbutton.

5.8.2 Maintain the System Voltage on the 230 KV BUS VOLT meter as requested by the System Operator.

5.8.3 WHEN Turbine power rises above 10%, THEN check PCS alarm Y2060D, Exh Hood Sprays OFF, is received.

5.8.4 WHEN IMPULSE CHAMBER PRESSURE (Turbine Power) passes through 30 percent OR when the startup has stabilized, THEN check or depress the IMP IN pushbutton AND check that the IMP IN light is LIT and the IMP OUT light is NOT LIT. Enter N/A if Turbine control will remain in IMP OUT.

Evaluators Note: No further actions are expected for this event.

NOTE: If the team is allowed to ramp above 25% reactor power, reactor power may remain above 25% at Event 6 after the dropped rod; a reactor trip will not be required. If this occurs, the examiner may direct inserting Trigger 25 to drop an additional control rod.

END EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 13 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Time Position Applicants Action or Behavior 1-OP-CH-021, Alternate Dilution Using Blender RO 5.1 Alternate Dilution NOTE: This subsection will be used for the first alternate dilution of the shift. Attachment 1 will be used as a guide for further alternate dilutions for the remainder of the shift.

NOTE: If unit on Excess Letdown, 1-OP-CH-007 should be used.

5.1.1 Determine the required integrator setpoint by performing the following:

________________ gal (-) _____________= ______ Integrator setpoint (Desired Dilution) (anticipated additional flow, dependent on flowrate)

UNIT 2 If asked, perform IV for Step 5.1.1.

5.1.2 Notify Shift Supervision of impending Alternate Dilution.

5.1.3 Notify STA of impending Alternate Dilution.

5.1.4 Place the MAKE-UP MODE CNTRL switch in the STOP position.

5.1.5 Adjust both of the following controllers for the flow rate and total gallons of Primary Grade water for the dilution. IF the PG FLOW CNTRL controller setpoint has previously been set, THEN N/A Substep 5.1.5.a.

a. 1-CH-FC-1114A, PG FLOW CNTRL ______ GPM (IAW Attachment 2)

b. Record number of gallons of PG to be added from Step 5.1.1 and enter into 1-CH-YIC-1114A, PRI WATER SUP BATCH INTEGRATOR (GAL) as follows:

1. Depress PRESET A Button (Controller will read the last value entered into the controller; reads in gallons.)

2. To clear PRESET A, depress the CLR Button. Enter N/A if not required.

3. Enter desired PRESET A value. Enter N/A if not required.

4. Depress ENT Button

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 14 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Time Position Applicants Action or Behavior 1-OP-CH-021, Alternate Dilution Using Blender RO 5.1.6 Place the MAKE-UP MODE SEL switch in the ALT DIL position.

5.1.7 IF it is desired to direct the dilution water to the charging pump suction only, THEN place 1-CH-FCV-1114B, BLENDER TO VCT, in the CLOSE position. Otherwise, enter N/A.

5.1.8 Place the MAKE-UP MODE CNTRL switch in the START position.

5.1.9 Check all of the following conditions.

a. 1-CH-FCV-1113A, BORIC ACID TO BLENDER, is closed.

b. 1-CH-FCV-1113B, BLENDER TO CHG PUMP, is open.

c. 1-CH-FCV-1114A, PGW TO BLENDER, is controlling in AUTO.

d. 1-CH-FCV-1114B, BLENDER TO VCT, is open. IF Step 5.1.7 was performed, THEN enter N/A.

5.1.10 IF it is desired to stop the Dilution before the selected amount, THEN place the MAKE-UP MODE CNTRL switch in the STOP position. IF the PRI WATER SUP BATCH INTEGRATOR (GAL) is used to stop the flow, THEN enter N/A for this step.

5.1.11 WHEN the desired amount of makeup has been reached, THEN check both of the following valves closed.

• 1-CH-FCV-1113B

• 1-CH-FCV-1114B RO 5.1.12 Check or place 1-CH-FCV-1114B in AUTO.

5.1.13 Check or place the following controllers in Automatic.

• 1-CH-FC-1113A, BA FLOW CNTRL

• 1-CH-FC-1114A, PG FLOW CNTRL 5.1.14 Place the MAKE-UP MODE SEL switch in the AUTO position.

5.1.15 Place the MAKE-UP MODE CNTRL switch in the START position.

5.1.14 Notify Shift Supervision of Blender status. (Reference 2.4.1)

Additional Alternate Dilutions will be performed using 1-OP-CH-021, Attachment 1 (Next Page).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 1 Page 15 of 81 Event

Description:

Place unit online.

Cue: When team ready.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 2 Page 16 of 81 Event

Description:

CC RM Fail upscale with failure of HCV-CC-100 to auto close.

Cue: After MFRVs in AUTO and Bypass HCVs closed.

Time Position Applicants Action or Behavior BOP Diagnoses failure of 1-RM-CC-105 with the following indications/alarms:

Alarms:

• 0-RM-L5 CC HX A/B OUT ALERT/FAILURE

• 0-RM-M5 1-CC-RI-105 HIGH Indications:

1-CC-RI-105 indicates a step change to 5.7 E+06 cpm.

1-CC-RI-105, HIGH, WARN and RANGE lights LIT.

NOTE: RM-M5 Guidance located at end of this section, starting at page 17.

0-RM-L5 BOP NOTES Prior to Step 1:

• If a monitor fails, the automatic functions associated with that monitor must be checked or performed.

• When HP has surveyed the area and declared radiation levels normal, the components that were realigned due to monitor failure may be returned to normal and activities in the affected area may continue.

SRO

• Tech Spec 3.13.E requires that HCV-CC-100 remain closed if either CC radiation monitor is inoperable.

0-RM-L5 BOP

1. CHECK ALARM - READING ON MONITOR GREATER THAN OR EQUAL TO ALERT SETPOINT OR RADIATION LEVEL HAS TRENDED UP

• 1-CC-RI-105, HDR A

• 1-RM-RR-150C, Pen 1 BOP will identify that the meter indicates a steeply rising trend. Goes to RNO.

NOTE: It is expected for the team to determine the rad monitor has failed, based on the RM indication and stable indication on the other CC RM (106).

0-RM-L5, Step 1 RNO BOP a) IF all EEEEEs indicated on display, THEN GO TO 0-OPT-RM-001, Radiation Monitoring Equipment Check.

NOTE: The team will not perform 0-OPT-RM-001.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 2 Page 17 of 81 Event

Description:

CC RM Fail upscale with failure of HCV-CC-100 to auto close.

Cue: After MFRVs in AUTO and Bypass HCVs closed.

Time Position Applicants Action or Behavior RM-M5 Note: Candidate may refer to this ARP initially in response to the High Alarm.

BOP NOTE before step 1:

• If a monitor fails, the automatic functions associated with that monitor should be verified or performed.

• When HP has surveyed the area and declared radiation levels normal, the components that were realigned due to monitor failure may be returned to normal and activities in the affected area may continue.

• Tech Spec 3.13.E requires that HCV-CC-100 remain closed if either CC radiation monitor is inoperable.

1. CHECK ALARM - READING ON MONITOR GREATER THAN OR EQUAL TO HIGH SETPOINT

• 1-CC-RI-105, HDR A

• 1-RM-RI-150C, Pen 1 Identifies Monitor reading is greater than High Alarm.

RM-M5 BOP

2. CHECK CC HEAD TANK VENT VALVE - CLOSED a) Place HCV-CC-100 in OFF (Unit 1)

Places HCV-CC-100 in Off.

b) Place SOV-CC-200 in CLOSE (Unit 2)

Directs Unit 2 operator to place SOV-CC-200 in close.

UNIT 2 Reports that SOV-CC-200 has been placed in CLOSE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 2 Page 18 of 81 Event

Description:

CC RM Fail upscale with failure of HCV-CC-100 to auto close.

Cue: After MFRVs in AUTO and Bypass HCVs closed.

Time Position Applicants Action or Behavior RM-M5 NOTE before step 3:

The following components are the most likely sources of inleakage to the CC System:

• RCP Thermal Barrier

• NRHX

• Primary Sample coolers

• Excess Letdown HX

• HRSS coolers

• RHR HX

• SFP coolers

• RHR Pump Seal coolers BOP 3. MONITOR CC HEAD TANK LEVEL AND CC TEMP FOR INCREASING LEAKAGE TO CC SYSTEM RM-M5 BOP 4. NOTIFY HP TO DO THE FOLLOWING:

• Check area evacuated as necessary

• Control access as necessary

• Investigate cause

• Determine need for setpoint change BOP Notifies HP.

RM-M5 BOP 5. PERFORM ( )-OPT-RC-10.0, REACTOR COOLANT LEAKAGE OR ( )-AP-16.00, EXCESSIVE RCS LEAKAGE, AS NECESSARY Notifies RO/SRO to perform 1-OPT-RC-10.0, as necessary. Determines 1-AP-16.00 is not necessary.

RM-M5 BOP 6. DETERMINE LEAKAGE SOURCE BY SAMPLING AS NECESSARY Notifies SRO concerning Step.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 2 Page 19 of 81 Event

Description:

CC RM Fail upscale with failure of HCV-CC-100 to auto close.

Cue: After MFRVs in AUTO and Bypass HCVs closed.

Time Position Applicants Action or Behavior RM-M5 BOP 7. ISOLATE LEAKAGE Notifies SRO of need to isolate leakage if discovered by sampling. No isolation is required.

RM-M5 BOP 8 PROVIDE NOTIFICATIONS AS NECESSARY:

• Shift Supervision

• OMOC

• STA

• Health Physics

• Instrumentation Department Informs SRO of required notifications.

END EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 20 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Time Position Applicants Action or Behavior RO Charging Line Flow Controller 1-CH-FC-1122 Fails High.

Diagnose the failure based on the following alarms and indications:

• 1-CH-FC-1122C indicates maximum demand.

• Charging Line Flow, 1-CH-FI-1122A shows step drop to 0 gpm.

• Annunciator 1D-E5, CHG PP TO REGEN HX HI-LO FLOW

• Pressurizer Level lowers slowly on all Level channels.

• Pressurizer Pressure lowers slowly on all channels.

• VCT Level rising slowly.

SRO Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.

NOTE: The team pay perform ARP 1D-E5, CHG PP TO REGEN HX HI-LO FLOW, in addition to 0-AP-53.00.

RO Performs immediate actions of 0-AP-53.00, Loss of Vital Instrumentation /

Controls:

[1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL Checks Pressurizer Level Protection Channels 1, 2 and 3 are NORMAL.

[2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FCV-1122 in manual and raises charging flow.

Reports 0-AP-53.00 Immediate Actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 21 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Time Position Applicants Action or Behavior SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of PRZR level with CH flow in MANUAL.

STA STA will have no input for the brief.

0-AP-53.00 RO 3. VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO will identify that reactor power is less than 100% using PCS Display of Core Thermal Power.

0-AP-53.00 SRO Caution prior to step 4:

• If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

Notes Prior to Step 4:

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 11.

0-AP-53.00 SRO

• 4. DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

RO Identifies that 1-CH-FC-1112C is not on the list at Step 4.

Based on the second Note at Step 4, recovery actions should continue at Step 11.

NOTE: The team may perform Step 9 based on Charging Flow impact on Pressurizer Level Control. Step 9 is included on the next page.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 22 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Time Position Applicants Action or Behavior Step 9, AP-53.00 SRO 9 a) CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL RO Responds NO, 1-RC-FC-1122C Abnormal.

SRO 9 a) RNO 1) Place either of the following in MANUAL:

• 1-CH-FC-1122C, CHG FLOW CNTRL, OR

• 1-CH-LC-1459G, PRZR LEVEL CNTRL RO Responds Yes, 1-CH-FC-1122C is in MANUAL SRO 9 a) RNO 2) Control PRZR Level at Program Level.

RO Responds Maintain PRZR Level at program +/- band set by SRO SRO 9 a) RNO 3) Move PRZR Level - CH SEL switch to Defeat the failed channel.

RO/BOP Responds There is no failed channel.

SRO 9 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.

BOP Responds 1-RC-LR-1459 is on an operable channel.

SRO 9a) RNO 5) Refer to Tech Specs 3.1.A.5, Table 3.7-1 Item 9, and Table 3.7-6, Item 13.

• 3.1.A.5 (If Pzr heaters deenergized): This LCO is met.

• Table 3.7-1, item 9: This LCO is met.

• TS Table 3.7-6, Item 13: This LCO is met.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 23 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Time Position Applicants Action or Behavior 0-AP-53.00 SRO 9. a) RNO 6) Refer to Attachment 3.

SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for review.

Note: Attachment 3 is at the end of this section.

0-AP-53.00 SRO 9. b) Check Pressurizer Heaters - Energized.

RO Checks Required Pressurizer Heaters energized, and reports that Pressurizer heaters are energized.

SRO 9. c) Check Letdown - IN SERVICE.

RO Reports Letdown in service.

SRO 9. d) Check PRZR level control - IN AUTOMATIC.

RO Reports pressurizer level control in MANUAL.

SRO 9. d) RNO Do the following as required:

1) Check PRZR level restored to program.

2) Unsaturate ( )-CH-LC-( )459G, PRZR LEVEL CNTRL, as required.

3) Return ( )-CH-FCV-( )122 to AUTOMATIC by checking or placing the following in AUTOMATIC:

• ( )-CH-FCV-( )122, CHG FLOW CNTRL

• ( )-CH-LC-( )459G, PRZR LEVEL CNTRL.

RO Notifies SRO that Charging flow control cannot be returned to AUTOMATIC; maintains manual control.

0-AP-53.00 SRO Recalls NOTE 2 Prior to Step 4 and goes to Step 11 of AP-53.00.

SRO 11. Check Calorimetric - Functional IAW 1-OPT-RX-001, Attachment 4.

RO/BOP Performs Attachment 4, and reports Calorimetric is functional.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 24 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Time Position Applicants Action or Behavior 0-AP-53.00 SRO 12. REVIEW THE FOLLOWING:

• Tech Spec 3.7

• VPAP 2802 Notifications and Reports

• TRM

• Reg Guide 1.97

• EP-AA-303, Equipment Important to Emergency Response.

Directs STA to review all documents listed.

STA STA reports that all documents have been reviewed and discussed with the Shift Manager.

0-AP-53.00 SRO 13. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS The team will identify that no new additional failures exist (i.e., all failures have already been addressed), proceed to the RNO section, and this will direct the team to Step 15.

0-AP-53.00 SRO 15. PROVIDE NOTIFICATIONS AS NECESSARY:

• Shift Supervision

• OMOC

• STA (PRA determination)

• I&C END EVENT #3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 3 Page 25 of 81 Event

Description:

Normal Charging Flow Controller Fails High (1-CH-FC-1112C).

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 4 Page 26 of 81 Event

Description:

Trip of running EH pump with failure of Stby to Auto Start. (1-TS-D2)

Cue: By Examiner.

Time Position Applicants Action or Behavior BOP Diagnose loss of the running EH pump by one or more of the following conditions:

• 1-EH-P-MP1 green light indication.

• PCS Status Change, Y2067D EHC FLUID PMP BKR.

• Annunciator 1-TS-D2 LIT, EH FLUID LO PRESS (approx. 3 min)

NOTE: The SRO may hold a focus brief and start the standby EH pump prior to reading ARP TS-D2.

1-TS-D2 SRO Briefs the loss of the running EH pump and directs team to performance of 1-TS-D2, EH FLUID LO PRESS.

1-TS-D2 BOP NOTE: The EH fluid lo pressure alarm is set to actuate at 1550 psig. Actuation between 1500-1600 psig is acceptable.

1. CHECK STANDBY EH PUMP-AUTO STARTED

• MP1

• MP2 BOP starts 1-EH-P-MP2.

Critical Task (CT-1): Start the standby EH Fluid Pump prior to automatic OR manual Reactor/Turbine trip.

1-TS-D2 BOP 2. LOCALLY CHECK EH SYSTEM - LEAKAGE INDICATED.

Contacts Field Operator to determine if there is any EH leakage.

1-TS-D2 BOP 3. ATTEMPT TO RETURN EH PRESSURE TO NORMAL.

a) Check annunciator 1-TS-D1 - NOT LIT b) Locally identify and isolate leakage c) Start the standby EH pump and stop the running EH pump as necessary to isolate leakage.

d) Initiate refilling of the EH reservoir as necessary.

e) Check EH pressure - RETURNED TO NORMAL f) Submit a Condition Report g) GO TO Step 5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 4 Page 27 of 81 Event

Description:

Trip of running EH pump with failure of Stby to Auto Start. (1-TS-D2)

Cue: By Examiner.

BOP BOP reports that annunciator 1-TS-D1 is NOT LIT. Field operator reports that there is no indicated leakage and all conditions are normal.

END EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 5 Page 28 of 81 Event

Description:

A CH SW pump overload trip, with auto start failure of B CH SW pump.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-SW-P-10A overload trip / 1-SW-P-10B fail to auto start RO Diagnose the failure based on the following alarms and indications:

Annunciator 1D-G5, SW OR CC PPS DISCH TO CHG PPS LO PRESS.

1-SW-P-10A NOT running.

SRO Direct performance of ARP 1D-G5 NOTE: The SRO may hold a focus brief and start the standby CH SW pump RO prior to reading ARP 1D-G5. RO starts 1-SW-P-10B.

NOTE: SRO may direct the BOP to perform 0-AP-12.00, Service Water System Abnormal Conditions. 0-AP-12.00 actions located at end of this section.

1D-G5 Annunciator Response Procedure BOP 1. CHECK CHG PUMP CC OR SW PP(S) - TESTING IN PROGRESS RO Reports No, testing not in progress.

BOP Step 1 RNO: GO TO Step 3.

1D-G5 Annunciator Response Procedure Note before Step 3: The standby CH Pump SW Pump will auto-start at 8 psig.

BOP 3. CHECK STANDBY CHG PUMP CC PP OR SW PP - AUTO STARTED RO Report No, 1-SW-P-10B not running.

BOP Step 3 RNO DO the following:

a) Check running or start one CHG Pump CC and/or SW PP.

RO Starts 1-SW-P-10B.

BOP b) Locally check CHG Pump CC and SW PPs.

RO/BOP Dispatches an Operator to check the CH Pump CC and SW pumps.

BOP c) Monitor CHG Pump CC and SW flows on PCS (ERFCS if not removed):

1-CC-P-2A, F1CC003A 1-CC-P-2B, F1CC004A 1-SW-P-10A, F1SW007A 1-SW-P-10B, F1SW008A RO/BOP Monitors parameters using the PCS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 5 Page 29 of 81 Event

Description:

A CH SW pump overload trip, with auto start failure of B CH SW pump.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1D-G5 Annunciator Response Procedure BOP 3.d) IF CHG Pump CC and SW PPs are operating normally, THEN do the following:

RO Reports Yes, Pumps are operating properly.

BOP 1) Submit a Condition Report.

2) Increase surveillance of CHG Pump CC and SW PPs.

3) Increase surveillance of CHG Pump temperature using PCS Digital Trend #1.

4) GO TO Step 13.

1D-G5 Annunciator Response Procedure BOP 13. PROVIDE NOTIFICATIONS:

• OMOC

• STA

• System Engineering Notifies SRO of required notifications.

Reviews Tech Specs:

SRO T.S. 3.0.1 is in effect, because the requirements of Tech Spec 3.3.B.3 (also 3.2.C.1) are not met. Place the unit in HSD in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and CSD in the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Reviews TRM:

SRO TRM 3.7.9, TRM 3.7.9.A.2 (MRule - No, App R - yes), Implement App R fire watch in the area(s) associated with the nonfunctional equipment in Table 3.7.9-1 in accordance with TRM Section 5.2 within 14 days and restore the equipment to functional status in 60 days.

NOTE: 1-SW-P-10B will remain FUNCTIONAL because it is still capable of performing its design function per the TRM definition: to provide cooling support for the Charging Pump seals and lube oil coolers.

SRO Notifies Shift Manager of T.S.3.0.1 in effect.

NOTE: Informs the SRO that they will call the OMOC and will update the team on the course of action to be taken. The Shift Manager will not call back.

NOTE: This is the end of the event using ARP 1D-G5. The next pages contain steps in 0-AP-12.00, Service Water Abnormal Conditions, in the event the team uses that procedure instead.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 5 Page 30 of 81 Event

Description:

A CH SW pump overload trip, with auto start failure of B CH SW pump.

Cue: By Examiner.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 5 Page 31 of 81 Event

Description:

A CH SW pump overload trip, with auto start failure of B CH SW pump.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-12.00 SRO Note: A copy of this procedure is located in MER 3.

Direct performance of ARP 1D-G5

1. CHECK MER 3 OR 4 EQUIPMENT - AFFECTED

• Charging Pump Service Water Pumps

• MER 3 Chillers RO Identifies Charging Pump SW pumps affected, Goes to Step 2.

0-AP-12.00 SRO 2. Check Charging Pump SW Pumps Affected.

RO Continues to Step 3.

0-AP-12.00 SRO CAUTION: Charging pumps should be secured if bearing temperatures reach 185°F.

NOTE:

• Preparations should be made to shift charging pumps if bearing temperatures exceed 180°F.

• The system engineer should be notified as soon as possible if charging pump bearing temperatures exceed 180°F.

0-AP-12.00 SRO 3. CHECK CHG PUMP TEMPERATURES - LESS THAN 180°F BOP Checks CH Pump temperatures using PCS.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 5 Page 32 of 81 Event

Description:

A CH SW pump overload trip, with auto start failure of B CH SW pump.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-12.00 SRO Note: A vacuum condition in the SW header(s) is indicated by abnormal conditions on multiple SW header loads.

4. CHECK SW PARAMETERS - NORMAL a) MER 3 b) MER 4 BOP Directs Service Building Operator to check status of MER 3 and 4 SW parameters using 0-AP-12.00, Pages 3 and 4.

Field operators will report Unit 1 Charging SW Pumps are not running and discharge pressures are not greater than 15 psig.

SRO Goes to Step 4 RNO.

0-AP-12.00 SRO Step 4 RNO.

IF a vacumm condition exists in the SW header(s), THEN do the following.

RO Reports no vacuum condition exists.

SRO IF SW header(s) NOT in a vacuum, THEN perform the following:

a) Check running or Start standby CHG pump SW pump(s).

RO Starts 1-SW-P-10B END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 33 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior Diagnose the failure using the following:

Alarm:

1G-H2, RPI ROD BOTTOM < 20 STEPS Indications:

SBB G-9 CERPI indicates 0 steps.

Any Rod On Bottom light lit Rod-to-Rod Deviation light lit.

Tave and NI levels lowering NOTE: The team will likely trip the reactor and go to 1-E-0, based on the dropped rod at low power. If so, 1-E-0 instructions begin at page 34.

NOTE: If the team is allowed to ramp above 25% reactor power, reactor power may remain above 25% after the dropped rod; a reactor trip will not be required.

If this occurs, the examiner may direct inserting Trigger 25 to drop an additional control rod.

0-AP-1.00 SRO Enters 0-AP-1.00 (Rod Control System Malfunction).

SRO CAUTION prior to Step 1:

• If Tave decreases below 541 °F, ( )-E-0, Reactor Trip or Safety Injection, must be implemented.

RO [1] CHECK FOR EITHER OF THE FOLLOWING:

• Continuous rod withdrawal

• Continuous rod insertion Reports no rod motion and Immediate actions of 0-AP-1.00 are complete.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP progression.

STA STA will have no input for the brief.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 34 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-1.00 (0-AP-1.00 Step 1 RNO directs going to Step 6)

SRO 6. CHECK IF ANY ROD DROPPED:

• Annunciator ( )G-H2, RPI ROD BOTTOM 20 STEPS - LIT OR

• Annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE 5%

PER 2 SEC - LIT OR

• Rod Bottom Lights - ANY LIT OR

• Any Rod On Bottom light - LIT OR

• Indication of a partially dropped rod in the core RO Reports multiple indications of a dropped rod in the core.

0-AP-1.00 SRO 7. CHECK REACTOR STATUS PRIOR TO FAILURE - CRITICAL RO Reports yes, reactor critical.

0-AP-1.00 SRO 8. CHECK ONLY ONE ROD AFFECTED RO Reports yes, only one rod affected.

NOTE: If Trigger 25 was required, the RO will report no and a reactor trip will be required.

0-AP-1.00 SRO 9. CHECK REACTOR POWER - GREATER THAN 25%

RO Reports NO, reactor power is less than 25%.

SRO Goes to RNO: Trip Reactor and GO TO ( )-E-0, REACTOR TRIP OR SAFETY INJECTION.

Directs RO to perform immediate actions of 1-E-0.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 35 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-E Reactor Trip or Safety Injection

[1] CHECK REACTOR TRIP:

RO a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

• All Rods On Bottom light - LIT

• Reactor trip and bypass breakers - OPEN

• Neutron flux - LOWERING 1-E Reactor Trip or Safety Injection

[2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes both turbine trip push buttons.

b) Check all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV RO

• 1-MS-SOV-104 d) Check generator output breakers - OPEN (Time Delayed) 1-E Reactor Trip or Safety Injection RO

[3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 36 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-E Reactor Trip or Safety Injection RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

• LHSI pumps - RUNNING

• SI annunciators - LIT

• A-F-3 SI INITIATED - TRAIN A

• A-F-4 SI INITIATED - TRAIN B RO will determine that SI has not occurred and perform step 4a RNO actions:

RO 4a RNO Check if SI is required or imminent as indicated by any of the following:

• Low PRZR pressure

• High CTMT pressure

• High steamline differential pressure

• High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

IF SI is not required, GO TO ES-0.1.

Determines that SI is NOT imminent. Does Not Manually initiate SI.

SRO Transitions to 1-ES-0.1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 37 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-ES-0.1 SRO After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.

STA The STA will state that he has no input.

SRO NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.

• 1.CHECK RCS TEMPERATURE CONTROL a) Check RCPS - ANY RUNNING RO Reports all RCPs running SRO b) Monitor RCS Average Temperature

1) STABLE AT 547°F OR

2) TRENDING TO 547°F RO Reports RCS Tave at 547 °F and stable SRO Assigns BOP to perform Attachment 5, Transient AFW Control.

NOTE: 1-ES-0.1 CAP and Attachment 5 are included at the end of this section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 38 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-ES-0.1 SRO 2. CHECK FW STATUS:

a) Check RCS Average temperatures - L:ESS THAN 554°F RO Reports Tave less than 554°F SRO b) Check Feed REG valves - CLOSED RO/BOP Reports MFRVs are closed SRO c) Close SG FW isolation MOVs

• 1-FW-MOV-154A

• 1-FW-MOV-154B

• 1-FW-MOV-154C RO/BOP Closes 1-FW-MOV-154A/B/C SRO NOTE: Once 1-FW-MOV-154C is closed the SBLOCA will automatically trigger in.

d) Check AFW pumps - RUNNING RO/BOP

• Motor Driven AFW pumps

• TD AFW pump SRO Reports, NO, TD AFW pump is not running (auto-start failure)

Goes to Step 2.d) RNO.

1-ES-0.1 SRO Step 2d RNO:

IF AFW pump(s) required, THEN do the following:

1) Start MD AFW pumps.

RO Reports MD AFW pumps are running.

SRO 2) Open TD AFW pump steam supply valves:

• 1-MS-SOV-102A

• 1-MS-SOV-102B RO/BOP Places control switches for 1-MS-SOV-102A and -102B in OPEN.

SRO 3) GO TO Step 2e END EVENT #6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 39 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 6 Page 40 of 81 Event

Description:

Dropped Rod below 25% reactor Power.

Cue: By Examiner.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 41 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior Team Diagnoses excessive RCS leakage by the following:

Alarms:

1C-B8, PRZR LO PRESS 1B-A3, CTMT SUMP HI LVL 1-RM-Q8, CTMT GAS ALERT/FAILURE Indications:

Containment sump level rising Lowering RCS Pressure PRZR Level decreasing Team may go back to E-O based on ES-0.1 CAP.

SRO Directs RO to re-perform Immediate Actions of AP-16.00.

1-AP-16.00 Notes before step 1:

• If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.

• RCS average temperature has a direct impact on pressurizer level.

RO

[1] MAINTAIN PRZR LEVEL:

• Isolate Letdown

• Control Charging flow Closes 1-CH-LCV-1460A and 1-CH-LCV-1460B.

Raises Charging flow using 1-CH-FCV-1122 to control PRZR level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 42 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior 1-AP-16.00 SRO The team will hold a short transient brief, commensurate with the event.

STA STA will have no input for the brief.

NOTE: As soon as team determines leak is in excess of Charging flow, the SRO will direct team goes back to E-0 and manually initiates SI.

1-AP-16.00 SRO 2. VERIFY THE FOLLOWING PARAMETERS - STABLE OR INCREASING

• PRZR Level

• PRZR Pressure

• RCS Subcooling RO Identifies Pressurizer level and pressure are still lowering.

SRO Goes to Step 2 RNO. Directs the Immediate Actions of 1-E-0.

NOTE: SRO may direct RO to manually safety inject at this point due to degrading plant parameters. SRO may direct RO to Manually initiate SI at Step 4 of 1-E-0.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 43 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior 1-E-0, Reactor Trip or Safety Injection (high level steps only for Steps 1 - 3)

RO [1] CHECK REACTOR TRIP:

RO [2] CHECK TURBINE TRIP:

RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED 1-E-0

[4] CHECK IF SI INITIATED:

RO a) Check if SI is actuated:

• LHSI pumps - RUNNING

• SI annunciators - LIT

• A-F-3 SI INITIATED - TRAIN A

• A-F-4 SI INITIATED - TRAIN B RO b) Manually initiate SI The RO will manually initiate SI at step 4 by pushing both SI pushbuttons.

Reports Immediate actions of 1-E-0 are complete, with High Head SI flow to the core. SI is initiated. No LHSI pumps are running.

SRO After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a commensurate brief.

STA STA will have no input for the brief.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 44 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior 1-E-0 SRO 5. INITIATE ATTACHMENT 1.

Directs RO to perform Attachment 2 of 1-E-0. Directs BOP to perform Attachments 1 and 3 of 1-E-0.

NOTE: Attachment 1, 2, and 3 located at the end of this section. Also acceptable for SRO to direct BOP to perform all Attachments because HHSI is operating.

1-E-0 SRO CAUTION: 1-MS-15 may need to be closed to stop RCS cooldown and 1-MS-17 opened to supply AS to GS.

• 6. CHECK RCS AVERAGE TEMPERATURE

• STABLE AT 547°F OR

• TRENDING TO 547°F RO Reports no, RCS temperature is lowering (and provide current temperature).

SRO Goes to Step 6 RNO (if RCS temperature is less than 547°F and lowering):

IF temperature less than 547°F AND lowering, THEN do the following:

a) Stop dumping steam.

RO Reports Yes, Steam Dumps are closed.

SRO b) IF cooldown continues, THEN control total feed flow. Maintain total feed flow greater than 350 gpm [450 gpm] until narrow range level greater than 12% [18%] in at least one SG.

RO Identify RCS Tave Lowering.

SRO Direct RO to throttle AFW to each SG to ~120 gpm.

RO Throttle AFW to the SGs to ~120 gpm per SG and report when complete.

SRO c) IF RCS cooldown is occurring, THEN close 1-MS-15 AND open 1-MS-17 to align AS to GS.

RO d) IF Cooldown continues, THEN close MSTVs.

Reports they will monitor RCS temperature for cooldown.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 45 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior 1-E-0 SRO 7. CHECK PRZR PORVs AND SPRAY VALVES:

a) PRZR PORVs - CLOSED RO Reports Yes, PRZR PORVs closed.

SRO b) PRZR spray controls Demand at Zero OR Controlling pressure RO Reports Yes, Demand at zero.

SRO c) PORV block valves - AT LEAST ONE OPEN RO Reports Yes, both block valves open.

1-E-0 Step 8 NOTE Prior to Step 8:

Seal injection flow should be maintained to all RCPs.

SRO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Reports Yes, 3 running and flowing to the RCS. May report 2 running depending upon BOP speed of progression through E-0, Attachment 1.

SRO b) RCS subcooling - LESS THAN 30°F [85°F]

RO Reports No, RCS subcooling is (value greater than 30°F).

SRO Goes to Step 8.b) RNO:

8.b) RNO: GO TO Step 9 Goes to Step 9.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 46 of 81 Event

Description:

Small Break LOCA with failure of Low Head SI pumps to auto start.

Cue: Examiner cue.

Time Position Applicants Action or Behavior 1-E-0 SRO

9. CHECK IF SGs ARE NOT FAULTED:

• Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO Will observe either stable SG pressures, or a slightly lowering trend on SG pressures (attributed to the RCS cooldown). The team will not transition to 1-E-2.

1-E-0 SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

• Condenser air ejector radiation - NORMAL

• SG blowdown radiation - NORMAL

• SG MS radiation - NORMAL

• TD AFW pump exhaust radiation - NORMAL

• SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO Observes all parameters are normal.

1-E-0 SRO 11 CHECK RCS - INTACT INSIDE CTMT

• CTMT radiation - NORMAL

• CTMT pressure - NORMAL

• CTMT RS sump level - NORMAL RO Reports Containment pressure, sump level, and/or radiation NOT normal.

SRO Goes to Step 11 RNO.

Goes to 1-E-1, Loss of Reactor or Secondary Coolant.

NOTE: The next event (Large Break LOCA) will be inserted after the SRO makes the transition to 1-E-1, during the 1-E-1 transient brief.

END EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 47 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior ATTACHMENT 1 OF E-0 BOP 1. CHECK FW ISOLATION:

• Feed pump discharge MOVs - CLOSED

• 1-FW-MOV-150A

• 1-FW-MOV-150B

• MFW pumps - TRIPPED

• Feed REG valves - CLOSED

• SG FW bypass flow valves - DEMAND AT ZERO

• SG blowdown TVs - CLOSED ATTACHMENT 1 OF E-0 BOP

2. CHECK CTMT ISOLATION PHASE I:

• Phase I TVs - CLOSED

• 1-CH-MOV-1381 - CLOSED

• 1-SV-TV-102A - CLOSED

• PAM isolation valves - CLOSED

• 1-DA-TV-103A

• 1-DA-TV-103B ATTACHMENT 1 OF E-0 BOP

3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 48 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior Attachment 1 of 1-E-0 BOP 4. CHECK SI PUMPS RUNNING:

• CHG pumps - RUNNING

• LHSI pumps - RUNNING Starts both LHSI pumps, if not previously started in Attachment 2.

Critical Task (CT-2): Start at least one LHSI pump prior to required transition to 1-FR-C.1.

BOP 5. CHECK CHG PUMP AUXILIARIES:

• CHG pump CC pump - RUNNING

• CHG pump SW pump - RUNNING

6. CHECK INTAKE CANAL:

BOP

• Level - GREATER THAN 24 FT

• Level - BEING MAINTAINED BY CIRC WATER PUMPS

7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

• E-F-10 (High Steam Flow SI)

• B-C-4 (Hi Hi CLS Train A)

• B-C-5 (Hi Hi CLS Train B)

BOP Identifies annunciators not lit, annunciator E-H-10 also not lit, and goes to step 8.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 49 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior Attachment 1 of 1-E-0 BOP

• 8 CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA 8, a) RNO Do the following:

1) IF CTMT pressure has exceeded 17.7 psia, THEN check or align the following valves:

Identifies CTMT pressure is elevated, but still below 17.7 psia.

2) GO TO Step 10.

Attachment 1 of 1-E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

Attachment 1 of 1-E-0 BOP

• 11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Verify Permissive Status light F LIT

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 50 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior Attachment 1 of 1-E-0 NOTE:

• CHG pumps should be run in the following order of priority: C, B, A.

• Subsequent SI signals may be reset by re-performing Step 12.

BOP 12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

• 1-SI-FI-1961 (NQ)

• 1-SI-FI-1962 (NQ)

• 1-SI-FI-1963 (NQ)

• 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO Stops one CHG pump and leaves control switch in AUTO.

e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Check reset or reset SI.

2) Stop one LHSI pump and put in AUTO.

3) GO TO Step 13 Resets SI.

Stops one LHSI pump and leaves control switch in AUTO.

Goes to Step 13.

Attachment 1 of 1-E-0 BOP

13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

Attachment 1 of 1-E-0 BOP

14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 51 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior Attachment 1 of 1-E-0 BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 NOTE: See attached copy of Attachment 2. (following this attachment)

NOTE: Depending on SRO prioritization, this attachment may already be completed by The RO.

BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 NOTE: See attached copy of Attachment 2.

Unit 2 Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if asked after differential pressure indications are requested.

BOP 17. CHECK RCS DILUTION FLOWPATH - ISOLATED AND LOCKED, SEALED, OR OTHERWISE SECURED

• Close and lock, seal, or otherwise secure 1-CH-223 May contact the Desk (WCC) SRO to Close and lock, seal, or otherwise secure 1-CH-223.

Unit 2 Unit 2 will also accept responsibility to complete Attachment 3 if asked after differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 52 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 RO NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 RO 1. Check opened or open CHG pump suction from RWST MOVs.

• 1-CH-MOV-1115B

• 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 RO 2. Check closed or close CHG pump suction from VCT MOVs.

• 1-CH-MOV-1115C

• 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 RO 3. Check running or start at least two CHG pumps. (listed in preferred order)

• 1-CH-P-1C

• 1-CH-P-1B

• 1-CH-P-1A ATTACHMENT 2 of 1-E-0 RO 4. Check opened or open HHSI to cold legs MOVs.

• 1-SI-MOV-1867C

• 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 RO 5 Check closed or close CHG line isolation MOVs.

• 1-CH-MOV-1289A

• 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 53 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 RO 6. Check closed or close Letdown orifice isolation valves.

• 1-CH-HCV-1200A

• 1-CH-HCV-1200B

• 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 RO 7. Check opened or open LHSI suction from RWST MOVs.

• 1-SI-MOV-1862A

• 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 RO 8. Check opened or open LHSI to cold legs MOVs.

• 1-SI-MOV-1864A

• 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 RO 9. Check running or start at least one LHSI pump.

• 1-SI-P-1A

• 1-SI-P-1B Starts both LHSI pumps, if not already started in Attachment 1.

ATTACHMENT 2 of 1-E-0 RO 10. Check High Head SI flow to cold legs indicated.

• 1-SI-FI-1961

• 1-SI-FI-1962

• 1-SI-FI-1963

• 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 54 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

ATTACHMENT 2 of 1-E-0 RO 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

• Alternate SI to Cold legs

• Hot leg injection Enters N/A for this step.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 55 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 56 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 57 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 58 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 59 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 4 Event No.: 7 Page 60 of 81 Event

Description:

Small Break LOCA: E-0 ATTACHMENTS 1-3.

Cue: Examiner cue.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2015-1 Scenario No.: 4 Event No.: 8 Page 61 of 81 Event

Description:

Large Break LOCA with failure of Containment Spray actuation.

Cue: Examiner cue, after 1-E-0 Attachments 1 and 2.

Time Position Applicants Action or Behavior 1-E-1 SRO The team will conduct a transient brief. During the brief, the Large Break LOCA will begin. At that time, the SRO will truncate the brief and continue in 1-E-1.

STA STA will have no input for the brief.

Team Diagnoses Large Break LOCA by the following:

Alarms:

Multiple Hi and Hi-Hi CLS alarms Multiple Containment Radiation alarms Indications:

Containment pressure rising Rapidly lowering RCS Pressure STA Reports an ORANGE path for Containment when the team identifies CS not in service, or after Step 1 of 1-E-1 is complete, whichever is sooner.

NOTE: 1-FR-Z.1 begins on the next page of this guide.

1-E-1 NOTE: It is expected that the team has addressed RCP Trip and CH miniflow Recirc criteria by the time this step is reached.

SRO 1. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Reports Yes, 3 running and flowing to the RCS.

SRO b) RCS subcooling - LESS THAN 30°F [85°F]

RO Reports RCS subcooling is less than 30°F [85°F].

SRO c) Stop all RCPs d) RCS pressure - LESS THAN 1275 psig [1475 PSIG]

e) Close CHG pump miniflow recirc valves:

• 1-CH-MOV-1275A

• 1-CH-MOV-1275B

• 1-CH-MOV-1275C RO Reports RCPs are stopped and CHG pump Mini-flow recirc valves closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2015-1 Scenario No.: 4 Event No.: 8 Page 62 of 81 Event

Description:

Large Break LOCA with failure of Containment Spray actuation.

Cue: Examiner cue, after 1-E-0 Attachments 1 and 2.

Time Position Applicants Action or Behavior 1-FR-Z.1, Response to Containment High Pressure SRO Acknowledges recommendation by STA and transitions to 1-FR-Z.1.

1-FR-Z.1 SRO CAUTION before step 1:

If 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, is in effect, containment spray systems should be operated as directed by 1-ECA-1.1, instead of Step 1 below.

1 CHECK IF CS REQUIRED:

a) Check CTMT pressure - HAS INCREASED TO GREATER THAN 23 PSIA b) Check CS pumps - RUNNING RO Reports no CS pumps running.

SRO Goes to Step 1 b) RNO.

RNO b) IF RWST level greater than 3%, THEN start CS pumps. IF any CS pump can NOT be started, THEN monitor OSRS pumps for cavitation.

RO Starts 1-CS-P-1A / 1B. Determines that 1-CS-P-1A trips immediately on overcurrent.

SRO

• IF cavitation is indicated, THEN put affected OSRS pump in PTL RO Reports no cavitation indicated.

SRO c) Check CS system valves - OPEN

• 1-CS-MOV-100A

• 1-CS-MOV-100B

• 1-CS-MOV-101A and B

• 1-CS-MOV-101C and D

• 1-CS-MOV-102A and B RO Reports No, 1-CS-MOV-101A/B/C/D are closed.

SRO Goes to Step 1 c) RNO.

c) RNO Manually align CS valves.

RO Manually opens 1-CS-MOV-101A/B/C/D.

Critical Task (CT-3): Start at least one CS pump prior to exiting 1-FR-Z.1 to restore function. (Starting B CS Pump and opening either 1-CS-MOV-101C or 1-CS-MOV-101D satisfies this CT)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2015-1 Scenario No.: 4 Event No.: 8 Page 63 of 81 Event

Description:

Large Break LOCA with failure of Containment Spray actuation.

Cue: Examiner cue, after 1-E-0 Attachments 1 and 2.

SRO d) Stop all RCPs RO Reports yes, RCPs are stopped.

NOTE: After completion of Step 1, the Examiner may terminate the scenario.

1-FR-Z.1 SRO 2. CHECK SW FLOW TO RS HXs - GREATER THAN 4750 GPM a) Check the following valves - OPEN

• 1-SW-MOV-103A, B, C, and D

• 1-SW-MOV-104A, B, C, and D

• 1-SW-MOV-105A, B, C, and D RO Reports all listed MOVs are open.

1-FR-Z.1 SRO 3. CHECK RS SYSTEMS:

a) Check RWST level -LESS THAN 60%

RO Reports RWST level is greater than 60%.

SRO Goes to 3.a) RNO.

a) Do the following:

1) Monitor RWST level.

2) WHEN RWST level is less than 60%, THEN perform Steps 3b and 3c.

Goes to Step 4.

1-FR-Z.1 SRO 4. CHECK INTAKE CANAL LEVEL - GREATER THAN 24 FT RO/BOP Reports Intake Canal Level greater than 24 feet.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2015-1 Scenario No.: 4 Event No.: 8 Page 64 of 81 Event

Description:

Large Break LOCA with failure of Containment Spray actuation.

Cue: Examiner cue, after 1-E-0 Attachments 1 and 2.

1-FR-Z.1 SRO 5. CHECK CTMT ISOLATION VALVES - CLOSED IAW ATTACHMENT 1 Directs BOP to perform Attachment 1.

1-FR-Z.1 SRO 6. CHECK MSTVs - CLOSED Reports yes, MSTVs are closed.

1-FR-Z.1 SRO Cautions before step 7:

• At least one SG must be maintained available for RCS cooldown.

• If all SGs are faulted, at least 60 gpm [100 gpm] feed flow should be maintained to each SG.

7. CHECK IF FEED FLOW SHOULD BE ISOLATED TO ANY SG(s):

a) Check pressures in all SGs:

• ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR

• ANY SG COMPLETELY DEPRESSURIZED BOP Reports SGs NOT Faulted.

SRO Goes to Step 8.

1-FR-Z.1 8 CHECK SERVICE WATER AVAILABLE:

a) Check Intake Canal level - BEING MAINTAINED BY CIRC WATER PUMPS Reports current Intake Canal Level, being maintained by CW pumps.

b) RETURN TO procedure and step in effect Returns to 1-E-1.

End Event 8 END of Scenario

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 65 of 81 SIMULATOR OPERATORS GUIDE Simulator Scenario Checklist Perform Simulator Turnover Pre-session, and Post-session Checklist prior to the first Scenario of the day.

Perform Simulator Turnover Post-session Checklist after the last Scenario of the day.

Perform/Verify Simulator Setup:

Recall IC -379 (13%) and verify Trigger #30 implemented.

OR Recall Base 5% IC, Perform applicable seps of 1-GOP-1.8/1-OP-TM-001 to place the unit online, block P-10 permissives and place Steam Dump control in Auto (Tave mode).

Open Schedule file for Scenario 6. Run Schedule file, and implement Trigger 30.

Verify the NI-NR-A and B Chart recorders are on 1 min/div speed.

Verify the SF/FF recorders are on narrow range, and Tave/Tref recorder is on wide range.

Verify PRZR LVL-CH SEL positioned to CH3/CH2 (Position 3).

Verify 1-EH-P-MP1 is red-flagged, and 1-EH-P-MP2 is green-flagged.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 66 of 81 SIMULATOR OPERATORS GUIDE Enter/Verify the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RM1109 PROCESS RAD 5 10 1 3450 6e+06 MANUAL MONITOR RI-CC-105 FAILURE CC07 DISABLE CC-HCV-100 0 0 1 FALSE TRUE MANUAL AUTO CLOSURE CH28 CHG LINE FLOW 5 30 3 0 +2.0 MANUAL CONTROLLER FC-1122A FAILS TU1802 EH FLUID PUMP 2 FAILS 0 0 5 FALSE TRUE MANUAL TO AUTO START TU1001 LOSS OF FLUID PUMP 1 5 0 5 FALSE TRUE MANUAL SW1202 Disable SW-P-10B Auto 0 0 7 FALSE TRUE MANUAL Start SW0401 OVERLOAD TRIP OF 5 0 7 FALSE TRUE MANUAL PUMP SW-P-10A RD1214 DROPPED RCCA, G-9, 5 0 9 FALSE TRUE MANUAL SHUT DOWN BANK B SI4001 DISABLE LHSI PUMP SI- 0 0 11 FALSE TRUE AUTO P-1A AUTO START SI4002 DISABLE LHSI PUMP SI- 0 0 11 FALSE TRUE AUTO P-1B AUTO START RC04 RCS LEAK NONISOLABLE 5 60 11 0 35 AUTO (0-1200 GPM)

RC0101 RCS COLD LEG A PIPE 5 120 13 0 50 MANUAL RUPTURE CS1601 DISABLE CSP1A AUTO 0 0 13 FALSE TRUE MANUAL START CS1602 DISABLE CSP1B AUTO 0 0 13 FALSE TRUE MANUAL START CS12 DISABLE CSMOV101A 0 0 13 FALSE TRUE MANUAL AUTO OPEN CS13 DISABLE CSMOV101B 0 0 13 FALSE TRUE MANUAL AUTO OPEN CS14 DISABLE CSMOV101C 0 0 13 FALSE TRUE MANUAL AUTO OPEN CS15 DISABLE CSMOV101D 0 0 13 FALSE TRUE MANUAL AUTO OPEN CS0801 CS-P-1A BKR 14H5 5 0 15 FALSE TRUE AUTO OVERCURRENT TRIP RD1205 DROPPED RCCA, J-3, 5 0 25 FALSE TRUE MANUAL SHUT DOWN BANK A FP0301 FPS FACP07 ALARM 0 0 30 FALSE TRUE MANUAL HORN FAILURE FP0302 FPS PC SPEAKER 0 0 30 FALSE TRUE MANUAL FAILURE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 67 of 81 SIMULATOR OPERATORS GUIDE Enter/Verify the following EVENT TRIGGERS:

Event ID Event code Command 11 Fwmov154c <= 0.02 Sets Trigger 11 15 CVP000>23 Sets Trigger 15 TRIGGER TYPE DESCRIPTION 1 MAN Fails CC-RM-105 high.

3 MAN Fails Normal Charging Flow Controller high.

5 MAN Trips running EH pump and defeats auto start of standby pump.

7 MAN Trips running Charging SW pump and defeats auto start of standby pump.

9 MAN Drops control rod G-9.

Small Break LOCA and defeats auto start of both LSHI pumps 11 AUTO when 1-FW-MOC-154C is closed.

Large Break LOCA and defeats auto start of B CS pump and all 13 MAN CS discharge MOVs.

Lockout of 1-CS-P-1A 5 seconds after Containment Pressure 15 AUTO exceeds 23 psia 25 MAN (Contingency) Drops additional RCCA if power > 25% at Event 6.

MAN FP0301 FPS FACP07 ALARM HORN FAILURE 30 ACTIVE FP0302 FPS PC SPEAKER FAILURE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 68 of 81 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 5% power operation indications.

Verify Red Magnets on the following components:

Verify All pink magnets collected from previous scenarios.

Verify vertical board PCS monitor on ALARM SCREEN.

Reset ICCMs.

Verify all calcalc points are displayed on PCS: None.

Verify Component Switch Flags; 1-VS-F-58A and 1-VS-F-58B switches (AUTO AFTER STOP).

Verify Brass Caps properly placed (Hi-Hi CLS, MSTVs, CH-MOV-1350, CW and SW MOVs, CTMT Hogger suction, CNDSR Vacuum breaker).

Radiation Monitors all clear.

Verify SG PORVs set for 1035 psig.

Verify D bank rod height at 145 steps and Bank Overlap Counter at 529.

Advance Charts.

Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset).

Verify SYNC keys in proper place.

Verify BOL reactivity plans and benchboard Reactivity Placard is current.

Reset Blender Integrators for Boric Acid to 100 and PG to 1000.

Verify Stop Watches are available for RO and BOP.

Verify Simulator Session In Progress light is turned ON.

Verify no persons are logged onto network computer to ensure no procedures displayed.

Verify PCS time matches Sim time.

Check PCS Delta Flux target matched reactivity placard.

Verify fresh copies of 1-GOP-1.8 and 1-OP-TM-001 are available in a binder.

Verify no Dropped Rod report in printer.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 69 of 81 SIMULATOR OPERATORS GUIDE Spot check all ARPs are clean, verify the following ARPs are clean.

0-RM-L5 1D-G5 0-RM-M5 1D-E5 1G-H2 TS-D2 Verify CLEAN copies of the following procedures are in place.

CSFSTs 0-AP-53.00 0-AP-1.00 1-AP-16.00 1-E-0 1-ES-0.1 1-E-1 1-FR-Z.1 1-OP-ZZ-002 1-OPT-RX-001 1-OP-CH-007

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 70 of 81 SIMULATOR CREW BRIEF This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated.

In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

TEAM 1 TEAM 2 TEAM 3 SRO RO BOP Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 71 of 81 SIMULATOR CREW TURNOVER Conduct shift turnover:

Unit 1 is online at 13% reactor power with the following parameters:

• RCS boron concentration of 1413 ppm.

• Steam Dumps are in AUTO in Tave mode.

• Pimp is 8%.

• RCS Tave is 550°F; Tref is 549°F.

• Rod Control is in MANUAL.

• A surrogate operator is controlling S/G levels at 40% +/- 4%, using the main feedwater bypass HCVs until the team relieves the watch. At that time, the team will assume feed control and the surrogate will leave the simulator.

Unit startup is in progress, with reactor power being held at 13% for turnover.

All systems and crossties are operable with the following exception:

• Containment Smoke and heat detectors are non-functional due local fire panel failure (2 days ago). TRM Section 3.3.1, Fire Detection Instrumentation, Condition B, Smoke Detectors, and Condition C, Heat Detectors is in effect. Containment air temperatures monitored once/hour, and restore to Functional status in 14 days. OC-18 for Containment Temperature Monitoring being performed by Unit 2 BOP for both Units.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to place unit 1 main feedwater regulating valves in AUTO and commence power escalation in accordance with 1-GOP-1.8 (starting with step 5.6.27), 1-OP-TM-001 and a ramp plan upon relieving the watch. From there, continue the power escalation to 20-25% turbine power. Performance of these startup procedures have been authorized and have been PSA analyzed for current plant conditions.

The last shift performed dilutions as necessary to support unit startup, with PG currently in the blender piping.

Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 72 of 81 SIMULATOR OPERATORS GUIDE Pre Session Checks:

Safety Injection Section (Magnets) CW/SW Section RCS Section CVCS SI-MOV-1865A R G Brass Caps Tcold Loop Stop Pos (R - O) Core Life Plaque SI-MOV-1865B R G SW MOVs A B C Ramp Plan Book SI-MOV-1865C R G 103A 103B 103C 103D Loop Bypass Valves (G - C) OP-RX-010 Book SI-MOV-1869A R G A B C PG Int Set 1000 SI-MOV-1869B R G CW MOVs Thot Loop Stop Pos (R - O) BA Int Set 100 SI-MOV-1890A R G T/O 106A 106B 106C 106D A B C SI-MOV-1890B R G T/O Tavg/Tref Rec.

SI-MOV-1890C R G T/O CW Inlet Throttle Plaques (10%) SFP PPs Pwr Norm Alt NI-NR-B Brass Cap CLS TR A CLS TR B 100A 100B 100C 100D PZR Level Recorder Group Step Ctrs CERPIs CTMT Hogger Suction Cap CH-MOV-1350 Main Steam/Feedwater Electrical/VSP PCS RM/WD/BR SG PORVs Set Synch Key PCS Main Screen RM-112 A B C MSTV Caps A B C SVB Power H J U9103 RM-113 A B C SF/FF Rec Scale LO System Switches U9104 Comm RM Pwr 1J 2J Cond Vac Bkr Cap VS-F-58A Pwr H J Grn Flag U9105V Synch Key VS-F-58B Pwr H J Grn Flag Alarm Screen (List)

Post Session Checks:

PCS Screens (Cleared/Display) RO BOP SM STA PCs Logged OFF (including Booth) Phone cleared Recall IC-1 Restore NI-NR, SF/FF, and Tave/Tref Chart recorder settings Advance Charts Procedures Changed Red Light Binders Stored Trash Picked Up/Emptied Vacuum Reqd?

Pink Magnets in Drawer BB and VB Scenario Magnets removed E-Mail to SSG Required DVD Finalized EAL Charts Note Pads Manning Sheets Sticky Tabs (SRO/SM/ARPs) Markers (ARPs) Personnel/Comms Tracking Sheets (Booth)

Floor timers reset/In place Booth timers reset/In place Printers ready/have paper

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 73 of 81 SIMULATOR OPERATORS GUIDE EVENT 1 Place unit online When the team and Examiner ready, place the Simulator in RUN.

30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-GOP-1.8, 1-OP-TM-001, 1-OP-CH-021 and an approved ramp plan.

System Operator and Energy Supply (MOC):

If contacted, acknowledge the unit is coming online. Acknowledge when the unit is placed online.

Operations Supervisor/Management/Work Week Coordinator:

If contacted, acknowledge the unit is coming online.

Surrogate RO (Feed Control):

Provide feed control until the team is ready to assume the watch. At that time, turn over feed control responsibilities, relieve yourself and leave the simulator floor.

Shift Technical Advisor:

If asked to support monitoring while placing the unit online; acknowledge the request, but do not provide any information about the unit.

Field operator:

If dispatched, report all Main Transformer pumps and fans are in operation.

If contacted as CP, report that 5 polishers are in service.

Unit 2:

• If 0-BR-D2, OVHD GAS COMPR STBY START alarms (Due to VCT backing up), perform actions of ARP 0-BR-D2.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 74 of 81 SIMULATOR OPERATORS GUIDE EVENT 2 1-CC-RM-105 failure When cued by examiner, implement Trigger 1.

Shift Manager:

• If contacted, will acknowledge the failure of 1-CC-RM-105 and will also acknowledge any TS LCOs.

• If asked, will contact the OMOC.

• If asked, will take responsibility for contacting I&C department.

• If asked, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the failure of 1-CC-RM-105 and will also acknowledge any TS LCOs.

• If asked, the STA will report that all documents have been reviewed and discussed with the Shift Manager.

• If the team has a transient brief: The STA will state that he has nothing to add.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge instrumentation failure and commence investigations.

Health Physics:

• If contacted, will acknowledge the failure of 1-CC-RM-105.

• If asked, will take responsibility for conducting local surveys.

Unit 2 Operator:

• If asked, will report they have placed SOV-CC-200 in CLOSE.

• If asked, will take responsibility for performing 1-OPT-RC-10.0.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 75 of 81 SIMULATOR OPERATORS GUIDE EVENT 3 Charging Flow Controller fails high.

When cued by examiner, implement Trigger 3.

BOOTH NOTE: Ensure Blender is not operating when malfunction is entered.

Operations Supervisor/Management:

• If contacted, will acknowledge the failure of the Charging Flow Controller and also acknowledge entry into 0-AP-53.00.

• If contacted, will contact the OMOC.

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the failure of the Charging Flow Controller.

• If asked, the STA will report that all documents have been reviewed and discussed with the Shift Manager.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Unit 2:

• If 0-BR-D2, OVHD GAS COMPR STBY START alarms (Due to VCT backing up), perform actions of ARP 0-BR-D2.

Maintenance/Work Week Coordinator:

If contacted, will acknowledge the Charging Flow Controller failure and commence investigations.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 76 of 81 SIMULATOR OPERATORS GUIDE EVENT 4 EH pump trip, standby EH pump fails to auto start.

When cued by examiner, implement Trigger 5.

Critical Task (CT-1): Start the standby EH Fluid Pump prior to automatic OR manual Reactor/Turbine trip.

Operations Supervisor/Management:

• If contacted, will acknowledge the failure of 1-EH-P-MP1 and MP-2 to auto-start.

• If asked, will contact the OMOC.

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the failure of 1-EH-P-MP1 and MP-2 to auto-start.

• If asked, the STA will report that all documents have been reviewed and discussed with the Shift Manager.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Maintenance/Work Week Coordinator:

If contacted, will acknowledge EH pump failure and commence investigations.

Field Operators: (Wait three minutes between direction to perform local action/status check and report.)

• If contacted, 1-EH-P-MP1 will have no local indications for cause of the trip.

• If contacted, to investigate breaker MCC 1A1-2-7C (1-EH-P-MP1), report the breaker is in the ON position.

• If contacted, 1-EH-P-MP2 post start checks are sat.

Unit 2 Operator:

• If contacted, will acknowledge the failure of 1-EH-P-MP1 and MP-2 to auto-start. Also acknowledge when 1-EH-P-MP-2 is running.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 77 of 81 SIMULATOR OPERATORS GUIDE EVENT 5 A CH SW pump trip, failure of B CH SW pump to auto start.

When cued by examiner, implement Trigger 7.

Operations Supervisor/Management:

• If contacted, will acknowledge the failure of CH CC and will also acknowledge any TS LCOs.

• If contacted, will contact the OMOC.

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the failure of CH CC.

• If asked, the STA will report that all documents have been reviewed and discussed with the Shift Manager.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Field Operators: (Wait three minutes between direction to perform local action/status check and report.)

• If contacted, report CH SW parameters consistent with the number of CH SW pumps running.

• If contacted, 1-SW-P-10A will have no local indications for cause of the trip.

• When contacted, to investigate breaker MCC 1H1-1-1D (1-SW-P-10A), report the breaker is in the ON position.

• If contacted, 1-SW-P-10B post start checks are sat.

Maintenance/Work Week Coordinator:

If contacted, will acknowledge the CH SW pump failure and commence investigations.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 78 of 81 SIMULATOR OPERATORS GUIDE EVENT 6 Dropped Rod below 25% reactor power When cued by examiner, implement Trigger 9.

If reactor power is allowed to ramp above 25%, an additional dropped RCCA will be necessary. If that occurs, implement Trigger 25 when cued by examiner.

Operations Supervisor/Management:

• If contacted, will acknowledge the dropped rod and will also acknowledge any TS LCOs and entry into 0-AP-1.00 / 1-E-0 (as notified).

• If contacted, will contact the OMOC.

• If asked, will take responsibility for contacting I&C department.

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the dropped rod and will also acknowledge any TS LCOs and entry into 0-AP-1.00 / 1-E-0 (as notified).

• If asked, the STA will report that all documents have been reviewed and discussed with the Shift Manager.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge the dropped rod and commence investigations.

Unit 2 Operator:

• If asked, will perform 0-AP-50.00.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 79 of 81 SIMULATOR OPERATORS GUIDE EVENT 7 Small Break LOCA with failure of LHSI pumps to auto start When 1-FW-MOV-154C is manually closed by the team, Trigger 11 will automatically insert.

Critical Task (CT-2): Start at least one LHSI pump prior to requiring transition to 1-FR-C.1.

Operations Supervisor/Management:

• If contacted, will acknowledge the small break LOCA and entry into 1-E-0.

• If contacted, will acknowledge the need to evaluate EPIPs. (Will not discuss EALs with the team.)

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will acknowledge the small break LOCA and entry into 1-E-0.

• If contacted, will acknowledge the need to evaluate EPIPs. (Will not discuss EALs with the team.)

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge failure of LHSI pumps to auto start and will commence investigation.

Unit 2 Operator:

• If contacted, will acknowledge the Safety Injection initiation on unit 1.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 80 of 81 SIMULATOR OPERATORS GUIDE EVENT 8 Large Break LOCA with failure of CS pumps and valves to automatically align When cued by examiner, implement Trigger 13.

Booth Note: To ensure team enters FR-Z.1 insert trigger AFTER operator has completed Attachment 1 and Attachment 2 of E-0 and team is performing E-1 Step 1.

Critical Task (CT-3): Start at least one CS pump prior to exiting 1-FR-Z.1 to restore function.

Operations Supervisor/Management:

• If contacted, will acknowledge the large break LOCA, loss of Containment Spray function and entry into 1-E-1 / 1-FR-Z.1 (as notified).

• If contacted, will acknowledge the need to evaluate EPIPs. (Will not discuss EALs with the team.)

• If contacted, will take responsibility for writing the CR.

STA:

• When the team identifies the loss of Containment Spray function (or after Step 1 of 1-E-1 is complete (whichever is sooner), report an ORANGE path to 1-FR-Z.1 using the CSFSTs.

• If contacted, will acknowledge the large break LOCA, loss of Containment Spray function and entry into 1-E-1 / 1-FR-Z.1 (as notified).

• If contacted, will acknowledge the need to evaluate EPIPs. (Will not discuss EALs with the team.)

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state that he has nothing to add.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge failure of CS pumps to auto start and align, and will commence investigation.

Unit 2 Operator:

• If contacted, will acknowledge the CLS Hi-Hi initiation on unit 1.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 4 Page 81 of 81 SIMULATOR OPERATORS GUIDE The scenario will end upon completing step 1 of 1-FR-Z.1, or at the lead examiners discretion.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Facility: Surry Power Station Scenario No.: 5 Op-Test No.: 2021-301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 and 2 at 100% power; MOL. All systems and crossties are operable with the following exceptions:

• AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.30.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Event Event Type* Event No. Description 1 N RO/SRO Test cycle Pressurizer PORV, Block Valve breaker will trip when re-TS SRO opened. (1-PT-18.6I)

I RO/SRO 2 PRZR Level Transmitter fails low. 0-AP-53.00 (CT-1)

TS SRO 3 C BOP/SRO B Main Feed Reg Valve Controller fails low. 0-AP-53.00 (CT-2) 4 C BOP/SRO SG C PORV fails open. 1-AP-38.00.

5 R RO/SRO Isophase Bus Duct Hi Temp, requiring ramp to 90% power. ARP 1G-E5, N BOP 0-AP-23.00.

6 C RO/SRO Steam Generator Tube Leak B SG at approximately 20 gpm. 1-AP-16.00, 1-AP-24.00.

C BOP Auto actions of Air Ejector Hi RM do not function, requiring manual alignment.

7 M ALL SGTL B SG escalates to SGTR. 1-E-0, 1-E-3 (CT-3) 8 M ALL PRZR PORV 1-RC-PCV-1455C will not open when switch placed in open position. 1-ECA-3.3.

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

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 CT # EVENT DESCRIPTION MET ()

2, PZR Stabilize Pressurizer Level to prevent automatic OR Level manual Reactor Trip. With no operator action, CT-1 Transmitter Pressurizer level will continue to rise to the high level Fails Low reactor trip setpoint (88%).

3, B SG Stabilize B SG Level prior to automatic OR manual MFRV Reactor Trip. With no operator action, a Reactor trip CT-2 Controller will occur in approximately 2 minutes.

Fails Low Isolate feedwater flow into the ruptured S/G before S/G B NR reaches 100%. Failing to isolate CT-3 7, SGTR Feedwater into the ruptured S/G will cause the S/G to fill faster. Once NR level reaches 100% there is no accurate method for determining S/G level due to the inaccuracy of the WR S/G levels. Once a S/G is fully flooded the hydrodynamic loading on the S/G, MS lines, and other components may exceed their allowable stress rating, possibly causing the S/G to fail catastrophically. Note: With no operator action it is estimated that SG C will fill to 100% in approximately 40 minutes from the time the SG is ruptured.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Event 1: PT-18.6 I, PZR Block Valve Stroke Test. (N- RO/SRO, TS - SRO)

The Team will pre-brief this evolution prior to entering the Simulator. Upon entry of the Team to the Simulator, the Scenario brief will be given, Questions answered, and the Team allowed ~ 5 minutes to become acclimated to the Simulator Environment.

When the RO closes 1-RC-MOV-1535, 1-RC-PCV-1456 block valve, and attempts to re-open 1-RC-MOV-1535, a series of triggers actuate to trip the power supply breaker to 1-RC-MOV 1535.

Verifiable Action(s):

1) RO will close 1-RC-MOV-1535 and time the stroke.

2) RO will place the 1-RC-MOV-1456 PORV control switch in the close position following Tech Spec review.

Technical Specifications:

The SRO will review Tech Specs (3.1.A.6.d) and determine a one (1) hour clock exists to place 1-RC-PCV-1456 in manual (switch to close); and a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to return the block valve to an OPERABLE status, or be in HSD in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and RCS temperature <350°F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

This Event sets up entry into ECA-3.3, SGTR without Pressure Control; Major Event later in the Scenario.

Event 2: PRZR level Upper Channel Fails Low (-.2 DEG) PRZR level on selected Upper Channel fails to ~25%. (I - RO, TS - SRO). ARP 1C-D8, PRZR LO Level.

The RO will diagnose the failure based on CH to Regen HX Hi/Low flow alarm (Annunciator 1D-E5) or identification of CH flow increasing and PZR level Channel III decreasing.

Verifiable Actions(s):

1) The RO will place CH flow in Manual and control PRZR level at setpoint IAW AP-53.00, Loss of Vital Instrumentation/Controls.

2) BOP will select an operable channel on the pressurizer level recorder.

3) The RO will defeat the failed channel IAW AP-53.00, and return CH flow to automatic when normal PRZR level restored.

Critical Task:

CT-1: Stabilize Pressurizer Level prior to automatic OR manual Reactor Trip.

Technical Specifications (1):

1) TS 3.7, Table 3.7-1, item 9 (Pressurizer High Water Level), Operator Action 7. With the number of OPERABLE Channels less than the Total number of channels; place the failed channel in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowable to bypass the channel for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, if requirements not met reduce power to less than P-7 (10%) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

TRM Actions (1):

1) TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461. Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 (Hourly), within 14 days and restore the failed channel in 60 days.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Event 3: B SG Main Feed Reg Valve Controller Fails Low. (C - BOP/SRO)

BOP will diagnose the failure based upon alarms and indications received and take the Immediate Actions of 0-AP-53.00. The Team will implement 0-AP-53.00, Loss of Vital Instrumentation/Controls. The BOP will manually control B SG NR level for the remainder of the scenario.

Verifiable Action(s):

1) BOP will place the B FRV in manual and verify proper response.

2) BOP will maintain B SG level at program band.

Critical Task:

CT-2: Stabilize B SG Level prior to automatic OR manual Reactor Trip.

Event #4: SG C PORV fails open. (C - BOP/SRO)

The BOP will diagnose the failure based upon PCS alarms and indication received. The Team will initiate 1-AP-38.00, Main Steam System Control Malfunction.

Verifiable Actions:

1) BOP: Place the C SG PORV in Manual and lower output to close the PORV.

Event 5: ISOPHASE BUS DUCT HI TEMP REQUIRING 10% Power Reduction. (R - RO, R - SRO, N - BOP)

The SRO will lead a Team Brief where the reactivity plan will be discussed to reduce reactor power in 10% increments to lower isophase bus duct temp to less than 239 deg. F. The RO and SRO will be credited with a Reactivity Manipulation and the BOP with a Normal Evolution.

Verifiable Action(s):

1) RO: Manipulate control rods to control delta flux and/or Tave.

2) RO: Manipulate CVCS controls to Emergency Borate.

3) RO: Manipulate CVCS control to establish a normal boration to assist in Tave control.

4) BOP: Manipulate Turbine Controls to establish power reduction.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Event #6: Steam Generator Tube Leak B Steam Generator. Failure of Auto actions of A/E RM. (C - RO/SRO, C - BOP)

When the Evaluation Team is satisfied with the Reactivity manipulation, the event will be triggered. A SGTL of approximately 20 gpm will initiate requiring the RO to perform ARP 1A-A3, N-16 HIGH, which will direct evaluation of 1-AP-16.00 based on the observable change in RCS inventory trends. The actions of 1-AP-16.00 to quantify the leakrate. The A/E RM will go into High alarm due to the primary to secondary leakage; the BOP will manually align A/E discharge to containment IAW A/E RM ARP.

Verifiable Actions:

1) RO will isolate LD flow and place charging flow in manual to quantify leakrate.

2) BOP will respond to failure of auto actions on A/E RM High alarm by swapping A/E discharge to containment.

Event #7: SGTR in B SG, approximately 600 gpm. (M - ALL)

When the evaluation Team is ready, a SGTR in the B SG will be implemented. The RO will re-assess RCS leakage in response to alarms and indications received. The RO will determine that RCS leakage exceeds the capacity of a single CH pump, and the Team will return to E-0 and manually initiate SI.

The SRO will perform a commensurate brief and continue with E-0. While the RO and SRO continue with E-0, the BOP will be directed to perform E-0 Attachments 1 through 3. BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

Verifiable Actions:

1) RO: Increase CH flow in manual per Immediate Action Steps of 1-AP-16.00, Excessive RCS Leakage to determine if RCS leakage is greater than the capacity of a single CH pump.

2) RO: Re-perform High Level Steps of 1-E-0, and manually Safety Inject on Step 4 of 1-E-0.

3) BOP: Perform actions of Attachments 1 through 3 of 1-E-0. BOP Failures in 1-E-0 Attachments: 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not auto close, 1-VS-MOD-103A not auto close, 1-MS-TV-109 and 1-DA-TV-100A/B will not auto close (Listed as Event 9).

Critical Task:

CT-3: Isolate feedwater flow into the ruptured S/G before S/G B NR reaches 100%. Failing to isolate Feedwater into the ruptured S/G will cause the S/G to fill faster. Once NR level reaches 100% there is no accurate method for determining S/G level due to the inaccuracy of the WR S/G levels. Once a S/G is fully flooded the hydrodynamic loading on the S/G, MS lines, and other components may exceed their allowable stress rating, possibly causing the S/G to fail catastrophically. Note: With no operator action it is estimated that SG C will fill to 100% in approximately 40 minutes from the time the SG is ruptured.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Event #8: SGTR with Loss of Pressure control. (M - All)

The Team continues through the EOP progression 1-E-0 to 1-E-3.

After the Team has completed the rapid cooldown of 1-E-3 and moves to the Depressurization steps, the Team will be presented with the inability to depressurize the RCS (No RCPs - No Spray available), 1 PZR PORV inoperable, and the last Pzr PORV not responding to placing the control switch in Open. This will require the Team to Transition to 1-ECA-3.3, SGTR without Pressure Control.

When 1-ECA-3.3 is entered, it is expected that the ruptured SG level will be > 73% NR leading to Team moving to Step 6, Check If SI Can Be Terminated.

Verifiable Actions:

1) RO: Isolate AFW flow to the Ruptured SG.

2) BOP: Reset SI and secure A CH pump and one of the running LHSI pumps. (Discretionary CT - within 30 minutes).

3) RO: Manipulate steam dump controls for rapid cooldown.

4) RO/BOP: Block SI signals when conditions established.

5) RO: Manipulate SI/CVCS control to terminate SI, establish CH flow, and restore letdown flow.

The Scenario is terminated at Lead Evaluator discretion or at Step 17 of 1-ECA-3.3, Check If CS Should Be Stopped (CH and LD flow have been re-established).

Scenario Recapitulation Total Malfunctions: 10 Abnormal Events: 6, 0-AP-53.00 (twice), ARP 1D-C5, 1-AP-38.00, 1-AP-24.00, 1-AP-16.00.

Major Transients: 1 EOPs Entered: 2 (1-E-0, 1-E-3)

EOP Contingencies: 1 (1-ECA-3.3)

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #5 Initial Conditions: Unit 1 and 2 Operating at 100%.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Turnover:

Team will perform PT-18.6I, PZR Block Valve Stroke Test. The performance of this procedure has been analyzed based on the current plant configurations and the PRA indicates green.

Scenario Objectives:

A. Given a failure of 1-RC-MOV-1535 to re-open during performance of 1-PT-18.6I, PZR Block Valve Stroke Test.

B. Given a pressurizer level channel deviation, respond IAW 0-AP-53.00 to control Pressurizer level.

C. Given a Low Failure of B SG Main Feed Reg Valve Controller, take action IAW 0-AP-53.00 to control SG level.

D. Given a failure of C SG PORV, respond IAW 1-AP-38.00.

E. Given degraded Isophase Bus Duct Cooling, respond IAW ARP 1G-E5 and 0-AP-23.00 to reduce power on Unit 1.

F. Given a SG B Tube Leak with failure of Air Ejector auto swapover, respond IAW ARPs 1-RM-G8 and 1A-A3.

G. Given a Design Basis SG Tube Rupture, respond IAW 1-E-0, and 1-E-3, Steam Generator Tube Rupture.

H. Given the Failure of 1-RC-PCV-1445C to open to depressurize the RCS, transition to 1-ECA-3.3, Steam Generator Tube Rupture without Pressurizer Pressure Control.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

• AAC DG is tagged out for maintenance. Expected to be returned to services in 3 days. Per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are, upon relieving the watch, to perform PT-18.6I, PZR Block Valve Stroke Test.

Performance of this procedure has been authorized and has been PSA analyzed for current plant conditions.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 1 Page 9 of 90 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-PT-18.6I SRO/RO NOTE - Team will pre-brief this evolution prior to entering the simulator. Initial Conditions and Precautions and Limitations will be completed before entering the simulator.

RO 6.1.1 Check closed or close PRZR PORV 1-RC-PCV-1456.

RO 6.1.2 Check key switch for PRZR PORV 1-RC-PCV-1456 OVPRESS Mitigating System is in DISABLE.

RO 6.1.3 Check PRZR PORV Block Valve 1-RC-MOV-1535 is open. IF 1-RC-MOV-1535 is closed RO 6.1.4 Stroke PRZR PORV Block Valve 1-RC-MOV-1535 through one complete cycle, timing valve movement in each direction. Time from signal initiation to complete valve travel.

RO Closes 1-RC-MOV-1535 and identifies it fails to reopen.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 1 Page 10 of 90 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

SRO Refer to Technical Specification 3.1.A.6.d for required actions.

With one block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to operable status or place the associated PORV in manual. In addition, restore the block valve to operable status in the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or, be in at least HSD within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature to < 350°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

RO Places 1-RC-PCV-1456 in CLOSE.

SRO Exit 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> clock to place 1-RC-PCV-1456 in manual.

Start 72 Hour Clock to repair Block Valve.

SRO Direct RO/BOP to notify Service Building Operator to check status of 1H1-2S 6A breaker for 1-RC-MOV-1535.

RO/BOP Contact Service Building Operator to check status of 1-RC-MOV-1535 Breaker.

RO/BOP When notified by field operator that 1H1-2S 6A breaker is tripped, report information to the Team using a Focus Brief.

SRO Notify Shift Manager of Block Valve failure and suspension of PT performance.

Request Electrical Maintenance support to investigate breaker trip.

SRO Perform brief to update Team on Technical Specification requirements. Brief driven by brief card and placards.

-- END EVENT 1 -

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 2 Page 11 of 90 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior RO Diagnoses failure of 1-RC-LI-1461 with the following indications/alarms:

Alarms:

• 1C-D8 PRZR LO LEVEL Indications:

• CH Flow rises on 1-CH-FI-1122A to ~110 gpm

• PRZR Level on 1-RC-LI-1461 lowers to 25%

In accordance with the immediate actions of 0-AP-53.00 the RO will take manual control of pressurizer level control by placing 1-CH-FV-1122 in manual and lowering charging flow to maintain program level (per 0-AP-53.00).

SRO Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.

0-AP-53.00 RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL Checks 1-RC-LI-1459, Pressurizer Level Channel 1, and 1-RC-LI-1460, Pressurizer Level Channel 2 are NORMAL.

0-AP-53.00 RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FV-1122 in manual and lowers charging flow.

Critical Task (CT-1): Stabilize Pressurizer Level prior to automatic OR manual Reactor Trip.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of PRZR level with CH flow in MANUAL.

STA The STA will state they have nothing to add to the brief.

0-AP-53.00 RO *3 CHECK REACTOR POWER - LESS THAN OR EQUAL TO 100%

Reports Actual Reactor Power and Trend using PCS 30 minute power indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 2 Page 12 of 90 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-53.00 SRO CAUTION Prior to Step 4: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

NOTES prior to Step 4:

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 11.

0-AP-53.00 SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

• PRZR Level Control, Step 9.

RO The RO will identify that 1-RC-LI-1461 has failed.

0-AP-53.00 SRO 9. CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL a) Check PRZR LVL Instrumentation - NORMAL RO Responds NO, 1-RC-LI-1461 Abnormal.

SRO 9 a) RNO 1) Place either of the following in MANUAL:

• 1-CH-FC-1122C, CHG FLOW CNTRL, OR

• 1-CH-LC-1459G, PRZR LEVEL CNTRL RO Responds 1-CH-FC-1122C is in MANUAL SRO 9 a) RNO 2) Control PRZR Level at Program Level.

RO Responds Maintain PRZR Level at program +/- band set by SRO SRO 9 a) RNO 3) Move PRZR LVL - CH SEL switch to defeat the failed channel.

RO/BOP Transfers CH SEL switch to 1 / 2 Position.

SRO 9 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.

BOP Checks or adjusts PRZR Level Recorder to 1-RC-LI-1459 or 1-RC-LI-1460.

SRO 9a) RNO 5) Refer to Tech Spec 3.7-1, Item 9.

TS 3.7, Table 3.7-1, item 9; Operator Action 7. Number of Operable channels one less than Total number of channels: Place Inoperable channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowed to bypass channel for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 2 Page 13 of 90 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

for surveillance, If conditions not met within allowed time, reduce power to less than P-7 in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SRO 9 a) RNO 6) Refer to Attachment 3.

SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for review.

NOTE: Attachment 3 (one-line diagram) is provided at the end of this section.

0-AP-53.00 SRO 9 b) Check Pressurizer Heaters - Energized.

RO Reports Pressurizer heaters are energized.

9 c) Check Letdown - IN SERVICE.

SRO Reports Letdown is in service.

RO 9 d) Check PRZR level control - IN AUTOMATIC.

SRO Reports pressurizer level control in MANUAL.

0-AP-53.00 SRO 9 d) RNO

1) Check PRZR level restored to program.

SRO 2) Unsaturate 1-CH-LC-1459G, PRZR LEVEL CNTRL, as required.

RO/BOP Places 1-CH-LC-1459G in MANUAL to unsaturated the controller.

SRO 3) Return 1-CH-FCV-1122 to AUTOMATIC by checking or placing the following in AUTOMATIC:

• 1- CH-FC-1122C, CHG FLOW CNTRL

• 1-CH-LC-1459G, PRZR LEVEL CNTRL RO/BOP Places 1-CH-FC-1122C and 1-CH-LC-1459G in AUTO.

0-AP-53.00 SRO Recalls NOTE 2 Prior to Step 4 and goes to Step 11 of AP-53.00.

SRO 11. CHECK CALORIMETRIC - FUNCTIONAL IAW 1-OPT-RX-001, ATTACHMENT 4 Directs BOP to perform 1-OPT-RX-001, Attachment 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 2 Page 14 of 90 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Reports Yes, Calorimetric is Functional IAW 1-OPT-RX-001, Attachment 4.

RO/BOP 1-OPT-RX-001, Attachment 4 at end of this section.

0-AP-53.00 SRO 12. REVIEW THE FOLLOWING:

• Tech Spec 3.7

• VPAP-2802, NOTIFICATIONS AND REPORTS

• TRM SECTION 3.3, INSTRUMENTATION

• Reg Guide 1.97

• EP-AA-303, Equipment Important to Emergency Response TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461.

Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 within 14 days.

STA If directed to perform reviews required for the failure, STA will report reviews have been completed and results discussed with the Shift Manager.

0-AP-53.00 SRO 13. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS RO/BOP Reports No, no further malfunction exists.

SRO GOES TO Step 15.

0-AP-53.00 SRO 15. PROVIDE NOTIFICATIONS AS NECESSARY:

• Shift Supervision

• OMOC

• STA (PRA determination)

• I&C SRO consults Shift Manager concerning notification of OMOC of the failure and request for I&C assistance; Notifies STA to add failure to PRA program.

-- END EVENT 2 -

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 3 Page 15 of 90 Event description: B SG MFRV Controller Fails Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior BOP Diagnoses failure of B MFRV Controller with the following:

Alarms:

• 1H-E6 STM GEN 1B FW >< STM FLOW

• 1F-C8 STM GEN 1B CH 3 FW < STM FLOW

• 1F-D8 STM GEN 1B CH 4 FW < STM FLOW

• 1H-G6 STM GEN 1B LVL ERROR.

Indications:

• Lowering B SG Feed Flow on both CH-3 and CH-4

• Lowering B SG Level.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS 0-AP-53.00 BOP

[1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies all other B SG indications are NORMAL.

0-AP-53.00 BOP

[2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and increases demand (FF > SF) to restore level to program.

Critical Task (CT-2): Stabilize B SG Level prior to prevent automatic OR manual Reactor Trip.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of B SG level with B FRV in MANUAL.

STA The STA will state they have nothing to add to the brief.

0-AP-53.00 SRO

• VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Checks Reactor Power < 100% using PCS Calorimetric. Due to restoration of FF on 1B SG, power increase may be noted. As required, the SRO may

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 3 Page 16 of 90 Event description: B SG MFRV Controller Fails Low, 0-AP-53.00.

Cue: By Examiner.

direct the BOP to initiate Attachment 7. This attachment has a NOTE directing use of Delta-T and PRNIs as power indications due to the secondary transient 0-AP-53.00 SRO CAUTION Prior to Step 4: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

NOTES prior to Step 4:

RO/BOP

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

SRO

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 11.

• 4. DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

Identifies 1B SG Feed Flow affected.

Goes to Step 7.

0-AP-53.00 SRO CAUTION Prior to Step 7: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS - NORMAL

• Steam Pressure

• Steam Flow

• Feed Flow

• Steam Generator Level BOP Determines SGWLCS instrumentation for B SG is normal.

SRO Recalls the second note at Step 4 (When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 11)

Goes to Step 11.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 3 Page 17 of 90 Event description: B SG MFRV Controller Fails Low, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 11. CHECK CALORIMETRIC - FUNCTIONAL IAW 1-OPT-RX-001, ATTACHMENT 4 Directs BOP to perform 1-OPT-RX-001, Attachment 4.

Reports Yes, Calorimetric is Functional IAW 1-OPT-RX-001, Attachment 4.

BOP 0-AP-53.00 SRO 12. REVIEW THE FOLLOWING:

• Tech Spec 3.7

• VPAP-2802, NOTIFICATIONS AND REPORTS

• TRM SECTION 3.3, INSTRUMENTATION

• Reg Guide 1.97

• EP-AA-303, Equipment Important to Emergency Response SRO If directed to perform reviews required for the failure, STA will report reviews have been completed and results discussed with the Shift Manager.

0-AP-53.00 SRO 13. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS RO Reports No, no further malfunction exists.

SRO GOES TO Step 15.

0-AP-53.00 SRO 15. PROVIDE NOTIFICATIONS AS NECESSARY:

• Shift Supervision

• OMOC

• STA (PRA determination)

• I&C SRO consults Shift Manager concerning notification of OMOC of the failure and request for I&C assistance; Notifies STA to add failure to PRA program.

END EVENT 3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 4 Page 18 of 90 Event

Description:

C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

Cue: By Evaluator Time Position Applicants Action or Behavior BOP Diagnoses failure based on the following indications:

C SG PORV RED open light LIT C SG SG PORV Demand ramping to 100%

Rising CALCALC trends Multiple PCS alarms related to C SG parameters 0-AP-53.00 Perform Immediate Action Steps of 0-AP-53.00:

BOP [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL Identifies C SG pressure NORMAL.

[2] PLACE AFFECTED CONTROL(S)/ COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places C SG PORV in Manual, and reduces demand to close the C SG PORV.

Checks C SG PORV RED light out and GREEN light LIT.

Reports Immediate Actions of 0-AP-53.00 complete.

0-AP-53.00 SRO Conducts a Transient Brief Summarizes Event and queries RO and BOP for Annunciators received and Critical Parameters.

RO RO reports PCS alarms and CALCALC trend received.

BOP BOP reports SG parameters.

STA STA will have no input for the Brief.

SRO SRO Concludes the Brief and continues 0-AP-53.00 at Step 3.

0-AP-53.00 SRO *3 CHECK REACTOR POWER - LESS THAN OR EQUAL TO 100%

BOP Reports Actual Reactor Power and Trend using PCS 30-minute power indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 4 Page 19 of 90 Event

Description:

C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

Cue: By Evaluator Time Position Applicants Action or Behavior 0-AP-53.00 CAUTION Prior to Step 4: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

NOTES prior to Step 4:

• Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.

• When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 11.

SRO *4. DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

• Steam Dumps / SG PORVs 1-AP-38.00 BOP Reports Yes, SG C SG PORV.

SRO Goes to 1-AP-38.00 Note: SRO may have directly entered 1-AP-38.00, Main Steam System Malfunction.

1-AP-38.00 NOTE Prior to Step 1: Attachment 3 has one-line diagrams of steam dump permissive and modulating circuits.

SRO 1. CHECK STEAM DUMP VALVES - CLOSED BOP Reports Yes, Steam Dumps closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 4 Page 20 of 90 Event

Description:

C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

Cue: By Evaluator Time Position Applicants Action or Behavior 1-AP-38.00 SRO 2. CHECK SG PORVS - CLOSED BOP Reports, Yes C SG PORV closed, but was open.

(NOTE: If 1-AP-38.00 was entered directly, the report will be No, C SG PORV open, and the team will perform Step 2 RNO.)

SRO 2. RNO IF SG pressure greater than desired pressure, THEN check PORV(s) close when SG pressure lowers below desired pressure AND GO TO Step 3.

BOP Reports No, C SG Pressure NORMAL.

SRO IF SG pressure less than desired pressure, THEN do the following:

a) Place affected PORV controller in Manual and close valve.

BOP Reports Yes, C SG PORV in Manual and closed.

(NOTE: If 0-AP-53.00 was not performed, this is where the BOP will place the C SG PORV Controller in MANUAL, lower output to 0%, and verify the valve closes.)

SRO b) IF any SG PORV NOT closed, THEN do either of the following:

BOP Reports No, PORV is closed.

SRO c) Check associated MS line pressure transmitter (1-MS-PI-101A, B, C) for the affected PORV at the ASD Panel to determine if transmitter failure is cause of PORV failure.

BOP Directs BOP to dispatch Service Bldg Inside operator to check status of MS line pressure indicators on Aux Shutdown Panel.

Note: Service Bldg Inside operator will report 1-MS-PI-101C indicates 800 psig.

SRO continues to Step 3, while awaiting local report.

1-AP-38.00 SRO 3. CHECK THE FOLLOWING CONDITIONS:

• Reactor power - LESS THAN OR EQUAL TO 100%

• Turbine load - NORMAL BOP Reports Yes, reactor power is less than 100% and Turbine load is normal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 4 Page 21 of 90 Event

Description:

C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

Cue: By Evaluator Time Position Applicants Action or Behavior 1-AP-38.00 NOTES prior to Step 4:

• The power reductions required by Step 4 are intended for failures causing full or partial closure of a control valve, or if valve closure is required for maintenance.

• 1-MS-FCV-104B has been upgraded to a different style valve and may start to drift closed with IA pressure less than 65 psig.

SRO

4. CHECK MAIN TURBINE AND MSR STEAM CONTROL VALVES:

a) MSR Steam supply MOVs and FCVs - NORMAL b) Turbine Governor Valves and Stop Valves - NORMAL c) Reheat Stop and Intercept Valves - NORMAL BOP Reports Yes, Turbine and MST Steam Control Valves normal.

1-AP-38.00 SRO 5. CHECK TURBINE MONITORING LIGHTS - NORMAL BOP Reports Yes, Turbine Monitoring Lights are normal.

1-AP-38.00 SRO 6. STABILIZE UNIT CONDITIONS:

a) Adjust Turbine load as necessary b) Borate or dilute as necessary RO/BOP Report Yes, Unit Conditions Stable.

1-AP-38.00 SRO 7. SUBMIT CONDITION REPORT AS NECESSARY RO/BOP Acknowledge CR submission required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 4 Page 22 of 90 Event

Description:

C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

Cue: By Evaluator Time Position Applicants Action or Behavior 1-AP-38.00 SRO 8. PROVIDE NOTIFICATIONS:

• Shift Supervision

• STA (PRA determination)

• OMOC

• MOC SRO will contact Shift Manager; notify of failure, Unit Status, and procedure entered; request OMOC and I&C be notified.

1-AP-38.00 SRO 9. CHECK ABNORMAL CONDITION - CORRECTED 9 RNO:

a) Consult with Shift Supervision.

b) Submit Condition Report.

c) IF problem of short term nature, THEN GO TO Step 10 when problem corrected.

SRO will conduct a focus brief and discuss failure with the Crew; 1-AP-38.00 will be suspended until resolution by I&C.

END EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 23 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator Time Position Applicants Action or Behavior BOP Diagnoses failure based on the following indications:

Alarms:

1G-E5, GEN LEADS CLG TRBL PCS Alarms for high Main Generator Phase Temperature Indications:

Rising Main Generator B Phase Temperature on PCS (T2456A)

ARP 1G-E5 BOP NOTE: The following Computer points may be used to monitor duct temperature trend.

• T2545A EP-TIS-IPBDA - Isolated Phase Bus Duct A Phase Air Temperature

• T2546A EP-TIS-IPBDB - Isolated Phase Bus Duct B Phase Air Temperature

• T2547A EP-TIS-IPBDC - Isolated Phase Bus Duct C Phase Air Temperature 1 SEND OPERATOR TO 1-EP-PNL-IPBD1, IPBD LOCAL ANNUNCIATOR PANEL 2 LOCALLY CHECK DROP - HIGH TEMPERATURE Field operator will report Yes, the local drop is High Temperature.

ARP 1G-E5 BOP NOTE: Do not delay required actions while establishing portable fan cooling.

3. LOCALLY CHECK TEMPERATURE INDICATION ON 1-EP-PNL IPBD2, TEMPERATURE MONITORING SYSTEM

• Phase Temp greater than 115°C / 239°F (Any of three phases)

Field operator will report local temperature in Celsius.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 24 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator Time Position Applicants Action or Behavior ARP 1G-E5 BOP 4. REDUCE TURBINE LOAD BY 10% OF CURRENT LOAD AT NORMAL RAMP RATE SRO Directs the RO to review the Reactivity Plan for a 10% Turbine Load reduction at normal ramp rate.

Informs the team they are initiating 0-AP-23.00, Rapid Load Reduction.

(0-AP-23.00 actions begin on the next page.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 25 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator Time Position Applicants Action or Behavior Start of 0-AP-23.00 SRO Conducts a Brief summarizing the Event and Establish priorities.

The RO/BOP will report Annunciators received related to the event, and Critical Parameters affected.

STA STA will have no input for the brief.

RO Reactivity control during 0-AP-23.00 Ramp:

65 gallons of Boric Acid needed to reduce power to 90% using normal boration. Control Bank D rod height at end of ramp 213 Steps.

SRO Completes Brief and continues with 0-AP-23.00.

0-AP-23.00 SRO Caution Prior to Step 1:

• Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

• Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO

• When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.

• Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.

• The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.

• For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

0-AP-23.00 RO 1. TURN ON ALL PRZR HEATERS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 26 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00

2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Verify turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

SRO a) Check or place Turbine in Operator Auto.

BOP d) Verify or place turbine in IMP IN or IMP OUT as determined by Shift Supervision SRO The SRO can choose IMP IN or IMP OUT.

BOP e) Adjust SETTER to desired power level f) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (setting of 6 = 0.3%/minute) g) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) h) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.

0-AP-23.00 SRO 3. CHECK EMERGENCY BORATION - REQUIRED RO Report No, not required.

SRO Goes to Step 3 RNO - GO TO Step 5.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 27 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00 RO

5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

SRO may direct manual rod motion to maintain flux within specified band.

0-AP-23.00 SRO Notes Prior to Step 6:

• If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 36.

• RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.

• I & C should be contacted to provide assistance with adjusting IRPIs.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 28 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00 RO 6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG 0-AP-23.00 RO *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

0-AP-23.00 BOP 8. MONITOR STEAM DUMPS FOR PROPER OPERATION 0-AP-23.00 SRO 9. NOTIFY THE FOLLOWING:

• Energy Supply (MOC)

• Polishing Building

• Chemistry

• OMOC 0-AP-23.00 SRO 10. EVALUATE THE FOLLOWING:

• EPIP applicability SM The Shift Manager will review EPIPs for applicability. (They are not applicable.)

• VPAP-2802, NOTIFICATIONS AND REPORTS, applicability STA If directed to review VPAP-2802. The STA reports completion of review of VPAP-2802 and required notifications discussed with SM.

No further actions are required for this event.

0-AP-23.00 SRO

11. CHECK RAMP WILL BE TO LESS THAN APPROXIMATELY 35%

REACTOR POWER RO Reports No, ramping to 90% power.

SRO Goes to Step 11 RNO - GO TO Step 13.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 29 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00 SRO *13. CHECK REACTOR POWER HAS LOWERED MORE THAN 15% IN ONE HOUR.

RO Reports No, Reactor power will not be lowered more than 15% in one hour.

SRO Goes to Step 13 RNO - GO TO Step 15.

0-AP-23.00 SRO CAUTION: Secondary plant evolutions affecting Feedwater Flow or temperature will affect RCS temperature and Reactor Power. This effect will be greater at beginning of core life due to a lower value for isothermal temperature coefficient. The operating team must be prepared to mitigate the effects of the secondary evolutions on the RCS.

15. AT APPROXIMATELY 70% REACTOR POWER CHECK AUXILIARY STEAM MAINTAINING BETWEEN 160 AND 180 PSIG.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 30 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MOD SEL switch in the BORATE position.

RO 5. Place the MAKE MODE CNTRL switch in the START position.

RO 6. Verify proper valve positions.

RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Verify controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 5 Page 31 of 90 Event

Description:

Degraded Isophase Bus Duct Cooling, ARP 1G-E5 and 0-AP-23.00.

Cue: By Evaluator 0-AP-23.00 Attachment 5 (Manual Makeups) Actions

1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.

3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.

4. Place the MAKE-UP MODE SEL switch in the MANUAL position.

5. Place the MAKE-UP MODE CNTRL switch in the START position.

6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.

7. Check proper valve positions.

8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position

9. Place the MAKE-UP MODE CNTRL switch in the STOP position.

10. Check or place the control switches in the AUTO position.

11. Check controllers for Primary Grade water and Boric Acid are set correctly.

12. Place the MAKE-UP MODE SEL switch in the AUTO position.

13. Place the MAKE-UP MODE CNTRL switch in the START position.

14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 6 Page 32 of 90 Event

Description:

SG Tube Leak 20 gpm, A/E Auto Functions Fail, Cue: By Evaluator.

Time Position Applicants Action or Behavior Team Diagnose SGTL B SG based on the following:

Alarms:

• 1A-B3 N-16 ALERT

• 1A-A3 N-16 HIGH

• RM-G8 CNDSR AIR EJECTOR ALERT/FAILURE

• RM-H8 1-SV-RI-111 HIGH Indications:

• Increasing trend on 1-MS-RR-193, Control Room N16 Trend Recorder, from Normal to 200 GPD.

• STM LINE B Trend will Lead STM LINE A and STM LINE B.

BOP Perform ARP 1A-A3, N-16 HIGH.

Note: ARP 1A-A3 is included in this guide after ARP 1-RM-H8.

Unit 2 Note: Unit 2 Operator will only silence and announce the alarms for A/E and Blowdown RM. If asked, Unit 2 will state they are unavailable to perform the ARPs or any actions associated with the ARPs.

ARP RM-H8, A/E RM HIGH (Unit 2 will hand the ARP to the BOP at Step 6)

BOP NOTE: On a high alarm, air ejector gaseous effluent is diverted from vent stack to containment.

6. CHECK AUTOMATIC ACTIONS - VALVES POSITIONED AS FOLLOWS:

• 1-SV-TV-103 - CLOSED Identifies 1-SV-TV-103 Open, places control switch in CLOSE.

• 1-SV-TV-102 - OPEN Identifies 1-SV-TV-102 Closed, places control switch in OPEN.

RM-H8 BOP 7. CHECK AIR EJECTOR VENT TO CTMT VV - OPEN

• 1-SV-TV-102A Identifies 1-SV-TV-102A open Report to SRO that A/E manually aligned to containment.

Note: No other verifiable actions are in this ARP.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 6 Page 33 of 90 Event

Description:

SG Tube Leak 20 gpm, A/E Auto Functions Fail, Cue: By Evaluator.

Time Position Applicants Action or Behavior RM-H8 BOP 8. LOCALLY CHECK PROPER AIR EJECTOR OPERATION AND LOOP SEAL INTACT Direct Field operator to locally check Air Ejector operation and loop seals intact.

RM-H8 BOP 9. CHECK FLOW RATE MEASURING DEVICES - OPERABLE:

• 1-CN-SC-1A

• 1-CN-SC-1B Direct Field operator to locally check Air Ejector flow rates RM-H8 BOP 10. PROVIDE NOTIFICATIONS AS NECESSARY:

• Shift Supervision

• OMOC

• STA

• Health Physics

• Instrumentation Department Informs the SRO of required notifications.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 6 Page 34 of 90 Event

Description:

SG Tube Leak 20 gpm, A/E Auto Functions Fail, Cue: By Evaluator.

Time Position Applicants Action or Behavior ARP 1A-A3, N-16 HIGH BOP NOTES before Step 1:

• N-16 Radiation Monitor setpoints are available in the NI/Radiation Monitor information book.

• N-16 Radiation Monitor readings are invalid when Reactor power is less than 25%.

1. CHECK REACTOR POWER - GREATER THAN 25%

Identifies Reactor power is greater than 25% (value depending on ramp in progress).

1A-A3 BOP 2. CHECK N-16 RECORDER - ANY MONITOR READING GREATER THAN OR EQUAL TO HIGH SETPOINT

• 1-MS-RR-193 Identifies all three monitors reading greater than setpoint.

1A-A3 BOP NOTE before Step 3: A Steam Generator tube leak of 150 gpd equates to 0.1 gpm. Leaks of this size will probably not cause an observable change in primary system parameters.

3. CHECK RCS LEAK RATE:

• PRZR level - DECREASING OR

• Annunciator 1D-E5, CHG PP TO REGEN HX HI-LO FLOW - LIT OR

• A discernible negative change in VCT level trend has developed Depending on the control of the ramp, the team may identify a discernable negative change in VCT level trend.

1A-A3 BOP 4. INITIATE 1-AP-16.00, EXCESSIVE RCS LEAKAGE SRO Direct the RO to perform the Immediate Action Steps of 1-AP-16.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 6 Page 35 of 90 Event

Description:

SG Tube Leak 20 gpm, A/E Auto Functions Fail, Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-AP-16.00 RO NOTE:

• If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.

• RCS average temperature has a direct impact on pressurizer level.

[ 1 ] ___ MAINTAIN PRZR LEVEL:

RO

• Isolate Letdown Close 1-CH-LCV-1460A and 1-CH-LCV-1460B

• Control Charging flow Place 1-CH-FCV-1122, CH Flow Control Valve, in Manual.

Monitor CH Flow on 1-CH-FI-1122 Identify RCS leak rate less than the capacity of a single CH pump.

Continue adjustment of CH flow to quantify leak rate to determine if reactor trip required 1-AP-16.00 SRO Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.

1-AP-16.00 SRO

2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

• PRZR level

• PRZR pressure

• RCS subcooling RO Report that PRZR Level is rising; Pressure and Subcooling are stable RO continues actions to quantify leakrate 1-AP-16.00 SRO 3. PLACE THE FOLLOWING COMPONENTS IN OFF:

• CTMT sump pumps RO Places 1-DA-P-4B control switch on OFF

• CTMT vacuum pumps Places 1-CV-P-1A control switch in OFF

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 6 Page 36 of 90 Event

Description:

SG Tube Leak 20 gpm, A/E Auto Functions Fail, Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-AP-16.00 SRO NOTE before Step 4: Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

SRO 4. CHECK REACTOR TRIP - REQUIRED

• Leak rate - GREATER THAN 50 GPM OR

• Adequate makeup not being provided by blender RO Reports RCS leak rate is less than 50 gpm.

SRO GO TO Step 7.

NOTE: Due to transient on RCS caused by Ramp for previous event, exact quantification of leak rate will be difficult.

1-AP-16.00 SRO 7. CHECK SECONDARY RADIATION - NORMAL OR STABLE IF THERE IS PRE-EXISTING TUBE LEAK

• Air Ejector Rad Monitor

• SG Blowdown Rad Monitors

• Main Steam Line Rad Monitors

• Secondary sample

• N-16 Rad Monitors RO Reports No, secondary radiation is not normal, based on multiple secondary RM alarms in.

SRO Goes to Step 7 RNO:

1-AP-16.00 SRO Step 7 RNO:

Do the following:

a) Consult with Shift Manager.

b) IF Reactor trip NOT required, THEN initiate 1-AP-24.00, MINOR SG TUBE LEAK.

RO Reports Reactor trip is not required.

NOTE: Performing 1-AP-24.00 is not part of this scenario. If not done already, the next event (SGTR) is to be initiated at this time.

END EVENT 6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 37 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior Diagnose SGTR B SG based on the following:

Indications:

• Change in Pressurizer level trend.

• Change in B SG Level trend

• Change in B MS Rad Monitor trend Alarms:

• 1C-B8 PRZR LO PRESS

• 1C-D8 PRZR LO LVL

• 0-RMA-A2 UNIT 1 MN STM ABC RAD ON ALERT / HI RO 1-AP-16.00 (Performed a second time)

NOTE:

• If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.

• RCS average temperature has a direct impact on pressurizer level.

RO [ 1 ] MAINTAIN PRZR LEVEL:

• Isolate Letdown

• Control Charging flow With 1-CH-FCV-1122, CH Flow Control Valve, already in Manual, raises flow to maximum.

Reports Immediate Actions of 1-AP-16.00 are complete.

1-AP-16.00 SRO Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.

1-AP-16.00 SRO

2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

• PRZR level

• PRZR pressure

• RCS subcooling RO Reports that PRZR Level, Pressure and Subcooling are all lowering.

Goes to Step 2 RNO.

1-AP-16.00 SRO Step 2 RNO. GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION.

Directs RO to perform 1-E-0 Immediate Actions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 38 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-0, Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes a reactor trip pushbutton.

b) Check the following:

• All Rods On Bottom light - LIT

• Reactor trip and bypass breakers - OPEN

• Neutron flux - DECREASING Reports Reactor Tripped at completion of Step 1.

1-E-0 RO [2] CHECK TURBINE TRIP:

a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Check all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

• 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

Reports Turbine Tripped at completion of Step 2.

1-E-0 RO [3] VERIFY BOTH AC EMERGENCY BUSES - ENERGIZED Reports Both AC Emergency Buses Energized at completion of Step 3.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 39 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-0 RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

• LHSI pumps - RUNNING

• SI annunciators - LIT

• A-F-3 SI INITIATED - TRAIN A

• A-F-4 SI INITIATED - TRAIN B RO RO will determine that SI has not occurred and perform step 4a RNO actions:

4a RNO Check if SI is required or imminent as indicated by any of the following:

• Low PRZR pressure

• High CTMT pressure

• High steamline differential pressure

• High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

Determines SI is imminent. Manually depresses SI Initiation pushbuttons.

NOTE: The SRO may have directed the RO to manually initiate SI at Step 4 of 1-E-0. In that case, the RO will have already determined that SI is imminent.

RO reports 1-E-0 Immediate Actions are complete, SI is in service after RO completion of Step 4.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0 and conduct a commensurate brief.

During the Brief RO/BOP reports that ALL RCPs are tripped.

Identify 1B SG experiencing a SG Tube Rupture.

STA The STA will have nothing to add to the brief.

SRO Establish priorities at Brief End, RO:

• 1-E-0, Attachment 9, RUPTURED SG ISOLATION AND AFW FLOW CONTROL.

BOP:

• 1-E-0 Attachments 1, 2, and 3.

• Contact Service Building Operator to check status of RCP breakers.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 40 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-0 SRO/BOP 5. Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained under last section of Event 9.

SRO/RO SRO may direct the RO to perform Attachment 9 of 1-E-0 for Ruptured SG Isolation and AFW Control. This may or may not be initiated at any time during the performance of E-0. Attachment 9 actions are contained at the end of this section, beginning at page 52.

1-E-0 SRO CAUTION before Step 6: 1-MS-15 may need to be closed to stop RCS cooldown and 1-MS-17 opened to supply AS to GS.

• 6. CHECK RCS AVERAGE TEMPERATURE

• STABLE AT 547°F OR

• TRENDING TO 547°F RO Reports No, Tave less than 547°F and lowering.

SRO Goes to Step 6 RNO.

NOTE: Based on the duration of the 1-E-0 transient brief, RCS Tave may not be lowering at this time.

6. RNO: IF temperature less than 547°F AND lowering, THEN do the following:

a) Stop dumping steam.

b) IF cooldown continues, THEN control total feed flow. Maintain total feed flow greater than 350 gpm [450 gpm] until narrow range level greater than 12% [18%] in at least one SG.

c) IF RCS cooldown is occurring, THEN close 1-MS-15 AND open 1-MS-17 to align AS to GS.

d) IF cooldown continues, THEN close MSTVs.

RO Throttles total AFW flow to stop RCS cooldown.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 41 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-0

7. CHECK PRZR PORVs AND SPRAY VALVES:

SRO a) PRZR PORVs - CLOSED b) PRZR spray controls

• Demand at Zero (or)

• Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN 1- E-0 SRO NOTE before Step 8: Seal injection flow should be maintained to all RCPs.

• 8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

RO a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling will NOT be less than 30 °F RNO for the step is to go to step 9.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 42 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-0 SRO 9. CHECK IF SGs ARE NOT FAULTED:

• Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO Reports a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

1-E-0 SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

• Condenser air ejector radiation - NOT NORMAL

• SG blowdown radiation - NOT NORMAL

• SG MS radiation - NORMAL

• TD AFW pump exhaust radiation - NORMAL

• SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO Reports No, B SG NR level going up uncontrollably.

SRO RNO: GO TO 1-E-3, STEAM GENERATOR TUBE RUPTURE.

SRO The team will hold a transition brief. During the brief it will be identified that B SG is ruptured, current isolation status of the ruptured SG and that the team is transitioning to 1-E-3.

STA The STA will have nothing to add to the transient brief.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 43 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior BEGIN Step 1, 1-E-3:

SRO NOTE before Step 1: Seal injection flow should be maintained to all RCPs.

• CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO RO will identify that two charging pumps are running.

SRO b) RCS subcooling - LESS THAN 30°F [85°F]

RO RO will identify that RCS subcooling is greater than 30°F SRO Goes to Step 1 RNO - GO TO step 2 1-E-3 SRO 2. IDENTIFY RUPTURED SG(s):

• Unexpected rise in any SG narrow range level OR

• High radiation from any SG MS line monitor OR

• High radiation from any SG blowdown line OR

• High radiation from any SG sample RO Reports B SG NR level rising unexpectedly.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 44 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO CAUTIONS before Step 3:

• If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.

• At least one SG must be maintained available for RCS cooldown.

3. ISOLATE RUPTURED SG(s):

a) Adjust ruptured SG PORV controller setpoint to 1035 psig b) Check ruptured SG(s) PORV - CLOSED c) Verify blowdown TVs from ruptured SG(s) - CLOSED d) Locally close steam supply valve(s) to TD AFW pump:

• 1-MS-120 for B SG If 1-MS-120 not closed iaw attachment 9 of 1-E-0, then a field operator will be RO dispatched to close it at this time.

e) Close ruptured SG(s) MSTV (1-MS-TV-101B)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 45 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO CAUTION before Step 4: If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

• 4. CHECK RUPTURED SG LEVEL:

a) Narrow range level - GREATER THAN 12% [18%]

b) Stop feed flow to ruptured SG(s)

RO Identifies B SG level >12%, closes 1-FW-MOV-151C/D to isolate AFW Flow SRO c) Check ruptured SG AFW MOVs auto-open signal - DEFEATED Identifies auto-open signal not defeated, SRO goes to Step 4 c) RNO RO NOTE: BOP may have performed the following IAW Attachment 9.

1) Select the ruptured SG AFW MOVs using the following switches:

• H TRAIN DISABLE SELECTOR SWITCH (C)

• J TRAIN DISABLE SELECTOR SWITCH (D)

2) Defeat the auto-open signal for the selected MOVs by placing the following key switches in the DISABLE SELECTED position:

• H TRAIN AUTO OPEN ENABLE SWITCH

• J TRAIN AUTO OPEN ENABLE SWITCH 1-E-3 SRO CAUTION before Step 5: Major steam flow paths from the ruptured SG(s) should be isolated before initiating RCS cooldown.

5. CHECK RUPTURED SG(S) PRESSURE - GREATER THAN 350 PSIG RO Reports Yes, B SG pressure ~ 1000 psig.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 46 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO *6. CHECK LOW PRZR PRESS SI SIGNAL - BLOCKED

• Permissive Status light C LIT RO Identifies PSL C-2 is LIT.

NOTE: BOP should have completed this action in E-0, Attachment 1.

1-E-3 SRO *7. CHECK LOW TAVE SI SIGNAL - BLOCKED

• Permissive Status light F LIT RO Identifies PSL F-1 NOT LIT.

SRO WHEN Tave less than 543°F, THEN do the following:

RO a) Turn both HI STM FLOW & LO TAVG OR LP switches to block.

b) Check Permissive Status light F LIT.

NOTE: These actions may be performed after the 1-E-3 cooldown is initiated.

NOTE: BOP may have completed this action in E-0, Attachment 1, if Tave was allowed to lower below 543°F.

1-E-3 SRO CAUTIONS and NOTE before Step 8:

CAUTION:

• Flow on each Main Steamline should be kept less than 1.0 x 106 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps.

• If no RCPs are running, RCS cooldown and depressurization may cause a false Integrity Status Tree indication on the ruptured loop.

The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 36.

NOTE: RCP trip criteria does NOT apply after initiation of an operator controlled cooldown.

SRO/BOP 8. INITIATE RCS COOLDOWN:

a) Determine required core exit temperature (ONE TIME):

Concur Target CETC temperature 485 °F if SG pressure between 901 and 1000 psig, or 495° if SG pressure between 1001 and 1085 psig.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 47 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO Step 8, continued:

BOP b) Place Steam Dump Mode Select switch in Steam Pressure mode RO c) Check RCS Tave - LESS THAN 543°F BOP d) Place the STM DUMP CNTRL switch in BYP INTLK and then return to

\ ON RO e) Check Bypass Status light D LIT BOP f) Dump steam to condenser from intact SG(s) at maximum rate SRO g) Check CETCs - LESS THAN REQUIRED TEMPERATURE When RCS Temperature < 543°F, SRO will direct the block of HSF SI and check of PSL F-1 LIT.

When RCS pressure < 2000 psig, SRO will direct the block of Low Pressure/Header-to-Line SI Signal, and check the PSL C-2 LIT.

RO Performs the Block of SI Signals and check of PSLs when directed.

h) Stop RCS cooldown RO When target CETC Temperature reached, RO throttles back on steam dumps.

SRO i) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE SRO will direct a band for control of CETC temperature.

1-E-3 SRO *9. CHECK INTACT SG LEVELS:

a) Any narrow range level - GREATER THAN 12% [18%]

b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%

RO/BOP Adjust AFW to restore A and C SG NR Level to 22-50%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 48 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO CAUTION before Step 10: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure lowers to less than 2335 psig.

• 10. CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE b) PRZR PORVs - CLOSED c) PRZR PORV block valves - AT LEAST ONE OPEN 1-E-3 SRO 11. RESET BOTH TRAINS OF SI RO Push SI Reset Pushbuttons if SI not previously reset.

1-E-3 SRO 12. RESET CLS:

a) Check CTMT pressure - HAS EXCEEDED 17.7 psia RO Report No, CTMT has not exceeded 17.7 psia.

RNO a) GO TO Step 13.

1-E-3 SRO 13. CHECK INSTRUMENT AIR AVAILABLE:

a) Check annunciator B-E NOT LIT RO Report Yes, B-E-6 Not Lit.

SRO b) Check at least one CTMT IA compressor - RUNNING

• 1-IA-C-4A or 1-IA-C-4B RO Report Yes, 1-IA-C-4A running SRO c) Check 1-IA-TV-100 - OPEN RO Report Yes, 1-IA-TV-100 open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 49 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO 14. ALIGN CONDENSER AIR EJECTOR TO CTMT:

a) Check the following:

• 1-SV-TV-102 - OPEN

• 1-SV-TV-103 - CLOSED RO Reports valves in required position. Valves Manually Aligned by BOP on A/E RM auto failure during Event 6.

SRO b) Open the following valve:

• 1-SV-TV-102A RO/BOP Opens 1-SV-TV-102A.

1-E-3 SRO CAUTION before Step 15: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig],

one LHSI pump must be manually restarted to supply water to the RCS.

• 15. CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO Reports one LHSI pump running with suction aligned to RWST.

b) RCS pressure - GREATER THAN 250 PSIG [400 PSIG]

RO Reports RCS pressure greater than 250 psig.

c) Stop LHSI pumps and put in AUTO RO Stops running LHSI pump and places in AUTO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 50 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO 16. CHECK IF RCS COOLDOWN SHOULD BE STOPPED:

a) Check CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports CETCs < required temperature SRO b) Stop RCS cooldown RO/BOP Reports RCS Coodown stopped.

SRO c) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports that RCS temperature being maintained in required band.

1-E-3 SRO 17. CHECK RUPTURED SG(s) PRESSURE - STABLE OR INCREASING BOP Reports Yes, B SG pressure stable.

1-E-3 SRO 18. CHECK RCS SUBCOOLING BASED ON CETCs - GREATER THAN 50°F

[105°F]

BOP Reports indicated subcooling value.

1-E-3 SRO 19. DEPRESSURIZE RCS TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) Check normal spray - AVAILABLE

• RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR

• RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE RO Identifies No pressurizer spray available, SRO Goes To Step 19 a) RNO -

GO TO Step 20.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 51 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior 1-E-3 SRO CAUTIONS and NOTE before Step 20:

CAUTION:

• The PRT may rupture if a PRZR PORV is used for RCS depressurization. Rupturing the PRT may result in abnormal containment conditions.

• Cycling of the PRZR PORV should be minimized.

NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.

20. DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) PRZR PORV - AT LEAST ONE AVAILABLE b) Open one PRZR PORV until ANY of the following conditions satisfied:

(Attachment 3 lists conditions)

• PRZR level - GREATER THAN 69%

OR

• RCS subcooling based on CETCs - LESS THAN 30°F [85°F]

OR

• BOTH of the following exist:

1) RCS pressure - LESS THAN RUPTURE SG(s) PRESSURE

2) PRZR level - GREATER THAN 22% [50%]

RO When Attempt Made to open 1-RC-PCV-1455C, PCV will Not Open.

SRO Transition to 1-ECA-3.3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 52 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

Time Position Applicants Action or Behavior ATTACHMENT 9 of 1-E-0

1. Check SI is in progress. IF SI NOT in progress, THEN RETURN TO procedure step in effect.

RO/BOP RO/BOP identifies that SI is in progress.

ATTACHMENT 9 of 1-E-0 RO/BOP 2. Identify Ruptured SG by one of the following conditions:

• Unexpected rise in any SG Narrow Range level

• High radiation from any SG MS line monitor

• High radiation from any SG Blowdown line Identifies B SG as the ruptured SG ATTACHMENT 9 of 1-E-0 RO/BOP 3. Check running or start AFW Pumps, as necessary

• 1-FW-P-3A

• 1-FW-P-3B

• 1-FW-P-2 ATTACHMENT 9 of 1-E-0 RO/BOP 4. When ruptured SG Narrow Range level is greater than 12%, then isolate feed flow to ruptured SG by closing SG AFW Isolation MOVs:

• SG B, 1-FW-MOV-151C and 1-FW-MOV-151D RO/BOP closes 1-FW-MOV-151C/D when SG level is greater than 12%

Narrow Range.

This step completes Critical Task (CT-3): Isolate feed flow to the ruptured SG before B SG NR Level reaches 100%.

ATTACHMENT 9 of 1-E-0 RO/BOP 5. Select the ruptured SG AFW MOVs using the following switches:

• H TRAIN DISABLE SELECTOR SWITCH

• J TRAIN DISABLE SELECTOR SWITCH

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 7 Page 53 of 90 Event

Description:

SGTL becomes SGTR (600) gpm, AP-16.00, E-0, RCPs trip on swap to RSST, E-3.

Cue: By Evaluator, prior to entry to 1-AP-24.00.

ATTACHMENT 9 of 1-E-0 RO/BOP 6. Disable the auto-open signal for the selected MOVs by placing the following keyswitches in the DISABLE SELETED position:

• H TRAIN AUTO OPEN ENABLE SWITCH

• J TRAIN AUTO OPEN ENABLE SWITCH ATTACHMENT 9 of 1-E-0 RO/BOP CAUTION: At least one SG must be maintained available for RCS heat sink.

7. Locally close steam supply valve to the TD AFW pump:

• SG B, 1-MS-120 RO/BOP directs field operator to close 1-MS-120.

The field operator will acknowledge the requirement to close 1-MS-120. The field operator will later report that 1-MS-120 is closed.

ATTACHMENT 9 of 1-E-0 RO/BOP 8. Control Feed Flow to the SG IAW the following requirements:

• Minimum AFW flow is 350 gpm with SI initiated, until one SG Narrow Range level is greater than 12%

• When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50%.

• SG A, 1-FW-MOV-151E and 1-FW-MOV-151F

• SG C, 1-FW-MOV-151A and 1-FW-MOV-151B ATTACHMENT 9 of 1-E-0 RO/BOP 9. Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves No Emergency Bus MOVs are deenergized.

END EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 8 Page 54 of 90 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Transition from 1-E-3.

Time Position Applicants Action or Behavior 1-ECA-3.3 Actions SRO CAUTION: If no RCPs were running during the cooldown performed in 1-E-3, SI flow may cause a false Integrity Status Tree indication on the ruptured loop. The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 21.

1. CHECK RUPTURED SG(S) NARROW RANGE LEVEL - LESS THAN 75%

[73%]

RO Reports that B SG Level is greater than 75%.

SRO 1. RNO - GO TO Step 6 1-ECA-3.3 SRO 6. CHECK IF SI CAN BE TERMINATED:

a) Check RCS subcooling based on CETCs - GREATER THAN 30°F

[85°F]

RO/BOP Identifies that RCS subcooling is greater than 30°F.

b) Check secondary heat sink:

• Total feed flow to SGs - GREATER THAN 350 GPM [450 GPM]

AVAILABLE OR

• Narrow range level in at least one intact SG - GREATER THAN 12% [18%]

RO/BOP Identifies That >350 gpm AFW Available, and A and C SG NR level

>12%.

SRO c) Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs RVLIS INDICATION Running Full Range Dynamic Range 0 GREATER THAN 63%

1 GREATER THAN 36%

2 GREATER THAN 51%

3 GREATER THAN 82%

RO/BOP Identify that RVLIS Full Range is Greater than 63%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 8 Page 55 of 90 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Transition from 1-E-3.

Time Position Applicants Action or Behavior 1-ECA-3.3 SRO Step 6, continued:

d) Check any ruptured SG narrow range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH BOP Identify that B SG Level is Off-Scale High.

SRO 7. STOP ALL BUT ONE CHG PUMP AND PUT IN AUTO RO Secures one of the running charging pumps SRO 8. ISOLATE HHSI TO COLD LEGS:

a) Verify the following:

RO 1) CHG pump suctions from RWST - OPEN

• 1-CH-MOV-1115B

• 1-CH-MOV-1115D

2) Check CHG pump miniflow recirc valves - OPEN

• 1-CH-MOV-1275A

• 1-CH-MOV-1275B

• 1-CH-MOV-1275C

• 1-CH-MOV-1373 b) Close HHSI to Cold Leg:

• 1-SI-MOV-1867C RO

• 1-SI-MOV-1867D

• 1-SI-MOV-1842 END Event 8 End Scenario

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 56 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 OF 1-E-0 BOP 1. CHECK FW ISOLATION:

• Feed pump discharge MOVs - CLOSED

• 1-FW-MOV-150A

• 1-FW-MOV-150B

• MFW pumps - TRIPPED

• Feed REG valves - CLOSED

• SG FW bypass flow valves - DEMAND AT ZERO

• SG blowdown TVs - CLOSED Attachment 1 OF 1-E-0 BOP 2. CHECK CTMT ISOLATION PHASE I:

• Phase I TVs - CLOSED

• 1-CH-MOV-1381 - CLOSED

• 1-SV-TV-102A - CLOSED

• PAM isolation valves - CLOSED

• 1-DA-TV-103A

• 1-DA-TV-103B BOP will identify 1-DA-TV-100A/B, and 1-MS-TV-109 OPEN and CLOSE them.

Attachment 1 OF 1-E-0 BOP 3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 57 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of 1-E-0 BOP 4. CHECK SI PUMPS RUNNING:

• CHG pumps - RUNNING

• LHSI pumps - RUNNING BOP starts 1-SI-P-1B Attachment 1 OF 1-E-0

5. CHECK CHG PUMP AUXILIARIES:

BOP

• CHG pump CC pump - RUNNING

• CHG pump SW pump - RUNNING Attachment 1 OF 1-E-0 BOP 6. CHECK INTAKE CANAL:

• Level - GREATER THAN 24 FT

• Level - BEING MAINTAINED BY CIRC WATER PUMPS Attachment 1 OF 1-E-0 BOP 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

• E-F-10 (High Steam Flow SI)

• B-C-4 (Hi Hi CLS Train A)

• B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

Attachment 1 OF 1-E-0

• 8. CHECK IF CS REQUIRED:

BOP a) CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 58 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of 1-E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Check Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

Attachment 1 OF 1-E-0 BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Check Permissive Status light F LIT Attachment 1 OF 1-E-0 BOP NOTE:

• CHG pumps should be run in the following order of priority: C, B, A.

• Subsequent SI signals may be reset by re-performing Step 12.

12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

• 1-SI-FI-1961 (NQ)

• 1-SI-FI-1962 (NQ)

• 1-SI-FI-1963 (NQ)

• 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI d) Stop one CHG pump and out in AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 59 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of 1-E-0 BOP e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.

2) Stop one LHSI pump and put in AUTO.

Stops either 1-SI-P-1A or 1B and leaves control switch in AUTO.

3) GO TO Step 13.

Attachment 1 of 1-E-0 BOP 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

Attachment 1 of 1-E-0 BOP 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

Attachment 1 of 1-E-0 BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next page of this guide)

Attachment 1 of 1-E-0 BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Identify failure of 1-VS-MOD-103A CLOSES the MOD.

Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 60 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of 1-E-0 BOP 17. CHECK RCS DILUTION FLOWPATH - ISOLATED AND LOCKED, SEALED, OR OTHERWISE SECURED

• Close and lock, seal, or otherwise secure 1-CH-223 May contact the Desk (WCC) SRO to Close and lock, seal, or otherwise secure 1-CH-223.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 61 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Time Position Applicants Action or Behavior Attachment 2 of 1-E-0 BOP NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

Attachment 2 of 1-E-0 BOP 1. Check opened or open CHG pump suction from RWST MOVs.

• 1-CH-MOV-1115B

• 1-CH-MOV-1115D Attachment 2 of 1-E-0 BOP 2. Check closed or close CHG pump suction from VCT MOVs.

• 1-CH-MOV-1115C

• 1-CH-MOV-1115E Attachment 2 of 1-E-0 BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)

• 1-CH-P-1C

• 1-CH-P-1B

• 1-CH-P-1A Attachment 2 of 1-E-0 BOP 4. Check opened or open HHSI to cold legs MOVs.

• 1-SI-MOV-1867C

• 1-SI-MOV-1867D Attachment 2 of 1-E-0 BOP 5. Check closed or close CHG line isolation MOVs.

• 1-CH-MOV-1289A

• 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 62 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 2 of 1-E-0 BOP 6. Check closed or close Letdown orifice isolation valves.

• 1-CH-HCV-1200A

• 1-CH-HCV-1200B

• 1-CH-HCV-1200C RO/BOP will CLOSE 1-CH-HCV-1200A and 1-CH-HCV-1200B Attachment 2 of 1-E-0 BOP 7. Check opened or open LHSI suction from RWST MOVs.

• 1-SI-MOV-1862A

• 1-SI-MOV-1862B Attachment 2 of 1-E-0 BOP 8. Check opened or open LHSI to cold legs MOVs.

• 1-SI-MOV-1864A

• 1-SI-MOV-1864B Attachment 2 of 1-E-0 BOP 9. Check running or start at least one LHSI pump.

• 1-SI-P-1A

• 1-SI-P-1B BOP START 1-SI-P-1B if not already performed in Attachment 1.

Attachment 2 of 1-E-0 BOP 10. Check High Head SI flow to cold legs indicated.

• 1-SI-FI-1961

• 1-SI-FI-1962

• 1-SI-FI-1963

• 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 63 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 2 of 1-E-0 BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

• Alternate SI to Cold legs

• Hot leg injection

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 64 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 65 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 66 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 67 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 68 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 69 of 90 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 70 of 90 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 71 of 90 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 72 of 90 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2021-1 Scenario No.: 5 Event No.: 9 Page 73 of 90 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 74 of 90 SIMULATOR CREW BRIEF Simulator Scenario Checklist Perform Simulator Turnover Pre-session, and Post-session Checklist prior to the first Scenario of the day.

Perform Simulator Turnover Post-session Checklist after the last Scenario of the day.

Perform/Verify Simulator Setup:

Recall IC-380 (100%) and verify Trigger #30 implemented.

OR Recall Base IC (IC-001), Open Schedule, and Event Files for Scenario 5. Run Schedule file, and implement Trigger 30.

Verify Impulse Pressure is selected for channel 3.

Enter/Verify the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC4903 PRZR LEVEL XMTR 5 20 1 0.0 -0.3 Manual CH 3 FAILURE (461)

FW1902 B S/G MN FD FLOW 5 30 3 0.0 -0.5 Manual CNTRLR FC-1488 FAILS MS1503 SG C PORV 5 30 5 0.0 +1.0 Manual CONTROLLER FAILS HIGH/LOW GL0102 IPBD CONDUCTOR 0 0 7 0.0 70 Manual TEMPERATURE HIGH PHASE B RC2402 STEAM GENERATOR 5 30 9 0.0 3 Manual B TUBE RUPTURE RC2402 STEAM GENERATOR 5 30 11 0.0 100 Manual B TUBE RUPTURE (New Event)

RC64 MOV-RC-535 49 Thermal 0 0 16 1 0 AUTO Overload RC5601 RC-P-1A BKR 15A3 0 0 17 FALSE TRUE AUTO SPURIOUS TRIP RC5602 RC-P-1B BKR 15B3 0 0 17 FALSE TRUE AUTO SPURIOUS TRIP RC5603 RC-P-1C BKR 15C3 0 0 17 FALSE TRUE AUTO SPURIOUS TRIP AS02 DISABLE SV-TV-102 0 0 30 FALSE TRUE ACTIVE AUTO OPEN AS05 DISABLE SV-TV-103 0 0 30 FALSE TRUE ACTIVE AUTO CLOSURE SI2409 SI RELAY CI1A FAILS 0 0 30 FALSE TRUE ACTIVE TO ACTUATE SI2505 SI RELAY SI5B FAILS 0 0 30 FALSE TRUE ACTIVE TO ACTUATE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 75 of 90 SIMULATOR CREW BRIEF Enter/Verify the following EVENT TRIGGERS:

Event ID Event code Command Trigger setup to trip 1-RC-MOV-1535 breaker when control switch in open to stroke test open time, Event 1.

Trigger 14 sets when 1-RC-MOV-1535 closed. Trigger 15 sets when 1-RC-MOV-1535 control switch taken to open. Trigger 16 set when both Trigger 14 and 15 are TRUE. Trigger 16 implements Remote Function trip of 1-RC-MOV-1535 breaker.

14 rcmov535 <= 0.0002 Sets Trigger 14 15 mov535_open Sets Trigger 15 16 et_array(14) & et_array(15) Sets Trigger 16 Trigger setup to trip A, B, C, RCPs when Main Generator Output breakers open. (EL2 Auto Trigger).

Actuates Trigger which implements Malfunction RC5601/5602/5603.

17 "!(elg102_bkr(2) & elg1T240_bkr) Sets Trigger 17 Enter/Verify the following REMOTE FUNCTIONS:

Trigger Description Delay Ramp Trigger Value Final Type (Auto or Manual)

AAC_SMS_MODE OFF AAC DG 0 0 30 STANDBY OFF MANUAL LOCAL MODE SWITCH POSITION MS-120 STEAM GENERATOR B 300 15 13 100 0 MANUAL STEAM SUPPLY TO FW-P-2 Enter/Verify the following SWITCH OVERRIDES:

Override Override To: Trigger PCV455C_OPEN RC-PCV-1455C OFF 11 OPEN POS PRZR RELIEF VALVE PCV455C_ENABLE RC-PCV- OFF 11 1455C ENABLE POS OVERPRESS MITIGATION ENABLE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 76 of 90 SIMULATOR CREW BRIEF TRIGGER TYPE DESCRIPTION 1 MAN Fails PZR Level CH III to 25%.

3 MAN B SG MFRV controller fails low.

5 MAN C SG PORV fails open 7 MAN B Isophase Bus Duct High Temperature 9 MAN Steam Generator Tube Leak, 20 gpm Overrides 1-RC-PCV-1455C control switch in Close 11 MAN Overrides OPMS key switch for PCV-1455C in DISABLE 13 MAN Close 1-MS-120 B SG supply to TDAFW Pump 16 AUTO Open Breaker to 1-RC-MOV-1535 17 AUTO Spurious Trip A/B/C RCPs when Gen. Output Bkrs open AS02 DISABLE SV-TV-102 OPEN AS03 DISABLE SV-TV-103 CLOSE SI2409 SI RELAY CI1A FAILS TO ACTUATE 30 ACTIVE SI2505 SI RELAY SI5B FAILS TO ACTUATE AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 77 of 90 SIMULATOR CREW BRIEF Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Verify All pink magnets collected from previous scenarios.

Verify vertical board PCS monitor on ALARM SCREEN.

Reset ICCMs.

Verify all calcalc points are displayed on PCS: U9103, U9104, U9105V.

Verify Component Switch Flags; 1-VS-F-58A and 1-VS-F-58B switches (AUTO AFTER STOP).

Verify Brass Caps properly placed (Hi-Hi CLS, MSTVs, CH-MOV-1350, CW and SW MOVs, CTMT Hogger suction, CNDSR Vacuum breaker).

Radiation Monitors all clear.

Verify SG PORVs set for 1035 psig.

Verify D bank rod height at 229 steps and Bank Overlap Counter at 612.

Verify Chart recorders are on the correct scale (SF/FF and Tave/Tref) and speed (NI)

Advance Charts.

Verify Air Ejector Discharge is aligned through 1-SV-TV-103 (all RMs reset).

Verify SYNC keys in proper place.

Verify MOL reactivity plans and benchboard Reactivity Placard is current.

Reset Blender Integrators for Boric Acid to 100 and PG to 1000.

Verify Stop Watches are available for RO and BOP.

Verify Simulator Session In Progress light is turned ON.

Verify no persons are logged onto network computer to ensure no procedures displayed.

Verify PCS time matches Sim time.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 78 of 90 SIMULATOR CREW BRIEF Spot check all ARPs are clean, verify the following ARPs are clean.

1A-A3 1F-D8 1A-B3 1G-E5 1C-B8 1H-E6 1C-D8 1-RM-G8 1F-C8 1-RM-H8 Verify CLEAN copies of the following procedures are in place.

AP-53.00 (2) AP-18.00 AP-23.00 AP-16.00 AP-24.00 E-0 E-3 ECA-3.3 OP-CH-007 Reactivity Sheet OP-ZZ-002 PT-18.6I

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2019-1 Scenario No.: 5 Page 79 of 90 SIMULATOR CREW BRIEF Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated.

In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

TEAM 1 TEAM 2 TEAM 3 SRO RO BOP Ask for and answer questions.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 80 of 90 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

• AAC DG is tagged out for maintenance. In accordance with VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, Pressurizer Block Valve Stroke Test. Performance of PT-18.6I has been authorized and has been PSA analyzed for current plant conditions.

The last shift performed two 35 gallon dilutions followed by a manual makeup. A BAST boron concentration is 8.0 w/%.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 81 of 90 SIMULATOR OPERATORS GUIDE Pre Session Checks:

Safety Injection Section (Magnets) CW/SW Section RCS Section CVCS SI-MOV-1865A R G Brass Caps Tcold Loop Stop Pos (R - O) Core Life Plaque SI-MOV-1865B R G SW MOVs A B C Ramp Plan Book SI-MOV-1865C R G 103A 103B 103C 103D Loop Bypass Valves (G - C) OP-RX-010 Book SI-MOV-1869A R G A B C PG Int Set 1000 SI-MOV-1869B R G CW MOVs Thot Loop Stop Pos (R - O) BA Int Set 100 SI-MOV-1890A R G T/O 106A 106B 106C 106D A B C SI-MOV-1890B R G T/O Tavg/Tref Rec.

SI-MOV-1890C R G T/O CW Inlet Throttle Plaques (10%) SFP PPs Pwr Norm Alt NI-NR-B Brass Cap CLS TR A CLS 100A 100B 100C 100D PZR Level Recorder Group Step Ctrs TR B CERPIs CTMT Hogger Suction Cap CH-MOV-1350 Main Steam/Feedwater Electrical/VSP PCS RM/WD/BR SG PORVs Set Synch Key PCS Main Screen RM-112 A B C MSTV Caps A B C SVB Power H J U9103 RM-113 A B C SF/FF Rec Scale LO System Switches U9104 Comm RM Pwr 1J 2J Cond Vac Bkr Cap VS-F-58A Pwr H J Grn Flag U9105V Synch Key VS-F-58B Pwr H J Grn Flag Alarm Screen (List)

Post Session Checks:

PCS Screens (Cleared/Display) RO BOP SM STA PCs Logged OFF (including Booth) Phone cleared Recall IC-1 Advance Charts Procedures Changed Red Light Binders Stored Trash Picked Up/Emptied Vacuum Reqd?

Pink Magnets in Drawer BB and VB Scenario Magnets removed E-Mail to SSG Required DVD Finalized EAL Charts Note Pads Manning Sheets Sticky Tabs (SRO/SM/ARPs) Markers (ARPs) Personnel/Comms Tracking Sheets (Booth)

Floor timers reset/In place Booth timers reset/In place Printers ready/have paper

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 82 of 90 SIMULATOR OPERATORS GUIDE EVENT 1 Test Cycle PORV Block Valves, 1-PT-18.6I BOOTH:

30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-PT-18.6I, Pressurizer Block Valve Stroke Test. The team will pre-brief the PT prior to entering the simulator.

Trigger setup to trip 1-RC-MOV-1535 breaker when control switch in open to stroke test open time, Event

1. Monitor the following triggers as 1-RC-MOV-1535 is closed/opened.

Trigger 14 sets (becomes Active) when 1-RC-MOC-1535 closed.

Trigger 15 sets (becomes Active) when 1-RC-MOV-1535 control switch taken to open.

Trigger 16 sets when both Trigger 14 and 15 are TRUE.

Trigger 16 implements the Malfunction to trip 1-RC-MOV-1535 breaker.

Operations Supervisor/Management/Work Week Coordinator:

• If contacted, will acknowledge 1-RC-MOV-1535 breaker tripped when the valve was re-opened, suspension of the PT, and Tech Spec Clock identified (1 hour/72 hour).

Field Operator: (3 minute delay from request to answer)

• If Contacted, as Service Building Operator, to check the status of 1-RC-MOV-1535 breaker, 1H1-2S 6A; report that the breaker has tripped (in the trip free position).

STA:

• If contacted, will take responsibility for writing the CR.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 83 of 90 SIMULATOR OPERATORS GUIDE EVENT 2 PRZR Level Transmitter 1-RC-LI-1461 Fail to 25%, 0-AP-53.00.

When cued by examiner, implement Trigger #1.

Critical Task (CT-1): Stabilize Pressurizer Level prior to automatic OR manual Reactor Trip.

Operations Supervisor/Management:

• If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00.

• If contacted, will recommend to the team that channels remain as they are for now (i.e., do not perform 1-OP-RP-001 at this time).

• If contacted, will take responsibility for writing the CR.

STA:

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state they have nothing to add.

Field Operators:

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.

Unit 2 Operator:

• No action for this event.

Role play as other individuals as needed.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 84 of 90 SIMULATOR OPERATORS GUIDE EVENT 3 B Main Feed Reg Valve Controller Fails Low, 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Critical Task (CT-2): Stabilize B SG Level prior to automatic OR manual Reactor Trip.

Operations Supervisor/Management:

• If contacted, acknowledge B MFRV controller failure.

• If contacted, will take responsibility for writing the CR.

• If contacted, will acknowledge entry into 0-AP-53.00.

STA:

• If contacted, will acknowledge B MFRV controller failure.

• If contacted, will take responsibility for writing the CR.

• IF contacted: CEP-0029 has been reviewed, Reg. Guide 1.97 only requires one channel of Feed Flow indication per steam generator. VPAP-2802 and TRM section 3.3 are not affected.

• IF contacted: acknowledge that TRM 3.3.5 requires the calorimetric program be changes from the Feedwater UFM System to the Normalized Feedwater Venturi System, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; and, Restore the UFM system to FUNCTIONAL status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

• If the team has a transient brief: The STA will state they have nothing to add.

Field Operators:

• Will perform actions as directed.

Maintenance/ Work Week Coordinator:

• If contacted, will acknowledge the B MFRV controller failure and contact I&C to commence preparation to troubleshoot.

Unit 2:

• If contacted, will acknowledge the B MFRV controller failure.

Role-play as other individuals as needed.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 85 of 90 SIMULATOR OPERATORS GUIDE EVENT 4 C SG PORV spuriously opens, 0-AP-53.00 and 1-AP-38.00.

When the Evaluator indicates Ready, Activate Trigger #5.

Operations Supervisor/Management:

• If contacted, will acknowledge the failure of C SG PORV.

• If contacted, will take responsibility for writing the CR.

• If contacted, will acknowledge entry into 0-AP-53.00 and 1-AP-38.00.

STA:

• If contacted, will acknowledge the failure of C SG PORV.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state they have nothing to add.

Maintenance/ Work Week Coordinator:

• If contacted, will acknowledge the failure and notify I&C to investigate.

Field Operators: (Wait three (3) minutes from direction of a local action to the report of local condition found.)

• If contacted, the operator will report no abnormalities observed locally at the C SG PORV.

• If contacted, the operator will report 1-MS-PI-101C indicates ~780 psig (at the Aux Shutdown Panel).

Unit 2:

• If contacted, will acknowledge the failure of C SG PORV.

Role-play as other individuals as needed.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 86 of 90 SIMULATOR OPERATORS GUIDE EVENT 5 B Isophase Bus Duct High Temperature, ARP 1G-E5 and 0-AP-23.00.

When the Evaluator is ready, implement Trigger # 7. (Annunciator 1G-E5 will alarm ~4 minutes after the trigger is inserted.)

Operations Supervisor/Management:

• If contacted, will acknowledge the high B Phase IBD Temperature.

• If contacted, will acknowledge the required 10% load reduction.

• If contacted, will take responsibility for writing the CR.

• When contacted: The Shift Manager will review EPIPs for applicability.

STA:

• If contacted, will acknowledge the high B Phase IBD Temperature.

• If contacted, will take responsibility for writing the CR.

• When contacted: The STA reports that he has completed his review of VPAP-2802 and no notifications are required.

• If the team has a transient brief: The STA will state they have nothing to add.

• If asked, will concur with the reactivity plan for the load reduction.

Unit 2 Operator:

• If notified of Ramp: Acknowledge ramp of Unit 1.

Field Operators:

• If contacted, the condensate polishing building operator will acknowledge the need to ramp the unit.

• If contacted, report the B Phase High Air Temperature drop is in.

• If contacted, report the temporary fans are staged for the isophase bus ducts.

• NOTE: To report IBD Air temperatures, convert PCS indication from °F to °C and report that value. To convert, use the following: (°F - 32°) x 5/9 = °C Role play as other individuals as needed.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 87 of 90 SIMULATOR OPERATORS GUIDE EVENT 6 B SGTL 20 gpm, A/E RM Auto Actions Fail.

When the Evaluator is ready, implement Trigger # 9.

Critical Task (CT-2): Manually align A/E discharge to containment IAW A/E RM ARP prior to SGTR.

Note: It would be preferable to wait until power is 90% to implement this failure to allow for ramp stabilization prior to creating RCS leak to allow the team to assess leakrate with more precision.

Operations Supervisor/Management:

• If contacted, will acknowledge RCS leakage into the B SG. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.

• If contacted, will take responsibility for writing the WR and CR.

• If contacted, will take responsibility for writing the CR.

• If contacted, will acknowledge entry into 1-AP-16.00.

Unit 2 Operator:

• When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.

• If asked, Unit 2 will state they are unavailable to perform the ARPs or any actions associated with the ARPs. Unit 2 Operator will only silence and announce the alarms for A/E and Blowdown RM.

• If contacted, Unit Two has implemented 0-AP-50.00, and all conditions on U2 are normal.

STA:

• If contacted, will acknowledge the RCS leakage into the B SG.

• If asked to calculate the RCS leak rate, state that it is difficult to ascertain at this time, but you will continue to monitor as time permits.

• If contacted, will take responsibility for writing the CR.

• If the team has a transient brief: The STA will state they have nothing to add.

Field Operators:

• If contacted, the air ejector loop seal temperatures are normal.

EVENT 7 B SGTR (600) gpm). RCPs Trip on swap to RSST. 1-AP-16.00, 1-E-0, 1-E-3.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 88 of 90 SIMULATOR OPERATORS GUIDE When Examiner ready, implement Trigger 11.

Critical Task (CT-3): Isolate feed flow to the ruptured SG before B SG NR Level reaches 100%.

Operations Supervisor/Management:

• If contacted, will acknowledge the SGTR on B SG.

• If contacted, will acknowledge entry into 1-E-0, 1-E-3.

• If contacted, will take responsibility for writing the WR and CR.

• If contacted, will acknowledge the isolation of B SG (if informed).

STA:

• If the team has a transient brief: The STA will state they have nothing to add.

Unit Two:

• If asked, blowdown and air ejector RM readings are [as indicated at the time].

• If requested, acknowledge RM alarms, and perform ARP actions.

• If asked: Silence the alarms at the Fire Protection IMS Panel.

• If contacted, Unit Two has implemented 0-AP-50.00, and all conditions on U2 are normal.

• If asked: Unit 2 RWST cross-tie valves are open.

• If asked: take responsibility to notify HP of B SG PORV lifting.

Field Operators (3 minutes after being contacted):

• If contacted, report all RCP breakers (15A3, 15B3, 15C3) are open with no other abnormal conditions.

• If contacted, field operators will perform valve manipulations as required:

• Closing 1-MS-120 - implement Trigger 13. When the Final value for MS_120 = 0, report 1-MS-120 is closed.

• Acknowledge direction to place Number 1 and 2 Turbine Building Sump pumps in OFF locally, and initiate 0-OSP-PL-003, Turbine Building Sump Pump Status Verification.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 89 of 90 SIMULATOR OPERATORS GUIDE EVENT 8 PZR PORV 1-RC-PCV-1455C not open, 1-ECA-3.3.

Operations Supervisor/Management:

• If contacted, will acknowledge entry into 1-ECA-3.3.

• If contacted, will acknowledge the SGTR on B SG.

• If contacted, will take responsibility for writing the CR.

• If contacted, will acknowledge the isolation of B SG (if informed).

STA:

• If the team has a transient brief: The STA will state they have nothing to add.

Unit Two:

• If asked, blowdown and air ejector RM readings are [as indicated at the time].

• If requested, acknowledge RM alarms, and perform ARP actions.

• If contacted, Unit Two has implemented 0-AP-50.00, and all conditions on U2 are normal.

Field Operators:

• If contacted, field operators will perform valve manipulations as required:

• 1-MS-120 - set ms_120 to zero upon request EVENT 9 BOP Failures, 1-SI-P-1B no auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

Operations Supervisor/Management:

• If contacted, will take responsibility for writing the WR and CR.

Unit Two:

• If contacted, Unit Two has implemented 0-AP-50.00, and all conditions on U2 are normal.

• If asked, MCR differential pressure is as found. Unit 2 will assume responsibility for throttling SW flow IAW E-0, Attachment 3 guidance.

Op-Test No.: Surry 2021-1 Scenario No.: 5 Page 90 of 90 SIMULATOR OPERATORS GUIDE Field Operators:

• If contacted, field operators will perform valve manipulations as required.

Maintenance/Work Week Coordinator:

• If contacted, will acknowledge the failures and commence investigations.

HP:

• If contacted, will acknowledge B SGTR.

STA:

• If asked, will report that he will calculate the time to B fill, time permitting.

• If contacted, will enter the control room and commence reviewing status trees and prepare for the transient brief (items are reported as you see them or previously reported).

Role play as other individuals as needed.

The scenario will end upon reaching Step 11 of 1-ECA-3.3 or at the lead examiners discretion.

Surry 2021-301 Emergency Borate AP-3.00 U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA: 024AA1.17 3.9/3.9]

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Emergency Borate the RCS in accordance with 1-AP-3.00, Emergency Boration K/A: 024AA1.17, Ability to operate and / or monitor the following as they apply to Emergency Boration:

Emergency borate control valve and indicators (3.9 / 3.9).

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 7 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Manually adjusts Charging flow to > 75 gpm.

• Attempts to open 1-CH-MOV-1350.

• Aligns charging to RWST (Sequence Critical):

o Opens 1-CH-MOV-1115B OR D.

o CLOSES 1-CH-MOV-1115C OR E.

Procedures

• 1-AP-3.00, Emergency Boration.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry 2021-301 Emergency Borate AP-3.00 Simulator Setup

• Recall 100% power IC and initialize or recall IC-381. Place simulator in RUN.

• Set 1-CH-MOV-1350 to thermal on auto trigger when .001 open. CH73 Trigger 1, Auto Trigger Event CHMOV350

.ge. 0.0001.

• Insert meter Override CHFI110, EMRG BORATE FLOW, 0, ACTIVE.

• Trip Reactor and Stabilize at Hot Shutdown.

• Adjust CH flow using 1-CH-LC-1459G to 50 gpm and return to Auto.

Page 2 of 9

Surry 2021-301 Emergency Borate AP-3.00 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME_______:

STEP 1

_______ SAT NOTES Prior to Step 1 (AP-3.0 step 1)

_______ UNSAT

• If a Reactor Trip occurs or is required, 1-E-0, REACTOR TRIP OR SAFETY INJECTION, should be implemented.

• When the Reactor is shutdown with the Shutdown Banks withdrawn, tripping the Shutdown Banks may eliminate the need for emergency boration.

STANDARD:

• Acknowledges Notes.

EVALUATORS NOTE:

COMMENTS:

STEP 2 (CRITICAL STEP)

_______ SAT CHECK CHARGING FLOW - GREATER THAN 75 GPM (AP-3.0 step 1)

_______ UNSAT STANDARD:

a) Checks CHG Line Flow on 1-CH-FI-1122A and identifies flow < 75 gpm.

b) Goes to Step 1 RNO c) Manually adjusts charging flow to greater than 75 gpm. CRITICAL STEP

• Using 1-CH-LC-1459G, PRZR LEVEL CNTRL, in Manual -OR-

• Using 1-CH-FCV-1122, CHG FLOW CNTRL in Manual EVALUATORS NOTE:

NONE.

COMMENTS:

Page 3 of 9

Surry 2021-301 Emergency Borate AP-3.00 STEP 3

_______ SAT START EMERGENCY BORATION (AP-3.0 step 2a) a) Transfer the in-service BATP to FAST. _______ UNSAT STANDARD:

• Places control switch for 1-CH-P-2A, Boric Acid Transfer Pump to FAST.

• Identifies RED Slow Light - OUT; RED FAST light - LIT

• Acknowledges Annunciator 1D-C5, BA XFER PPS NON-AUTO CONT.

EVALUATORS NOTE:

NONE.

COMMENTS:

STEP 4 (CRITICAL STEP)

_______ SAT START EMERGENCY BORATE (AP-3.0 step 2b)

NOTE: Opening breaker prior to local operation of 1-CH-MOV-1350 is NOT required in this _______ UNSAT AP, based on the urgent need to borate.

b) Open 1-CH-MOV-1350.

STANDARD:

a) Acknowledges Note.

b) Open 1-CH-MOV-1350. CRITICAL STEP

• Removes Brass Cap on 1-CH-MOV-1350 control switch and places in OPEN position.

• Identifies RED and GREEN MOV Indicating lights extinguish.

• Identifies 0 indicated flow on 1-CH-FI-1110, EMRG BORATE FLOW indicator.

• Reports trip indication for 1-CH-MOV-1350 to Evaluator.

• GOES to Step 2b) RNO. (This begins the Faulted Portion of the JPM).

EVALUATORS NOTE:

When Notified: Acknowledge 1-CH-MOV-1350 indication report.

IF asked: Will direct electricians to investigate MCC 1H1-2S 7C breaker status.

BOOTH OPERATOR:

IF Asked: Report that a time compression has occurred and 1-CH-P-2A breaker MCC-1H1-2S 7C Thermal Overload is tripped.

COMMENTS:

Page 4 of 9

Surry 2021-301 Emergency Borate AP-3.00 STEP 5 (CRITICAL STEP)

_______ SAT START EMERGENCY BORATION (AP-3.0 step 2b RNO)

Locally open 1-CH-MOV-1350. _______ UNSAT IF 1-CH-MOV-1350 can NOT be opened, THEN do the following:

1) Manually open 1-CH-FCV-1113A.

2) Locally open 1-CH-228.

3) Monitor Boric Acid flow on FR-1-113.

4) GO TO Step 3.

5) If neither valve can be opened, THEN manually align CHG pump suction to the RWST AND GO TO Step 5.

STANDARD:

a) Directs Auxiliary Building Operator to locally open 1-CH-MOV-1350, Emergency Borate MOV.

b) Acknowledges Statement: IF 1-CH-MOV-1350 can NOT be opened:

c) Manually open 1-CH-FCV-1113A.

• Checks 1-CH-FCV-1113A indicates open.

• Places 1-CH-FCV-1113A control switch in OPEN.

d) Directs Auxiliary Building Operator to Open 1-CH-228.

e) Monitors for Boric Acid flow on FR-1-1113 (red trace).

f) Acknowledge Statement IF neither valve can be opened, THEN manually align CHG pump suction to the RWST AND GO TO Step 5.

g) Opens 1-CH-MOV-1115B AND 1-CH-MOV-1115D, CH Pump Suction from RWST.

CRITICAL STEP, and Sequence Critical: Either 1-CH-MOV-1115B OR 1-CH-MOV-1115D OPEN will provide the necessary flowpath to the CH Pump and will satisfy the Critical Step. This must be done before closing 1-CH-MOV-1115C, and 1115E.

h) Closes 1-CH-MOV-1115C AND 1-CH-MOV1115E, CH Pump Suction From VCT.

Critical Step. Either 1-CH-MOV-1115C OR 1-CH-MOV-1115E CLOSED will isolate the CH pump suction from the VCT and will satisfy the Critical Step. Goes to Step 5 EVALUATORS NOTE:

CUE: Another operator will take over from here.

BOOTH OPERATOR:

If Directed: Report that a Time Compression has occurred and MCC 1H1-2S 7C breaker is open.

When Directed: Report that a Time Compression has occurred and 1-CH-MOV-1350 motor will not disengage, and the handwheel will not move.

When Directed: Report that a Time Compression has occurred and 1-CH-228 handwheel spins without changing valve stem position.

After flow from the RWST; Announce the following: Time compression, Shutdown Margin has been verified.

COMMENTS:

END OF JPM Page 5 of 9

Surry 2021-301 Emergency Borate AP-3.00 STOP TIME: _______

Page 6 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initiating Conditions Unit 1 tripped approximately 10 minutes ago. The STA just informed the Team that we have a challenge to our shutdown margin requirements based on RCS boron results just obtained from Chemistry. The STA recommends a twenty (20) minute emergency boration.

Initiating Cues

• Here is a copy of 1-AP-3.00, Emergency Borate. Your task is to Emergency Borate from the Boric Acid Storage tanks for twenty (20) minutes in accordance with 1-AP-3.00.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initiating Conditions Unit 1 tripped approximately 10 minutes ago. The STA just informed the Team that we have a challenge to our shutdown margin requirements based on RCS boron results just obtained from Chemistry. The STA recommends a twenty (20) minute emergency boration.

Initiating Cues

• Here is a copy of 1-AP-3.00, Emergency Borate. Your task is to Emergency Borate from the Boric Acid Storage tanks for twenty (20) minutes in accordance with 1-AP-3.00.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 Transfer SI to Cold Leg Recirc U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure 013A4.01

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Transfer the SI System to the Cold Leg Recirculation Mode K/A: 006A3.08 Ability to monitor automatic operation of the ECCS, including: Automatic transfer of ECCS flowpaths. (4.2/4.3)

Applicability Validation Time Actual Time RO/SRO(I) 10 Minutes _____ minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Determines only one LHSI pump in service and secures 1-CH-P-1B and places in PTL.

• Manually initiate RMT by depressing both Train RMT pushbuttons simultaneously.

• Opens 1-SI-MOV-1860B by placing control switch to OPEN.

• Closes 1-SI-MOV-1862B by placing control switch to CLOSE after 1-SI-MOV-1860B is FULL OPEN.

• Closes 1-CH-MOV-1115B by placing control switch to CLOSE.

• Closes 1-CH-MOV-1115D by placing control switch to CLOSE.

• Long term RMT established before SI pump cavitates as indicated by fluctuating amps and discharge pressure.

Procedures

• 1-ES-1.3, Transfer to Cold Leg Recirculation. (Rev. 20)

Tools and Equipment Safety Considerations

• None

• None 1 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc Simulator Setup

• Recall IC-382.

-OR-

• Call up 100% power IC and initialize. Place simulator in RUN.

• Initiate malfunction for A loop cold leg rupture (RC0101).

• Perform E-0 & transition to 1-E-1. Perform 1-E-1 through Step 21, which checks for transition to ES-1.3.

• Two (2) LHSI pumps, two (2) HHSI pumps & all ISRS pumps, OSRS pumps and CS pumps should be running.

HHSI pumps should be on redundant flowpath alignment and charging pump mini-flow recirc valves should be closed.

• When RWST level is 21% insert the following malfunctions:

o EL1201 - Loss of 480v Emergency Switchgear 1H. This will result in loss of power to 1-RS-P-1A (ISRS), 1-RS-P-2A (OSRS), and 1-SI-P-1A (LHSI). The red lights should remain lit, but there will be no amps indicated for these pumps.

o SI1701, 1702. This will cause a loss of RMT (AUTO).

o SI29. This will disable SI-MOV-1860B from auto opening.

o SI31. This will disable SI-MOV-1862B from auto closing.

o CH78, 79. This will disable CH-MOV-1115B and D from auto closing.

• When RWST level is 20% (RWST LOW LEVEL alarm is LIT), freeze simulator for performance.

Notes

• When possible place Simulator in RUN prior to the candidate entering the Simulator.

2 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

_______ SAT CAUTIONS and NOTES Prior to Step 1.

_______ UNSAT STANDARD:

a) Reads caution that SI recirc flow to RCS must be maintained at all times.

b) Reads caution that transfer to recirculation may cause high radiation in the Auxiliary Building.

c) Notes that Steps 1 through 5 should be performed without delay and FRs should not be implemented before completion of these steps.

d) Notes that if sump blockage or a complete loss of sump suction capability occurs, FRs should NOT be implemented until directed in Attachment 1, or in 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION.

COMMENTS:

STEP 2:

_______ SAT CHECK OR PLACE BOTH RMT MODE TRANSFER SWITCHES IN RMT. (Step 1)

_______ UNSAT STANDARD:

Verifies BOTH RMT Transfer Switches in RMT position.

COMMENTS:

3 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 3:

_______ SAT RESET SI. (Step 2)

_______ UNSAT STANDARD:

Depresses both SI Reset Pushbuttons on Benchboard 1-1.

COMMENTS:

STEP 4:

_______ SAT CHECK SI RECIRC PHASE HEAT SINK. (Step 3)

_______ UNSAT Check SW flow established to at least two RSHXs. (Step 3a)

STANDARD:

Checks the following flow indications for SW flow to at least two RS HXs:

a) 1-SW-FI-106A (SW flow to "A" RSHX).

b) 1-SW-FI-106B (SW flow to "B" RSHX).

c) 1-SW-FI-106C (SW flow to "C" RSHX).

d) 1-SW-FI-106D (SW flow to "D" RSHX).

COMMENTS:

STEP 5:

_______ SAT Check AC emergency buses - ENERGIZED BY OFF-SITE POWER. (Step 3b)

_______ UNSAT STANDARD:

a) Checks "H" Bus voltage indicated (between 4000 and 4400 volts).

b) Checks "H" Bus normal supply breaker, 15H8, closed (red light on & green off).

c) Checks "J" Bus voltage indicated (between 4000 and 4400 volts).

d) Checks "J" Bus normal supply breaker, 15J8, closed (red light on & green off).

COMMENTS:

4 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 6:

_______ SAT Check RS pumps associated with RSHXs supplied by SW - AT LEAST TWO RUNNING. (Step 3c) _______ UNSAT STANDARD:

Checks if the following pumps to determine if at least two are running:

a) 1-RS-P-1A (associated w/ A RSHX) - breaker closed BUT NO AMPS INDICATED.

b) 1-RS-P-1B (associated w/ B RSHX) - breaker closed, amps indicated.

c) 1-RS-P-2A (associated w/ C RSHX) - breaker closed BUT NO AMPS INDICATED.

d) 1-RS-P-2B (associated w/ D RSHX) - breaker closed, amps indicated.

COMMENTS:

STEP 7: CRITICAL STEP

_______ SAT CHECK LHSI PUMPS. (Step 4)

_______ UNSAT LHSI pumps - BOTH RUNNING. (Step 4a)

IF RCS pressure is less than 185 psig AND only one LHSI pump can be started then run only ONE CHG pump. IF SI headers are split, then run the CHG pump supplying the normal header and place the remaining CHG pump in PTL.

STANDARD:

a) Checks 1-SI-P-1A breaker indication red light on BUT NO amps indicated.

b) Check RCS Pressure - LESS THAN 185 psig.

• Checks 1-SI-P-1B breaker indication red light on and amps indicated.

• Determines only one LHSI pump in service and secures 1-CH-P-1B and places in PTL. CRITICAL STEP (the B CHG pump is supplying the alternate header).

• Verifies 1-CH-P-1A in PTL.

• Checks RCS Pressure is less than 185 psig (yes).

EVALUATORS NOTE:

• Cue: If asked about SI headers, state that SI headers are split. Note: this is also given under Initial Conditions.

• NOTE: The operator can determine which pump is running on the normal and alternate headers by vertical board indication.

COMMENTS:

5 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 8:

_______ SAT ALIGNS SI SYSTEM FOR RECIRC. (Step 5a & b)

_______ UNSAT

• CAUTION: If suction source is lost to any SI or CS pump, the pump should be stopped.

a) Close CHG pump miniflow recirc valves

• 1-CH-MOV-1275A

• 1-CH-MOV-1275B

• 1-CH-MOV-1275C b) RWST Level - LESS THAN 13%

STANDARD a) Checks 1-CH-MOV-1275A, 1275B, and 1275C closed by observing green light on and red light off for each MOV.

b) Checks RWST level less than 13% on the following indicators:

• 1-CS-LI-100A

• 1-CS-LI-100B

• 1-CS-LI-100C

• 1-CS-LI-100D

1) If RWST level not less than 13%, waits for level to reach 13%.

EVALUATORS NOTE:

If annunciators 1A-A2, 1A-B2, 1A-C2, and 1A-D2 are lit, the operator should identify auto RMT failure and proceed to Step 5c.

COMMENTS:

6 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 9: CRITICAL STEP

_______ SAT Check Phase 1 - INITIATED. (Step 5c(1) and RNO)

_______ UNSAT STANDARD:

a) Checks Phase 1 White Status light NOT lit. (Goes to RNO) b) Pushes both RMT actuation pushbuttons for Train A.

c) Pushes both RMT actuation pushbuttons for Train B.

d) Verifies RMT has actuated and that valves automatically align.

EVALUATORS NOTE:

• Phase 1 White Status light is lit. (Alternate Path)

• RMT actuation pushbuttons will function when pushed.

COMMENTS:

STEP 10:

_______ SAT LHSI discharge to HHSI - OPEN. (Step 5c(2))

_______ UNSAT STANDARD:

a) Checks OPEN 1-SI-MOV-1863A by observing red light on and green light off.

b) Checks OPEN 1-SI-MOV-1863B by observing red light on and green light off.

COMMENTS:

7 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 11:

_______ SAT LHSI Recirc valves - CLOSED. (Step 5c(3))

_______ UNSAT STANDARD:

a) Checks CLOSED 1-SI-MOV-1885A closed by observing green light on & red off.

b) Checks CLOSED 1-SI-MOV-1885B closed by observing green light on & red off.

c) Checks CLOSED 1-SI-MOV-1885C closed by observing green light on & red off.

d) Checks CLOSED 1-SI-MOV-1885D closed by observing green light on & red off.

COMMENTS:

STEP 12:

_______ SAT Check Phase 2 - INITIATED. (Step 5d(1) and RNO)

_______ UNSAT STANDARD:

a) Checks Phase 2 Amber Status light LIT.

b) Ensures 1 minute elapsed since RMT should have actuated prior to continuing.

EVALUATORS NOTE:

• Phase 2 amber light will automatically light one minute after Phase 1.

• Phase 2 amber light will work, but only the A train will respond. This is the train that has the de-energized LHSI pump. The B train will not automatically respond, requiring the operator to manually align the B train.

COMMENTS:

8 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 13: CRITICAL STEP

_______ SAT LHSI suction from sump - OPEN. (Step 5d(2))

_______ UNSAT STANDARD:

a) Checks OPEN 1-SI-MOV-1860A open by observing red light on & green off.

b) Opens 1-SI-MOV-1860B by placing control switch to OPEN. CRITICAL STEP c) Checks 1-SI-MOV-1860B open by observing red light on & green off.

EVALUATORS NOTE:

These valves take approximately 1 minute to open.

COMMENTS:

STEP 14: CRITICAL STEP

_______ SAT LHSI suction from RWST - CLOSED. (Step 5d(3))

_______ UNSAT STANDARD:

a) Checks CLOSED 1-SI-MOV-1862A closed by observing green light on & red off.

b) Closes 1-SI-MOV-1862B by placing control switch to CLOSE. CRITICAL STEP. Note: MOV-1862B should not be closed until after MOV-1860B is FULL OPEN.

c) Checks 1-SI-MOV-1862B closed by observing green light on & red off.

EVALUATORS NOTE:

• Fully opening 1-SI-MOV-1860B prior to closing 1-SI-MOV-1862B ensures a suction flow path to the B Low Head SI Pump.

COMMENTS:

9 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 15: CRITICAL STEP.

_______ SAT CHG pump suction from RWST valves - CLOSED. (Step 5d(4))

_______ UNSAT STANDARD:

a) Closes 1-CH-MOV-1115B by placing control switch to CLOSE. CRITICAL STEP.

b) Checks 1-CH-MOV-1115B closed by observing green light on & red off.

c) Closes 1-CH-MOV-1115D by placing control switch to CLOSE. CRITICAL STEP.

d) Checks 1-CH-MOV-1115D closed by observing green light on & red off.

EVALUATORS NOTE:

• Both 1-CH-MOV-1115B, and 1115D need to be CLOSED to isolate this suction path.

COMMENTS:

10 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc STEP 16:

_______ SAT Check recirculation flow - ESTABLISHED. (Step 5e)

_______ UNSAT STANDARD:

Verifies SI flow to the Rx core via cold leg flowpath by checking the following flow instrumentation: CRITICAL STEP. Recirc flow should be established prior to any indication of pump cavitation. Pump cavitation is indicated by fluctuating pump amps (1-SI-P-1B) and flow fluctuations (1-SI-FI-1946)

• 1-SI-FI-1945 (A LHSI FT) - 0 gpm,

• 1-SI-FI-1946 (B LHSI FT) - ~3400 gpm,

• 1-SI-FI-1961 (A Loop FT) - ~ 150 gpm,

• 1-SI-FI-1962 (B Loop FT) - ~ 150 gpm,

• 1-SI-FI-1963 (C Loop FT) - ~ 150 gpm,

• 1-SI-FI-1943 (Total flow normal hdr) - ~440 gpm,

• 1-SI-FI-1943A (Total flow normal hdr) - ~ 440 gpm,

• 1-SI-FI-1940 (Total flow alt hdr) - 0 gpm,

• 1-SI-FI-1940A (Total flow alt hdr) - 0 gpm.

EVALUATORS NOTE:

• No flow should be noted on the A LHSI and Alternate Header flow indicators since 1-SI-P-1A has no power and only the Charging Pump aligned to the Normal Header is running.

• NOTE: Indications of pump cavitation would constitute failure of this JPM.

• CUE: Another operator will take over from here.

COMMENTS:

END STOP TIME: _________

11 of 19

Surry 2021-301 Transfer SI to Cold Leg Recirc Simplified drawing of RECIRC MODE. Shown in red circles are the MOVs the operator will need to manually operate in order to place the B train in RMT.

12 of 19

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• A Large-Break LOCA has occurred on Unit 1.

• A few minutes ago, power was lost to 480V switchgear 1H. Electrical maintenance has been dispatched to investigate.

• RWST level is lowering and the team has just transitioned to 1-ES-1.3.

• The SI headers are split.

Initiating Cue

• Perform steps 1-5 of 1-ES-1.3, Transfer to Cold Leg Recirculation.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A Large-Break LOCA has occurred on Unit 1.

• A few minutes ago, power was lost to 480V switchgear 1H. Electrical maintenance has been dispatched to investigate.

• RWST level is lowering and the team has just transitioned to 1-ES-1.3.

• The SI headers are split.

Initiating Cue

• Perform steps 1-5 of 1-ES-1.3, Transfer to Cold Leg Recirculation.

Surry 2021-301 E-3 Depressurization U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA: 038EA1.04 4.3/4.1]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Depressurize the RCS to minimize SGTR Breakflow.

K/A: 038EA1.04, Ability to operate and / or monitor the following as they apply to a SGTR: PZR spray, to reduce coolant system pressure (4.3 / 4.1).

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 10 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Opens both Pressurizer Spray valves to begin depressurization.

• Determines Spray Termination is satisfied.

• Closes both Pressurizer Spray valves to stop depressurization prior to the Pressurizer reaching Solid conditions.

Procedures

• 1-E-3, Steam Generator Tube Rupture.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry 2021-301 E-3 Depressurization Simulator Setup

• Initialize Simulator to IC #383 OR Call up 100% power IC and perform the following:

o Enter malfunction for SGTR in "B" SG at ~450 gpm (RC2402 @ 50% degradation).

o Call up the "B" Main Steam line & close 1-MS-120.

o Place sim in RUN, trip Unit, perform 1-E-0 and transition to 1-E-3. Perform 1-E-3 up to Step 19, (incl SI blocks). RCPs should still be running & subcooling greater than 50°F. Throttle AFW flow to A & C SGs down to ~175 gpm.

o Verify SR NIS detectors are energized and the SR scale is indicated on 1-NI-NR-A/B.

o Freeze simulator until ready for JPM performance.

Page 2 of 9

Surry 2021-301 E-3 Depressurization PERFORMANCE CHECKLIST Notes to the Evaluator

• Operator is given a copy of 1-E-3, SGTR, Step 19 during directions

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME_______:

STEP 1

_______ SAT 1-E-3 Step 19

_______ UNSAT a) Check normal spray - AVAILABLE

• RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR

• RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE STANDARD:

a) Checks all RCPs are running.

b) Checks both Pressurizer Spray valves are in AUTO.

EVALUATORS NOTE:

COMMENTS:

Page 3 of 9

Surry 2021-301 E-3 Depressurization STEP 2 (CRITICAL STEP) 1-E-3 Step 19, continued b) Spray PRZR with maximum available spray STANDARD:

a) Places PZR spray valve controllers (1-RC-PC-1444G and 1-RC-PC-1444H) in MANUAL and raises valve demand to open both for maximum available spray.

CRITICAL STEP.

OR b) Places PZR Master Controller (1-CH-PC-1444J) in MANUAL and raises demand to open both spray valves for maximum available spray (keeps Output < 80% to prevent PORV from opening). CRITICAL STEP.

EVALUATORS NOTE:

Performing either Standard a) or b) satisfies the CRITICAL STEP.

NOTE: If PZR Master Controller output is allowed to reach 80%, PZR PORV 1455C will open and annunciator 1D-H4 (BLUE) will alarm. This constitutes JPM failure.

COMMENTS:

Page 4 of 9

Surry 2021-301 E-3 Depressurization STEP 3 (CRITICAL STEP)

_______ SAT 1-E-3 Step 19, continued

_______ UNSAT c) Check PRZR pressure satisfactorily lowering until ANY of the following satisfied:

(Attachment 3 lists conditions)

• PRZR level - GREATER THAN 69%

OR

• RCS subcooling based on CETCs - LESS THAN 30°F [85°F]

OR

• BOTH of the following exist:

1) RCS pressure - LESS THAN RUPTURED SG(s) PRESSURE

2) PRZR level - GREATER THAN 22% [50%]

OR

• BOTH of the following exist:

1) RCS pressure - WITHIN 300 PSI OF RUPTURED SG(s) PRESSURE

2) PRZR level - GREATER THAN 52%

STANDARD:

a) Monitors all associated critical parameters listed instep 19 c).

b) Identifies one of the four bulleted criteria are satisfied.

c) Continues to Step 19 d).

EVALUATORS NOTE:

• During Validation: RCS press within 300# with PRZR level > 52% was criteria reached.

COMMENTS:

Page 5 of 9

Surry 2021-301 E-3 Depressurization STEP 4 (CRITICAL STEP)

_______ SAT 1-E-3 Step 19, continued

_______ UNSAT d) Close PRZR normal spray valves STANDARD:

a) Places PZR spray valve controllers (1-RC-PC-1444G and 1-RC-PC-1444H) in MANUAL and lowers valve demand to close both spray valves prior to the Pressurizer going Solid. CRITICAL STEP.

OR b) Places PZR Master Controller (1-CH-PC-1444J) in MANUAL and lowers demand to close both spray valves prior to the Pressurizer going Solid. CRITICAL STEP.

EVALUATORS NOTE:

Note: Operator may place Spray valve controllers in AUTO or the control switches to CLOSE to close valves.

Note: Full closed indication on both spray valves (i.e. Green light lit, Red light off),

whether auto or manual operation is used, satisfies the CRITICAL STEP.

Note: Pressurizer solid indications are; Pressurizer level indication 100%, and RCS pressure rising rapidly. Pressurizer Solid indications will be reached in approximately 8 minutes after meeting conditions to stop depressurization.

COMMENTS:

Page 6 of 9

Surry 2021-301 E-3 Depressurization STEP 6

_______ SAT Reports to Shift Manager

_______ UNSAT STANDARD:

a) Reports that 1-E-3 depressurization is complete.

EVALUATORS NOTE:

COMMENTS:

END OF JPM STOP TIME: _______

Page 7 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initiating Conditions There is a SGTR in the Unit 1 "B" SG. The SG has been identified and isolated, SI has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to perform the RCS depressurization to minimize the SGTR breakflow.

Initiating Cues

• Here is a copy of 1-E-3 Step 19. Your task is to depressurize the RCS IAW Step 19.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initiating Conditions There is a SGTR in the Unit 1 "B" SG. The SG has been identified and isolated, SI has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to perform the RCS depressurization to minimize the SGTR breakflow.

Initiating Cues

• Here is a copy of 1-E-3 Step 19. Your task is to depressurize the RCS IAW Step 19.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 Loss of Decay Heat U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure 005A2.03

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title RESPOND TO A LOSS OF DECAY HEAT REMOVAL K/A: 005A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR pump / motor malfunction. (2.9 / 3.1)

Applicability Validation Time Actual Time RO/SRO(I) 13 minutes _____minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Lower RHR HX outlet temperature by opening 1-RH-HCV-1758.

• Manually close RH Control valves; 1-RH-FCV-1605, and 1-RH-HCV-1758.

• Manually start RHR pump 1-RH-P-1B started.

• Manually opens 1-RH-FCV-1605.

• Manually opens 1-RH-HCV-1758.

• Manually opens 1-CC-TV-109A.

Procedures

• 1-AP-27.00, Loss of Decay Heat Removal Capability.

Tools and Equipment Safety Considerations

• None

• None Page 1

Surry 2021-301 Loss of Decay Heat Simulator Setup

• Recall IC-384.

-OR-

• Call up RHR IC (028) and initialize. Place simulator in RUN.

• Verify "A" RHR pump running and "B" in AUTO.

• Verify 1-RH-FCV-1605 in auto with flow rate set at 3400 gpm.

• Verify 1-RH-HCV-1758 set at approximately 81% demand (9.03 on pot).

• Ensure PCS display has OSP-RC-001 displayed.

• Place simulator in FREEZE until ready to perform JPM.

Place Simulator in RUN and let the candidate take the watch.

When the Evaluator is ready implement the following malfunctions/overrides to cause a loss of RHR:

• MALF RH0501, RHR pump 1-RH-P-1A Overcurrent trip T1.

• OVRD TVCC109A_CLOSE (auto deletes after 10 seconds)

• Simulator Operator Note: Place RED magnets on 1-RH-MOV-1700, 1701 and 1720A red bulbs. Place green magnets on SI accumulator green bulbs and verify magnets are correct for SI system for CSD. Place a white magnet and green arrow on the Pressurizer level cold cal channel 1-RC-LI-1460 and make sure the trend recorder is set for this channel.

Notes

• This JPM is pre-briefed.

Page 2

Surry 2021-301 Loss of Decay Heat PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1: CRITICAL STEP

_______ SAT Adjusting RHR temperature. (1-OP-ZZ-002, step 5.16.1)

_______ UNSAT NOTE: The thermal design rated flow for the RHR Heat Exchanger is 4200 gpm.

5.16.1 RHR temperature can be adjusted by performing one or both of the following.

Enter N/A for any valves not operated.

o Adjust 1-RH-HCV-1758, RHR HXS FLOW.

o Adjust SW outlet valves for 1-CC-E-1A or 1-CC-E-1B as required. 1-SW-39.

STANDARD:

• Acknowledges note.

• Lowers RHR HX outlet temperature by opening 1-RH-HCV-1758. This is a CRITICAL STEP.

EVALUATORS NOTES:

• IF ASKED: for preference on raising cooldown rate. Respond by telling operator that they should use the method requiring adjusting of 1-RH-HCV-1758.

• Once the applicant identifies AP-27.00 as required THEN tell applicant where a copy is located.

BOOTH NOTE: When Evaluator is ready implement Malfunctions to cause trip of 1-RH-P-1A, AND closure of T-CC-TV-109A.

COMMENTS:

Page 3

Surry 2021-301 Loss of Decay Heat STEP 2:

_______ SAT CAUTIONS and NOTE PRIOR TO STEP 1 (AP-27.00 step 1)

_______ UNSAT CAUTION:

• Loss of RHR due to a total loss of IA is addressed by 0-AP-40.00, NON-RECOVERABLE LOSS OF IA.

• Loss of RHR due to a total loss of AC Power is addressed by 1-AP-10.27, LOSS OF ALL AC POWER WHILE ON RHR.

• Loss of RHR may cause CTMT radiological and heat stress conditions to degrade. Local actions in CTMT should be coordinated with HP.

• During solid plant operation, inadvertent actuation of the OPMS may occur if letdown is isolated.

• If RCS boiling occurs, non-essential personnel should be evacuated from CTMT.

NOTE: EPIPs may be applicable.

STANDARD:

• Acknowledges note and acknowledges cautions and recognizes that a total loss of IA or AC Power is not occurring.

COMMENTS:

STEP 3:

_______ SAT CHECK ENTRY INTO THIS PROCEDURE DUE TO LOSS OF INVENTORY.

(AP-27.00Step 1) _______ UNSAT STANDARD:

• Determines that RCS inventory is NOT lowering and performs RNO to transition to procedure STEP 5.

EVALUATORS NOTE:

COMMENTS:

Page 4

Surry 2021-301 Loss of Decay Heat STEP 4:

_______ SAT CHECK RHR PUMP - ONE RUNNING AND PROVIDING FLOW. (Step 5)

_______ UNSAT STANDARD:

• Checks that no RHR pumps are running by observing zero amps indicated and 1-RH-P-1A has red and amber lights lit, 1-RH-P-1B has green light lit. 1-RH-P-1A also has overload light due to overcurrent trip. Goes to RNO.

EVALUATORS NOTES:

• Note: Annunciator 1B-G7, RHR PP 1A IN LOCAL CONTROL OR OL TRIP, will be LIT. The Applicant should not attempt to restart 1-RH-P-1A.

COMMENTS:

STEP 5: CRITICAL STEP

_______ SAT IF Emergency Bus power is available, THEN do the following: (Step 5d-g RNO)

_______ UNSAT d) Manually close RH control valves:

o 1-RH-FCV-1605 o 1-RH-HCV-1758 e) Start one RHR pump.

f) Adjust RH control valves to return flow to pre-event rate:

o 1-RH-FCV-1605 o 1-RH-HCV-1758 g) IF an RHR pump can NOT be started, THEN GO TO Step 17. (NO, proceeds to step 6)

STANDARD:

• Places 1-RH-FCV-1605 in manual and closes valve. CRITICAL STEP.

• Notes setpoint on ten turn pot for 1-RH-HCV-1758 (9.8) and then closes 1-RH-HCV-1758 using ten turn pot. CRITICAL STEP.

• Starts 1-RH-P-1B by taking control switch to the start position and verifying amps are indicated. CRITICAL STEP.

• Manually opens 1-RH-FCV-1605 using controller pushbuttons. CRITICAL STEP.

• Manually opens 1-RH-HCV-1758. CRITICAL STEP.

• Proceeds to Step 6 since an RHR pump was started and the cause of trip was NOT due to a loss of Emergency Bus power.

EVALUATOR NOTE:

• 1-RH-FCV-1605, and 1-RH-HCV-1758 should be opened to the approximate pre-event value. However its not critical that this exact value be established.

Page 5

Surry 2021-301 Loss of Decay Heat COMMENTS:

STEP 6:

_______ SAT CHECK RHR FLOW - INDICATED ON RHR SYS FLOW. (Step 6)

_______ UNSAT

• 1-RH-FI-1605 STANDARD:

• Checks RHR flow restored on 1-RH-FI-1605.

COMMENTS:

STEP 7:

_______ SAT CHECK RHR PUMP - VORTEXING (Step 7)

_______ UNSAT

• Flow indication on 1-RH-FI-1605 - OSCILLATING

• Amperage indication - OSCILLATING STANDARD:

• Checks flow steady on 1-RH-FI-1605 and amps steady for 1-RH-P-1B.

• Goes to step 7 RNO and transitions to Step 13.

COMMENTS:

STEP 8:

_______ SAT CHECK RHR HEAT SINK: (Step 13)

_______ UNSAT a) Flow on 1-RH-FI-1605 - NORMAL b) CC to RHR HX b)

1) In-Service RHR HX CC Outlet HDR Flow - NORMAL

• 1-CC-FI-110A OR

• 1-CC-FI-110B STANDARD:

• Checks flow on 1-RH-FI-1605 indicating normal (approximately 3400 gpm)

• Checks CC to RHR HX on 1-CC-FI-110A NOT normal at zero gpm. Goes to RNO.

Page 6

Surry 2021-301 Loss of Decay Heat EVALUATORS NOTE:

COMMENTS:

STEP 9: CRITICAL STEP

_______ SAT

1) Check opened or open 1-CC-TV-109A or 1-CC-TV-109B. (Step 13b(1) RNO)

_______ UNSAT STANDARD:

a) Opens 1-CC-TV-109A. CRITICAL STEP EVALUATORS NOTE:

• If asked for In service RHR/HX: Inform the Candidate that this information has already been provided. (information provided on Cue sheet).

• 1-CC-TV-109B is OPEN which is normal, but there is no flow through that valve because there are other manual valves that need to be open to provide flow. It is possible the candidate would believe the step is satisfied because 1-CC-TV-109B is open. In service RHR/HX is the A RHR HX. This is incorrect because it is NOT the in-service HX. If this happens the candidate can recover by performing next step and realizing that temp is not lowering.

• Note: If the operator doesnt depress the OPEN pushbutton long enough, 1-CC-TV-109A may reclose. If this happens the operator should try to reopen 1-CC-TV-109A.

COMMENTS:

STEP 10:

_______ SAT In-Service RHR HX CC Outlet Header Temp -NORMAL. (Step 13b(2))

_______ UNSAT STANDARD:

• Monitors 1-CC-TI-109A and determines that temperature is returning to Normal..

COMMENTS:

Page 7

Surry 2021-301 Loss of Decay Heat STEP 12:

_______ SAT Check RCS TEMPERATURE -STABLE OR LOWERING. ( Step 14)

_______ UNSAT STANDARD:

a) Monitors RCS temperature.

b) May adjust 1-RH-HCV-1758.

EVALUATORS NOTE:

• Adjustment of 1-RH-HCV-1758 not critical because this was performed/satisfied by returning HCV-1758 to pre-event value in step 6.

COMMENTS:

END OF JPM STOP TIME:

Page 8

Surry 2021-301 Loss of Decay Heat SIM DRAWING RHR & COMP COOLING FOLLOWING LOSS OF RHR PUMP Page 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• The Unit has been operating on RHR with 1-RH-P-1A in service on "A" RHR HX at 3400 gpm.

• The Pressurizer is at 60% Cold Cal and slowly rising in preparation for going solid.

• RCS temperature: 177 oF and stable.

Initiating Cues

• You are to lower RCS temperature and stabilize the RCS cold leg (C) to between 170oF - 175oF per 1-OP-ZZ-002, Maintenance of Plant Operations, section 5.16, Adjusting RHR Temperatures. It is desirable that you stabilize by adjusting 1-RH-HCV-1758.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• The Unit has been operating on RHR with 1-RH-P-1A in service on "A" RHR HX at 3400 gpm.

• The Pressurizer is at 60% Cold Cal and slowly rising in preparation for going solid.

• RCS temperature: 177 oF and stable.

Initiating Cues

• You are to lower RCS temperature and stabilize the RCS cold leg (C) to between 170oF - 175oF per 1-OP-ZZ-002, Maintenance of Plant Operations, section 5.16, Adjusting RHR Temperatures. It is desirable that you stabilize by adjusting 1-RH-HCV-1758.

U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA: 028A4.03 3.1/3.3]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Place Hydrogen Analyzer in Service Following a LOCA in accordance with 1-E-1, Loss of Reactor or Secondary Coolant.

K/A: 028A4.03, Ability to manually operate and / or monitor in the control room: Location and operation of hydrogen sampling and analysis of containment atmosphere, including alarms and indications (3.1 / 3.3).

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 7 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

• A LOCA has occurred from 100% power.

• A determination of Containment Hydrogen concentration is desired.

Standards

• Places XFER CKT UNIT #1 TO UNIT #2 in the UNIT 1 position.

• Places H2 Analyzer (H2A-GW-104) Heat Trace Panel 6, 1-HT-HTP-6, in ON.

• Opens 1-GW-TV-100, 1-GW-TV-101, 1-GW-TV-102, and 1-GW-TV-103.

• Places H2A-GW104 in ANALYZE.

Procedures

• 1-E-1, Attachment 2, Hydrogen Analyzer Operation.

Tools and Equipment Safety Considerations

• None

• None

Simulator Setup

• Recall IC #385 OR do the following:

• Call up 100% IC, initialize & place simulator in RUN.

• Initiate LBLOCA malfunction. Continue until Recirc Mode Transfer is complete.

• Allow CTMT pressure to increase and return to < 18 psia.

• Place selector switch for H2A-GW104 in the Unit 2 position.

• Verify selector switch for the H2 ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP-6, is in the AUTO position & reset SI. Check heat tracing de-energized.

• Freeze simulator.

PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME_______:

STEP 1

_______ SAT NOTES Prior to Step 1 (1-E-1 Attachment 2,Section I)

_______ UNSAT

• Containment pressure should be between 9 and 60 PSIA.

• Containment temperature should be between 40°F and 290°F.

STANDARD:

• Acknowledges Notes.

EVALUATORS NOTE:

COMMENTS:

STEP 2

_______ SAT Select Hydrogen Analyzer to be placed in service: (Attachment 2, Step 1)

H2A-GW104 or H2A-GW204 _______ UNSAT STANDARD:

a) Determines from Initial Conditions that the Unit 1 Hydrogen Analyzer (1-H2A-GW-104) is to be placed in service and checks the applicable block.

b) Goes to Step 2.

EVALUATORS NOTE:

If asked, tell the Candidate this information has already been provided.

COMMENTS:

STEP 3 (CRITICAL STEP)

_______ SAT IF H2A-GW104 is to be placed in service, THEN do the following: (Attachment 2, step 2.a.)

_______ UNSAT

a. Put selector switch XFER CKT UNIT #1 TO UNIT #2 (for H2A-GW104) in the UNIT 1 position. (Switch is located on Unit 1 PAM Panel.)

STANDARD:

• Places selector switch "XFER CKT UNIT #1 TO UNIT #2" (for H2A-GW104) to the UNIT 1 position. (CRITICAL STEP)

• Checks WHITE analyzer indicating light for Unit 1 is LIT.

EVALUATORS NOTE:

• • This step is also sequence critical; it must be performed before Step 6 of this JPM.**

COMMENTS:

STEP 4 (CRITICAL STEP)

_______ SAT ENERGIZE HEAT TRACING (Attachment 2, Step 2.b.)

_______ UNSAT

b. Put selector switch H2 ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP-6, in ON. Record the time Heat Tracing is energized _________.

STANDARD:

• Places selector switch for H2 ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP-6, in the ON position. (CRITICAL STEP)

• Checks RED light illuminates after switch is in ON position.

• Records time that heat tracing was energized in the appropriate block.

EVALUATORS NOTE:

• • This step is also sequence critical; it must be performed before Step 6 of this JPM.**

COMMENTS:

STEP 5 (CRITICAL STEP)

_______ SAT ALIGN FLOW PATH (Attachment 2, Steps 2.c., 2.d., 2.e., 2.f.)

_______ UNSAT

c. Open 1-GW-TV-100, H2 ANALYZER VLV.

d. Open 1-GW-TV-101, H2 ANALYZER VLV.

e. Open 1-GW-TV-103, H2 ANALYZER VLV.

f. Open 1-GW-TV-102, H2 ANALYZER VLV.

STANDARD:

(a) Places control switch for 1-GW-TV-100 in OPEN. (CRITICAL STEP)

(b) Checks valve open by observing red indicating light lit & green off.

(c) Places control switch for 1-GW-TV-101 in OPEN. (CRITICAL STEP)

(d) Checks valve open by observing red indicating light lit & green off.

(e) Places control switch for 1-GW-TV-103 in OPEN. (CRITICAL STEP)

(f) Checks valve open by observing red indicating light lit & green off.

(g) Places control switch for 1-GW-TV-102 in OPEN. (CRITICAL STEP)

(h) Checks valve open by observing red indicating light lit & green off.

EVALUATORS NOTE:

• • The order of valve operation is NOT sequence critical, but performing this step before Step 6 of this JPM IS sequence critical.**

COMMENTS:

STEP 6 (CRITICAL STEP)

_______ SAT ENSURES MINIMUM TIME REQUIREMENT MET FOR HEAT TRACING (Attachment 2, Steps 2.g and 2.h.) _______ UNSAT NOTE: Before the Hydrogen Analyzer is placed in service, the heat tracing circuit must be energized for 20 minutes.

g. Check that 20 minutes have elapsed since the time recorded in Step 2b.

h. Put selector switch H2 ANALYZER H2A-GW104 in the ANALYZE position.

STANDARD:

(a) Acknowledges NOTE before substep g.

(b) Determines the 20 minute period has NOT yet elapsed and a wait period will be required.

(c) Following a 20 minute heat tracing warm-up period, proceeds to next step.

(d) Places H2A-GW104 mode select switch to the ANALYZE position. (CRITICAL STEP)

(e) Checks RED and GREEN lights are both illuminated after switch is in ANALYZE position.

EVALUATORS NOTE:

After the Candidate reports a 20 minute wait period is required, inform them a TIME COMPRESSION has occurred and 20 minutes have elapsed.

• • This step is sequence critical.**

After the Candidate places H2A-GW104 to ANALYZE, inform them another operator will continue from here and the JPM is complete.

COMMENTS:

END OF JPM STOP TIME: _______

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• There has been a Large Break LOCA on Unit 1.

Initiating Cues

• Here is a copy of 1-E-1, Attachment 2, Hydrogen Analyzer Operation. I need you to place Unit 1's hydrogen analyzer in service on Unit 1 Containment.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• There has been a Large Break LOCA on Unit 1.

Initiating Cues

• Here is a copy of 1-E-1, Attachment 2, Hydrogen Analyzer Operation. I need you to place Unit 1's hydrogen analyzer in service on Unit 1 Containment.

• When you finish the actions necessary to accomplish this, please inform me.

U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA 064.A4.06]

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Respond to a Failure of #3 EDG to Start and Load on 1J 4160V Bus.

K/A: 064.A4.06; Manual start, loading, and stopping of the ED/G, RO 3.9 / SRO 3.9 Applicability Validation Time Actual Time RO 9 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• EMERG GEN NO. 3 ENGINE START pushbutton is depressed.

• AUTO-EXERCISE EMERG GEN 3 switch is placed in AUTO.

• SYNC-ACB-15J3 key switch is placed to ON.

• EMERG GEN NO 3 FIELD FLASH pushbutton is depressed.

• Attempts to raise incoming voltage by placing EMERG GEN NO 3 VOLT ADJ to RAISE.

• EDG 3 secured by depressing both ENGINE STOP pushbuttons simultaneously.

Procedures

• 0-AP-17.05, EDG 3 - Emergency Operations.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 7

Simulator Setup

• Call up 100% power IC and initialize (IC386). Place simulator in RUN.

• Load the following Malfunctions/Overrides:

• EL0501, Loss of reserve Station Service XMFMR A, TRUE T1.

• ED0503, EDG3 Voltage Regulator Failure, -1, T1.

• ED0403, EDG 3 Auto Start Failure T1.

• Remote U2_EGR3_Bypass to U2, T3.

• Remote SW_25J3_RF to PTL, T3.

• Strip the 1J bus per Attachment 3.

• Place AUTO-EXERCISE EMERG GEN 3 switch to EXERCISE.

• Acknowledge Alarms.

• Freeze and Snap IC until ready for evaluation.

Notes Page 2 of 7

PERFORMANCE CHECKLIST Notes to the Evaluator

• This JPM may be Pre-briefed as directed by the Chief Examiner.

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee, and perform actions for Unit 2.

• START TIME _____:

STEP 1: CRITICAL STEP Check Load Limit at maximum, Start EDG 3, Check #3 EDG Speed at 900 RPM, Place #3 EDG AUTO EXERCISE Switch in Auto. (Step 4, 5, and 6 of Attachment 2)

STANDARD:

a) Candidate presses the EDG NO. 3 Engine Start pushbutton. CRITICAL STEP.

b) Candidate will check EDG started using RPM indication.

c) Candidate will place the AUTO-EXERCISE Switch for EDG #3 in AUTO position.

CRITICAL STEP.

d) Candidate will note that #3 EDG has not energized the 1J Bus.

e) Candidate returns to AP-17.05, Step 8.

EVALUATORS NOTE:

COMMENTS:

STEP 2:

_______ SAT CHECK BOTH J BUSES - ENERGIZED BY OFFSITE POWER. (Step 8)

_______ UNSAT STANDARD:

a) Candidate Identifies 1J Bus is still de-energized.

b) Candidate Goes To Step 10.

EVALUATORS NOTE:

COMMENTS:

Page 3 of 7

STEP 3:

Notes prior to Step 10 _______ SAT

• If the B DC Bus is deenergized, the EDG output breaker and the J Bus load breakers _______ UNSAT must be closed manually.

• The following conditions must exist for the EDG output breaker to close automatically:

• EDG speed greater than 870 rpm

• EDG INCOMING voltage greater than 113 volts

• J8 breaker open

• Control switch for the J3 breaker in AUTO AFTER TRIP

• DC control power available to the J3 breaker CHECK EDG 3 - SUPPLYING J BUS. (Step 10)

STANDARD:

a) Acknowledges Notes.

b) Candidate Identifies 15J3 - NOT Closed.

c) Candidate performs RNO. Identifies that loads are already stripped per Attachment 3.

d) Candidate goes to step 15 EVALUATORS NOTE:

• Evaluator Cue: Attachment 3 has been completed by another operator.

• IF asked: Status of Breaker 25-J3, reply refer to the Initial conditions.

COMMENTS:

STEP 4: CRITICAL STEP

_______ SAT CHECK EDG 3 INCOMING VOLTAGE GREATER THAN 113 VOLTS. (Step 15)

_______ UNSAT STANDARD:

a) Candidate turns SYNC-ACB-15J3 key switch to ON. CRITICAL STEP.

b) Candidate identifies no generator voltage and momentarily depresses EMERG GEN NO 3 FIELD FLASH pushbutton. Identifies Voltage established.

CRITICAL STEP.

c) Candidate attempts to raise incoming voltage to 120 volts using the EMERG GEN NO 3 VOLT ADJ control switch. CRITICAL STEP.

d) Candidate determines there is no Voltage increase, and goes to 15.c RNO.

EVALUATORS NOTE:

Evaluator Note: Operator may go to 15bRNO because of step 15 b wording.

Evaluator Cue: If asked to check the Field Ckt Breaker. Report that field operator has checked the Field Ckt Breaker was closed.

Evaluator Cue: If asked to reset the NO FIELD annunciator on the EDG Control panel. Report that field operator has reset this annunciator.

COMMENTS:

Page 4 of 7

STEP 5: CRITICAL STEP

_______ SAT SECURES #3 EDG. (Step 15.c RNO)

_______ UNSAT STANDARD:

a) Candidate notifies Electrical Department.

b) Candidate secures #3 EDG by momentarily pressing the EMERG GEN NO.3 ENGINE STOP pushbuttons. CRITICAL STEP.

c) Candidate notifies Shift Manager.

EVALUATORS NOTE:

• If asked to notify the Electrical department: Acknowledge request.

• Both ENGINE STOP pushbuttons must be depressed simultaneously.

• The EDG will go into a cooldown cycle and will shutdown in 9.5-13 minutes. The amber light for the Aux Trip relay is an indication that both pushbuttons were depressed simultaneously and the Diesel is in a cooldown cycle.

• If the applicant continues and closes 15-J3, this constitutes failure because of elevated bus current and potential damage to equipment.

• Evaluator Cue: After this step is done inform applicant that another operator will take over from here.

BOOTH NOTE:

• Ensure Synch key is returned to the proper location.

COMMENTS:

JPM ENDS STOP TIME_______:

Page 5 of 7

CUTAWAY OF EDG3 PANEL. After BOTH ENGINE STOP PUSHBUTTONS ARE DEPRESSED, THE AUX TRIP RELAY LIGHT WILL LIGHT. There will be no other indications that the EDG has been shutdown because the EDG is in a cooldown cycle.

Page 6 of 7

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit 1 operating at 100% power.

• The Loss of the A RSST has occurred and #3 EDG has failed to start and load on 1J 4160V Bus.

• Starting and loading #3 EDG on the 1J 4160V bus IAW 0-AP-17.05, EDG 3 - Emergency Operations is in progress and is complete through step 3 of Attachment 2.

Initiating Cues

• You are the Unit 1 BOP and are to continue with starting and loading of #3 EDG per 0-AP-17.05, starting with Attachment 2 step 4.

• When you finish the actions necessary to accomplish this, please inform me.

Page 7 of 7

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 operating at 100% power.

• The Loss of the A RSST has occurred and #3 EDG has failed to start and load on 1J 4160V Bus.

• Starting and loading #3 EDG on the 1J 4160V bus IAW 0-AP-17.05, EDG 3 - Emergency Operations is in progress and is complete through step 3 of Attachment 2.

Initiating Cues

• You are the Unit 1 BOP and are to continue with starting and loading of #3 EDG per 0-AP-17.05, starting with Attachment 2 step 4.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure 015A1.01 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Adjust the PRNIs in accordance with 1-OPT-RX-001 K/A: 015A1.01 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: NIS calibration by heat balance. (3.5 / 3.8)

Applicability Estimated Time Actual Time RO/SRO 10 Minutes ___ Minutes Conditions

• This JPM to be Pre-briefed with marked up copy of procedure.

• This JPM is performed in the Simulator.

• Unit 1 operating at 89.5% power. 1-OPT-RX-001 has been completed up to Section 6.2.

Standards

• Places rod control in Manual prior to adjusting N44 gain pot.

• Adjusts N44 Gain Potentiometer to a minimum indication of 89.5% IAW 1-OPT-RX-001, Section 6.2 and Attachment 1.

• Places rod control in Auto with no rod motion.

Initiating Cues

• Unit 1 operating at 89.5% power.

• The Unit 1 RO has completed 1-OPT-RX-001, Section 6.1.

• You are to perform 1-OPT-RX-001, Section 6.2.

Terminating Cues

• 1-OPT-RX-001, Attachment 1, has been completed.

Procedures

• 1-OPT-RX-001, Reactor Power Calorimetric Using PCS Computer Program, Rev. 51 Tools and Equipment Safety Considerations Page 1 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001

• None

• None Simulator Setup

• Recall IC-387.

-OR-

• Call up 90% power IC and initialize.

• Place simulator in RUN.

• Adjust/Check N41, N42, and N43 to 89.5% indication using drawer gain control.

• Adjust N44 to an indication of 88% power using the drawer gain control.

• Place Simulator in Freeze until JPM performance.

Notes

• The Applicant is given the marked-up copy of 1-OPT-RX-001. This evolution may be pre-briefed.

• When possible place Simulator in RUN prior to the candidate entering the Simulator.

Page 2 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME:

STEP 1:

_______ SAT Compare each NI channel percent power indication with the Calcalc Total Thermal Pwr (UFM, Venturi or Normalized Feedwater) or Calcalc 10-Min Avg Pwr (Steam Flow), whichever is the _______ UNSAT standard. (Each NI should be within + 2% and - 0% of the Calorimetric value if Reactor power is greater than or equal to 90%, OR within + 4% and - 0% of the Calorimetric value if Reactor power is less than 90%.). (Step 6.2.1)

STANDARD:

a) Reads and Initials Step 6.2.1.

b) Refers to Step 6.1.12 to determine Calcalc Total Thermal Power: 89.5%.

c) Locates to PRNI drawers and observes N41 indicating 90%, N42 indicating 90%, N43 indicating 90%, and N44 indicating 88%.

COMMENTS:

Page 3 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 STEP 2:

_______ SAT NOTE: Gain potentiometer adjustment can cause average flux deviation alarms as well as high flux rod stop alarms. This should be anticipated when adjusting gain potentiometers. (Reference _______ UNSAT 2.4.6).

STANDARD:

Reviews NOTE prior to Step 6.2.2.

COMMENTS:

STEP 3:

_______ SAT IF the NI Channel is within tolerance but adjustment will better align it with the calorimetric, THEN obtain Shift Supervision concurrence AND adjust NI Channel IAW Attachment 1 to the _______ UNSAT value recorded in Step 6.1.12 or Step 6.1.13. Record initials on Attachment 1. IF no NI adjustment is made, OR NI is NOT within tolerance, THEN enter N/A. (Step 6.2.2)

STANDARD:

Enters N/A and Initials Step 6.2.2.

COMMENTS:

STEP 4:

_______ SAT IF NI channel is NOT within tolerance, THEN obtain Shift Supervision concurrence AND adjust the gain potentiometer on the front panel of each NI Channel IAW Attachment 1 to the value _______ UNSAT recorded in Step 6.1.12 or Step 6.1.13. Record initials on Attachment 1. IF all NI channels are within tolerance, THEN enter N/A. (Step 6.2.3)

STANDARD:

a) Initials Step 6.2.3.

b) Reports to Shift Manager (Evaluator) that N44 requires adjustment, and requests authorization to make these adjustments.

c) Initiates Attachment 1.

EVALUATORS NOTE:

If asked: Shift Supervision has concurred with adjustment of PRNIs.

COMMENTS:

Page 4 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 STEP 5:

_______ SAT Attachment 1, 1-OPT-RX-001, NI Calibration.

_______ UNSAT CAUTION: To prevent introducing non-conservative High Flux Trip and High Flux Rod Stop setpoints, setpoint changes required by the following step must be completed before any associated Gain Potentiometer adjustments are performed.

STANDARD:

Reviews CAUTION Prior to Step 1 of Attachment 1.

COMMENTS:

STEP 6:

_______ SAT IF Reactor power is less than 90% AND the Gain Potentiometer on any NI will be decreased, THEN before adjusting NIs, have I & C lower the High Flux Trip and High Flux Rod Stop _______ UNSAT setpoints on all NIs based on current Reactor power level. Otherwise, enter N/A. (Reference 2.4.5). (Attachment 1, Step 1)

STANDARD:

Enters N/A and Initials Step 1 of Attachment 1.

COMMENTS:

STEP 7:

_______ SAT N41. (Attachment 1 Table)

_______ UNSAT STANDARD:

a) Enters N/A in Item 3) block, N41 column of the Table.

b) Enters N/A in item 4) block, N41 column of the Table.

c) Enters N/A in Item 5) block, N41 column of the Table.

EVALUATORS NOTE: A KEY is provided on Page 9 of 11, depicting the completed Table on Page 26 of 1-OPT-RX-001.

COMMENTS:

Page 5 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 STEP 8:

_______ SAT N42. (Attachment 1 Table)

_______ UNSAT STANDARD:

a) Enters N/A in Item 3) block, N42 column of the Table.

b) Enters N/A in item 4) block, N42 column of the Table.

c) Enters N/A in Item 5) block, N42 column of the Table.

COMMENTS:

STEP 9:

_______ SAT N43. (Attachment 1 Table)

_______ UNSAT STANDARD:

a) Enters N/A in Item 3) block, N43 column of the Table.

b) Enters N/A in item 4) block, N43 Column of the Table.

c) Enters N/A in Item 5) block, N43 column of the Table.

COMMENTS:

Page 6 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 STEP 10: CRITICAL STEP

_______ SAT N44. (Attachment 1 Table)

_______ UNSAT STANDARD:

a) Places Rod control in manual, and initials item 2) block, N44 column of the Table.

CRITICAL STEP.

b) Enters 88% in Item 3) block, N44 column of the Table.

c Checks alternate indications of reactor Power (i.e., N41, N42, N43, Turbine Impulse Pressure, and Calorimetric power) prior to adjustment of N44 IAW P&L 4.6.

d) Adjusts gain control on N44 Drawer to 89.5% indication. (Band: 89.5 - 93.5%).

CRITICAL STEP.

e) Enters Initials in item 4) block, N44 Column of the Table.

f) Records 89.5% in Item 5) block, N44 column of the Table.

h) Allows at least one (1) minute to pass before placing rod control in automatic following gain control manipulation.

i) Places Rod control in Automatic, with no rod motion. Initials item 6) block, N44 column of the Table. CRITICAL STEP.

EVALUATORS NOTE:

When N44 gain control is adjusted, it will be adjusted in the clockwise direction.

COMMENTS:

Page 7 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 STEP 11: _______ SAT NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) WITH STATUS OF TASK. _______ UNSAT Candidate should report completion of N44 gain adjustment and that rod control is in AUTO.

COMMENTS:

• • JPM COMPLETE **

STOP TIME:

Page 8 of 11

Surry 20121-301 Adjust PR NI 1-OPT-RX-001 KEY (for Examiner)

Candidate Initials N/A N/A N/A 88%

N/A N/A N/A Candidate Initials N/A N/A N/A 89.5%

Candidate Initials Page 9 of 11

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit 1 is operating at 89.5%.

• The Unit 1 RO has completed 1-OPT-RX-001, Section 6.1, Calculating Reactor Power Using Primary Performance Program, and recorded CALCALC Total Thermal Power on Step 6.1.12.

Initiating Cues

• You are to perform 1-OPT-RX-001, Section 6.2, Adjusting NI Channels.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 is operating at 89.5%.

• The Unit 1 RO has completed 1-OPT-RX-001, Section 6.1, Calculating Reactor Power Using Primary Performance Program, and recorded CALCALC Total Thermal Power on Step 6.1.12.

Initiating Cues

• You are to perform 1-OPT-RX-001, Section 6.2, Adjusting NI Channels.

Surry 2021-301 Realign MCR Ventilation U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA: 036G2.1.44 3.9/3.8]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title MCR pressure boundary verification using 0-AP-22.00, Fuel Handling Abnormal Conditions K/A: 036G2.1.44, Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation (3.9 / 3.8).

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 7 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Closes either 1-VS-MOD-103A or -103C.

• Closes either 1-VS-MOD-103B or -103D.

• Opens one of the following MODs: 1-VS-MOD-104A, 2-VS-MOD-204A, 1-VS-MOD-104B, 2-VS-MOD-204B.

• Starts the ONE Supply fan associated with the opened MOD: 1-VS-F-41, 1-VS-F-42, 2-VS-F-41, 2-VS-F-42.

• Places 1-VS-43-VS103X to OFF.

Procedures

• 0-AP-22.00, Fuel Handling Abnormal Conditions.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry 2021-301 Realign MCR Ventilation Simulator Setup

• Recall IC 388, or recall 100% IC and initialize.

• Place simulator in RUN.

Page 2 of 9

Surry 2021-301 Realign MCR Ventilation PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• START TIME_______:

STEP 1

_______ SAT CHECK FUEL REPAIR - IN PROGRESS (0-AP-22.00 step 1)

_______ UNSAT STANDARD:

a) Recalls from initial conditions or Shift Manager prompt that fuel repair is not in progress.

b) Goes to Step 4 EVALUATORS NOTE:

IF asked: Fuel repair was not in progress.

COMMENTS:

STEP 2

_______ SAT STOP FUEL HANDLING OPERATIONS (0-AP-22.00 step 4)

_______ UNSAT STANDARD:

a) Recalls from initial conditions that the Fuel Building has been evacuated, or from Shift Manager prompt that fuel handling operations are secured.

b) Goes to Step 5.

EVALUATORS NOTE:

IF asked: Fuel handling operations are secured.

COMMENTS:

Page 3 of 9

Surry 2021-301 Realign MCR Ventilation STEP 3

_______ SAT EVACUATE THE AFFECTED AREA (0-AP-22.00 step 5)

• Containment _______ UNSAT OR

• Fuel Building STANDARD:

a) Recalls from initial conditions that the Fuel Building has been evacuated, or from Shift Manager prompt that fuel handling operations are secured.

b) Goes to Step 6.

EVALUATORS NOTE:

IF asked: The Fuel Building has been evacuated.

COMMENTS:

STEP 4

_______ SAT CHECK MCR EMERGENCY VENTILATION - NOT IN SERVICE (0-AP-22.20 step 6)

_______ UNSAT STANDARD:

a) Observes on the MCR Ventilation panel that no emergency ventilation fans are running.

b) Observes normal MCR ventilation is in service.

c) Goes to Step 7.

EVALUATORS NOTE:

COMMENTS:

Page 4 of 9

Surry 2021-301 Realign MCR Ventilation STEP 5 CRITICAL STEP

_______ SAT SECURE NORMAL VENTILATION (0-AP-3.0 step 7) a) Close 1-VS-MOD-103A a) _______ UNSAT b) Close 1-VS-MOD-103B b) c) Close 1-VS-MOD-103C c) d) Close 1-VS-MOD-103D STANDARD:

a) Turns control switch for 1-VS-MOD-103A to CLOSE.

b) Turns control switch for 1-VS-MOD-103B to CLOSE.

c) Turns control switch for 1-VS-MOD-103C to CLOSE.

d) Turns control switch for 1-VS-MOD-103D to CLOSE.

e) Observes GREEN lights lit for 1-VS-MOD-103A/B/C/D.

f) Goes to Step 8.

EVALUATORS NOTE:

• NOTE: 1-VS-MOD-103A and -103C are in series. Closing either MOD satisfies the CRITICAL STEP.

• NOTE: 1-VS-MOD-103B and -103D are in series. Closing either MOD satisfies the CRITICAL STEP.

COMMENTS:

Page 5 of 9

Surry 2021-301 Realign MCR Ventilation STEP 6

_______ SAT VERIFY STOPPED OR STOP MCR VENTILATION FANS (0-AP-22.00 step 8)

• 1-VS-F-15 _______ UNSAT

• 1-VS-AC-4 STANDARD:

a) Observes GREEN light lit for 1-VS-F-15.

b) Observes GREEN light lit for 1-VS-AC-4.

c) Goes to Step 9 EVALUATORS NOTE:

NOTE: 1-VS-AC-4 will automatically stop when 1-VS-MOD-103A or -103C are closed. 1-VS-F-15 will automatically stop when either 1-VS-MOD-103B or -103D are closed.

COMMENTS:

STEP 7

_______ SAT CAUTIONS before Step 9.

_______ UNSAT STANDARD:

a) Acknowledges Cautions concerning Unit 1 and Unit 2 MCR AHU Chilled water flow rates.

b) Acknowledges Cautions concerning flowing through a wet filter.

c) Acknowledges Cautions concerning the limit of one Emergency Supply fan.

EVALUATORS NOTE:

• Cue: IF asked, another operator will throttle Chilled water to the in-service MCR Air Handling Units (AHU)

COMMENTS:

Page 6 of 9

Surry 2021-301 Realign MCR Ventilation STEP 8 CRITICAL STEP

_______ SAT IMMEDIATELY START ONE EMERGECNY SUPPLY FAN IAW THE FOLLOWING (1-VS-F-41 OR 2- VS-F -41 PREFERRED) (0-AP-22.00 step 9) _______ UNSAT a) Start 1-VS-F-41 IAW the following:

1) Open 1-VS-MOD-104A, CONT RM EMERG SUP MOD

2) Start 1-VS-F-41 OR b) Start 2-VS-F-41 IAW the following:

1) Open 2-VS-MOD-204A, CONT RM EMERG SUP MOD

2) Start 2-VS-F-41 OR c) Start 1-VS-F-42 IAW the following:

1) Open 1-VS-MOD-104B, CONT RM EMERG SUP MOD

2) Start 1-VS-F-42 OR d) Start 2-VS-F-42 IAW the following:

1) Open 2-VS-MOD-204B, CONT RM EMERG SUP MOD

2) Start 2-VS-F-42 e) Adjust Chilled Water flow to MCR AHUs IAW Step 9 Caution STANDARD:

a) Opens ONE of the following MODs: CRITICAL STEP 1-VS-MOD-104A 2-VS-MOD-204A 1-VS-MOD-104B 2-VS-MOD-204B b) Starts the Emergency Supply 41 or 42 fan associated with the opened MOD.

CRITICAL STEP.

EVALUATORS NOTE:

• NOTE: Opening ONE Emergency supply MOD and its associated Supply fan satisfies the CRITICAL STEP.

• CUE: Another operator will take care of Chilled Water.

• NOTE: The applicant should only start one fan, however if he starts two fans this does not constitute a failure of this Critical Step, as long as he opens the correct MOD associated with the Emergency Fan.

COMMENTS:

Page 7 of 9

Surry 2021-301 Realign MCR Ventilation STEP 9 CRITICAL STEP

_______ SAT PLACE 1-VS-43-VS103X, MCR ISOLATION SWITCH ON UNIT 2 VS PANEL IN OFF (0-AP-22.00 step 10) _______ UNSAT STANDARD:

a) Places 1-VS-43-VS103X switch in OFF. CRITICAL STEP EVALUATORS NOTE:

COMMENTS:

END OF JPM STOP TIME: _______

Page 8 of 9

Examiner Key Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initiating Conditions

• Unit 1 is operating at 100% power; Unit 2 is in Refueling Shutdown. Fuel shuffling was in progress in the Fuel Building.

• There has been a Fuel Handling accident in the Fuel Building.

• The Fuel Handling crew has placed the leaking fuel assembly in the designated storage location and has evacuated the Fuel Building.

Initiating Cues

• Your task is to perform 0-AP-22.00, Fuel Handling Abnormal Conditions.

• When you finish the actions necessary to accomplish this, please inform me.

• This JPM is NOT Time Critical.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initiating Conditions

• Unit 1 is operating at 100% power; Unit 2 is in Refueling Shutdown. Fuel shuffling was in progress in the Fuel Building.

• There has been a Fuel Handling accident in the Fuel Building.

• The Fuel Handling crew has placed the leaking fuel assembly in the designated storage location and has evacuated the Fuel Building.

Initiating Cues

• Your task is to perform 0-AP-22.00, Fuel Handling Abnormal Conditions.

• When you finish the actions necessary to accomplish this, please inform me.

• This JPM is NOT Time Critical.

Surry 2021-301 DROPPED ROD RECOVERY U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure APE003 AA1.02 (3.6, 3.4)

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title RECOVER A DROPPED ROD K/A: APE003 AA1.02 (3.6, 3.4), Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod.

Applicability Validated Time Actual Time RO/SRO(I)/SRO(U) 13 Minutes ____ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

1. Rotates ROD CONT MODE SEL SWITCH from the MANUAL to the CBA position.

2. Places all disconnect switches for affected bank in "disconnect".

3. Places switch for P-10 in "connect.

4. Resets the GROUP 2 step counter to zero for CBA.

5. Places SHUTDN AND CONT ROD CONT SWITCH to the OUT position.

6. Candidate contacts I&C to reset CBA bank demand to 000

7. Fully withdraws the affected rod.

8. Places all disconnect switches for affected bank in "CONNECT".

9. Momentarily depresses ROD CONT SYS INTERNAL ALARM RESET pushbutton

10. Places ROD CONT MODE SEL switch to MANUAL.

Procedures

• 0-AP-1.01, Control Rod Misalignment.

Page 1 of 12

Surry 2021-301 DROPPED ROD RECOVERY Tools and Equipment Safety Considerations

• None

• None Simulator Setup Reset to IC 361 OR Call up 70% power IC.

Call up CERPI_MTP_F_KEY using remotes RD system.

Enter the following malfunction:

RD1224, DROPPED RCCA, P-10 CONTROL BANK A, INSERT Enter the following REMOTE:

CERPI_MTP_F_KEY, Position to ACTIVE, Event 3, Delay 0, Insert CBA_MAN_POS, CERPI CB A Demand Position Manual Input, FINAL VALUE to 0, Delay 5, TRIGGER 3, INSERT.

CERPI_MTP_F_KEY, Position to INACTIVE, Event 3, Delay 10, Insert Perform 0-AP-1.00 through step 23 and transition to 0-AP-1.01 step 5, perform through step 13 and stabilize plant.

Set up trend recorder for Tave and Tref to wide range indication.

REMOVE MALFUNCTION (RD1224) & freeze simulator until ready to perform JPM.

Place a Pink Magnet next to the Control Bank A Rod Position Recorder.

Procedure Setup:

Mark-up a copy of 0-AP-1.01 by initialing steps 5 through step 13.

o Note that AP-1.00 step 23 directs the operator to 0-AP-1.01 STEP 5 Page 2 of 12

Surry 2021-301 DROPPED ROD RECOVERY PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME_______

STEP 1:

_______ SAT 0-AP-1.01 - CAUTIONS prior to step 14:

• This procedure is NOT valid for realignment of a control rod if Reactor is _______ UNSAT subcritical.

• Realignment SHALL be performed with Reactor power held less than or equal to 75%.

STANDARD:

Candidate acknowledges cautions.

COMMENTS:

STEP 2: CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 14 TRANSFER ROD CONT MODE SEL SWITCH TO AFFECTED BANK

_______ UNSAT STANDARD:

a. Rotates ROD CONT MODE SEL SWITCH from the MANUAL to the CBA position

[CRITICAL STEP].

b. Verifies rod speed indication of 48 spm on ROD SPEED SI-1-408.

c. Records Rod P-10 in CBA affected.

COMMENTS:

Page 3 of 12

Surry 2021-301 DROPPED ROD RECOVERY STEP 3:

_______ SAT 0-AP-1.01 - STEP 15 RECORD AFFECTED ROD AND ROD BANK:

• Rod:___________ _______ UNSAT

• Rod Bank:___________

STANDARD:

a) Enters P-10 for affected rod b) Enters CBA for affected rod bank COMMENTS:

STEP 4: CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 16 ALIGN LIFT COIL DISCONNECT SWITCHES FOR AFFECTED BANK:

a) Place all disconnect switches to DISCONNECTED/DOWN position _______ UNSAT b) Place affected rod disconnect switch to CONNECTED/UP position c) Have alignment of disconnect switches independently checked STANDARD:

a) Proceeds behind Vertical Board 1-2 to Lift Coil Disconnect Switch Panel and opens panel door.

b) Notes sign requiring removal of jewelry prior to entry.

c) Places all disconnect switches for affected bank in "disconnect".

• F-2 [CRITICAL STEP]

• B-10 [CRITICAL STEP]

• K-14 [CRITICAL STEP]

• P-6 [CRITICAL STEP]

• K-2 [CRITICAL STEP]

• B-6 [CRITICAL STEP]

• F-14 [CRITICAL STEP]

d) Places switch for P-10 in "connect [CRITICAL STEP].

e) Requests alignment of Lift Coil Disconnect Switches to be independently verified.

EVALUATORS NOTE/CUE:

• If asked: Lift Coil Disconnect Switches have been independently verified.

COMMENTS:

Page 4 of 12

Surry 2021-301 DROPPED ROD RECOVERY STEP 5:

_______ SAT 0-AP-1.01 - STEP 17 RECORD BANK POSITION OF AFFECTED ROD. (ENTER N/A FOR NON-AFFECTED GROUP): _______ UNSAT

• Group 1 Step Counter:___________

• Group 2 Step Counter:___________

STANDARD:

(a) Enters N/A for Group 1 Step Counter (b) Enters 229 for Group 2 Step Counter COMMENTS:

STEP 6:

_______ SAT 0-AP-1.01 - CAUTIONS prior to step 18:

• The affected withdrawal rate during realignment is limited to 2/P (P=fraction of _______ UNSAT Core Power where 100% power is equal to 1.0) steps per hour (if not a whole number, round down to the whole number) if affected rod remains misaligned for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or the duration of misalignment can NOT be determined.

• The withdrawal rate limitation may be relaxed with authorization from the Reactor Engineer or Nuclear Analysis and Fuels.

STANDARD:

a) Acknowledges CAUTIONS b) Recalls from initial conditions that rod dropped 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago and these cautions are NOT applicable.

COMMENTS:

Page 5 of 12

Surry 2021-301 DROPPED ROD RECOVERY STEP 7:

_______ SAT 0-AP-1.01 - STEP 18 RECORD THE FOLLOWING:

• Reactor power:____________ _______ UNSAT

• Withdrawal rate:__________

STANDARD:

a) Candidate records current reactor power (approximately 70%)

b) Candidate records withdrawal rate at 48 steps/minute.

EVALUATORS NOTE/CUE:

If asked: Do not exceed 75% power, a 1 dpm SUR, or temperature >569°F during dropped rod recovery.

COMMENTS:

STEP 8:

_______ SAT 0-AP-1.01 - NOTE prior to step 19: Refer to Attachment 2 before resetting Group Step Counter. _______ UNSAT STANDARD:

Candidate refers to attachment 2 for assistance in resetting group step counters.

COMMENTS:

STEP 9:

_______ SAT 0-AP-1.01 - STEP 19 CHECK AFFECTED ROD - ON BOTTOM

_______ UNSAT STANDARD:

Candidate verifies P10 at 0 (zero) steps.

COMMENTS:

Page 6 of 12

Surry 2021-301 DROPPED ROD RECOVERY STEP 10:

_______ SAT 0-AP-1.01 - STEP 20 REFER TO TECH SPEC 3.12.E.

_______ UNSAT STANDARD:

Candidate directs the Shift Manager to review Tech Specs.

EVALUATORS NOTE/CUE:

If asked: The shift manager review of Tech Spec 3.12.E is complete and continue with the task.

COMMENTS:

STEP 11:

_______ SAT 0-AP-1.01 - NOTE prior to step 21: If only one dropped rod, then only one Group Step Counter and one Bank Demand will be reset. _______ UNSAT STANDARD:

Candidate acknowledges the NOTE.

COMMENTS:

Step 12 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 21 RESET AFFECTED GROUP STEP COUNTER TO 0.

_______ UNSAT STANDARD:

Utilizing attachment 2 as guidance, the candidate resets the GROUP 2 step counter to zero for CBA [CRITICAL STEP].

EVALUATORS NOTE/CUE:

If asked: Provide golf tee to candidate to assist in resetting the group step counter.

COMMENTS:

Page 7 of 12

Surry 2021-301 DROPPED ROD RECOVERY Step 13 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 22 HAVE I&C RESET AFFECTED BANK DEMAND TO 000.

_______ UNSAT STANDARD:

Candidate contacts I&C to reset CBA bank demand to 000 [CRITICAL STEP].

BOOTH NOTES:

When asked to reset affected bank as IC, report that 1G-E2, 1G-G5, and 1G-H5 will be received as part of the resetting of the affected bank demand.

Initiate TRIGGER 3 to reset affect bank demand to 0 (zero).

When 1G-E2 clear (or 10 seconds has elapsed), report back to candidate that the A control bank demand has been reset to zero.

COMMENTS:

Step 14

_______ SAT 0-AP-1.01 - NOTE prior to step 21: Annunciator ( )G-A6, ROD CONT SYS URGENT FAILURE, will alarm when the affected rod is withdrawn indicating that the lift coils _______ UNSAT of the remaining rods in the bank are deenergized..

STANDARD:

Candidate acknowledges NOTE COMMENTS:

Step 15 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 23 REALIGN AFFECTED ROD TO ITS BANK POSITION RECORDED IN STEP 17. _______ UNSAT STANDARD:

a) Places SHUTDN AND CONT ROD CONT SWITCH to the OUT position [CRITICAL STEP].

b) Verifies outward rod motion indicated by observing affected rod IPRI.

c) Acknowledges annunciator 1G-A6 (ROD CONT SYS URGENT FAILURE).

d) Withdraws affected rod to required position (229 steps) [CRITICAL STEP].

e) Continuously monitors SUR, PR NI's, IR NI's, T, Tave, group step counters, IRPI, rod speed, out indication light and TR-1-409A.

COMMENTS:

Page 8 of 12

Surry 2021-301 DROPPED ROD RECOVERY Step 16 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 24 PLACE AFFECTED BANK LIFT COIL DISCONNECT SWITCHES TO THE CONNECTED/UP POSITION _______ UNSAT STANDARD:

a) Proceeds behind Vertical Board 1-2 to Lift Coil Disconnect Switch Panel and opens panel door.

b) Notes sign requiring removal of jewelry prior to entry.

c) Places all disconnect switches for affected bank in "CONNECT".

• F-2 [CRITICAL STEP]

• B-10 [CRITICAL STEP]

• K-14 [CRITICAL STEP]

• P-6 [CRITICAL STEP]

• K-2 [CRITICAL STEP]

• B-6 [CRITICAL STEP]

• F-14 [CRITICAL STEP]

d) Requests alignment of Lift Coil Disconnect Switches to be independently verified.

COMMENTS:

Step 17

_______ SAT 0-AP-1.01 - STEP 25 HAVE ALIGNMENT OF DISCONNECT SWITCHES INDEPENDENTLY CHECKED _______ UNSAT STANDARD:

Candidate requests independent verification of disconnect switch positions.

EVALUATORS NOTE/CUE:

• If asked: Lift Coil Disconnect Switches have been independently verified.

COMMENTS:

Page 9 of 12

Surry 2021-301 DROPPED ROD RECOVERY Step 18 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 26 RESET ROD CONTROL URGENT FAILURE

• Depress ROD CONT SYS INTERNAL ALARM RESET pushbutton _______ UNSAT STANDARD:

a) Momentarily depresses ROD CONT SYS INTERNAL ALARM RESET pushbutton

[CRITICAL STEP].

b) Verifies annunciator 1G-A6 (ROD CONT SYS URGENT FAILURE) clears.

COMMENTS:

Step 19 CRITICAL STEP

_______ SAT 0-AP-1.01 - STEP 27 TRANSFER ROD CONT MODE SEL SWITCH TO MANUAL

_______ UNSAT STANDARD:

Rotates ROD CONT MODE SELECT Switch from the CBA position to the MANUAL position [CRITICAL STEP].

COMMENTS:

Step 20

_______ SAT REPORTS TO SHIFT MANAGER (EVALUATOR).

_______ UNSAT STANDARD:

Verbal status report made that rod withdrawn and rod control in manual.

COMMENTS:

JPM END STOP TIME:

Page 10 of 12

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• With the unit stable at 70% power, control Rod P-10 dropped about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to a failed fuse.

• Instrument Techs have replaced the fuse.

• A pre-job brief has been held and we are now ready to withdraw the rod.

• I&C is standing by for your instructions.

Initiating Cues

• Here's a copy of 0-AP-1.01, I want you to recover the dropped control rod IAW steps 14 through and including step 27.

• When you finish the actions necessary to accomplish this and return the rods to MANUAL, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• With the unit stable at 70% power, control Rod P-10 dropped about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to a failed fuse.

• Instrument Techs have replaced the fuse.

• A pre-job brief has been held and we are now ready to withdraw the rod.

• I&C is standing by for your instructions.

Initiating Cues

• Here's a copy of 0-AP-1.01, I want you to recover the dropped control rod IAW steps 14 through and including step 27.

• When you finish the actions necessary to accomplish this and return the rods to MANUAL, please inform me.

Surry 2021-301 RESPOND TO RCP SEAL FAILURE U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title RESPOND TO RCP SEAL FAILURE IAW 1-AP-9.00 (ALTERNATE PATH)

K/A: 002A2.01 Ability to predict the impacts loss of coolant inventory on the RCS and based on those predictions use procedures to correct, control, or mitigate 4.3/4.4.

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 8 Minutes _____ Minutes Conditions

• Task is to be PERFORMED in the simulator.

• ARP 1C-C4, RCP 1C SEAL LEAKOFF HI FLOW, has directed initiation of 1-AP-9.00 Standards

• Depresses Reactor Trip pushbutton.

• After 5 minutes closes 1-RC-PCV-1455B Spray Valve.

• Stops 1-RC-P-1C.

Procedures

• 1-AP-9.00 - RCP ABNORMAL CONDITIONS Tools and Equipment Safety Considerations

• None

• None Page 1 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE Simulator Setup Reset to IC 362 OR Call up 100% power IC and initialize. Place simulator in RUN.

Malfunctions, RC1203 (Failure of RCP Seal #1), Final Value = 100%, Insert.

Malfunctions, RC1303 (Failure of RCP Seal #2), Final Value = 50%, Event 1, Insert Page 2 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME_______:

STEP 1:

_______ SAT 1-ARP-1C-C4 - STEP 1, CHECK NUMBER 1 SEAL LEAKOFF GREATER THAN 3.0 GPM. -

OBSERVES THE CAUTIONS AND NOTES PRIOR TO STEP 1. _______ UNSAT STANDARD: Uses 1-CH-FR-1190 and determines seal leakoff is 3.08 gpm.

COMMENTS:

STEP 2:

_______ SAT 1-ARP-1C-C4 - STEP 2, INITIATE 1-AP-9.00, RCP ABNORMAL CONDITIONS.

_______ UNSAT STANDARD: Candidate initiates 1-AP-9.00.

COMMENTS:

• Provide 1-AP-9.00 when candidate identifies this is the procedure that is to be performed next.

Page 3 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 3:

_______ SAT 1-AP-9.00 - OBSERVES THE CAUTIONS AND NOTES PRIOR TO STEP 1.

CAUTION: If RCP seal injection flow is lost, RCP seal or bearing temperatures _______ UNSAT can be expected to reach maximum operating limits within one to two hours, even with normal Thermal Barrier CC flow.

NOTE:

• If an RCP needs to be tripped with the Reactor critical, a Reactor trip must be performed before securing the RCP.

• Attachment 1 and Attachment 6 list PCS points which may be used to monitor RCP performance.

• If PCS unavailable, monitor RCP temperatures on 1-RC-TR-1448.

STANDARD: Candidate acknowledges Caution and Notes COMMENTS:

STEP 4:

_______ SAT 1-AP-9.00 - STEP 1 -

• CHECK SEAL INJECTION - FLOW INDICATED

_______ UNSAT STANDARD:

Uses Vertical Board meter and observes Seal Injection flows to all RCPs.

• 1-CH-FI-1130A - A RCP Seal Injection Flow

• 1-CH-FI-1127A - B RCP Seal Injection Flow

• 1-CH-FI-1124A - C RCP Seal Injection Flow EVALUATORS NOTE: The (*) denotes a continuous action step.

COMMENTS:

Page 4 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 5:

_______ SAT 1-AP-9.00 - STEP 2 - CHECK RCS PRESSURE - LESS THAN 2100 PSIG

_______ UNSAT STANDARD:

Determines RCS Pressure is NOT less than 2100 PSIG and goes to Step 4 per Step 2 RNO.

COMMENTS:

STEP 6:

_______ SAT 1-AP-9.00 - STEP 4 - *CHECK RCP SEAL WATER OUTLET TEMPERATURE-LESS THAN 200°F _______ UNSAT

• PCS Point T0181A - RCP A

• PCS Point T0182A - RCP B

• PCS Point T0183A - RCP C STANDARD:

a) Checks PCS Point T0183A - for RCP C less than 200°F.

b) May check the other RCP Seal Water Outlet Temperatures as well.

COMMENTS:

STEP 7:

_______ SAT 1-AP-9.00 - OBSERVES THE NOTE PRIOR TO STEP 5.

NOTE: First, Second, and Third Stage Seal DP is indicated on the PCS, or may _______ UNSAT be determined using Notes on Attachment 1, page 2.

STANDARD: Candidate acknowledges note.

COMMENTS:

Page 5 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 8:

_______ SAT 1-AP-9.00 - Step 5 - *CHECK RCP SEAL STAGES - NOT FAILED

• P across each seal stage - LESS THAN 2000 PSID _______ UNSAT STANDARD:

Checks differential across each seal stage less than 2000 psid on PCS.

COMMENTS:

STEP 9:

_______ SAT 1-AP-9.00 - OBSERVES THE NOTE PRIOR TO STEP 6.

NOTE: Differential pressure of greater than 1440 psid is an indication that one _______ UNSAT seal stage has failed and a second seal stage is degrading. Unit operation with only one failed seal stage is acceptable.

STANDARD: Candidate acknowledges note.

COMMENTS:

STEP 10:

_______ SAT 1-AP-9.00 - STEP 6 - *CHECK RCP SEAL STAGES - LESS THAN ONE SEAL STAGE FAILED. _______ UNSAT

• P across each seal stage - LESS THAN 1440 PSID STANDARD:

Checks differential across each seal stage less than 1440 psid on PCS.

COMMENTS:

Page 6 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 11:

_______ SAT 1-AP-9.00 - OBSERVES THE CAUTION AND NOTES PRIOR TO STEP 7.

• CAUTION: RCPs may be operated without seal water return flow for up to _______ UNSAT 30 minutes.

• NOTES:

• Attachment 3 may be used to check suspect Seal Leakoff flow instrumentation.

• Changes to RCS chemistry, e.g., large dilutions or borations, can affect RCP Seal Leakoff and Number 2 & 3 Seal DP values. Use other instrumentation as necessary to validate changing conditions.

STANDARD: Candidate acknowledges caution and notes.

BOOTH NOTE:

When the operator is reading the CAUTION and NOTES before Step 7, insert TRIGGER 1 to fail the second stage.

EVALUATORS NOTE:

a) At this point the candidate may go one of either two paths:

• Identifies Seal stage #3 is > 2000 PSID and returns to Step 5 RNO (JPM Step 13)

• Continues with step 7 (next JPM step)

COMMENTS:

STEP 12:

_______ SAT 1-AP-9.00 - STEP 7 - CHECK RCP SEAL LEAKOFF - LESS THAN 3.3 GPM.

_______ UNSAT STANDARD: Observes seal leakoff at approximately 4.4 gpm and goes to RNO column.

COMMENTS:

Page 7 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 13: CRITICAL STEP

_______ SAT 1-AP-9.00 - STEP 7 RNO - Do the following:

a) IF flow greater than 4.2 gpm, THEN do the following: _______ UNSAT

1) Trip the Reactor.

2) Initiate 1-E-0, Reactor Trip or Safety Injection.

STANDARD:

a) Informs the Shift Manager of the need to trip the reactor and initiate 1-E-0 b) Depresses a Reactor Trip pushbutton [CRITICAL STEP]

c) Identifies that All Rods on Bottom Light - is LIT, Rx Trip and Bypass Breakers -

OPEN, Neutron Flux Lowering.

d) Manually trips turbine.

e) Checks all Turbine Stop Valves - CLOSED.

f) Isolates the MSR Steam Supply by closing 1-MS-SOV-104.

g) Checks generator output breakers - OPEN h) Checks both AC Emergency Buses - ENERGIZED.

i) Verifies SI is not actuated or required: LHSI Pumps not running A-F-3/4 not LIT and no issues with PZR pressure, CTMT pressure, Steamline differential or High Steam flow.

j) Recommends transition to 1-ES-0.1, Rx Trip Response.

BOOTH NOTE:

EVALUATORS NOTE:

a) Direct the Operator to initiate 1-E-0 when informed of the requirement to trip the reactor.

b) Following completion of immediate actions, inform the candidate that another operator will perform ES-0.1 actions.

COMMENTS:

Page 8 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE STEP 14: CRITICAL STEP

_______ SAT 1-AP-9.00 - STEP 7 RNO (CONTINUED) - Do the following:

3) WHEN approximately five minutes have elapsed since Reactor Trip, _______ UNSAT THEN do the following:

a. IF RCP A affected, THEN close 1-RC-PCV-1455A, Pressurizer Spray Valve From Loop A.

b. IF RCP C affected, THEN close 1-RC-PCV-1455B, Pressurizer Spray Valve From Loop C.

c. Stop the affected RCP(s).

• 1-RC-P-1A

• 1-RC-P-1B

• 1-RC-P-1C

d. GO TO Step 9.

STANDARD:

a) After 5 minutes (time compressed), closes the spray valve by placing 1-RC-PCV-1455B in MANUAL and lowering demand to 0% OR by taking 1-RC 1455B to CLOSE [CRITICAL STEP].

b) Stops 1-RC-P-1C [CRITICAL STEP]

c) GOES TO Step 9 EVALUATORS NOTE/CUE:

• Inform the operator that a five minute time compression has occurred and they are to continue performing 1-AP-9.00. Another operator will perform 1-ES-0.1.

• When the operator continues to Step 9, inform them the JPM is complete.

COMMENTS:

JPM END STOP TIME: ______________

NOTES:

Page 9 of 11

Surry 2021-301 RESPOND TO RCP SEAL FAILURE Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• ARP 1C-C4, RCP 1C SEAL LEAKOFF HI FLOW, has been received.

Initiating Cues

• You are to perform ARP 1C-C4.

• Another Operator will monitor the rest of the plant

• When you finish the actions necessary to accomplish this, please inform me.

Page 10 of 11

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• ARP 1C-C4, RCP 1C SEAL LEAKOFF HI FLOW, has been received.

Initiating Cues

• You are to perform ARP 1C-C4.

• Another Operator will monitor the rest of the plant.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 Establish L/D Following SI U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure EPE.E02.EK3.3 (3.9/3.9)

Alternate Path Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title RE-ESTABLISH NORMAL LETDOWN FOLLOWING SI K/A: EPE.E02.EK3.3, Manipulations of controls required to obtain desires operating results during abnormal, and emergency situations. 3.9 / 3/9 Applicability Validated Time Actual Time RO/SRO(I)/SRO(U) 21 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Places 1-CH-HCV-1389 to the PDTT position.

• Opens 1-CH-HCV-1201.

• Opens either 1-RC-HCV-1557A, or B, or C Loop Drain valves.

• Opens 1-CH-HCV-1137.

• Places 1-CH-HCV-1389 to the VCT position.

Procedures

• 1-ES-1.1, SI Termination, Rev. 52.

• 1-OP-CH-006, Shifting or Increasing/Decreasing Letdown Flow, Rev.22.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 13

Surry 2021-301 Establish L/D Following SI Simulator Setup Reset to IC 363. OR Call up 100% power IC and initialize.

Run through the following steps:

Initiate SI.

Perform E-0 and attachment 1 Reduce AFW flow to 200 gpm to each SG Transition to ES-1.1 and perform it through Step 14.

Insert the following overrides:

o CHFC122C_RAISE, Override to OFF, INSERT o CHFC122C_AUTO, Override to OFF, INSERT Close 1-CH-LCV-1460A & B.

Open 1-CC-TV-109B.

Turn ON all pressurizer heaters.

Press Green Pushbutton on 1-DG-TV-108A/B and pump down the PDTT until pump secures.

Set seal injection at 8 gpm.

Allow simulator until SR energize, place in freeze and snap until ready to run JPM.

Page 2 of 13

Surry 2021-301 Establish L/D Following SI PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME_______

STEP 1:

_______ SAT 1-ES-1.1 - STEP 15 ESTABLISH LETDOWN:

_______ UNSAT a) Adjust CHG line flow to establish greater than 40 gpm STANDARD:

a. Candidate attempts to raise charging flow and identifies that the charging flow controller will not respond. This is the ALTERNATE PATH start.

b. Goes to Step 15 RNO, Establish excess letdown IAW 1-OP-CH-006, SHIFTING OR INCREASING/DECREASING LETDOWN FLOW.

COMMENTS:

• Provide copy of 1-OP-CH-006 to applicant after the applicant identifies this procedure.

STEP 2:

_______ SAT 1-OP-CH-006 - PRECAUTIONS AND LIMITATIONS.

_______ UNSAT STANDARD:

(a) Reviews initial conditions, precautions and limitations.

(b) Determines Section 5.8 (Placing Excess Letdown in Service with Normal Letdown Isolated) is to be used.

COMMENTS:

Page 3 of 13

Surry 2021-301 Establish L/D Following SI STEP 3:

_______ SAT 1-OP-CH-006 - STEP 5.8.1 Close or check closed the following:

• 1-CH-LCV-1460A, LETDOWN LINE ISOL _______ UNSAT

• 1-CH-LCV-1460B, LETDOWN LINE ISOL STANDARD:

a) Candidate checks closed 1-CH-LCV-1460A.

COMMENTS:

STEP 4:

_______ SAT 1-OP-CH-006 - STEP 5.8.2 Check all of the following Loop Drain header isolation valves are closed. _______ UNSAT

• 1-RC-HCV-1557A, LOOP A DRAIN

• 1-RC-HCV-1557B, LOOP B DRAIN

• 1-RC-HCV-1557C, LOOP C DRAIN STANDARD:

Candidate verifies all listed valves are CLOSED COMMENTS:

STEP 5:

_______ SAT 1-OP-CH-006 - STEP 5.8.3 Check 1-CH-HCV-1201, EXCESS LETDOWN HX ISOL, valve is closed. _______ UNSAT STANDARD:

Candidate verifies 1-CH-HCV-1201 is CLOSED COMMENTS:

STEP 6:

_______ SAT 1-OP-CH-006 - STEP 5.8.4 Check 1-CH-HCV-1137, EXCESS LETDOWN FLOW, setpoint is zero. _______ UNSAT STANDARD:

Candidate verifies 1-CH-HCV-1137 demand is at ZERO.

COMMENTS:

Page 4 of 13

Surry 2021-301 Establish L/D Following SI STEP 7:

_______ SAT 1-OP-CH-006 - STEP 5.8.5 Check 1-CH-HCV-1389, EXCESS LETDOWN DIVERT, valve is in the VCT position. _______ UNSAT STANDARD:

Candidate verifies 1-CH-HCV-1389 is in the VCT position.

COMMENTS:

STEP 8:

_______ SAT 1-OP-CH-006 - STEP 5.8.6 Check open or open 1-CH-MOV-1381, RCP SEAL RETURN.

_______ UNSAT STANDARD:

Candidate verifies 1-CH-MOV-1381 open.

COMMENTS:

Step 9

_______ SAT 1-OP-CH-006 - STEP 5.8.7 Check running at least one CC pump.

_______ UNSAT STANDARD:

Candidate verifies 1-CC-P-1A in service (RED bkr postion light and/or pump amps)

COMMENTS:

Step 10

_______ SAT 1-OP-CH-006 - STEP 5.8.8 Check 1-CC-FI-109, LETDOWN HX OUTLT FLOW, is indicating approximately 140 gpm. _______ UNSAT STANDARD:

Candidate verifies required flow as indicated on 1-CC-FI-109.

COMMENTS:

Page 5 of 13

Surry 2021-301 Establish L/D Following SI Step 11

_______ SAT 1-OP-CH-006 - NOTE prior to step 5.8.9 - The reset switch located on the RHR flats must be held in the open position until 1-CC-HCV-108, Excess Ldn HX CC Outlet _______ UNSAT Hand Cont Valve, opens fully.

STANDARD:

Candidate acknowledges NOTE COMMENTS:

Step 12

_______ SAT 1-OP-CH-006 - STEP 5.8.9 IF flow NOT indicated on 1-CC-FI-109, THEN locally reset and open 1-CC-HCV-108. Otherwise, enter N/A. _______ UNSAT STANDARD:

Candidate enters N/A for this step as flow is established.

COMMENTS:

Step 13

_______ SAT 1-OP-CH-006 - STEP 5.8.10 Check 1-CC-TI-108, LETDOWN HX OUTLT TEMP, is indicating ambient. _______ UNSAT STANDARD:

Candidate verifies ambient temperature indication on 1-CC-TI-108.

COMMENTS:

Step 14

_______ SAT 1-OP-CH-006 - STEP 5.8.11 Check 1-CH-PI-1138, EXCESS LETDOWN HX OUTLET PRESS, is indicating approximately 50 psig. _______ UNSAT STANDARD:

Candidate verifies pressure indication on 1-CH-PI-1138 approximately 50 psig.

COMMENTS:

Page 6 of 13

Surry 2021-301 Establish L/D Following SI Step 15

_______ SAT 1-OP-CH-006 - STEP 5.8.12 Check 1-CH-TI-1139, EXCESS LETDOWN HX OUTLET TEMP, is indicating ambient. _______ UNSAT STANDARD:

Candidate verifies ambient temperature indication on 1-CH-TI-1139.

COMMENTS:

Step 16

_______ SAT 1-OP-CH-006 - NOTES prior to step 5.8.13

• The first 50 gallons of Excess Letdown flow should be directed to the _______ UNSAT Primary Drain Transfer Tank (PDTT) so that the Excess Letdown flow is not returned to the RCS.

• PCS points Y4020A and U0911 for PDTT level can be found on the Pressurizer & Primary Relief Tank screen.

STANDARD:

Candidate acknowledges NOTES COMMENTS:

Step 17 CRITICAL STEP

_______ SAT 1-OP-CH-006 - STEP 5.8.13 Place 1-CH-HCV-1389, EXCESS LETDOWN DIVERT, in the PDTT position to flush the Excess Letdown Heat Exchanger. _______ UNSAT STANDARD:

Candidate places 1-CH-HCV-1389 in the PDTT position [CRITICAL STEP]

COMMENTS:

Step 18

_______ SAT 1-OP-CH-006 - STEP 5.8.14 Check 1-CH-PI-1138, EXCESS LETDOWN HX OUTLET PRESS, indicates approximately 10 psig. _______ UNSAT STANDARD:

Candidate verifies approximately 10 psig indicated on 1-CH-PI-1138.

COMMENTS:

Page 7 of 13

Surry 2021-301 Establish L/D Following SI Step 19 CRITICAL STEP

_______ SAT 1-OP-CH-006 - STEP 5.8.15 Open 1-CH-HCV-1201, EXCESS LETDOWN HX ISOL.

_______ UNSAT STANDARD:

Candidate opens 1-CH-HCV-1201 [CRITICAL STEP]

COMMENTS:

Step 20

_______ SAT 1-OP-CH-006 - NOTE prior to step 5.8.16 - Letdown flow from the loops is not accounted for in the calorimetric while on Excess Letdown. _______ UNSAT STANDARD:

Candidate acknowledges NOTE EVALUATORS NOTE:

Reactor is tripped so calorimetric is not utilized at this time.

COMMENTS:

Step 21

_______ SAT 1-OP-CH-006 - STEP 5.8.16 IF a calorimetric is being performed, THEN check initiated or initiate 1-OPT-RX-007, Shift Average Power Calculation. _______ UNSAT STANDARD:

Candidate enters N/A for this step.

COMMENTS:

Page 8 of 13

Surry 2021-301 Establish L/D Following SI Step 22

_______ SAT 1-OP-CH-006 - CAUTIONS prior to step 5.8.17:

• There are several potential leak points downstream of the loop drain _______ UNSAT valves.

• Only one loop drain valve may be open above 200°F, to prevent the possibility of bypassing SI flow to the two intact loops in a Design Basis Accident, due to loop cross-connect through the drain header. (Ref. 2.3.6)

STANDARD:

Candidate acknowledges CAUTIONS.

EVALUATORS NOTE:

Candidate may ask for assistance in monitoring for RCS leakage. If asked, report that another operator will perform requested monitoring.

COMMENTS:

Step 23 CRITICAL STEP

_______ SAT 1-OP-CH-006 - STEP 5.8.17 Open one of the following Loop Drain header isolation valves.

() _______ UNSAT

• 1-RC-HCV-1557A, LOOP A DRAIN

• 1-RC-HCV-1557B, LOOP B DRAIN

• 1-RC-HCV-1557C, LOOP C DRAIN STANDARD:

Candidate opens ONE of the listed valves [CRITICAL STEP]

EVALUATORS CUE:

If asked: There is no preference to the valve chosen.

COMMENTS:

Step 24

_______ SAT 1-OP-CH-006 - NOTE prior to step 5.8.18:

• An Excess Letdown flow rate can be calculated by using 1-DG-LI-107, _______ UNSAT PDTT LEVEL (2.5% level change is approximately 15 gallons), and/or change in Charging Flow.

• Attachment 1 may be used to lower Pressurizer Level if required.

STANDARD:

Candidate acknowledges NOTES.

COMMENTS:

Page 9 of 13

Surry 2021-301 Establish L/D Following SI Step 25 CRITICAL STEP

_______ SAT 1-OP-CH-006 - STEP 5.8.18 Slowly open 1-CH-HCV-1137, EXCESS LETDOWN FLOW, until Pressurizer level is stable or lowering. _______ UNSAT STANDARD:

Candidate opens 1-CH-HCV-1137 [CRITICAL STEP]

COMMENTS:

Step 26

_______ SAT 1-OP-CH-006 - STEP 5.8.19 Check 1-CC-TI-108, EXCESS LETDOWN HX OUTLT TEMP, indicates less than 150°F. _______ UNSAT STANDARD:

Candidate verifies 1-CC-TI-108 indicating less than 150°F COMMENTS:

Step 27

_______ SAT 1-OP-CH-006 - STEP 5.8.20 Check 1-CH-TI-1139, EXCESS LETDOWN HX OUTLET TEMP, indicates less than 195°F. _______ UNSAT STANDARD:

Candidate verifies 1-CH-TI-1139 indicating less than 195°F COMMENTS:

Page 10 of 13

Surry 2021-301 Establish L/D Following SI Step 28

_______ SAT 1-OP-CH-006 - NOTES prior to step 5.8.21:

• An RCS temperature change should be anticipated when placing Excess _______ UNSAT Letdown in service. (Ref. 2.4.3)

• Reactor Coolant Pump seal leakoff flow may become erratic when rapid changes to seal injection and seal leakoff occur. Providing a slow, steady transition when affecting charging or seal leakoff flows should keep seal leakoff flow steady. If seal leakoff flow becomes erratic, seal injection flow should be stabilized and management consulted to determine course of action. (Ref. 2.4.4)

STANDARD:

Candidate acknowledges NOTES COMMENTS:

Step 29 CRITICAL STEP

_______ SAT 1-OP-CH-006 - STEP 5.8.21 WHEN the PDTT level has risen at least 10% as indicated on 1-DG-LI-107, THEN transfer flow from the PDTT to the VCT by placing 1-CH- _______ UNSAT HCV-1389, EXCESS LETDOWN DIVERT, to the VCT position.

STANDARD:

Candidate places 1-CH-HCV-1389 to the VCT position [CRITICAL STEP]

EVALUATORS NOTE:

• Task may be ended at this point as there are only checks remaining in this procedure.

COMMENTS:

JPM END STOP TIME:

Page 11 of 13

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Plant was initially at 100% power with all systems operating normal and in automatic.

• The crew is currently recovering from a spurious SI initiation.

• 1-E-0, Reactor Trip or Safety Injection, was performed and the team transitioned to 1-ES-1.1.

• 1-ES-1.1, SI Termination has been completed up to Step 15.

• Pressurizer level is 60% and slowly rising.

Initiating Cues

• You are to re-establish letdown by performing step 15 of 1-ES-1.1, and restore Pressurizer level to 22%.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Plant was initially at 100% power with all systems operating normal and in automatic.

• The crew is currently recovering from a spurious SI initiation.

• 1-E-0, Reactor Trip or Safety Injection, was performed and the team transitioned to 1-ES-1.1.

• 1-ES-1.1, SI Termination has been completed up to Step 15.

• Pressurizer level is 60% and slowly rising.

Initiating Cues

• You are to re-establish letdown by performing step 15 of 1-ES-1.1, and restore Pressurizer level to 22%..

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 SWAP CN PUMPS U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title RESPOND TO A CONDENSATE PUMP AND REACTOR TRIP (ALTERNATE PATH)

K/A:

• 056A2.04, Loss of Condensate Pumps (2.6,2.8)

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 6 Minutes _____ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Starts Condensate pump, 1-CN-P-1B.

• Secures Condensate pump, 1-CN-P-1C.

• Manually trips the reactor prior to two SGs reaching 12% WR.

Procedures

• 1-OP-CN-001 - CONDENSATE SYSTEM OPERATION

• 1-AP-21.00 - LOSS OF MAIN FEEDWATER FLOW Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry 2021-301 SWAP CN PUMPS Simulator Setup Reset to IC 365, OR Call up 100% power IC and initialize.

Ensure 1-CN-P-1B is secured in AUTO Insert the following Malfunctions:

o Malfunctions, RD18 (FAILURE OF AUTO TRIP TO SCRAM RX), Insert.

o Malfunction CN0103 (Main CN Pump CN-P-1C Trips: Ovr-Current), Event 3, Insert o Malfunction CN1403 (CN Pump CN-P-1C Discharge Check Valve Failure), Event 3, Insert o Malfunction SI1301 (AMSAC Train A Fails to Activate), Insert o Malfunction SI1302 (AMSAC Train A Fails to Activate), Insert Create Event 3:

o Events (on the toolbar) o Select Event 003 o Edit Event o Event Code (the l below is the Operators just to the right of the & button)

CNP1C_STOP l CNP1C_LOCK o OK PRIOR TO JPM:

Pre-brief the applicant for swapping Condensate pumps per 1-OP-CN-001, Section 5.4.

Page 2 of 9

Surry 2021-301 SWAP CN PUMPS PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME_______:

STEP 1:

_______ SAT 1-OP-CN-001 - Initial Conditions & Precautions and Limitations.

_______ UNSAT STANDARD:

a) Reviews Initial Conditions b) Reviews Precautions and Limitations EVALUATORS NOTE (If Asked):

• IC 3.2 - Makeup water is available to fill the condenser

• P&L 4.13 - adequate CP demineralizers are in service to support the pump swap COMMENTS:

STEP 2:

_______ SAT 1-OP-CN-001 - STEP 5.4.1 Check the following conditions exist for condensate pump to be started. _______ UNSAT

• Seal water in service.

• Bearing Cooling water flow indicated to pump and motor.

• Oil level in reservoir sight glass is mid-range.(one of six motors may have two sight glasses)

STANDARD:

Refers to Candidate Brief Sheet and determines these verifications are complete.

EVALUATORS NOTE (If Asked):

• All required conditions are MET COMMENTS:

Page 3 of 9

Surry 2021-301 SWAP CN PUMPS STEP 3:

_______ SAT NOTE prior to step 5.4.2 - When Condensate Pump is started, HP Heater Drain Pump flow will be affected. The system should be monitored for proper _______ UNSAT response.

STANDARD:

Candidate acknowledges the NOTE.

COMMENTS:

STEP 4:

_______ SAT 1-OP-CN-001 - STEP 5.4.2 Check CALCALC 30 Minute Avg Power is less than or equal to 99.95%. IF CALCALC non-functional, THEN check Reactor Power is less _______ UNSAT than or equal to 100%. IF starting a Condensate Pump due to a secondary transient, THEN enter N/A.

STANDARD:

Trainee verifies CALCALC 30 minute average power <99.95% on PCS.

COMMENTS:

STEP 5: CRITICAL STEP

_______ SAT 1-OP-CN-001 - STEP 5.4.3 Start condensate pump selected to be started. ()

• 1-CN-P-1B _______ UNSAT STANDARD:

Candidate starts 1-CN-P-1B [CRITICAL STEP].

COMMENTS:

Page 4 of 9

Surry 2021-301 SWAP CN PUMPS STEP 6:

_______ SAT 1-OP-CN-001 - STEP 5.4.4 Check condensate pump discharge pressure, indicated on the local discharge pressure gauge, is between 550 psig and 650 psig, and LI- _______ UNSAT CN-103, CNDSR HOTWELL LVL, is stable.

STANDARD:

Contacts field operator to verify proper discharge pressure indication.

BOOTH NOTE:

• Local discharge pressure indicates 595 psig COMMENTS:

STEP 7: CRITICAL STEP

_______ SAT 1-OP-CN-001 - STEP 5.4.5 - Stop condensate pump to be removed from service and place control switch in AUTO or PTL. () _______ UNSAT

• 1-CN-P-1C STANDARD:

a) Secures 1-CN-P-1C [CRITICAL STEP].

b) Identifies significant drop in Main Feedwater Flow c) Candidate at this point can either elect to:

• Continue in 1-OP-CN-001

• Transition to 1-AP-21.00. (AP-21 actions commence at step 10)

• Go to 1-E-0 (E-0 actions commence at step 12).

EVALUATORS NOTE/CUE:

• If asked: it is desired to leave 1-CN-P-1C in AUTO.

• With no operator action, the first reactor trip signal is reached at 1:20.

• This step commences the alternate path of this task (check valve failure).

COMMENTS:

Page 5 of 9

Surry 2021-301 SWAP CN PUMPS STEP 8:

_______ SAT NOTE prior to step 5.4.6 - A stuck open check valve could cause the condensate pump to rotate backwards and result in a loss of feed. Do not attempt to _______ UNSAT start a pump that is rotating backwards. (Reference 2.4.12)

STANDARD:

a) Candidate acknowledges note b) Candidate may contact the turbine building operator to determine status of 1-CN-P-1C shaft rotation.

c) IF candidate contacts the turbine building operator and identifies shaft rotation as a failed check valve, candidate may transition to AP-21.00 or 1-E-0.

BOOTH NOTE:

• If contacted, report that the shaft is turning on 1-CN-P-1C but direction cannot be determined.

COMMENTS:

STEP 9:

_______ SAT 1-OP-CN-001 - STEP 5.4.6 Check Main Feed Pump suction pressure is normal. IF pressure NOT normal, THEN perform the following. IF pressure normal, THEN enter _______ UNSAT N/A.

a. Start or check started the pump stopped in Step 5.4.5. ()

• 1-CN-P-1C STANDARD:

a) Candidate determines that pump should not be started based on previous NOTE.

b) Candidate may transition to AP-21.00 or 1-E-0.

COMMENTS:

STEP 10:

_______ SAT 1-AP-21.00 - [STEP 1] CHECK MAIN FEED PUMP STATUS:

a) Check Reactor Power - GREATER THAN 80% _______ UNSAT b) Check Main Feed Pumps - TWO RUNNING STANDARD:

a) Verifies reactor power >80%

b) Identifies two main feed pumps in service COMMENTS:

Page 6 of 9

Surry 2021-301 SWAP CN PUMPS STEP 11:

_______ SAT 1-AP-21.00 - [STEP 2] START AN ADDITIONAL CONDENSATE PUMP

_______ UNSAT STANDARD:

a) If Candidate identifies the discharge valve stuck open he should NOT attempt to start 1-CN-P-1C.

b) If Candidate does NOT identify the failed discharge check valve he may attempt to start 1-CN-P-1C, BUT it wont start.

c) Candidate recognizes that reactor trip is imminent and goes to 1-E-0.

COMMENTS:

STEP 12: CRITICAL STEP

_______ SAT 1-E [STEP 1] - CHECK REACTOR TRIP a) Manually trip reactor _______ UNSAT b) Check the following:

• All rods on bottom light - LIT

• Reactor trip and bypass breakers - OPEN

• Neutron flux - LOWERING STANDARD:

a) Candidate depresses a reactor trip pushbutton prior to two SGs reaching 12%WR [Critical Step].

EVALUATORS NOTE:

• Once the reactor has been manually tripped, inform the candidate that the task is complete.

COMMENTS:

TASK COMPLETE STOP TIME: ______________

NOTES:

Page 7 of 9

Surry 2021-301 SWAP CN PUMPS Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit 1 is at 100% with all systems in AUTO.

• Maintenance is scheduled for 1-CN-P-1C which is currently in service.

Initiating Cues

• You are to start 1-CN-P-1B and secure 1-CN-P-1C in accordance with 1-OP-CN-001 section 5.4. 1-CN-P-1C should be left in AUTO after it is secured.

• The following has been verified on 1-CN-P-1B

• Seal water has been verified in service

• BC water flow is indicated to pump and motor

• Oil level in reservoir sight glass is mid-range

• An operator has been briefed and stationed in the turbine building near the condensate pumps.

• When you finish the actions necessary to accomplish this, please inform me.

Page 8 of 9

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 is at 100% with all systems in AUTO.

• Maintenance is scheduled for 1-CN-P-1C which is currently in service.

Initiating Cues

• You are to start 1-CN-P-1B and secure 1-CN-P-1C in accordance with 1-OP-CN-001 section 5.4. 1-CN-P-1C should be left in AUTO after it is secured.

• The following has been verified on 1-CN-P-1B

• Seal water has been verified in service

• BC water flow is indicated to pump and motor

• Oil level in reservoir sight glass is mid-range

• An operator has been briefed and stationed in the turbine building near the condensate pumps.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure WE14EA1.3 Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title PERFORM 1-E-0 ATTACHMENT 4 K/A: WE14EA1.3 Ability to operate and/ or monitor the following as they apply to the (High Containment Pressure): Desired operating results during abnormal and emergency situations. (3.3 / 3.8)

Applicability Validated Time Actual Time RO/SRO 14 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Closes 1-RM-TV-100B.

• Closes 1-IA-TV-101A.

• Secures Fan 1-VS-F-1B.

• Opens 1-SW-MOV-104B.

• Opens 1-SW-MOV-105C.

• Closes 1-CW-MOV-100B.

• Closes 1-CW-MOV-106C.

Procedures

• 1-E-0, Attachment 4 - CLS Component Verification (Rev 78)

Tools and Equipment Safety Considerations

• None

• None Page 1 of 8

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 Simulator Setup Reset to IC 366. OR Call up 100% power IC and initialize.

Enter Malfunctions:

CA03, Disable IA-TV-101A Auto Closure; Active EL01, Loss of Offsite Power, Trigger 1 RC0101, RCS Cold Leg A Pipe Rupture; final value = 50, Trigger 1 RM1002, Disable RM-TV-100B Auto Close; Active SW05, Disable SW-MOV-104B AUTO Open, INSERT SW10, Disable SW-MOV-105C AUTO Open, INSERT FP0301, FPS FACP07 ALARM HORN FAILURE, INSERT FP0302, FPS PC SPEAKER FAILURE, INSERT VS0802, Disable Cntmnt Recirc Fan VS-F-1B Auto Trip, INSERT CW18, Disable CW-MOV-100B AUTO Closed, INSERT CW23, Disable CW-MOV-106C AUTO Closed, INSERT Place Simulator in Run. Insert Trigger 1.

Throttle AFW to 200 gpm per SG Perform 1-E-0 actions up to Attachment 1, Step 8e.

Place Simulator in Freeze until JPM performance.

Page 2 of 8

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME: ________

STEP 1: CRITICAL STEP

_______ SAT Check Phase II and Phase III Containment Isolation Valves are closed.

_______ UNSAT STANDARD:

a) Locates to the Vertical Board.

b) Checks Phase II and Phase III Containment Isolation Valves Closed / Green lights lit.

c) For valves out of position, closes the valves:

• 1-RM-TV-100B [CRITICAL STEP]

• 1-IA-TV-101A [CRITICAL STEP]

d) Applicant annotates Attachment. Applicant may also place pink magnets on valves out of position.

EVALUATORS NOTE:

If asked: Acknowledge components out of position. Tell Applicant to continue performing attachment.

COMMENTS:

STEP 2: CRITICAL STEP

_______ SAT Checks Containment Air Recirculation Fans tripped.

a) Checks Containment Air Recirculation Fans OFF (green & amber lights lit): _______ UNSAT

• 1-VS-F-1A

• 1-VS-F-1B STANDARD:

a) Locates to the Unit 1 Ventilation Panel.

b) Checks Containment Air Recirculation Fans OFF (green & amber lights lit) c) Identifies 1-VS-F-1B in service and secures the fan by either placing fan in PTL or STOP. [CRITICAL STEP]

COMMENTS:

Page 3 of 8

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 STEP 3: CRITICAL STEP

_______ SAT Checks Recirculation Spray Service Water in operation by verifying the following valves OPEN: _______ UNSAT

• 1-SW-MOV-103A-D

• 1-SW-MOV-104A-D

• 1-SW-MOV-105A-D STANDARD:

a) Locates to the Bench Board.

b) Checks SW MOVs for all RSHXs Open / Red Lights lit:

• Identifies 1-SW-MOV-104B closed and opens the valve [CRITICAL STEP]

• Identifies 1-SW-MOV-105C closed and opens the valve [CRITICAL STEP]

c) Checks SW flow by observing SW flow through 1-SW-FI-106A through-106D between 6,000 and 12,500 gpm.

COMMENTS:

STEP 4:

_______ SAT Checks RSHX SW RM Sample Pumps running.

_______ UNSAT STANDARD:

a) Locates to Radiation Monitoring Panel.

b) Checks RSHX SW RM Sample Pumps running (time delayed - 1 minute). Red lights lit.

EVALUATORS NOTE:

COMMENTS:

Page 4 of 8

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 STEP 5:

_______ SAT Checks RSHX RM Pump No-Flow annunciators clear.

_______ UNSAT STANDARD:

a) Locates to Vertical Board.

b) Verifies all RSHX SW RM Pump alarms clear.

c) Acknowledges NOTE that CLS must be reset to allow RM pumps to be secured from MCR.

COMMENTS:

STEP 6:

_______ SAT Checks Containment Spray and Recirc Spray Systems valve positions.

_______ UNSAT STANDARD:

a) Locates to Bench Board.

b) Checks CS and RS System Valves Open / Red lights lit.

COMMENTS:

STEP 7: CRITICAL STEP

_______ SAT Checks Circulating and Service Water Systems isolation due to Hi-Hi CLS with LOOP.

_______ UNSAT STANDARD:

a) Recalls from Initial Conditions that a Loss of Offsite Power has also occurred.

b) Checks CW isolation valves for Main Condenser Closed / Green lights lit.

c) Identifies that 1-CW-MOV-100B did not auto-close and MANUALLY CLOSES the valve [CRITICAL STEP].

d) Identifies that 1-CW-MOV-106C did not auto-close and MANUALLY CLOSES the valve [CRITICAL STEP].

e) Checks SW isolation valves for BC and CC Heat Exchangers Closed / Green lights lit.

EVALUATORS NOTE:

COMMENTS:

Page 5 of 8

Surry 2021-301 PERFORM E-0 ATTACHMENT 4 STEP 8:

Notify Nuclear Shift Manager (Evaluator) Status of Task. _______ SAT Applicant should report completion of task. Applicant should also notify the SM _______ UNSAT (Evaluator) of components found out of position and actions taken.

COMMENTS:

JPM END STOP TIME: _______

Page 6 of 8

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• A LBLOCA has occurred on Unit 1 concurrent with a loss of offsite power.

• The Operating Team is currently performing 1-E-1, Loss of Reactor or Secondary Coolant.

Initiating Cues

• You are to perform 1-E-0, Attachment 4 - CLS Component Verification.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A LBLOCA has occurred on Unit 1 concurrent with a loss of offsite power.

• The Operating Team is currently performing 1-E-1, Loss of Reactor or Secondary Coolant.

Initiating Cues

• You are to perform 1-E-0, Attachment 4 - CLS Component Verification.

Surry 2021-301 Load AAC DG on 1J Bus U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure 056AK3.02 (4.4 / 4.7)

TIME CRITICAL Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title LOAD THE AAC DIESEL ON THE UNIT ONE J BUS K/A:056 AK3.02, Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power.

Applicability Time Critical Actual Time RO 10 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Place 0-AAC-43-15J8 in AAC position.

• Place the following components in PTL; 1-VS-F-1B, 1-SI-P-1B, Pzr Heater Group A, 1-CH-P-1B, 1-FW-P-3B, 1-RS-P-2B, 1-RS-P-1B, 1-CS-P-1B.

• Resets AMSAC by taking the AMSAC BYPASS switch to BYPASS.

• Rotates synch switch for 15J8 to the ON position.

• Closes breaker 15J8 by rotating 15J8 breaker HS clockwise to the CLOSE position for 5 seconds.

Procedures

• 0-AP-17.06, AAC Diesel Generator - Emergency Operations (Rev 31)

Tools and Equipment Safety Considerations

• None

• None Page 1 of 11

Surry 2021-301 Load AAC DG on 1J Bus Simulator Setup

• Call up IC # 364. OR 100% IC and initialize.

• Insert the following MALFUNCTIONS:

o ED0201, EDG 1 AIR START SYSTEM FAILURE, INSERT o ED0203, EDG 3 AIR START SYSTEM FAILURE, INSERT o EL01, LOSS OF OFFSITE POWER, Delay 1 sec, INSERT o FP0301, FPS FACP07 ALARM HORN FAILURE, INSERT o FP0302, FPS PC SPEAKER FAILURE, INSERT

• Using InSight, set SA_223 to 1.

• Place the simulator in run, implement all malfunctions, and perform the ECA-0.0 to Step 5c RNO step 1.

• Freeze the simulator and save this condition.

NOTES:

Time Critical Operator Action Background 0-DRP-049 lists event E11 operator action to Align the AAC Diesel to respective emergency bus with an action time of 10 minutes in accordance with ECA-0.0 and 0-AP-17.06. The DRP references training job aid 017, which contains the following for Plant Conditions:

• Loss of offsite power has occurred results in a loss of emergency busses. - OR - Offsite power is available and a loss of emergency busses has occurred.

• EDGs fail to auto start or auto load resulting in a loss of all emergency AC power.

• AAC DG is available to manually start and load.

These conditions are replicated in this JPM.

Page 2 of 11

Surry 2021-301 Load AAC DG on 1J Bus PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are Bolded.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME:

STEP 1:

_______ SAT 0-AP-17.06 - NOTES prior to step 1

• A one-line diagram showing the AAC Electrical distribution is provided in _______ UNSAT Attachment 1.

• The AAC Diesel Generator should automatically start when Transfer Buses D and F OR E and F are deenergized.

STANDARD:

Candidate acknowledges NOTES EVALUATORS NOTE:

JPM is TIME CRITICAL. 0-DRP-049, Time Critical Operator Actions, E11, allows 10 minutes to Align the AAC Diesel to respective emergency bus. Time starts when Simulator placed in RUN; Time Stops when breaker 15J8 closed and 1J bus energized.

If asked: Unit 2 Transfer buses are de-energized, #2 EDG is supplying 2H emergency bus.

COMMENTS:

STEP 2:

_______ SAT 0-AP-17.06 - STEP 1 - CHECK EMERGENCY BUSES 1J and 2H - EITHER OR BOTH DE-ENERGIZED. _______ UNSAT STANDARD:

a) Identifies 1J Bus is de-energized by observing zero (0) volts indicated on 1J bus.

b) Identifies from instructions or Unit 2 inquiry that 2H energized.

EVALUATORS NOTE:

If asked: "2H" Bus is energized from the #2 EDG.

COMMENTS:

STEP 3:

Page 3 of 11

Surry 2021-301 Load AAC DG on 1J Bus

_______ SAT 0-AP-17.06 - CAUTION prior to step 2

_______ UNSAT STANDARD:

Candidate acknowledges CAUTION.

EVALUATORS NOTE:

If asked: Temporary Air Compressor is in service COMMENTS:

STEP 4:

_______ SAT 0-AP-17.06 - STEP 2 - GO TO APPROPRIATE STEP BASED ON DESIRED USE OF THE AAC DIESEL GENERATOR. _______ UNSAT STANDARD:

a) Identifies 1J to be re-energized from the AAC Diesel from initial task briefing or Evaluator query.

EVALUATORS NOTE:

If asked: Load the AAC on 1J Bus.

COMMENTS:

STEP 5:

_______ SAT 0-AP-17.06 - STEP 3 - CHECK AAC DIESEL GENERATOR - AVAILABLE AND RUNNING.

• Annunciator 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1D - LIT _______ UNSAT AND

• Annunciator 0-WD-D1, AAC GENERATOR TRIP - NOT LIT STANDARD:

a) Observes 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1D, is lit.

b) Observes 0-WD-D1, AAC GENERATOR TRIP, is not lit.

COMMENTS:

Page 4 of 11

Surry 2021-301 Load AAC DG on 1J Bus STEP 6:

_______ SAT 0-AP-17.06 - CAUTION AND NOTE PRIOR TO STEP 4.

• CAUTION: An overcurrent fault on 15D1 will prevent 0-AAC-BKR-05L3 _______ UNSAT from closing.

• NOTE: Annunciator 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1D, should go out when 0-AAC-BKR-05L3 closes.

STANDARD:

Candidate acknowledges CAUTION and NOTE COMMENTS:

STEP 7: CRITICAL STEP

_______ SAT 0-AP-17.06 - STEP 4 - ENERGIZE TRANSFER BUS D BY CLOSING 0-AAC-BKR-05L3.

a) At Unit 1 EDG 3 Control Panel, place Transfer Switch _______ UNSAT NORMAL/AAC, 0-AAC-43-15J8, in AAC position b) Check Annunciator 1K-D3, BUS 1D UNDERVOLT - NOT LIT STANDARD:

a) Candidate places 0-AAC-43-15J8, in AAC position [CRITICAL STEP]

b) Check Annunciator 1K-D3, BUS 1D UNDERVOLT - NOT LIT.

c) Candidate may check annunciator 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1D extinguished (from NOTE prior to step).

COMMENTS:

Page 5 of 11

Surry 2021-301 Load AAC DG on 1J Bus STEP 8: CRITICAL STEP

_______ SAT 0-AP-17.06 - STEP 5a - CHECK OR PLACE THE FOLLOWING LOADS IN PTL.

a) Put the following switches in PTL / LOCKOUT: _______ UNSAT

• 1-VS-F-1B (14J7)

• 1-SI-P-1B (14J3)

• 1-RS-P-2B (14J8)

• 1-RS-P-1B (14J4)

• 1-CS-P-1B (14J5)

• PRZR Heater Group A (14J9)

• 1-CH-P-1B (15J5)

• 1-CH-P-1C (15J2, ALT)

• 1-FW-P-3B (15J4)

• 1-CC-P-1B (15J10)

• 1-VS-F-58B, if powered from Alternate source, 14J13 STANDARD:

• Candidate places the above components in PTL / LOCKOUT with the exception of 1-VS-F-58B which is not powered from the Alternate Source

• The following components MUST be in PTL: [CRITICAL STEP]

o 1-VS-F-1B o 1-SI-P-1B o PRZR Heater Group A (14J9) o 1-CH-P-1B (15J5) o 1-FW-P-3B (15J4) o 1-RS-P-1B o 1-RS-P-2B o 1-CS-P-1B EVALUATORS NOTE:

• Loads not listed as CRITICAL STEP are components that are already deenergized or aligned correctly.

• Placing 1-VS-F-58B in PTL does not constitute a critical task since neither unit has initiated SI (which would result in a need for the fan).

COMMENTS:

Page 6 of 11

Surry 2021-301 Load AAC DG on 1J Bus STEP 9:

_______ SAT 0-AP-17.06 - STEP 5b - Check breakers open by locally checking breaker position indicating lights - RED LIGHTS NOT LIT _______ UNSAT

• 1-CS-P-1B (1-EP-BKR-14J5)

• 1-RS-P-1B (1-EP-BKR-14J4)

STANDARD: Candidate verifies RED LIGHTS are not lit on listed components.

COMMENTS:

STEP 10:

_______ SAT 0-AP-17.06 - STEP 5c - Check breakers open by locally checking breaker position indicating lights - RED LIGHTS NOT LIT _______ UNSAT

• 1-FW-P-3B (1-EP-BKR-15J4)

STANDARD: Candidate identifies that the RED LIGHT is LIT on 1-FW-P-3B and goes to the RNO.

COMMENTS:

STEP 11: CRITICAL STEP

_______ SAT 0-AP-17.06 - STEP 5c RNO - Do the following:

• Reset AMSAC. _______ UNSAT OR

• Locally open MD AFW pump breaker:

• 1-FW-P-3B (1-EP-BKR-15J4)

STANDARD:

• Candidate resets AMSAC by taking the AMSAC BYPASS switch to RESET.

[CRITICAL STEP]

• Candidate may elect to locally open the associated breaker by contacting a field operator.

EVALUATORS NOTE/CUE:

• If candidate attempts to direct the local opening of 1-EP-BKR-15J4, inform them that no field operator is currently available.

COMMENTS:

Page 7 of 11

Surry 2021-301 Load AAC DG on 1J Bus STEP 12: CRITICAL STEP

_______ SAT 0-AP-17.06 - STEP 6 - ENERGIZE EMERGENCY BUS 1J.

a) Place the Sync switch for 1-EP-BKR-15J8 in ON _______ UNSAT b) Check breaker 1-EP-BKR-15J3 is OPEN c) Close breaker 1-EP-BKR-15J8 by holding control switch in the Closed position for at least five seconds d) Place the Sync switch for 1-EP-BKR-15J8 in OFF STANDARD:

a) Locates the generator synch switch and places it in 15J8.

b) Rotates the synch switch for 15J8 in the clockwise direction to the "ON" position [CRITICAL STEP].

c) Verifies breaker 15J3 is open (green light on red light off).

d) Rotates 15J8 breaker control switch in the clockwise direction to the close position and holds for 5 seconds, releases switch and verifies rotation back to 12:00 position [CRITICAL STEP].

NOTE: TIME CRITICAL ACTION COMPLETE; TIME _________.

e) Verifies 15J8 breaker closed (Red light on, green light off).

f) Verifies 1J Bus energized (frequency at approximately 60 HZ and voltage approximately 4200V).

g) Rotates the synch switch for 15J8 in the counterclockwise direction to the "OFF" position.

COMMENTS:

Page 8 of 11

Surry 2021-301 Load AAC DG on 1J Bus STEP 13:

_______ SAT REPORTS TO SHIFT MANAGER (EVALUATOR)

_______ UNSAT Standards Candidate reports AP-17.06 is completed up to Steps 1-6 are complete STOP TIME: ______

COMMENTS:

JPM END STOP TIME: _____

Page 9 of 11

Surry 2021-301 Load AAC DG on 1J Bus Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• The station has sustained a complete loss of the switchyard.

• Unit 1 has sustained a loss of all AC power and Unit 2 has only the "H" Bus energized from #2 EDG.

• #3 EDG started, but tripped immediately.

• The team is in 1-ECA-0.0, Loss of all AC Power, and has determined that EMERG Bus 1J needs to be energized.

• Unit 2 has aligned the Temporary Diesel Air Compressor to supply instrument air.

Initiating Cue

• This JPM is **TIME CRITICAL**.

• Here is a copy of 0-AP-17.06, AAC Diesel Generator - Emergency Operations.

• I need you to restore power to Unit 1 "J" Bus with the AAC Diesel Generator by performing steps 1-6 of 0-AP-17.06, AAC Diesel Generator - Emergency Operations.

• When you finish the actions necessary to accomplish this, please inform me so I can have the Operating Team restore loads on the Unit 1 "J" Bus.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• The station has sustained a complete loss of the switchyard.

• Unit 1 has sustained a loss of all AC power and Unit 2 has only the "H" Bus energized from #2 EDG.

• #3 EDG started, but tripped immediately.

• The team is in 1-ECA-0.0, Loss of all AC Power, and has determined that EMERG Bus 1J needs to be energized.

• Unit 2 has aligned the Temporary Diesel Air Compressor to supply instrument air.

Initiating Cue

• This JPM is **TIME CRITICAL**.

• Here is a copy of 0-AP-17.06, AAC Diesel Generator - Emergency Operations.

• I need you to restore power to Unit 1 "J" Bus with the AAC Diesel Generator by performing steps 1-6 of 0-AP-17.06, AAC Diesel Generator - Emergency Operations.

• When you finish the actions necessary to accomplish this, please inform me so I can have the Operating Team restore loads on the Unit 1 "J" Bus.

Surry 2021-301 SWAP SGWLCS INPUTS U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title SWAP SGWLCS INPUTS (ALTERNATE PATH)

K/A: 016A2.01, Detector Failure (3.0,3.1)

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 5 Minutes _____ Minutes Conditions

• Task is to be PERFORMED in the simulator.

• A S/G SF & FF channels were aligned to Channel 4 to support channel III maintenance.

• Maintenance is complete and it is now desired to swap A S/G SF and FF to channel III IAW 1-OP-RP-001 steps 5.4.4 and 5.4.5.

Standards

• Places 1-FW-FCV-1478 in MAN.

• Places STM GEN A -FW FLOW CH SEL switch in CH-477 position.

• Places STM GEN A - STM FLOW CH SEL switch in CH-474 position.

• Places 1-FW-FCV-1478 in AUTO.

• Places 1-FW-FCV-1478 in MAN and controls demand to restore and stabilize feed flow at the proper S/G level (approx. 44%)

Initiating Cues

• You are to align the A Steam Flow and Feed Flow channels to channel III in accordance with 1-OP-RP-001 steps 5.4.4 and 5.4.5.

• When you finish the actions necessary to accomplish this, please inform me Terminating Cues

• Candidate completes immediate actions of 0-AP-53.00 with A S/G level under their control.

Page 1 of 7

Surry 2021-301 SWAP SGWLCS INPUTS Procedures

• 1-OP-RP-001 - ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING

• 0-AP-53.00 - LOSS OF VITAL INSTRUMENTATION / CONTROLS Tools and Equipment Safety Considerations

• None

• None Simulator Setup Call up IC 367 OR 100% power IC and initialize.

Align A SG SF and FF channels to channel IV (YELLOW)

Insert malfunction FW1801, A S/G MN FD FLOW XMTR FT-1477 FAILS, Final Value +1.0, Event 1, Insert Create the following EVENT o EVENTS o Event 001 o Edit Event o Event code - FWFC478F_AUTO & FWFC478F_WHITE & FWSEL_CH476_477 - copy code within the quotes.

o OK Notes:

This JPM is designed to be pre-briefed.

Page 2 of 7

Surry 2021-301 SWAP SGWLCS INPUTS PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• An additional instructor may be needed to silence alarms for the examinee.

• START TIME_______:

STEP 1:

_______ SAT 1-OP-RP-001 - CAUTION and NOTES prior to step 5.4.4.

• CAUTION Due to the sensitivity of the Calorimetric Program to changes _______ UNSAT in Feed Flow while using the UFM, consideration should be given to proactively reducing Turbine load to raise the available margin to Maximum Allowable Power limit.

• NOTE: With Shift Supervision permission, steps within a subsection may be performed concurrently to limit the time a Feed Regulator valve is placed in MANUAL (i.e.; all three FRVs placed in MANUAL to allow swapping of SF/FF and Turbine First Stage Impulse Channels).

• NOTE: The Feedwater Regulator valve(s) should not be placed in MANUAL unless maintenance or testing will be performed on Channel IV of the particular valve.

• NOTE: Cycling Feed Flow / Steam Flow Channel select switches twice helps to ensure proper switch makeup.

STANDARD: Candidate acknowledges CAUTION and NOTES EVALUATORS NOTE (If Asked):

• Power reduction is not required for this task.

COMMENTS:

STEP 2:

_______ SAT 1-OP-RP-001 - STEP 5.4.4 - Check the following switch positions. Do not manipulate switches. _______ UNSAT

• STM GEN A - FW FLOW CH SEL SWITCH CH 477 position CH 476 position

• STM GEN A - STM FLOW CH SEL SWITCH CH 474 position CH 475 position STANDARD:

Candidate records AS-FOUND switch positions (CH476 / CH475).

COMMENTS:

Page 3 of 7

Surry 2021-301 SWAP SGWLCS INPUTS STEP 3: CRITICAL STEP

_______ SAT 1-OP-RP-001 - STEP 5.4.5 IF both switches are in CH 477 and CH 474 position, THEN enter N/A. IF either switch is NOT in the correct position, THEN perform _______ UNSAT the following:

a. Place 1-FW-FCV-1478, SG A FEED REG, in MAN position.

b. Cycle STM GEN A - FW FLOW CH SEL SWITCH at least twice and leave in CH-477 position.

c. Cycle STM GEN A - STM FLOW CH SEL SWITCH at least twice and leave in CH-474 position.

d. Check proper switch makeup by checking indications normal for plant conditions on 1-FW-FR-1478, SG A FLOW.

e. Place 1-FW-FCV-1478, SG A FEED REG, in AUTO position.

STANDARD:

a. Places 1-FW-FCV-1478 in MAN position. [CRITICAL STEP]

b. Places STM GEN A - FW FLOW CH SEL SWITCH in CH-477 position [CRITICAL STEP - to leave in 477 position].

c. Places STM GEN A - STM FLOW CH SEL SWITCH in CH-474 position

[CRITICAL STEP - to leave in 474 position].

d. Check proper switch makeup by checking indications on SF/FF recorder (1-FW-FR-1478).

e. Place 1-FW-FCV-1478 in AUTO position [CRITICAL STEP].

f. Upon restoration to AUTO, candidate identifies Feed Flow channel failure (1-FW-FI-1477 fails high) and commences the immediate actions of 0-AP-53.00.

EVALUATORS NOTE (If Asked):

• Another operator will monitor 1-FW-FCV-1478 while channel swap is performed.

• Concurrent verifications have been performed.

• Per the Note prior to step 5.4.4 the applicant will probably cycle the FW/STEAM FLOW selector switches twice (not critical).

COMMENTS:

STEP 4:

_______ SAT 0-AP-53.00 - [STEP 1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL _______ UNSAT STANDARD:

Candidate identifies normal feedwater flow on channel IV (1-FW-FI-1476).

COMMENTS:

Page 4 of 7

Surry 2021-301 SWAP SGWLCS INPUTS STEP 5: CRITICAL STEP

_______ SAT 0-AP-53.00 - [STEP 2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT _______ UNSAT INDICATION STANDARD:

a. Candidate places the A FRV in MANUAL (1-FW-FCV-1478) and controls demand to restore and stabilize at the proper S/G level (approximately 44%)

[CRITICAL STEP].

b. Candidate reports the immediate actions of 0-AP-53.00 are complete.

COMMENTS:

STEP 6:

TASK COMPLETE STOP TIME: ______________

NOTES:

Page 5 of 7

Surry 2021-301 SWAP SGWLCS INPUTS Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit 1 is at 100% power.

• A S/G SF & FF channels were aligned to Channel IV to support channel III maintenance.

• Maintenance is complete and it is now desired to swap A S/G SF and FF to channel III IAW 1-OP-RP-001 step 5.4.4 and 5.4.5.

Initiating Cues

• You are to align the A Steam Flow and Feed Flow channels to channel III in accordance with 1-OP-RP-001 steps 5.4.4 and 5.4.5.

• When you finish the actions necessary to accomplish this, please inform me.

Page 6 of 7

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 is at 100% power.

• A S/G SF & FF channels were aligned to Channel IV to support channel III maintenance.

• Maintenance is complete and it is now desired to swap A S/G SF and FF to channel III IAW 1-OP-RP-001 step 5.4.4 and 5.4.5.

Initiating Cues

• You are to align the A Steam Flow and Feed Flow channels to channel III in accordance with 1-OP-RP-001 steps 5.4.4 and 5.4.5.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 Locally Isolate U2 TDAFWP U.S. Nuclear Regulatory Commission Surry Power Station SR21301 In Plant Job Performance Measure EPE038G2.1.30 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Locally Isolate U2 TDAFW pump.

K/A: EPE 038 G2.1.30, Steam Generator Tube Rupture Ability to locate and operate components, including local controls. (4.4/4.0)

Applicability Estimated Time Actual Time RO/SRO 15 Minutes Conditions

• Task is to be SIMULATED in the Plant.

• Simulated plant conditions are that SGTRs have occurred and been identified in the Unit 2 "A" and B SGs. 2-E-3, SGTR, has been performed up to step 3d.

Standards

• 2-MS-87 is CLOSED.

• 2-MS-120 is CLOSED.

Initiating Cues

• Shift Manager direction.

Terminating Cues

• Report received that 2-E-3 step 3d is complete.

Procedures

• 2-E-3, Steam Generator Tube Rupture.

Tools and Equipment Safety Considerations

• None

• Standard Personal Safety Equipment 1 of 12

Surry 2021-301 Locally Isolate U2 TDAFWP PERFORMANCE CHECKLIST Notes to the Evaluator

• This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

• Task critical elements are bolded.

• START TIME: ________

STEP 1: CRITICAL STEP

_______ SAT Locally close steam supply valve(s) to TD AFW pump. (E-3, step 3d)

_______ UNSAT STANDARD:

a) Operator reports to Unit two Safeguards.

b) Locates the "A" & "B" main steam lines in relation to "C".

c) Closes chain valve 2-MS-87. CRITICAL STEP d) Closes chain valve 2-MS-120. CRITICAL STEP NOTE: Only 2-MS-87 and 2-MS-120 are to be closed.

EVALUATORS NOTE:

• Cue: When they state they are closing each chain valve, report: The chain stops pulling and the valve is closed.

• Both chain valves must be closed to satisfy the Critical Step.

COMMENTS:

2 of 12

Surry 2021-301 Locally Isolate U2 TDAFWP STEP 3:

_______ SAT Reports to Shift Manager that 2-E-3 Step 3d is complete.

_______ UNSAT EVALUATORS NOTE:

• Acknowledge report.

COMMENTS:

• • JPM COMPLETE **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

3 of 12

Surry 2021-301 Locally Isolate U2 TDAFWP Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• The Unit 2 "A" and B Steam Generators are Ruptured. We are in the process of isolating the Ruptured SGs iaw 2-E-3 step 3.

• 2-FW-P-3A and 2-FW-P-3B, A and B Motor Driven Aux Feedwater Pumps, are running.

Initiating Cues

• Here is Step 3 of 2-E-3. Your task is to perform Step 3d for the applicable Steam Generators.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• The Unit 2 "A" and B Steam Generators are Ruptured. We are in the process of isolating the Ruptured SGs iaw 2-E-3 step 3.

• 2-FW-P-3A and 2-FW-P-3B, A and B Motor Driven Aux Feedwater Pumps, are running.

Initiating Cues

• Here is Step 3 of 2-E-3. Your task is to perform Step 3d for the applicable Steam Generators.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 Locally Start an EDG U.S. Nuclear Regulatory Commission Surry Power Station SR16301 In Plant Job Performance Measure 061K4.01

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title LOCALLY START AN EDG.

K/A: APE068AA1.31 Ability operate and / or monitor the following as they apply to the Control Room Evacuation: EDG. (3.9/4.0)

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 20 Minutes ___ Minutes Conditions

• Task is to be SIMULATED in the plant.

Standards

• Depresses Engine Start pushbutton.

• Turns 4160 V EMERG GEN SUP FEED TO BUS 1H SYNCH TO ON.

• Raises incoming voltage to 120 volts using EMERG GEN 1H VOLTAGE CONTROL HS.

• Places EMERG GEN 1H FAST START DEFEAT HS to ON.

• Closes breaker 15H3 by taking breaker control switch to CLOSE.

Procedures

• 0-FCA-12.00 Tools and Equipment Safety Considerations

• None

• Standard PPE Required.

Page 1 of 9

Surry 2021-301 Locally Start an EDG PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves

• START TIME_______:

STEP 1:

_______ SAT NOTE and CAUTION prior to step 31. (FCA-12.00, step 31)

_______ UNSAT

• CAUTION: Personnel in the EDG Room should be wearing hearing protection at this time.

• NOTE: Local EDG start will cause both start circuits to actuate simultaneously.

Standards

• Acknowledges Note and Caution.

Evaluator's Notes Evaluator's Comments Page 2 of 9

Surry 2021-301 Locally Start an EDG STEP 2: CRITICAL STEP

_______ SAT LOCALLY START THE EDG. (AP-12.00, step 31).

_______ UNSAT a) Depress the ENGINE START Pushbutton.

b) Check EDG - STARTED.

c) Check EDG SPEED - 900 RPM.

d) Check EDG Output breaker closed.

Standards (a) Depresses the ENGINE START pushbutton (simulates). CRITICAL STEP.

(b) Check EDG started and speed at approximately 900 RPM.

(c) Determines that EDG Output breaker (15H3) did NOT close. Goes to 31d RNO which directs the operator to return to step 9.

Evaluators Cues Cue: Acknowledge EDG Start and inform the operator that the Diesel is starting.

Cue: When asked report that EDG is at 900 RPM by indicator on local panel.

Cue: If asked about EDG Output breaker (15H3) report the green light is ON and the red light OFF Evaluator's Notes Evaluator's Comments STEP 3:

_______ SAT NOTES prior to step 9.

_______ UNSAT

• The following conditions must exist in order for the EDG Output breaker to automatically close:

o EDG speed is greater than 870 RPM.

o EDG incoming voltage is greater than 113 volts.

o The 15H8 breaker is opened.

o The control switch for the 15H3 breaker is in the AFTER TRIP position.

o DC control power is available to the breaker.

Standards

• Acknowledges NOTES.

Evaluator's Notes Evaluator's Comments Page 3 of 9

Surry 2021-301 Locally Start an EDG STEP 4:

_______ SAT CHECK EDG SPEET - GREATER THAN 870 RPM. (FCA-12.00, step 9)

_______ UNSAT Standards (a) Determines that EDG speed is greater than 870 RPM. Continues to step 10.

Evaluator's Notes Evaluator Cue: If asked (again) indicate on the RPM meter that EDG speed is 900 RPM Evaluator's Comments STEP 5: CRITICAL STEP

_______ SAT CAUTION: EDG is running unloaded at this point.

_______ UNSAT RAISE EDG INCOMING VOLTAGE TO GREATER THAN 113 VOLTS: (FCA-12.00, step 10) a) Turn 4160V EMERG GEN SUP FEED TO BUS 1H SYNC 15H3 to ON position.

b) CHECK generator voltage - ESTABLISHED.

c) Raise incoming voltage to 120 volts using EMERG GEN 1H VOLTAGE CONTROL HAND SW.

Standards (a) Turn 4160V EMERG GEN SUP FEED TO BUS 1H SYNC 15H3 to ON position (simulates). CRITICAL STEP.

(b) Check generator voltage - ESTABLISHED. Determines generator voltage has been established.

(c) Raises incoming voltage to 120 volts using VOLTAGE CONTROL HS. CRITICAL STEP Evaluators Cues Cue: After Synch sw is placed; If asked for generator voltage value. Indicate on voltage gauge that EDG voltage is APPROXIMATELY 115 VOLTS.

Cue: After Voltage control handswitch is operated indicate that Generator volts is rising to 120 volts.

Evaluator's Notes If the operator incorrectly turns on the 15H8 Sync switch, both INCOMING and RUNNING volt meters will remain at 0 volts.

Evaluator's Comments Page 4 of 9

Surry 2021-301 Locally Start an EDG STEP 6:

_______ SAT CHECK 15H8 BREAKER - OPEN. (FCA-12.00, step 11)

_______ UNSAT Standards (a) Operator determines that breaker 15H8 is OPEN.

Evaluators Cues Cue: If asked breaker 15H8 indication is green light ON, red light OFF.

Evaluator's Notes Evaluator's Comments STEP 7:

_______ SAT CHECK CONTROL POWER FOR BREAKER 15H3 - AVAILABLE. (FCA-12.00, step 12)

_______ UNSAT

• Breaker indicating lights - LIT Standards

• Operator determines that Breaker 15H3 has control power.

Evaluators Cues Cue: If asked for breaker indicating lights, report that the green light is ON and the red light is OFF.

Evaluator's Notes Evaluator's Comments Page 5 of 9

Surry 2021-301 Locally Start an EDG STEP 8:

_______ SAT CHECK BREAKER 15H3 CLOSED. (FCA-12.00, step 13)

_______ UNSAT Standards Operator determines that breaker 15H3 is NOT CLOSED. Goes to step 13 RNO, which directs the operator to go to step 15.

Evaluators Cues Cue: If asked, breaker 15H3 is as you see it (green light lit, red light out).

Evaluator's Notes Evaluator's Comments STEP 9: CRITICAL STEP

_______ SAT MOMENTARILY PLACE EMERG GEN 1H FAST START DEFEAT HAND SW TO ON.

(FCA-12.00, step 15) _______ UNSAT

• Red light - ON.

Standards

• Places EMERG GEN 1H FAST START DEFEAT HS TO ON. CRITICAL STEP.

• Checks red light on.

Evaluators Cues Cue: When asked for light indication, state that light above Fast Start Defeat HS is ON.

Evaluator's Notes Evaluator's Comments Page 6 of 9

Surry 2021-301 Locally Start an EDG STEP 10:

_______ SAT CHECK INCOMING VOLTAGE - 120 VOLTS. (FCA-12.00, step 16)

_______ UNSAT Standards

• Operator checks incoming voltage is 120 volts.

Evaluators Cues Cue: If Operator asks for incoming voltage (and indicates correct indicator). Inform him voltage is 120 volts.

Evaluator's Notes Evaluator's Comments STEP 11:

_______ SAT NOTES before step 17:

_______ UNSAT

• Running voltage will be zero and the synchroscope will be motionless at this time.

• If DC Bus A is deenergized, the EDG output breaker and Bus 1H load breakers must be manually closed.

Standards

• Acknowledges NOTES.

Evaluator's Notes Evaluator's Comments Page 7 of 9

Surry 2021-301 Locally Start an EDG STEP 12: CRITICAL STEP

_______ SAT CLOSES EMERG SUP BREKER 15H3 (FCA-12.00, step 17)

_______ UNSAT Standards

• Operator places HS for Breaker 15H3 to CLOSE. CRITICAL STEP.

Evaluators Cues Cue: When asked for status of breaker 15H3 report that red light is lit and green light is off.

Cue: If asked for changes to Running Voltage, indicate that running voltage matches incoming voltage.

Evaluator's Notes Evaluator's Comments STEP 13:

_______ SAT TURN 4160 V EMERG GEN SUP FEED TO BUS 1H SYNCH 15H3 TO OFF. (FCA-12.00 step 18) _______ UNSAT Standards

• Places 15H3 Synch switch to OFF.

Evaluator's Notes Evaluator's Comments Page 8 of 9

Surry 2021-301 Locally Start an EDG STOP TIME ___________:

Page 9 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• The Main Control Room has been evacuated due to a fire.

• The crew is initiating actions per 0-FCA-1.00, LIMITING MCR FIRE

• Offsite power to the station has been lost and EDG #1 has failed to auto start.

Initiating Cues

• Another operator has completed the pre-start checks per 0-FCA-12.00, up to step 30. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is loaded on the bus.

• Here is a copy of 0-FCA-12.00. Your task is to start the #1 Emergency Diesel Generator at the local panel per 0-FCA-12.00 starting at step 31.

Notes to the Evaluator

• This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

• Critical step sequencing requirements: None.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• The Main Control Room has been evacuated due to a fire.

• The crew is initiating actions per 0-FCA-1.00, LIMITING MCR FIRE

• Offsite power to the station has been lost and EDG #1 has failed to auto start.

Initiating Cues

• Another operator has completed the pre-start checks per 0-FCA-12.00, up to step 30. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is loaded on the bus.

• Here is a copy of 0-FCA-12.00. Your task is to start the #1 Emergency Diesel Generator at the local panel per 0-FCA-12.00 starting at step 31.

U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Simulator Job Performance Measure [KA: 036G2.1.44 3.9/3.8]

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title MCR pressure boundary verification in plant using 0-AP-22.00, Fuel Handling Abnormal Conditions K/A: 036G2.1.44, Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. (3.9 / 3.8).

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 10 Minutes ___ Minutes Conditions

• Task is to be SIMULATED in plant.

Standards

• Opens breaker 1-EP-DB-HVAC Ckt 1.

• Opens 2-EP-DB-HVAC Ckt 2.

• Opens 1-EP-BKR-1B2-1-2D.

• Opens 2-EP-BKR-2B2-1-4D.

• Opens 1-EP-BKR-1B2-1-3D.

• Opens 2-EP-BKR-2B2-1-3D.

Procedures

• 0-AP-22.00, Fuel Handling Abnormal Conditions.

Tools and Equipment Safety Considerations

• None

• Ensure you use the handrail when climbing stairs.

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• NOTE: The pictures in the JPM are on white paper, but are NOT to be included in the instructions given to the applicant. They are to be used during the JPM as an examiner cue for the first two breakers listed on 0-AP-22.00 Attachment 1, Step 3.

• START TIME_______:

STEP 1 CRITIAL STEP

_______ SAT Secure MCR boundary fans by opening the following breakers (0-AP-22.00 Attachment 1, step

3) _______ UNSAT STANDARD:

a) Opens the supply breaker for every location listed below:

___

• CABLE TRAY ROOM AIR HANDLING UNIT AHU-1, 1-EP-DB-HVAC, Ckt 1 (Unit 1 Switchgear Room, West wall)

___

• CABLE TRAY ROOM AIR HANDLING UNIT, 2-EP-DB-HVAC, Ckt 2 (Unit 2 Switchgear Room, South wall)

___

• 1-VS-F-16, CABLE TUNNEL EXHAUST FAN, 1-EP-BKR-1B2-1-2D (Unit 1 Switchgear Room)

___

• 2-VS-F-16, CABLE TUNNEL EXHAUST FAN, 2-EP-BKR-2B2-1-4D (Unit 2 Switchgear Room)

___

• 1-VS-F-RAF-1, CABLE TRAY ROOM RETURN FAN, 1-EP-BKR-1B2-1-3D (Unit 1 Switchgear Room)

___

• 2-VS-F-RAF-2, CABLE TRAY ROOM RET FAN, 2-EP-BKR-2B2-1-3D (Unit 2 Switchgear Room)

___

• 1-VS-HV-2, CABLE VAULT HTG AND VENT UNITS, 1-EP-BKR-1A1-1EA1 (Unit 1 Upper Cable Vault) - Will NOT be performed

___

• 2-VS-HV-2, CABLE VAULT HTG AND VENT UNIT, 2-EP-BKR-2A1-1EA1 (Unit 2 Upper Cable Vault) - Will NOT be performed b) Goes to Step 4.

EVALUATORS NOTE:

Note: If the Candidate proceeds downstairs (toward the Upper Cable Vaults), inform the Candidate another operator will secure power to 1-VS-HV-2 and 2-VS-HV-2.

Cue: For the first two breakers listed, provide the attached pictures for each breaker as needed to prevent opening the electrical panel doors.

IF asked: For each of the breakers listed above, state the breaker is as they see it (all are expected to be closed).

IF asked: After the Applicant simulates opening each of the breakers listed above, indicate the breaker is in the OFF position.

Note: All listed breakers must be opened to satisfy the Critical Step.

COMMENTS:

STEP 2

_______ SAT Check readings on the following Differential Pressure Indicators - POSITIVE PRESSURE INDICATED (0-AP-22.20 Attachment 1, step 4) _______ UNSAT STANDARD:

a) Either walks toward the Main Control Room or asks the Shift Manager for current Pressure indications.

EVALUATORS NOTE:

Before the Candidate proceeds to the Main Control Room, inform them the JPM is complete.

COMMENTS:

END OF JPM STOP TIME: _______

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initiating Conditions

• Unit 1 is operating at 100% power; Unit 2 is in Refueling Shutdown. Fuel shuffling was in progress in the Fuel Building.

• There has been a Fuel Handling accident in the Fuel Building.

• The Fuel Handling crew has placed the leaking fuel assembly in the designated storage location and has evacuated the Fuel Building.

Initiating Cues

• Your task is to perform Step 3 of 0-AP-22.00 Attachment 1, MCR Pressure Boundary Verification.

• When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initiating Conditions

• Unit 1 is operating at 100% power; Unit 2 is in Refueling Shutdown. Fuel shuffling was in progress in the Fuel Building.

• There has been a Fuel Handling accident in the Fuel Building.

• The Fuel Handling crew has placed the leaking fuel assembly in the designated storage location and has evacuated the Fuel Building.

Initiating Cues

• Your task is to perform Step 3 of 0-AP-22.00 Attachment 1, MCR Pressure Boundary Verification.

• When you finish the actions necessary to accomplish this, please inform me.

Surry 2021-301 LOCALLY ALIGN RSSW U.S. Nuclear Regulatory Commission Surry Power Station SR21301 In Plant Job Performance Measure EPE011EA1.11 (4.2, 4.2)

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title LOCALLY ALIGN SW TO A RECIRC SPRAY HEAT EXCHANGER K/A: EPE011EA1.11 (4.2, 4.2), Ability to operate and monitor the following as they apply to a Large Break LOCA: long-term cooling of core.

Applicability Estimated Time Actual Time RO/SRO(I)/SRO(U) 10 Minutes ____ Minutes Conditions

• Task is to be SIMULATED in the plant.

• Simulated plant conditions are that a LOCA is in progress with a loss of offsite power and subsequent loss of EDG #3. 2-SW-MOV-204C and 2-SW-MOV-205C cannot be opened from the control room and need to be locally opened to establish one train of RS heatsink.

Standards

1. Locally opens 2-SW-MOV-204C

2. Locally opens 2-SW-MOV-205C Procedures

• 2-ECA-1.1, Loss of Emergency Coolant Recirculation, step 8c RNO.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 6

Surry 2021-301 LOCALLY ALIGN RSSW PERFORMANCE CHECKLIST Notes to the Evaluator

• This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

• Task critical elements are bolded.

• START TIME: ________

STEP 1: CRITICAL STEP

_______ SAT Locally open 2-SW-MOV-204C (C RSHX SW INLET MOV)

_______ UNSAT STANDARD:

a) Operator reports to Unit two Safeguards and goes to the basement.

b) Locates 2-SW-MOV-204C.

c) Manually declutches the MOV (presses handle DOWN) [CRITICAL STEP].

d) Opens 2-SW-MOV-204C by turning handwheel counter-clockwise until indicator points to OPEN [CRITICAL STEP].

EVALUATORS NOTE:

• Cue: When they correctly state they are opening the valve, report: The pointer moves and the handwheel stops rotating when the indicator points to OPEN.

• Cue: If declutch lever not depressed, then report that when the handwheel is rotated, no valve motion occurs.

COMMENTS:

STEP 2: CRITICAL STEP

_______ SAT Locally open 2-SW-MOV-205C (C RSHX SW OUTLET MOV)

_______ UNSAT STANDARD:

a) Locates 2-SW-MOV-205C.

b) Manually declutches the MOV (presses handle DOWN) [CRITICAL STEP].

c) Opens 2-SW-MOV-205C by turning handwheel counter-clockwise until indicator points to OPEN [CRITICAL STEP].

EVALUATORS NOTE:

• Cue: When they correctly state they are opening the valve, report: The pointer moves and the handwheel stops rotating when the indicator points to OPEN.

• Cue: If declutch lever not depressed, then report that when the handwheel is rotated, no valve motion occurs COMMENTS:

Page 2 of 6

Surry 2021-301 LOCALLY ALIGN RSSW Step 3 CRITICAL STEP

_______ SAT REPORTS TO SHIFT MANAGER (EVALUATOR).

_______ UNSAT STANDARD:

Verbal status report made that 2-SW-MOV-204C and 2-SW-MOV-205C have been opened.

COMMENTS:

JPM END STOP TIME:

Page 3 of 6

EXAM MATERIAL - DO NOT GIVE TO CANDIDATE - FOR EXAMINER REFERENCE ONLY Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A Large Break LOCA has occurred on Unit 2 concurrent with a loss of offsite power.

• #3 EDG tripped on overspeed resulting in the loss of the 2J 4160v bus.

• The team is performing 2-ECA-1.1, Loss of Emergency Coolant Recirculation, step 8c RNO which has directed the team to Align SW to at least two RS HXs.

• The C RSHX service water MOVs are CLOSED and cannot be opened from the control room.

• The supply breakers for each valve have been opened.

• 2-SW-MOV-203A through 2-SW-MOV-203D are all OPEN.

Initiating Cues

• Your task is to perform 2-ECA-1.1 step 8c RNO, by locally aligning SW flow to the C RSHX by manually operating 2-SW-MOV-204C and 2-SW-MOV-205C.

• When you finish the actions necessary to accomplish this please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A Large Break LOCA has occurred on Unit 2 concurrent with a loss of offsite power.

• #3 EDG tripped on overspeed resulting in the loss of the 2J 4160v bus.

• The team is performing 2-ECA-1.1, Loss of Emergency Coolant Recirculation, step 8c RNO which has directed the team to Align SW to at least two RS HXs.

• The C RSHX service water MOVs are CLOSED and cannot be opened from the control room.

• The supply breakers for each valve have been opened.

• 2-SW-MOV-203A through 2-SW-MOV-203D are all OPEN.

Initiating Cues

• Your task is to perform 2-ECA-1.1 step 8c RNO, by locally aligning SW flow to the C RSHX by manually operating 2-SW-MOV-204C and 2-SW-MOV-205C.

• When you finish the actions necessary to accomplish this please inform me.

Surry 2021-301 JPM j, Transfer SVB Power U.S. Nuclear Regulatory Commission Surry Power Station SR21301 In Plant Job Performance Measure 062A2.05 2.9/3.3 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Transfer Semi-Vital bus power supply.

K/A: SYS062A2.05, Methods for energizing a dead bus, 2.9/3.3 Applicability Validated Time Actual Time RO/SRO(I) 12 Minutes ___ Minutes Conditions

• Task is to be SIMULATED in the Plant.

Standards

• Places 1-EP-1H1-1-2A1 breaker switch in the OPEN position.

• Contacts MCR and has the Unit 1 SVB manual transfer switch placed in the 1J1 position.

• Closes 1-EP-1J1-1-7D1 breaker.

Procedures

• 1-AP-10.05, Loss of Semi-Vital Bus, Revision 36.

Tools and Equipment Safety Considerations

• None

• Standard Personal Safety Equipment Page 1 of 6

Surry 2021-301 JPM j, Transfer SVB Power PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as CRITICAL STEP.

• This task is to be SIMULATED. Do NOT allow the Candidate to manipulate controls, operate switches or reposition valves

• START TIME: ______

1-AP-10.05, Step 11

_______ SAT STEP 1: Acknowledge NOTE Prior to Step 11.

_______ UNSAT STANDARD:

a) Reviews NOTE: If the Semi-Vital Bus has been deenergized for greater than 30 minutes, the SG PORV controllers will return to Remote/Manual control when power is restored.

EVALUATORS NOTE:

If asked: Unit 1 SVB has been deenergized for 15 minutes.

If asked: Unit 1 SVB powered from the 1H bus supply prior to the power loss.

COMMENTS:

Page 2 of 6

Surry 2021-301 JPM j, Transfer SVB Power 1-AP-10.05, Step 11 CRITICAL STEP

_______ SAT Step 2 Locally open Semi-Vital Bus feeder breakers.

_______ UNSAT STANDARD:

(a) Locates to Unit 1 ESGR and Locates breaker 1-EP-BKR-1H1-1-2A1 on MCC 1H1-1.

(b) Simulates placing 1-EP-BKR-1H1-1-2A1 breaker switch in the OPEN position - CRITICAL STEP.

c) Locates breaker 1-EP-BKR-1J1-1-7D1 on MCC 1J1-1.

d) Checks breaker 1J1-1-7D1 in open position.

EVALUATORS NOTE:

If asked: Point to ON position on breaker 1H1-1-2A1.

If asked for 1H1-1-2A1 after opening: Point to the OFF position on breaker 1J1-1-7D1 handle.

COMMENTS:

1-AP-10.05, Step 11 CRITICAL STEP

_______ SAT Step 3b: Operate manual transfer switch to the desired power supply.

_______ UNSAT STANDARD:

a) Contacts MCR (Evaluator) and requests Unit 1 SVB manual transfer switch to be placed in the 1J1 position. CRITICAL STEP.

EVALUATORS NOTE:

When asked to transfer state: A time compression has occurred, the SVB manual transfer switch has been swapped to the 1J1 position.

Acceptable for the Candidate to go to the MCR to simulate placing the manual transfer switch in the 1J position.

COMMENTS:

Page 3 of 6

Surry 2021-301 JPM j, Transfer SVB Power 1-AP-10.05, Step 11 CRITICAL STEP

_______ SAT Step 4: Locally close the selected Semi-Vital Bus feeder breaker.

_______ UNSAT STANDARD:

a) Locates to breaker 1-EP-1J1-1-7D1 on MCC 1J1-1.

b) Simulates closing 1-EP-1J1-1-7D1 breaker. CRITICAL STEP.

c) Checks Semi-Vital Bus Energized by contacting MCR (Evaluator) to determine if SVB is energized.

EVALUATORS NOTE:

If asked: Inform Candidate that Unit 1 SVB has been reenergized.

COMMENTS:

Step 5: Inform Shift Manager (Evaluator) of Task Completion. _______ SAT STANDARD: _______ UNSAT Informs Evaluator task has been completed, EVALUATORS NOTE:

NONE COMMENTS:

END OF JPM STOP TIME:

Page 4 of 6

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A loss of Unit 1's Semi-Vital Bus has occurred.

• The team is performing 1-AP-10.05, LOSS OF SEMI-VITAL BUS.

Initiating Cues

• Here is a copy of 1-AP-10.05, Step 11. I need you to transfer the Unit 1 Semi-Vital Bus to the 1J Bus power supply by performing step 11 of 1-AP-10.05. When you inform me that the bus has been re-energized, I will have the Unit RO perform the required instrumentation evaluation.

• When you finish the actions necessary to accomplish this Task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A loss of Unit 1's Semi-Vital Bus has occurred.

• The team is performing 1-AP-10.05, LOSS OF SEMI-VITAL BUS.

Initiating Cues

• Here is a copy of 1-AP-10.05, Step 11. I need you to transfer the Unit 1 Semi-Vital Bus to the 1J Bus power supply by performing step 11 of 1-AP-10.05. When you inform me that the bus has been re-energized, I will have the Unit RO perform the required instrumentation evaluation.

• When you finish the actions necessary to accomplish this Task, please inform me.

Surry 2021-301 INITIATE CO2 EDG CARDOX U.S. Nuclear Regulatory Commission Surry Power Station SR21301 In Plant Job Performance Measure 086A2.04, (3.3,3.9)

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title INITIATE CO2 EDG CARDOX [Alternate Path]

K/A: 086A2.04, (3.3,3.9), Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure to actuate the FPS when required, resulting in fire damage.

Applicability Estimated Time Actual Time RO/SRO(I)/SRO(U) 10 Minutes ____ Minutes Conditions

• Task is to be SIMULATED in the plant.

• A fire has been reported in #2 EDG room and attempts to actuate CO2 from the MCR were unsuccessful.

Standards

1. Opens door at EDG 2 Local Panel.

2. Rotates EMPC throw-over lever at the local panel 180 degrees at the local panel for #2 EDG room.

3. Rotate EMPC throw-over lever at the Cardox supply tank 180 degrees.

Procedures

• 0-OP-FP-006, OPERATION OF FIRE PROTECTION SYSTEMS, Section 5.1.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 8

Surry 2021-301 INITIATE CO2 EDG CARDOX PERFORMANCE CHECKLIST Notes to the Evaluator

• This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

• Task critical elements are bolded.

• START TIME: ________

STEP 1:

_______ SAT 0-OP-FP-006 - STEP 5.1.1 Determine hazard area(s) which require CO2.

_______ UNSAT STANDARD:

a) Operator recalls that fire is in #2 EDG room.

COMMENTS:

STEP 2:

_______ SAT 0-OP-FP-006 - STEP 5.1.2 Initiate CO2 at manual actuation station by pulling down cover and depressing pushbutton. _______ UNSAT STANDARD:

a) Proceeds to CO2 control panel just outside #2 EDG room.

b) Simulates pulling down cover and depressing actuation button.

COMMENTS:

Page 2 of 8

Surry 2021-301 INITIATE CO2 EDG CARDOX STEP 3:

_______ SAT 0-OP-FP-006 - STEP 5.1.3 Check CO2 initiation and notify Main Control Room. IF CO2 fails to initiate THEN enter N/A AND GO TO Step 5.1.4. _______ UNSAT

• Green System Normal light NOT LIT

• Frost on CO2 supply piping

• Red Fire Indication light LIT STANDARD:

a) Candidate identifies that CO2 actuation did NOT occur and continues with step 5.1.4.

EVALUATORS NOTE/CUE:

• CUE: Report that Green System Normal light is LIT

• CUE: There is no Frost on CO2 supply piping

• CUE: Fire Indication light is NOT LIT

• CUE: If applicant goes to the wrong EDG then report the opposite indications.

COMMENTS:

STEP 4: CRITICAL STEP

_______ SAT 0-OP-FP-006 - STEP 5.1.4 IF CO2 fails to initiate, THEN break the glass AND open the door at the local panel for affected hazard(s). _______ UNSAT STANDARD:

a) Simulates breaking access glass and opening door at EDG 2 Local panel.

CRITICAL STEP EVALUATORS NOTE: Lever can be accessed without opening door.

COMMENTS:

Page 3 of 8

Surry 2021-301 INITIATE CO2 EDG CARDOX STEP 5:

_______ SAT 0-OP-FP-006 - CAUTION prior to step 5.1.5: If CO2 is released using the Electro-Mechanical Pilot Controller (EMPC) manual throw-over lever, the operator must terminate _______ UNSAT the release by placing the throw-over lever in CLOSE after a predetermined time. The time is posted on the EMPC for the affected hazard area.

STANDARD:

a) Candidate acknowledges CAUTION COMMENTS:

STEP 6: CRITICAL STEP

_______ SAT 0-OP-FP-006 - STEP 5.1.5 Rotate EMPC throw-over lever at the local panel 180 degrees for the time specified on affixed instruction placard. _______ UNSAT STANDARD:

a) Candidate simulates rotation of the throw-over lever 180° [CRITICAL STEP].

EVALUATORS NOTE/CUE:

CUE: If asked: Report that conditions did not change following rotation of throw-over lever (or conditions are as you see them).

COMMENTS:

STEP 7:

_______ SAT 0-OP-FP-006 - STEP 5.1.6 Check CO2 initiation and notify Main Control Room. IF CO2 fails to initiate, THEN enter N/A AND GO TO Step 5.1.7. _______ UNSAT STANDARD:

a) Candidate determines that CO2 failed to initiate and goes to step 5.1.7 EVALUATORS NOTE/CUE:

CUE: If asked: Report that conditions did not change following rotation of throw-over lever (or conditions are as you see them.

COMMENTS:

Page 4 of 8

Surry 2021-301 INITIATE CO2 EDG CARDOX STEP 8: CRITICAL STEP

_______ SAT 0-OP-FP-006 - STEP 5.1.7 IF CO2 fails to initiate, THEN leave EMPC throw-over lever in the OPEN position AND open the Master Control Valve (valve is located next to _______ UNSAT the Cardox supply tank outside of Unit 2 track-bay).

STANDARD:

a) Candidate relocates to just outside U2 track bay near the CO2 tank.

b) Candidate simulates breaking access glass and rotation of the throw-over lever 180° [CRITICAL STEP].

COMMENTS:

STEP 9:

_______ SAT 0-OP-FP-006 - STEP 5.1.8 Check CO2 initiation and notify Main Control Room

_______ UNSAT STANDARD:

a) Candidate contacts the MCR.

b) Candidate may relocate back to just outside #2 EDG room to verify CO2 discharge.

EVALUATORS NOTE/CUE:

CUE: If asked: CO2 line from the tank is frosted.

If asked: Just outside #2 EDG room, CO2 line is frosted.

COMMENTS:

STEP 10:

_______ SAT 0-OP-FP-006 - STEP 5.1.9 Return EMPC throw-over lever to the CLOSE position when directed by Main Control Room. _______ UNSAT STANDARD:

a) Candidate awaits cue from MCR to terminate CO2 discharge.

EVALUATORS NOTE/CUE:

CUE: Another operator will terminate CO2 discharge at the appropriate time.

COMMENTS:

Page 5 of 8

Surry 2021-301 INITIATE CO2 EDG CARDOX Step 11 :

_______ SAT REPORTS TO SHIFT MANAGER (EVALUATOR).

_______ UNSAT STANDARD:

Verbal status report made that CO2 discharge has been initiated to #2 EDG room.

COMMENTS:

JPM END STOP TIME: ___________

Page 6 of 8

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A fire has been reported in #2 EDG room and attempts to discharge CO2 from the control room have been unsuccessful.

Initiating Cues

• You are to locally discharge CO2 to #2 EDG room in accordance with 0-OP-FP-006, OPERATION OF FIRE PROTECTION SYSTEMS, section 5.1.

• When you finish the actions necessary to accomplish this please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A fire has been reported in #2 EDG room and attempts to discharge CO2 from the control room have been unsuccessful.

Initiating Cues

• You are to locally discharge CO2 to #2 EDG room in accordance with 0-OP-FP-006, OPERATION OF FIRE PROTECTION SYSTEMS, section 5.1.

• When you finish the actions necessary to accomplish this please inform me.

Surry 2021-301 Calorimetric U.S. Nuclear Regulatory Commission Surry Power Station SR16301 Administrative Job Performance Measure G2.1.19 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Perform calculation of reactor power using 1-OPT-RX-003, Reactor Power Calorimetric using Feed Flow and PCS Computer Points (Manual).

K/A: G2.1.19, Ability to use plant computers to evaluate system or component status. (3.9 / 3.8)

Applicability Validation Time Actual Time RO 45 Minutes Conditions

• Task is to be PERFORMED in the classroom.

• Unit 1 is at 90% power.

• Feedwater Ultrasonic Flow Measurement (UFM) is non-functional.

Standards

• Calculate Qtotal within acceptable band (step 6.2.14)

• Calculate Reactor power in MWth within acceptable limits (step 6.2.15).

• Calculate Reactor power in % within acceptable band (step 6.2.16).

Initiating Cues

• Nuclear Shift Manager direction.

Terminating Cues

• 1-OPT-RX-003, Sections 6.1 and 6.2 completed.

Procedures

• 1-OPT-RX-003, Reactor Power Calorimetric using Feed Flow and PCS Computer Points (Manual)

• 1-DRP-003, Curve Book (Unit 1)

Tools and Equipment Safety Considerations

• Calculator

• Extra copies of Attachment 3 pages 1 and 2.

Notes Page 1 of 18

Surry 2021-301 Calorimetric

• A marked-up copy of 1-OPT-RX-003 should be given to the Applicant.

• A copy of 1-DRP-003, Unit 1 Curve Book, or laptop shall be made available.

Page 2 of 18

Surry 2021-301 Calorimetric PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• START TIME: ________

STEP 1

_______ SAT Obtain the values for SG Pressure, FW Temperature, and Main Feedwater Flow for each loop from the PCS computer. Record the computer point values in the appropriate boxes _______ UNSAT below and on Attachment 3, Page 1. (Step 6.2.1)

• U9171 SG A Corrected Stm Press __829.98__ psia

• U9172 SG B Corrected Stm Press __828.62__ psia

• U9173 SG C Corrected Stm Press __827.66__ psia

• T0418A SG A FW Temp (RTD-111A) __431.16_°F

• T0438A SG B FW Temp (RTD-111B) __431.16_°F

• T0458A SG C FW Temp (RTD-111C) __431.16_°F U9174 SG A Filtered Average ___3391.24___x 103 lbm/hr Feed Flow U9175 SG B Filtered Average ___3392.67___x 103 lbm/hr Feed Flow U9176 SG C Filtered Average ___3392.99___x 103 lbm/hr Feed Flow STANDARD:

Using JPM Attachment 1 (PP Output Summary), Applicant fills in numbers for this step and on procedure Attachment 3.

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

Page 3 of 18

Surry 2021-301 Calorimetric STEP 2

_______ SAT IF Feedwater temperature for any loop is greater than 443°F, THEN notify Reactor Engineering. Otherwise, enter N/A. (Step 6.2.2) _______ UNSAT STANDARD:

a) Applicant notes that Feedwater temperature is 431.16°F.

b) Applicant places N/A in initial block.

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 3

_______ SAT IF Step 6.1.3 was performed, THEN return the Feed Reg Bypass HCVs to desired position.

Otherwise, enter N/A. (Step 6.2.3) _______ UNSAT STANDARD:

a) Applicant recalls that the Feed Reg Bypass HCVs were not manipulated.

b) Enters N/A in initial block.

EVALUATORS NOTE:

If asked: Feed Reg Valve bypasses were not manipulated.

COMMENTS:

Page 4 of 18

Surry 2021-301 Calorimetric STEP 4

_______ SAT Obtain pressurizer heater input by using the computer point listed below.

Record this value in the appropriate box on Attachment 3, Page 2. _______ UNSAT (Enter 0 KW if computer point inoperable) (Step 6.2.4)

• Q0400A Pressurizer Heater Power __850.7__ KW STANDARD:

a) Applicant references attached PP Output Summary from PCS.

b) Notes that PZR Heater Power is 850.7 KW.

c) Records 850.7 KW in the step block and on page 2 of Attachment 3.

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 5

_______ SAT NOTE:

• Blowdown flow must be maintained as constant as possible. The most accurate data will be obtained by isolating blowdown, but isolation is not required. _______ UNSAT

• PCS points for automatic Blowdown flow are the preferred inputs for the following step.

(NOTE prior to Step 6.2.5)

STANDARD:

Applicant acknowledges NOTE.

COMMENTS:

Page 5 of 18

Surry 2021-301 Calorimetric STEP 6

_______ SAT Obtain loop blowdown flow by using the PCS points or indicators listed below. Circle PCS point (preferred) or indicator used. Record these values in the appropriate boxes on _______ UNSAT Attachment 3, Page 1. (Step 6.2.5)

• (F2551A) FPP0001K, FI-BD-103A or FI-BD-104A SG A BD Flow ___57.540__ gpm

• (F2552A) FPP0002K, FI-BD-103B or FI-BD-104B SG B BD Flow ___62.593__ gpm

• (F2553A) FPP0003K, FI-BD-103C or FI-BD-104C SG C BD Flow ___58.400__ gpm STANDARD:

a) Applicant refers to attached PP Output Summary from PCS for blowdown flows.

b) Circles the PCS point (F2551A, etc.) and records value in step and on Attachment 3.

EVALUATORS NOTE:

If asked: Blowdown is in AUTO mode for PCS.

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 7

_______ SAT Find the enthalpy of steam, hs, for each loop using Corrected Steam Pressure from Attachment 3 and the Enthalpy Steam Table (100% Quality) in 1-DRP-003. Record values _______ UNSAT in the appropriate boxes on Attachment 3, Page 1. (Step 6.2.6)

STANDARD:

a) Applicant locates Enthalpy Steam Table (100% Quality) in 1-DRP-003 (Attachment 72).

b) Determines hs for each loop. Applicant may interpolate exact values or round to the nearest psia.

• Loop A - 1198.54 BTU/lbm (band 1198.51 - 1198.57 BTU/lbm)

• Loop B - 1198.57 BTU/lbm (band 1198.54 - 1198.60 BTU/lbm)

• Loop C - 1198.60 BTU/lbm (band 1198.57 - 1198.63 BTU/lbm) c) Records values on Attachment 3.

EVALUATORS NOTE:

The listed band was developed by rounding steam pressure to the nearest psia, then taking the enthalpy value for +/-1 psia.

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

Page 6 of 18

Surry 2021-301 Calorimetric STEP 8

_______ SAT NOTE: Using a FW pressure of 800 psia in the next step will be conservative for all Reactor Power levels. _______ UNSAT Find the enthalpy of feedwater, hf, for each loop, using Feedwater Temperature from Attachment 3 and the Enthalpy Compressed Liquid Table (800 psia) in 1-DRP-003. Record values in the appropriate boxes on Attachment 3, Page 1. (Step 6.2.7)

STANDARD:

a) Acknowledges NOTE prior to step that using FW pressure of 800 psia is conservative.

b) Applicant locates Enthalpy Compressed Liquid Table (800 psia) in 1-DRP-003 (Attachment 74).

c) Determines hf for each loop. Applicant may interpolate exact values or round to the nearest tenth of a degree.

• Loop A - 409.61 BTU/lbm (band 409.50 - 409.72 BTU/lbm)

• Loop B - 409.61 BTU/lbm (band 409.50 - 409.72 BTU/lbm)

• Loop C - 409.61 BTU/lbm (band 409.50 - 409.72 BTU/lbm) d) Records values on Attachment 3.

EVALUATORS NOTE:

The listed band was developed by rounding feedwater temperature to the nearest tenth of a degree, then taking the enthalpy value for +/-1/10th of a degree.

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 9

_______ SAT Calculate h1 = hs - hf for each loop and record results in appropriate boxes on Attachment 3, Page 1. (Step 6.2.8) _______ UNSAT STANDARD:

Applicant calculates h1 and records values.

• Loop A - 788.93 BTU/lbm (band 788.79 - 789.07 BTU/lbm)

• Loop B - 788.96 BTU/lbm (band 788.82 - 789.10 BTU/lbm)

• Loop C - 788.99 BTU/lbm (band 788.82 - 789.13 BTU/lbm)

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

Listed band was developed by taking each respective loop hs(max) - hf(min) for one limit, and hs(min) - hf(max) for the other limit.

COMMENTS:

Page 7 of 18

Surry 2021-301 Calorimetric STEP 10

_______ SAT Calculate Blowdown Flow Mbd (lbm/hr) = BD (gpm) x 496.6563 lbm/hr.

gpm _______ UNSAT Record values in the appropriate boxes on Attachment 3, Page 1. (Step 6.2.9)

STANDARD:

Applicant calculates Mbd and records values.

• Loop A - 28577.60350 lbm/hr (band 28577 - 28578 lbm/hr)

• Loop B - 31087.20779 lbm/hr (band 31087 - 31088 lbm/hr)

• Loop C - 29004.72792 lbm/hr (band 29004 - 29005 lbm/hr)

EVALUATORS NOTE:

The listed band was developed by rounding up or down to the nearest whole number.

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 11

_______ SAT Find the enthalpy of the blowdown, hbd, for each loop, using the Corrected Steam Pressure from Attachment 3 and the Enthalpy Saturated Liquid Table in 1-DRP-003. Record values _______ UNSAT in the appropriate boxes on Attachment 3, Page 1. (Step 6.2.10)

STANDARD:

a) Applicant locates Enthalpy Saturated Liquid Table in 1-DRP-003 (Attachment 73).

b) Determines hbd for each loop. Applicant may interpolate exact values or round to the nearest psia.

• Loop A - 515.00 BTU/lbm (band 514.83 - 515.17 BTU/lbm)

• Loop B - 514.83 BTU/lbm (band 514.66 - 515.00 BTU/lbm)

• Loop C - 514.66 BTU/lbm (band 514.49 - 514.83 BTU/lbm) c) Records values on Attachment 3.

EVALUATORS NOTE:

The listed band was developed by rounding steam pressure to the nearest psia, then taking the enthalpy value for +/-1 psia.

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

Page 8 of 18

Surry 2021-301 Calorimetric STEP 12

_______ SAT Calculate h2 = hs - hbd for each loop and record results in appropriate boxes on Attachment 3, Page 1. (Step 6.2.11) _______ UNSAT STANDARD:

Applicant calculates h2 and records values.

• Loop A - 683.54 BTU/lbm (band 683.34 - 683.74 BTU/lbm)

• Loop B - 683.74 BTU/lbm (band 683.54 - 683.94 BTU/lbm)

• Loop C - 683.94 BTU/lbm (band 683.74 - 684.14 BTU/lbm)

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

Listed band was developed by taking each respective loop hs(max) - hbd(min) for one limit, and hs(min) - hbd(max) for the other limit.

COMMENTS:

Page 9 of 18

Surry 2021-301 Calorimetric STEP 13

_______ SAT Perform the following for each loop: (Step 6.2.12)

_______ UNSAT

a. Calculate (Mf x h1) and (Mbd x h2) for each loop and record results in appropriate boxes on Attachment 3, Page 1

b. Calculate Qloop = (Mf x h1) - (Mbd x h2) for each loop and record results in appropriate boxes on Attachment 3, Page 1.

STANDARD:

a) Applicant calculates (Mf x h1) and (Mbd x h2) for each loop and record results in appropriate boxes on Attachment 3.

(Mbd x h2)

• Loop A - 19,533,935.10 BTU/hr (band 19,527,807.18 - 19,539,921.72 BTU/hr)

• Loop B - 21,255,567.45 BTU/hr (band 21,249,207.98 - 21,262,326.72 BTU/hr)

• Loop C - 19,837,493.61 BTU/hr (band 19,831,194.96 - 19,843,480.70 BTU/hr)

(Mf x h1)

• Loop A - 2,675,450,973 BTU/hr (band 2,674,976,200 - 2,675,925,747 BTU/hr)

• Loop B - 2,676,680,923 BTU/hr (band 2,676,205,949 - 2,677,155,897 BTU/hr)

• Loop C - 2,677,035,180 BTU/hr (band 2,676,560,162 - 2,677,510,199 BTU/hr) b) Applicant calculates Qloop = (Mf x h1) - (Mbd x h2) for each loop and record results in appropriate boxes on Attachment 3.

• Loop A - 2,655,917,038 BTU/hr (band 2,655,436,278 - 2,656,397,940 BTU/hr)

• Loop B - 2,655,425,356 BTU/hr (band 2,654,943,622 - 2,655,906,689 BTU/hr)

• Loop C - 2,657,197,686 BTU/hr (band 2,656,716,681 - 2,657,679,004 BTU/hr)

EVALUATORS NOTE:

• A completed table is attached at the end of this JPM showing all data.

• Listed band for Qbd based on: (mbd(min)) (h2(min)) AND (mbd(max)) (h2(max)).

• Listed band for Qfw based on: (mfw) (h1(min)) AND (mfw) (h1(max)).

• Listed band for Qloop based on [Qfw(max) - Qbd(min)], AND [Qfw(min) - Qbd(max)]

COMMENTS:

Page 10 of 18

Surry 2021-301 Calorimetric STEP 14

_______ SAT Convert Pressurizer Heat Input from KW to BTU/hr by multiplying by 3413.0 BTU/hr/KW, and record results in appropriate boxes on Attachment 3, Page 2. (Step 6.2.13) _______ UNSAT STANDARD:

a) Applicant multiplies PZR Heat Input (850.7 KW) by 3413.0 BTU/hr/KW.

b) Records 2,903,439.1 BTU/hr in appropriate block.

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

COMMENTS:

STEP 15 CRITICAL STEP

_______ SAT Calculate total heat from Reactor by using QTotal = Qloop A + Qloop B + Qloop C (BTU/hr) - PRZR HTR Input (BTU/hr) - RCP Heat Input (BTU/hr) + Letdown, Seal Injection, and Charging _______ UNSAT Heat Loss (BTU/hr) + Insulation Loss (BTU/hr). Record results in appropriate box on Attachment 3, Page 2 (Step 6.2.14)

STANDARD:

Applicant calculates QTotal.

• Qloop A + Qloop B + Qloop C = 7,968,540,080 BTU/hr (band 7,967,096,581 - 7,969,983,633 BTU/hr)

• -RCP Heat Input + Letdown, Seal Injection, and Charging Heat Loss +

Insulation Loss = - 18.78E6 BTU/hr

• -PZR Heat Input = 2,903,439.1 BTU/hr

• QT = 7,946,856,641 BTU/hr (band 7,945,413,142 - 7,948,300,194 BTU/hr)

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

Listed band for QloopTotal based on Qloop A+B+C(min) AND Qloop A+B+C(max).

Listed band for QT based on subtracting constants from Qlooptotal band.

COMMENTS:

Page 11 of 18

Surry 2021-301 Calorimetric STEP 16 CRITICAL STEP

_______ SAT Divide QT by 3.413 x 106 to find Reactor output in MWth. Record results in appropriate box on Attachment 3, Page 2. (Step 6.2.15) _______ UNSAT STANDARD:

Applicant calculates Reactor output in MWth.

• MWth = 7,946,856,641 BTU/hr ÷ 3413000

= 2,328.40804 (band 2,327.985 - 2,328.83099)

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

Listed band determined by dividing previous band limits by 3.413 E6.

COMMENTS:

STEP 17 CRITICAL STEP

_______ SAT Find the percent power level by using % Power = (MWth/2587) x 100.

Record results in appropriate box on Attachment 3, Page 2. (Step 6.2.16) _______ UNSAT STANDARD:

Applicant calculates % Reactor Power.

• % Power = (2,328.0804 ÷ 2587) MWth x 100

= 90.00 % (band 90.10% - 89.90%)

EVALUATORS NOTE:

A completed table is attached at the end of this JPM showing all data.

Band is based on rounding errors.

The Applicant may sign and date the Attachment at this time and report the JPM completed.

It is at the Evaluators discretion to continue the procedure.

COMMENTS:

Page 12 of 18

Surry 2021-301 Calorimetric STEP 18

_______ SAT IF the Manual Calorimetric Spreadsheet was used, THEN sign and date the computer generated printouts (performer and independent reviewer) and attach the printouts to this _______ UNSAT procedure. (Step 6.2.17)

STANDARD:

Applicant recalls that the Manual Calorimetric Spreadsheet was not used and enters N/A for the step.

EVALUATORS NOTE:

If asked: The Manual Calorimetric Spreadsheet was not used.

COMMENTS:

STEP 19

_______ SAT IF Attachment 3 was used, THEN sign and date Attachment 3 (performer and independent reviewer). (Step 6.2.18) _______ UNSAT STANDARD:

a) Applicant signs and dates Attachment 3.

b) Requests an Independent Verifier to check work.

EVALUATORS NOTE:

The Applicant may report the JPM complete at this time. It is at the Evaluators discretion to continue the procedure COMMENTS:

STEP 20

_______ SAT CAUTION To prevent exceeding maximum rated Reactor thermal power, Reactor power must not be _______ UNSAT increased based on the result of this calorimetric.

NOTE: Due to differences in the uncertainty calculations for Primary Plant Performance and the manual calorimetric, indicated power between the two may vary by 0.4%.

IF Reactor Power as calculated is greater than 98.4%, THEN perform the following: (Step 6.2.19)

a. Immediately reduce Reactor Power to less than 98.4% power IAW Attachment 4.

b. Terminate this procedure and reperform calorimetric.

STANDARD:

Applicant notes that Reactor Power is 90%. Enters N/A in both blocks.

COMMENTS:

Page 13 of 18

Surry 2021-301 Calorimetric STEP 21

_______ SAT Report to Shift Manager (Evaluator) completion of Task.

_______ UNSAT COMMENTS:

• • JPM COMPLETE **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Page 14 of 18

Surry Examiner Key Calorimetric LOOP A LOOP B LOOP C U9171 U9172 U9173 Corrected Steam Pressure (psia) 829.98 828.62 827.66 Enthalpy Steam hs (BTU/lbm) 1198.54 (1198.51-1198.57) 1198.57 (1198.54-1198.60) 1198.60 (1198.57-1198.63)

T0418A T0438A T0458A Feedwater Temp (°F) 431.16 431.16 431.16 Enthalpy FW hf (BTU/lbm) 409.61 (409.50-409.72) 409.61 (409.50-409.72) 409.61 (409.50-409.72) h1 = (hs-hf) BTU/lbm 788.93 (788.79-789.07) 788.96 (788.82-789.10) 788.99 (788.82-789.13)

(SG A) (SG B) (SG C)

Blowdown Flow (gpm) 57.540 62.593 58.400 x Conversion gpm to lbm/hr x 496.6563 x 496.6563 x 496.6563 Blowdown Flow Mbd (lbm/hr) 28,577.6035 (28577-28578) 31,087.20779 (31087-31088) 29,004.72792 (29004-29005)

Enthalpy hbd (BTU/lbm) 515.00 (514.83-515.17) 514.83 (514.66-515.00) 514.66 (514.49-514.83) h2 = (hs-hbd) BTU/lbm 683.54 (683.34-683.74) 683.74 (683.54-683.94) 683.94 (683.74-684.14) 19,533,935.10 (19,527,807.18- 21,255,567.45 (21,249,207.98- 19,837,493.61 (19,831,194.96-Mbd x h2 (BTU/hr) 19,539,921.72) 21,262,326.72) 19,843,480.70)

SG A Feed Flow SG B Feed Flow SG C Feed Flow Feedwater Flow Mfw (lbm/hr) 3391.24E3 3392.67E3 3392.99E3 2,675,450,973 (2,674,976,200- 2,676,680,923 (2,676,205,949- 2,677,035,180 (2,676,560,162-Mfw x h1 (BTU/hr) 2,675,925,747) 2,677,155,897) 2,677,510,199)

Qloop = ( Mfw x h1) - ( Mbd x h2) 2,655,917,038 (2,655,436,278- 2,655,425,356 (2,654,943,622- 2,657,197,686 (2,656,716,681-BTU/hr 2,656,397,940) 2,655,906,689) 2,657,679,004)

Pressurizer Heater Input (KW) 850.7 (Q0400A) x Conversion KW to BTU/hr x 3413 Pressurizer Heater Input = 2,903,439.1 (2.9E6)

Qloop A + Qloop B + Qloop C (BTU/hr) = 7,968,540,080 (7,967,096,581-7,969,983,633)

- RCP Input + Letdown, Charging, and Seal

- 18.78 x 106 BTU/hr Injection Losses + Insulation Losses

- Pressurizer Heater Input (BTU/hr) - 2903439.1 QT (BTU/hr) = 7,946,856,641 (7,945,413,142-7,948,300,194)

MWth = QT / 3413000 = 2,328.40804 MWth (2,327.985-2,328.83099)

% POWER = (MW/th / 2587) x 100 = 90.00417627% (89.90-90.10)

- Instructor-calculated values are in BOLD Italics.

Page 15 of 18

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit 1 is at a stable power and has been stable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. No periodic tests or calibration evolutions are in progress.

• Feed Water Ultrasonic Flow Measurement (UFM) is non-functional.

• The PCS Calorimetric program is otherwise functional.

• The following unit conditions exist:

- The Manual Calorimetric Spreadsheet will NOT be used.

- Feed Water Regulating Valve bypass valves are closed.

Initiating Cues

• Using the attached PP Output Summary sheet, perform Section 6.2 of 1-OPT-RX-003, Reactor Power Calorimetric using Feed Flow and PCS Computer Points (Manual).

• Your calculations should be performed as follows:

o Round off your calculations to four (4) significant digits.

o Do NOT use scientific notation.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 is at a stable power and has been stable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. No periodic tests or calibration evolutions are in progress.

• Feed Water Ultrasonic Flow Measurement (UFM) is non-functional.

• The PCS Calorimetric program is otherwise functional.

• The following unit conditions exist:

- The Manual Calorimetric Spreadsheet will NOT be used.

- Feed Water Regulating Valve bypass valves are closed.

Initiating Cues

• Using the attached PP Output Summary sheet, perform Section 6.2 of 1-OPT-RX-003, Reactor Power Calorimetric using Feed Flow and PCS Computer Points (Manual).

• Your calculations should be performed as follows:

o Round off your calculations to four (4) significant digits.

o Do NOT use scientific notation.

Surry 2021-301 Core Crew U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.1.5 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Determine shift Core Crew composition.

K/A: G.2.1.5 - Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (2.5/3.9)

Applicability Validation Time Actual Time SRO(I)(U) 15 Minutes ___________

Initial Conditions

• Task is PERFORMED in the CLASSROOM.

Standards

• Circles MET on the worksheet for the minimum D Shift complement.

• Lists the required actions in OP-AA-100: Attachment 2, 5.4.1 a and b on the worksheet.

Initiating Cue:

• You are to determine if the total D Shift complement requires a Condition Report.

• Based on current staffing, list all required actions to perform at the beginning of the shift.

• Record your answers on the attached form and submit them to me when complete.

Terminating Cues

• Completed worksheet given to the Evaluator.

Procedures

• OP-AA-100, Conduct Of Operations Tools and Equipment Safety Considerations

• Laptop for obtaining procedures

• None G2.2.12 SR21301

Surry 2021-301 Core Crew PERFORMANCE CHECKLIST Notes to the Evaluator.

• Task critical elements are bolded and noted by the words Critical Step at the end of the step.

• The Applicant is given a worksheet for this JPM.

• A laptop will be Available for the Applicant.

• START TIME: __________

STEP 1:

_______ SAT Review of requirements in OP-AA-100, Conduct Of Operations.

_______ UNSAT STANDARD:

(a) Locates Shift Staffing requirements in Attachment 2, Section 5.

(b) Notes at 5.2.1.b. that Core Crew requirement pertain to members that can stand watch in the Control Room:

a. Shift Manager

b. Unit Supervisor

c. Shift Technical Advisor

d. Reactor Operators (c) Determines that the Desk (WCC) SRO cannot be used to satisfy minimum core complement requirements.

EVALUATORS NOTE:

COMMENTS:

G2.2.12 SR21301

Surry 2021-301 Core Crew STEP 2: CRITICAL STEP

_______ SAT Evaluates current shift staffing against minimum core complement requirements.

_______ UNSAT STANDARD:

(a) Determines the following shift personnel meet the core crew requirements:

a. Shift Manager

b. Shift Technical Advisor (even if non-licensed)

c. U1 SRO

d. U1 OATC

e. U2 Asst RO (b) Notes in OP-AA-100 Att. 2 Step 5.2.1.d that 5 Core Crew members are required to meet minimum core compliment at Surry.

(c) Notes in OP-AA-100 Att. 2 Step 5.3.b that a CR is required when 5.2.1.d requirements are not met (in this case, they are MET).

(d) Circles NO on worksheet for Condition Report Required?

EVALUATOR NOTES:

COMMENTS:

STEP 3: CRITICAL STEP

_______ SAT Determines all required actions based on team members not being part of the Core Crew.

(OP-AA-100 Attachment 2) _______ UNSAT STANDARD:

(a) Determines the actions of 5.4.1 apply due to individuals on shift not being part of the Core Crew.

(b) Lists the required actions in OP-AA-100, Attachment 2, 5.4.1 a and b on the worksheet.

EVALUATOR NOTES:

• If the Candidate lists the specific procedure and step/substep numbers, it satisfies the CRITICAL STEP. (OP-AA-100, Attachment 2, 5.4.1.a. and b.)

COMMENTS:

G2.2.12 SR21301

Surry 2021-301 Core Crew STEP 4:

_______ SAT Turns in attached worksheet.

_______ UNSAT STANDARD:

EVALUATORS NOTE:

• Acknowledge the completion of the task.

COMMENTS:

STOP TIME: __________

G2.2.12 SR21301

Surry 2021-301 Core Crew EXAMINER REFERENCE MATERIAL:

Definititions:

A. Core Crew- Requires EVERY member of the associated crew members in order to be met (SM, both SROs, STA, and all ROs).

B. Minimum Core Complement- Requires at least 5 of the associated crew members of the team to be Core Crew members in order to be met.

From OP-AA-100, Attachment 2. CORE CREW requirement and MINIMUM CORE COMPLEMENT requirement:

G2.2.12 SR21301

Surry 2021-301 Core Crew EXAMINER KEY:

1. Condition Report required? YES / NO (circle one)

2. List all required actions for current staffing:

(From OP-AA-100, Attachment 2, 5.4.1.a. and b.)

G2.2.12 SR21301

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Both units are at 100% power.

• You are a Tagging office RO, who has been called in to work as the Unit 1 Assistant RO.

• An RO normally assigned to this shift called out sick.

• Todays shift complement is as follows:

o SM - core crew o STA (non-SRO licensed) - core crew o Desk (WCC) SRO - NOT core Crew o U1 SRO - core crew o U1 OATC - core crew o U1 Asst RO - (You) o U2 SRO - NOT core crew o U2 OATC -NOT core crew o U2 Asst RO - core crew Initiating Cue:

• You are to perform the following:

1) Determine if the total D Shift complement requires a Condition Report.

2) Based on your determination, list all required actions to perform at the beginning of the shift.

• Record your answers on the attached form and submit them to me when complete.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Both units are at 100% power.

• You are a Tagging office RO, who has been called in to work as the Unit 1 Assistant RO.

• An RO normally assigned to this shift called out sick.

• Todays shift complement is as follows:

o SM - core crew o STA (non-SRO licensed) - core crew o Desk (WCC) SRO - NOT core Crew o U1 SRO - core crew o U1 OATC - core crew o U1 Asst RO - (You) o U2 SRO - NOT core crew o U2 OATC -NOT core crew o U2 Asst RO - core crew Initiating Cue:

• You are to perform the following:

1) Determine if the total D Shift complement requires a Condition Report.

2) Based on your determination, list all required actions to perform at the beginning of the shift.

• Record your answers on the attached form and submit them to me when complete.

Applicant name: ___________________________

1. Condition Report required? YES / NO (circle one)

2. List all required actions based on current staffing:

Surry 2021-301 Determine Tagout Boundaries U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.2.13 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Determine Tagging Boundaries K/A: G.2.2.13 - Knowledge of Tagging and Clearance Procedures. (4.1/4.3)

Applicability Validation Time Actual Time SRO(I)(U) 30 Minutes ___________

Initial Conditions

• Task is PERFORMED in the CLASSROOM.

Standards

• Submits table with Component IDs and required positions in accordance with Boundary A in Step 4, OR

• Submits table with Component IDs and required positions in accordance with Boundary B in Step 4.

• Submits correct sequence of tagged components in the following order: 1) electrical supply, 2) isolation valves,

3) drains and vents.

Initiating Cues

• Using the provided Station Drawings, you are to determine a tagging boundary adequate to support removal of 1-RT-27.

• On the attached table, list all components and their required positions.

Terminating Cues

• Attached table is completed and submitted.

Procedures

• OP-AA-200, Equipment Clearance

• 11448-FM-124A Sheet 2

• 11448-FE-1K G2.2.13 SR10301 1 of 14

Surry 2021-301 Determine Tagout Boundaries Tools and Equipment Safety Considerations

• Laptop for obtaining procedures

• None

• 11448-FM-124A Sheet 2

• 11448-FE-1K

• High lighters G2.2.13 SR10301 2 of 14

Surry 2021-301 Determine Tagout Boundaries PERFORMANCE CHECKLIST Notes to the Evaluator.

• Task critical elements are bolded and noted by the words Critical Step at the end of the step.

• A laptop will be Available for the Applicant.

• START TIME: __________

STEP 1:

_______ SAT Reviews the initial conditions of the JPM and refers to the drawings and OP-AA-200, Equipment Clearance. _______ UNSAT STANDARD:

(a) Utilizes DocTop to obtain OP-AA-200, EVALUATORS NOTE:

• If asked, provide candidate with system to drawing number summary sheet.

COMMENTS:

G2.2.13 SR10301 3 of 14

Surry 2021-301 Determine Tagout Boundaries STEP 2: CRITICAL STEP

_______ SAT Reviews electrical drawing 11448-FE-1K and identifies the electrical boundary (480V supply breaker) _______ UNSAT STANDARD:

(a) Notes that 1-EP-BKR-1A2-1-4B will need to be opened This is a critical step.

(b) Notes that 1-EP-BKR-1A2-1-4B will need to be the first tagged component in the tagout. The sequencing is a critical step.

EVALUATOR NOTES:

• Candidate may also no tag the control switch in OFF.

• Component ID and required position are both critical.

COMMENTS:

G2.2.13 SR10301 4 of 14

Surry 2021-301 Determine Tagout Boundaries STEP 3: CRITICAL STEP

_______ SAT Reviews mechanical drawing 11448-FM-124A SH2 and identifies the mechanical boundaries (suction, discharge, vent, and drain) _______ UNSAT NOTE TO EVALUATOR:

There are two possible safe working boundaries for this component. They are listed below as Boundary A and Boundary B. All components for one choice are required for a safe working boundary.

STANDARD:

Isolation valves - For the selected Boundary, all CLOSED isolation valves must be included AND sequenced after the breaker tag in the previous step.

Boundary A Boundary B RT Suction Isol - CLOSED RT Suction Isol - CLOSED RT Pump ALT suction - CLOSED RT-37(38) - Suction Isol - CLOSED RT Chem injection Isol - CLOSED RT Chem injection Isol - CLOSED RT Discharge isol - CLOSED RT Discharge isol - CLOSED RT Discharge isol - CLOSED RT Pump Suction - OPEN (Not CS)

RT Pump Suction - OPEN (Not CS)

Vents/Drains - Numerous Vents/drains exists - at least one of the following drains and at least one of the following vents shall be open. These must be sequenced after the Isolation valves.

Boundary A Boundary B RT Suction drain - OPEN RT Suction drain - OPEN RT Suction drain - OPEN RT Suction drain - OPEN RT Discharge drain - OPEN RT Discharge drain - OPEN RT Suction Vent - OPEN RT Suction Vent - OPEN RT Disch Vent - OPEN with PI removed RT Disch Vent - OPEN with PI Removed RT Loop Drain - OPEN RT Suction Vent - OPEN - if 1-RT-38 used instead of 1-RT-37.

The correct sequence (breaker, isolations, vent/drain) is also required to satisfy the critical step.

EVALUATOR NOTES:

• Component ID and required position are both critical.

• If asked RT-S-1B will not be removed from the system.

COMMENTS:

G2.2.13 SR10301 5 of 14

Surry 2021-301 Determine Tagout Boundaries STEP 4 (Boundary A): CRITICAL STEP

_______ SAT Completes the attached table and reports that the task is complete.

_______ UNSAT STANDARD:

Table is completed as follows:

Boundary A Component ID Number / Name Position 1 1-RT-P-1B Control Switch OFF 2 1-EP-BKR-1A2-1-4B (B RT Pump OFF Supply Breaker) 3 1-RT Pump Suction Isolation CLOSED 3 1-RT Pump ALT Suction CLOSED 3 1-RT Chem Injection Isol CLOSED 3 1-RT Pump Discharge Isol CLOSED 3 1-RT Pump Discharge Isol CLOSED 3 1-RT Pump Suction OPEN At least one of the following Drains 4 1-RT Suction Drain OPEN 4 1-RT Suction Drain OPEN 4 1-RT Discharge Drain OPEN At least one of the following Vents 4 1-RT Suction Vent OPEN 4 1-RT Discharge Vent OPEN w/ PI Removed EVALUATORS NOTE:

• With the RT system at static head pressure, all isolation valves may be sequenced in any order, as long as they are AFTER the breaker and BEFORE the vents and drains, to satisfy the Critical Step.

• Because the Candidate cannot walk down the RT system, all vents and drains may sequenced in any order, as long as they are AFTER all isolation valves, to satisfy the Critical Step.

• Minimum of 1 vent and 1 drain required. Additional vents/drains may be utilized.

• Meeting all requirements of Boundary A or Boundary B Satisfies the Critical Step.

COMMENTS:

G2.2.13 SR10301 6 of 14

Surry 2021-301 Determine Tagout Boundaries STEP 4 (Boundary B): CRITICAL STEP, continued

_______ SAT Completes the attached table and reports that the task is complete.

_______ UNSAT STANDARD:

Table is completed as follows:

Boundary B Component ID Number / Name Position 1 1-RT-P-1B Control Switch OFF 2 1-EP-BKR-1A2-1-4B (B RT Pump OFF Supply Breaker) 3 1-RT Pump Suction Isolation CLOSED 3 1-RT-37/38 - Pump Suction Isol CLOSED 3 1-RT Chem Injection Isol CLOSED 3 1-RT Pump Discharge Isol CLOSED 3 1-RT Pump Suction OPEN At least one of the following Drains 4 1-RT Suction Drain OPEN 4 1-RT Suction Drain OPEN 4 1-RT Discharge Drain OPEN 4 1-RT Loop Drain OPEN At least one of the following Vents 4 1-RT Suction Vent OPEN 4 1-RT Discharge Vent OPEN w/ PI Removed 4 1-RT Suction Vent OPEN EVALUATORs NOTE - ONLY IF 1-RT-38 used vs. 1-RT-37 EVALUATORS NOTE:

• With the RT system at static head pressure, all isolation valves may be sequenced in any order, as long as they are AFTER the breaker and BEFORE the vents and drains, to satisfy the Critical Step.

• Because the Candidate cannot walk down the RT system, all vents and drains may sequenced in any order, as long as they are AFTER all isolation valves, to satisfy the Critical Step.

• Minimum of 1 vent and 1 drain required. Additional vents/drains may be utilized.

• Meeting all requirements of Boundary A or Boundary B Satisfies the Critical Step.

COMMENTS:

G2.2.13 SR10301 7 of 14

Surry 2021-301 Determine Tagout Boundaries STOP TIME: _____________

G2.2.13 SR10301 8 of 14

Surry 2021-301 Determine Tagout Boundaries From 11448-FE-1K, Breaker for 1-RT-P-1B:

G2.2.13 SR10301 9 of 14

Surry 2021-301 Determine Tagout Boundaries Boundary A Valves:

G2.2.13 SR10301 10 of 14

Surry 2021-301 Determine Tagout Boundaries Boundary B Valves:

G2.2.13 SR10301 11 of 14

Surry 2021-301 Determine Tagging Boundaries Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Unit One is at Refueling Shutdown. The Unit 1 B S/G Recirc Transfer system is secured, in preparation for tagout.

• A temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). The B RT pump normal suction valve, 1-RT-27, must be removed to install the suction blank.

• The suction strainer (1-RT-S-1B) will not be removed from the system.

• The eSOMS Clearance Module is not operational.

Initiating Cues

• Using the provided Station Drawings, you are to determine a tagging boundary adequate to support removal of 1-RT-27.

• On the attached table, list all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

• For this JPM, correct tagging sequence is required.

• For this JPM, component noun names are not required.

• When you have completed the attached table, inform an examiner.

G2.2.13 SR21301 11 of 14

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit One is at Refueling Shutdown. The Unit 1 B S/G Recirc Transfer system is secured, in preparation for tagout.

• A temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). The B RT pump normal suction valve, 1-RT-27, must be removed to install the suction blank.

• The suction strainer (1-RT-S-1B) will not be removed from the system.

• The eSOMS Clearance Module is not operational.

Initiating Cues

• Using the provided Station Drawings, you are to determine a tagging boundary adequate to support removal of 1-RT-27.

• On the attached table, list all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

• For this JPM, correct tagging sequence is required.

• For this JPM, component noun names are not required.

• When you have completed the attached table, inform an examiner.

G2.2.13 SR21301

(TO BE GIVEN TO APPLICANT)

Applicant Name: __________________________________________________

Tag sequence Component ID Number Position G2.2.13 SR21301

Surry 2021-301 RWP Adequacy U.S. Nuclear Regulatory Commission Surry Power Station SR09301 Administrative Job Performance Measure 2.3.7 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Determine the applicability of a RWP for a specific job and determine which personnel may be assigned the task based on personal qualifications and dose limitations.

K/A: G2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

(3.5/3.6)

Applicability Validation Time Actual Time RO 10 Minutes Conditions

• Task is to be PERFORMED in the classroom.

• 1-BR-E-10A (Gas Stripper Steam Heater) has developed external leakage and requires isolation and tagging to minimize contamination.

Standards

• Calculate dose received to perform a task when given survey maps and equipment location at 320 mrem.

• Determine Operator # 1 cannot perform the task because he is not qualified on the watchstation.

• Determine Operator # 2 cannot perform the task because he would exceed 85% of the admin dose limits (1700 mREM).

• Determine Operator # 3 can perform the task.

• Determine that work cannot be performed with current RWP because the dose received would be greater than the RWP Dose limit.

Initiating Cues

• Shift Manager direction Terminating Cues RWP compliance and personnel selection complete.

Procedures

• VPAP-2101 - Radiation Protection Program G2.3.7 SR09301 1 of 13

Surry 2021-301 RWP Adequacy Question 1: Determine the dose received.

Assume the following Initial Conditions:

• 1-BR-E-10A (Gas Stripper Steam Heater) is to be tagged out and drained due to a suspected tube leak.

• This task will take one Operator 64 minutes to complete, working the entire time in the vicinity of the heat exchanger.

• All valves that will be manipulated or tagged are located in the immediate vicinity of the heat exchanger.

Included are copies of the Radiological Survey Map and an ALARA Component Locator Map for the area.

You are to determine:

1- Dose received by one operator to complete this task.

300mr (dose rate in area) X 64 min (time for task completion) X 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> hour 60 minutes ANSWER- 320 mrem - this is a critical task G2.3.7 SR09301 2 of 13

Surry 2021-301 RWP Adequacy Question 2: Determine which operators can perform the task Qualification Level Total dose received year to date Operator #1 Step 4 1247 mrem Operator #2 Stepped Out 1600 mrem Operator #3 Step 6 1278 mrem (1) Which operator(s) could be assigned to perform this task based on qualification level and total dose? Include in your answer a reason why any operator cannot perform the task (Assume no dose upgrades will be authorized).

Standard:

Bolded & underlined text items are CRITICAL STEPS.

Operator #1: CANNOT be assigned the task. The Operator is not qualified on that Watchstation. The Operator must have completed step 5 in order to perform tasks in the Auxiliary Building.

Operator #2: CANNOT be assigned the task. The Operator would exceed 85% of the admin limits (1700 mRem//Yr). If task were performed, the additional 320 mr would put the operator at 1920 mRem which is over the 85% of the admin limit. VPAP-2101 (next page) states that RCA Access will be denied until an upgrade is approved.

Operator #3: CAN be assigned the task. The Operator is qualified on the Watchstation and their quarterly dose is below the administrative limit.

G2.3.7 SR09301 3 of 13

Surry 2021-301 RWP Adequacy VPAP-2101 Excerpts G2.3.7 SR09301 4 of 13

Surry 2021-301 RWP Adequacy Question 3:Determine if this task can be performed under RWP 09-0-1003-2 (attached) with one entry only, and provide justification for your answer.

• This task CANNOT be performed under RWP 09-0-1003 This determination (CANNOT) is a critical task

• Expected dose to be received, 320 mr, is above the RWP Dose limit of 100 mr - This reason (in excess of RWP dose limit) is a critical task STOP TIME:

NOTES:

G2.3.7 SR09301 5 of 13

Surry 2021-301 RWP Adequacy Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• 1-BR-E-10A (Gas Stripper Steam Heater) is to be tagged out and drained due to a suspected tube leak.

• This task will take one Operator 64 minutes to complete, working the entire time in the vicinity of the heat exchanger.

• All valves that will be manipulated or tagged are located in the immediate vicinity of the heat exchanger.

• The following operators listed below with their Qualification level and Total Year to Date Dose is listed below:

Qualification Level Total dose received year to date Operator #1 Step 4 1247 mrem Operator #2 Stepped Out 1600 mrem Operator #3 Step 6 1278 mrem Initiating Cue:

• Attached to this JPM are copies of the Radiological Survey Map and an ALARA Component Locator Map for the area.

• You are to answer the following questions on the attached sheet:

1) What is the total dose received by one operator to complete this task?

2) Which operator(s) could be assigned to perform this task based on qualification level and total dose? Include in your answer a reason why any operator cannot perform the task (Assume no dose upgrades will be authorized).

3) Can this task be performed under the attached RWP with one entry, and with no changes to the RWP? Provide justification for your answer if the task cannot be performed with this RWP.

G2.3.7 SR09301 6 of 13

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• 1-BR-E-10A (Gas Stripper Steam Heater) is to be tagged out and drained due to a suspected tube leak.

• This task will take one Operator 64 minutes to complete, working the entire time in the vicinity of the heat exchanger.

• All valves that will be manipulated or tagged are located in the immediate vicinity of the heat exchangers.

• The following operators listed below with their Qualification level and Total Year to Date Dose is listed below:

Qualification Level Total dose received year to date Operator #1 Step 4 1247 mrem Operator #2 Stepped Out 1600 mrem Operator #3 Step 6 1278 mrem Initiating Cue:

• Attached to this JPM are copies of the Radiological Survey Map and an ALARA Component Locator Map for the area.

• You are to answer the following questions on the attached Answer sheet:

1) What is the total dose received by one operator to complete this task?

2) Which operator(s) could be assigned to perform this task based on qualification level and total dose? Include in your answer a reason why any operator cannot perform the task (Assume no dose upgrades will be authorized).

3) Can this task be performed under the attached RWP with one entry, and with no changes to the RWP? Provide justification for your answer if the task cannot be performed with this RWP.

JPM ANSWER SHEET NAME________________

1) The total dose received by one operator is _________ mrem.

2) Which of the following Operators can perform this task?

Operator #1 - Qualification Level = Step 4; Total Dose = 1247 mrem CAN / CANNOT perform the task (circle one).

Justification-Operator #2 - Qualification Level = Stepped Out; Total Dose = 1600 mrem CAN / CANNOT perform the task (circle one).

Justification-Operator #3 - Qualification Level = Step 6; Total Dose = 1278 mrem CAN / CANNOT perform the task (circle one).

Justification-

3) Can this task be performed under this RWP as written? If the task cannot be performed provide reason in space below:

This task CAN / CANNOT be performed under RWP 09-0-1003-2.

Circle One Justification:

Surry 2021-301 PT Review U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.2.12 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Review 1-PT-41.1, Component Cooling Water Pumps Performance Test K/A: G.2.2.12 - Knowledge of surveillance procedures. (3.7/4.1)

Applicability Validation Time Actual Time SRO(I)(U) 30 Minutes ___________

Initial Conditions

• Task is PERFORMED in the CLASSROOM.

Standards

• Identifies 1-CC-P-1A delta-P is in the INOP range per Attachment 1.

• Identifies 1-CC-P-1B vibration point 9 is in the INOP range per Attachment 2.

• Determines that Technical Specification 3.13.B requires restoring three CC pumps to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If three pumps cannot be restored to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then the reactor must be placed in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Initiating Cues

• Here is the completed 1-PT-41.1, Component Cooling Water Pumps Performance Test.

• You are to perform the Shift Supervision review of 1-PT-41.1.

• When you have completed this task please inform me so the Unit 2 team can commence performance of 2-PT-41.1.

Terminating Cues

• Review of 1-PT-41.1 is complete and Tech Specs reviewed.

Procedures

• 1-PT-41.1, Component Cooling Water Pumps Performance Test

• Tech Spec 3.13 SR21301 10 of 12

Surry 2021-301 PT Review Tools and Equipment Safety Considerations

• Laptop for obtaining procedures

• None

• Completed copy of 1-PT-41.1 SR21301 20 of 12

Surry 2021-301 PT Review PERFORMANCE CHECKLIST Notes to the Evaluator.

• Task critical elements are bolded and noted by the words Critical Step at the end of the step.

• The Applicant is given a completed copy of 1-PT-41.1.

• A laptop will be Available for the Applicant.

• START TIME: __________

STEP 1:

_______ SAT Review of 1-PT-41.1 procedure body.

_______ UNSAT STANDARD:

(a) Starts review of the procedure, starting at Section 6.1.

(b) Identifies Step 6.3.1 is not initialed.

(c) Identifies that all notes at the beginning of Section 6.5 are not circle/slashed.

(d) Identifies the operator who performed Attachment 6 did not sign the table at Step 7.3.1.

EVALUATORS NOTE:

• Evaluator may direct the Applicant to provide comments after completing the 1-PT-41.1 review.

COMMENTS:

SR21301 30 of 12

Surry 2021-301 PT Review STEP 2: CRITICAL STEP

_______ SAT Evaluate the test results by reviewing the Acceptance criteria for the components tested. (Step 7.1.1, substep a.) _______ UNSAT

• 1-CC-P-1A - P and Vibration Values (Attachment 1) are not in the INOP Range.

STANDARD:

(a) Reviews data in Attachment 1.

(b) Identifies P is in the INOP range (not in the SAT range).

EVALUATOR NOTES:

• Evaluator may direct the Applicant to provide comments after completing the 1-PT-41.1 review.

COMMENTS:

STEP 3: CRITICAL STEP

_______ SAT Evaluate the test results by reviewing the Acceptance criteria for the components tested. (Step 7.1.1, substep b.) _______ UNSAT

• 1-CC-P-1B - P and Vibration Values (Attachment 2) are not in the INOP Range.

STANDARD:

(a) Reviews data in Attachment 2.

(b) Identifies Inboard Vibration (pt. 9) is in the INOP range (not in the SAT range).

EVALUATOR NOTES:

• Evaluator may direct the Applicant to provide comments after completing the 1-PT-41.1 review.

COMMENTS:

SR21301 40 of 12

Surry 2021-301 PT Review STEP 4:

_______ SAT Evaluate the test results by reviewing the Acceptance criteria for the components tested. (Step 7.1.1, substep c.) _______ UNSAT

• 1-CC-557, 1-CC-P-1A Discharge Check Valve, functioned correctly (Step 6.5.14 CC-557 fully closed).

STANDARD:

(a) Reviews Step 6.5.14 and determines 1-CC-557 fully closed.

EVALUATOR NOTES:

COMMENTS:

SR21301 50 of 12

Surry 2021-301 PT Review STEP 5:

Evaluate the test results by reviewing the Acceptance criteria for the components tested. (Step 7.1.1, substep d.)

• 1-CC-563, 1-CC-P-1B Discharge Check Valve, functioned correctly (Step 6.4.14 CC-563 fully closed).

STANDARD:

(a) Reviews Step 6.4.14 and determines 1-CC-563 fully closed.

EVALUATOR NOTES:

COMMENTS:

SR21301 60 of 12

Surry 2021-301 PT Review STEP 6:

_______ SAT Document the test results. (Step 7.1.2)

_______ UNSAT STANDARD:

(a) Determines the test is unsatisfactory.

(b) Determines 1-CC-P-1A is INOPERABLE.

(c) Determines 1-CC-P-1B is INOPERABLE.

EVALUATOR NOTES:

• Evaluator may direct the Applicant to provide comments after completing the 1-PT-41.1 review.

COMMENTS:

STEP 7:

_______ SAT Report results of 1-PT-41.1 to Shift Manager

_______ UNSAT STANDARD:

(a) Informs Shift Manager that 1-PT-41.1 is UNSAT for 1-CC-P-1A and 1-CC-P-1B.

EVALUATOR NOTES:

COMMENTS:

SR21301 70 of 12

Surry 2021-301 PT Review STEP 8: CRITICAL STEP Review of Tech Specs for applicability.

STANDARD:

(a) Determines that Technical Spec 3.13.B requires restoring three CC pumps to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If three pumps cannot be restored to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then the reactor must be placed in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

EVALUATOR NOTES:

• With both units at power, 3 of 4 CC pumps are required to be operable.

COMMENTS:

END OF JPM STOP TIME: __________

SR21301 80 of 12

Surry 2021-301 PT Review Summary of 1-PT-41.1 conflicts:

CRITICAL STEPS:

• Attachment 1, identifies Delta P for 1-CC-P-1A is in the INOP range (below SAT and ALERT ranges).

• Attachment 2, identifies Vibration pt. 9 for 1-CC-P-1B is in the INOP range.

• Determines that Technical Spec 3.13.B requires restoring three CC pumps to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If three pumps cannot be restored to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then the reactor must be placed in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Non-critical steps:

• Identifies Step 6.3.1 is not initialed.

• Identifies the Notes at beginning of Section 6.5 Not circle/slashed.

• Identifies the operator who performed Attachment 6 did not sign the table at Step 7.3.1.

SR21301 90 of 12

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Both Units are at 100% power.

• The Unit 1 team has just finished performing 1-PT-41.1, Component Cooling Water Pumps Performance Test.

• The Unit 2 team is scheduled to perform 2-PT-41.1, Component Cooling Water Pumps Performance Test, after the 1-PT-41.1 Supervisor review is complete.

Initiating Cue:

• Here is the completed 1-PT-41.1, Component Cooling Water Pumps Performance Test.

• You are to perform the Shift Supervision review of 1-PT-41.1, and determine if Tech Spec requirements are met.

• Document your answers on the attached sheet.

SR21301 10 of 12

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Both Units are at 100% power.

• The Unit 1 team has just finished performing 1-PT-41.1, Component Cooling Water Pumps Performance Test.

• The Unit 2 team is scheduled to perform 2-PT-41.1, Component Cooling Water Pumps Performance Test, after the 1-PT-41.1 Supervisor review is complete.

Initiating Cue:

• Here is the completed 1-PT-41.1, Component Cooling Water Pumps Performance Test.

• You are to perform the Shift Supervision review of 1-PT-41.1, and determine if Tech Spec requirements are met.

• Document your answers on the attached sheet.

Applicant name: ___________________________

1. 1-PT-41.1 test result : SAT / UNSAT (circle one)

2. Discrepancies noted, if any:

3. Tech Spec requirements MET / NOT MET (circle one)

If NOT MET, what are the Tech Spec required actions?

Surry 2021-301 Auth Fuel Move U.S. Nuclear Regulatory Commission Surry Power Station SR2021301 Administrative Job Performance Measure G2.1.40 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Authorize Fuel Movement K/A: G2.1.40 Knowledge of refueling administrative procedures (2.8/3.9)

Applicability Estimated Time Actual Time SRO(I)/SRO(U) 20 Minutes Conditions

• Task is to be PERFORMED in the simulator.

Standards

• Determines 1-VG-RI-131A is inoperable, which will prevent fuel movement per TS 3.10.B.1.

• Determines 1-VS-AC-1, and 1-VS-AC-2 are inoperable which will prevent fuel movement per TS 3.10.A.14.

• Only the above two conditions must be identified. Identification of any other condition will constitute unsatisfactory performance.

Procedures

• 1-OSP-ZZ-004, Unit 1 Safety Systems Status List For Cold Shutdown/Refueling Conditions.

• Technical Specifications Tools and Equipment Safety Considerations

• None

• None

Surry 2021-301 Auth Fuel Move Simulator Set-up

• Recall IC 390 (Protected) or (IC35 25% Cold Cal) and ensure that RHR pump discharge and RCS temperatures are below 140 oF.

• Align HHSI and fill pressurizer to 56.5% cold cal if necessary.

Fail Rad Monitor 1-VG-RI-131A HI by inserting Malf RM0701.

Fail Vent Stack #2 Rad Mon TRBS, 0-RMA-D5 by inserting Malf KAD5.

Verify Alarms 0-RMA-D6, VENT STACK #2 PART ALERT/HI is lit.

Simulate failure of MCR AHUs 1-VS-AC-1, and 1-VS-AC-2 by overriding red AND green lights OFF.

• Tagout 1-RH-P-1B and place a red magnet above control switch.

• VERIFY 1-RC-LR-100, RCS STANDPIPE RECORDER is turned ON.

• Override SR SUR bench board and backboard meters to 0 DPM:

o NI31D to 9%

o NI32D to 9%

o CR_STARTUP_RT_N35 to ON.

• Turn OFF SR Audio count rate.

This JPM is to be Pre-briefed.

Surry 2021-301 Auth Fuel Move PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• Determination of items to be in non-compliance that actually are in compliance constitutes a critical step failure.

• START TIME: _________________

STEP 1: _______ SAT Refueling Containment Integrity set. _______ UNSAT Remarks:

IAW 1-OP-FH-001 STANDARD:

_____ Recalls (or refers to) turnover statement that refuel integrity is SET.

_____ Initials in D block for Refueling Containment Integrity set EVALUATOR NOTES:

• If asked: The shift manager has verified that refueling integrity is set as directed by 1-OP-FH-001.

COMMENTS:

Surry 2021-301 Auth Fuel Move CRITICAL STEP STEP 2: _______ SAT Radiation Monitors Operable: _______ UNSAT

• Manipulator Crane 1 operable

• Containment Gaseous 1 operable

• Containment Particulate 1 operable

• SFP Bridge 1 operable

• Vent-Vent Gaseous 1 operable

• Vent-Vent Particulate 0 operable Remarks:

Alarms 0-RMA-D6 is LIT.

STANDARD:

_____ Examines each radiation monitor and verifies normal readings.

_____ Determines radiation monitor 1-VG-RI-131A inoperability prevents fuel movement. CRITICAL STEP.

_____ Determines that Tech Spec 3.10.B.1 is not met.

EVALUATOR NOTES:

• If asked: Radiation monitors are as they appear.

• Shown is 1-VG-RI-131A.

• If asked: Have candidate continue and identify any other problems.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 3: _______ SAT Source Range Detectors (audible indication in CTMT must be verified operable) _______ UNSAT

• 2 operable Remarks: None STANDARD:

_____ Observes normal indication on NI-31

_____ Observes normal indication on NI-32.

EVALUATOR NOTES:

• If asked: there is discernible audible count rate in containment.

COMMENTS:

STEP 4: _______ SAT Cavity level > 23 feet. _______ UNSAT Remarks:

OU-SU-201, should be maintained as high as possible. No fuel movement permitted if < 23 feet in Cavity STANDARD:

_____ Recalls (or refers to) turnover statement that cavity level is 26.5.

_____ Determines that adequate cavity level exists to support fuel movement.

EVALUATOR NOTES:

• If asked: cavity level has been verified at 26.5.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 5: _______ SAT RHR pump and Heat Exchanger: _______ UNSAT Cavity Level > 23 feet 1 operable Cavity Level < 23 feet 2 operable STANDARD:

_____ Recalls (or refers to) turnover statement that cavity level is 26.5.

_____ Observes 1 RHR pump in operation and one tagged out.

_____ Determines that with present cavity level and operable RHR pump, fuel movement can commence.

EVALUATOR NOTES:

• If asked: cavity level has been verified at 26.5.

COMMENTS:

STEP 6: _______ SAT Direct communication between the Control Room and Manipulator Crane _______ UNSAT Remarks: When changing core geometry STANDARD:

_____ Recalls (or refers to) turnover statement that communications have been established.

_____ Determines that communication capability allows for fuel movement.

EVALUATOR NOTES:

• If asked: operator is in the MCR equipped with a headset in communication with the refueling team.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 7: _______ SAT RCS Boron concentration- 2350 PPM (Admin limit) _______ UNSAT Remarks:

RCS must be sampled at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the head is unbolted (Not required if defueled and cavity is drained below flange level. (Ref 2.3.15)

STANDARD:

_____ Recalls (or refers to) turnover statement that RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

_____ Determines that current boron concentration allows for fuel movement.

EVALUATOR NOTES:

• If asked: RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

COMMENTS:

STEP 8: _______ SAT RHR Temperature: 140 °F _______ UNSAT Remarks: None STANDARD:

_____ Observes RHR pump discharge temperature and determines that current RCS temperature allows for fuel movement.

EVALUATOR NOTES:

• If asked: All RCS loops are isolated and drained.

• If asked: All CETCs have been disconnected.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 9: _______ SAT Reactor shutdown greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> _______ UNSAT Remarks: For movement of irradiated fuel STANDARD:

_____ Recalls (or refers to) turnover statement that unit has been shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br />.

_____ Determines that sufficient time from shutdown exists to allow fuel movement.

EVALUATOR NOTES:

• If asked: The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

COMMENTS:

STEP 10: _______ SAT Control Room and Relay Room Emergency Ventilation- 2 Trains _______ UNSAT Remarks: None STANDARD:

_____ Examines current configuration of MCR/ESGR ventilation and determines that all fans are available.

_____ Determines that current MCR/ESGR Emergency Ventilation configuration allows for fuel movement by observing the configuration of 1-VS-F-41/42 and 2-VS-F-41/42.

EVALUATOR NOTES:

• If asked: Conditions are as they appear.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 11: _______ SAT Control Room Chillers- 3 minimum _______ UNSAT Remarks: Operable IAW power supply requirements of TS 3.23 STANDARD:

_____ Examines current configuration of MCR chillers and determines that all chillers are available.

_____ Determines that current MCR Chiller configuration allows for fuel movement by observing the configuration of 1-VS-E-4A, B, C, D, E.

EVALUATOR NOTES:

• If asked: Conditions are as they appear.

COMMENTS:

Surry 2021-301 Auth Fuel Move CRITICAL STEP STEP 12: _______ SAT MCR/ESGR AHU- 8 minimum _______ UNSAT Remarks: Selected AHUs should be in operation STANDARD:

_____ Examines current configuration of MCR/ESGR air handlers and determines that MCR Air Handling Units 1-VS-AC-1 AND 1-VS-AC-2 are NOT operating. CRITICAL STEP.

_____ Determines that per TECH SPECS 3.10.A.14 we need at least one Unit 1 MCR AHU in operation for fuel movement, therefore Fuel movement is NOT allowed.

CRITICAL STEP.

EVALUATOR NOTES:

• If an operator is dispatched locally to 1-VS-AC-1, and 1-VS-AC-2: The AHUs supply breakers are both tripped with no indication as to the reason they are tripped. No other abnormalities noted.

• IF asked: Light bulbs have been checked and they are good.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 13: _______ SAT 120 Volt Vital Buses- 2 minimum _______ UNSAT Remarks: None STANDARD:

_____ Observes that all vital busses are energized and NO UPS/Battery charger alarms are LIT.

_____ Recalls (or refers to) turnover statement that all vital bus UPS are in a normal EVALUATOR NOTES:

• If asked: All vital bus UPS are in a normal configuration.

• If asked: Both station batteries are operable and split out.

COMMENTS:

STEP 14: _______ SAT SFP Cooling- 1 train available _______ UNSAT Remarks: None STANDARD:

_____ Observes that one spent fuel cooling pump is in service.

_____ Recalls (or refers to) turnover statement that both trains of SFP cooling are available with one in service.

EVALUATOR NOTES:

• If asked: both trains of SFP cooling are available with one in service.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 16: _______ SAT SFP makeup borated water source- 1 source available _______ UNSAT Remarks: None STANDARD:

_____ Recalls (or refers to) turnover statement that all make-up flowpaths to the SFP are available.

EVALUATOR NOTES:

• If asked: All make-up flowpaths to the SFP are available.

COMMENTS:

Surry 2021-301 Auth Fuel Move STEP 17: _______ SAT Reports to Shift Manager that task is complete _______ UNSAT STANDARD:

_____ Reports that fuel movement CANNOT commence until the following problems are resolved:

• 1-VG-RI-131A must be returned to operable status.

• 1-VS-AC-1, AND 1-VS-AC-2 must be returned to operable status.

EVALUATOR NOTES:

• Cue: Ask applicant: Are there any Tech Specs LCOs that are preventing fuel movement? Answer: Yes, TS 3.10.B.1 (Rad monitor required for Fuel Bldg.); TS 3.10.A.14 for CR AHUs.

COMMENTS:

STOP TIME_______________________________________:

Surry 2021-301 Auth Fuel Move Surry EXAMINER KEY Auth Fuel Move Surry EXAMINER KEY Auth Fuel Move Surry EXAMINER KEY Auth Fuel Move Surry EXAMINER KEY Auth Fuel Move Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Unit 1 is at Refueling Shutdown with the head and upper internals removed. A request from the refueling SRO has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004.

• Current conditions are as follows (items not observable from the control room):

o It is 0800 day shift.

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

o The Source Range Count Rate is audible in Containment.

• Headset communications between the MCR and the manipulator crane have been verified.

• The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues

• You are to verify plant conditions support fuel movement (core offload) by reviewing 1-OSP-ZZ-004.

• If conditions do not allow fuel movement to begin, then identify ALL issues, including Tech Spec requirements, that prohibit fuel movement.

• If conditions support fuel movement then notify the examiner that fuel movement may begin.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Unit 1 is at Refueling Shutdown with the head and upper internals removed. A request from the refueling SRO has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004.

• Current conditions are as follows (items not observable from the control room):

o It is 0800 day shift.

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

o The Source Range Count Rate is audible in Containment.

• Headset communications between the MCR and the manipulator crane have been verified.

• The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues

• You are to verify plant conditions support fuel movement (core offload) by reviewing 1-OSP-ZZ-004.

• If conditions do not allow fuel movement to begin, then identify ALL issues, including Tech Spec requirements that prohibit fuel movement.

• If conditions support fuel movement then notify the examiner that fuel movement may begin.

Surry 2021-301 Determine CTMT Partial Pressure U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.1.20 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Determine Partial Pressure following a Loss of Containment Cooling K/A: G2.1.20 - Ability to interpret and execute procedure steps. (4.6/4.6)

Applicability Validation Time Actual Time SRO(I)(U) 12 Minutes ___________

Initial Conditions

• Task is PERFORMED in the CLASSROOM.

Standards

• Obtains Tcont2 from PCS and determines T cont2 is 128oF, and records this on Attachment 3.

• Utilizing the 8/25/21 PT-36 determines that Tcont1 is 118.38, and records this on Attachment 3.

• Determines that the pre-event Containment Partial Pressure is 10.25 psia, and records this on Attachment 3.

• Determines Containment Partial Pressure, Pair2 is 10.42 psia (allowable tolerance -.01/+.01).

• Determines that Tech Specs Figure 3.8.D.1.a is required; restore air partial pressure to within acceptable limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Initiating Cues

• Given simulated plant conditions, perform Attachment 2 of Annunciator Response Procedure (ARP) 1B-A6, Containment Pressure -0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

Terminating Cues

• Steps 1-7 of Attachment 2 of ARP 1B-A6 are complete.

Procedures

• Attachment 2 of procedure 1B-A6, CTMT PRESS -0.1 PSI CH 1

• Tech Spec 3.8

Surry 2021-301 Determine CTMT Partial Pressure Tools and Equipment Safety Considerations

• Calculator

• None

• Tech Specs

• DRP-003

• Ruler

Surry 2021-301 Determine CTMT Partial Pressure PERFORMANCE CHECKLIST Notes to the Evaluator.

• Task critical elements are bolded and noted by the words Critical Step at the end of the step.

• START TIME: __________

STEP 1:

_______ SAT Notes prior to Step 1 of Attachment 2:

_______ UNSAT

• This calculation must be performed within one hour after Partial Pressure indication is declared inoperable and hourly thereafter.

• Determining partial pressure using local containment samples is required within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of declaring Partial Pressure indication inoperable and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> thereafter.

• Bleeding air into containment or running Containment Vacuum pumps will require Engineering or STA calculations.

• Partial pressure calculated using ideal gas laws is expected to rise as Containment Weighted Average rises.

• Partial pressure determined using local samples is more accurate and should be used if there is a difference in results between partial pressure determined using local samples and ideal gas law calculations.

• Determining Partial Pressure (PAir2 ) using the Ideal Gas Law is obtained from the formula Pair2 = (Tcont2 / T cont1 ) Pair 1 .

o Pair1 is the highest Containment Partial Pressure reading from the last valid 1-PT-36 reading.

o Tcont1 is the Containment Weighted Average Temperature reading from the last valid 1-PT-36 reading.

o Tcont2 is the current Containment Weighted Average Temperature.

• Determinig partial pressure (P air) is obtained from the formula Ptot - Psat = Pair

• Ptot is CTMT pressure from one of the following:

o The highest of 1-CV-PI-101A or 1-CV-PI-101B o The highest of Unit 1 PCS points P1LM002A, P1LM003A, P1LM001A, or P1LM004A

• Determining Psat relies on measurement of dew point or relative humidity, since the actual saturation temperature is a function of both dry-bulb temperature and relative humidity.

STANDARD:

(a) Acknowledges the notes.

EVALUATORS NOTE:

• If asked, it is desired to perform this calculation now.

• If asked, no containment air samples have been taken.

COMMENTS:

Surry 2021-301 Determine CTMT Partial Pressure STEP 2:

_______ SAT Step 1 of Attachment 2:

_______ UNSAT

1. Record the Date and Time in the Calculation of CTMT Air Partial Pressure Using Ideal Gas Law Data Table in Attachment 3.

STANDARD:

a) Records Date of 08/25/21 and Time of 2200 in Attachment 3.

EVALUATOR NOTES:

Attachment 3 will be filled out as follows:

Date/Time Tcont2 Tcont1 Pair1 Pair2 Initials 8/25/21:2200 COMMENTS:

STEP 3: CRITICAL STEP Step 2 of Attachment 2:

2. Obtain Tcont2 (current Containment Weighted Average Temperature) using PCS point U0091 and record in Attachment 3.

STANDARD:

a) Obtains Tcont2 from PCS Attachment and determines T cont2 is 128oF, and records this on Attachment 3. CRITICAL STEP EVALUATOR NOTES:

• Tcont2 can be determined using PCS by calling up CONT SPRAY DWG, CONT TEMP DWG, or by calling up individual point U0091.

• Cue: If mouse is hovered over or right click on CTMT Weighted Average Temp on PCS, computer point U0091 will appear.

Attachment 3 will be filled out as follows:

Date/Time Tcont2 Tcont1 Pair1 Pair2 Initials 8/25/21:2200 128oF COMMENTS:

Surry 2021-301 Determine CTMT Partial Pressure STEP 4: CRITICAL STEP

_______ SAT Step 3 of Attachment 2:

_______ UNSAT

3. Obtain Tcont1 (pre-event Containment Weighted Average Temperature) using the last valid 1-PT-36 log reading and record in Attachment 3.

STANDARD:

a) Utilizing the PT-36 determines that Tcont1 is 118.38, and records this on Attachment 3. CRITICAL STEP EVALUATOR NOTES:

• This information can be found on page 25 of 1-PT-36.

Attachment will be filled out as follows:

Date/Time Tcont2 Tcont1 Pair1 Pair2 Initials 8/25/21:2200 128oF 118.38 oF COMMENTS:

STEP 5: CRITICAL STEP Step 4 of Attachment 2:

4. Obtain Pair1 (pre-event Containment Partial Pressure) using the highest Containment Partial Pressure reading from the last valid 1-PT-36 log reading and record in Attachment 3.

STANDARD:

a) Determines that the pre-event Containment Partial Pressure is 10.25 psia, and records this on Attachment 3. CRITICAL STEP.

EVALUATOR NOTES:

Attachment 3 will be filled out as follows:

Date/Time Tcont2 Tcont1 Pair1 Pair2 Initials 8/25/21:2200 128oF 118.38 oF 10.25 COMMENTS:

Surry 2021-301 Determine CTMT Partial Pressure STEP 6: CRITICAL STEP

_______ SAT Step 5 of Attachment 2

_______ UNSAT

5. Determine Pair2 (current Containment Partial Pressure ) IAW the following:

a) Calculate Pair2 = [(Tcont2 + 459.6oF) / (Tcont1 + 459.6oF)] x Pair1 STANDARD:

a) Determines Pair2 is 10.42 psia (allowable tolerance -.01/+.01).

Pair2 = [(128 oF + 459.6oF) / (118.38 oF + 459.6oF)] x 10.25 psia EVALUATOR NOTES:

Attachment 3 will be filled out as follows (using PCS data):

Date/Time Tcont2 Tcont1 Pair1 Pair2 Initials 8/25/21:2200 128oF 118.38 oF 10.25 psia 10.42 psia COMMENTS:

STEP 7:

_______ SAT Step 6 of Attachment 2

_______ UNSAT

6. IF air has been bled into Containment OR Containment Vacuum Pumps have been in service since the last partial pressure reading, THEN contact Engineering or the STA to calculate change in containment air per ETS SU 2020-0057, Containment Air Partial Pressure Calculation.

STANDARD:

Determines air has not been bled into containment.

EVALUATOR NOTES:

CUE: If asked, inform applicant that air has NOT been bled into containment.

COMMENTS:

Surry 2021-301 Determine CTMT Partial Pressure STEP 7: CRITICAL STEP Step 7 of Attachment 2

7. Verify CTMT Air Partial Pressure is within Tech Spec 3.8-1 limits.

STANDARD:

a) Obtains a copy of Tech Specs and refers to Figure 3.8-1 and determines that Tech Spec 3.8.D.1.a is required; restore air partial pressure to within acceptable limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. CRITICAL STEP EVALUATOR NOTES:

• Given information: CW inlet temp will be 98F.

• If report is given that partial pressure is outside of Table 3.8-1 limits, ask the applicant to determine and report applicable LCO limits and actions required.

COMMENTS:

Surry 2021-301 Determine CTMT Partial Pressure STEP 8:

_______ SAT Reports task is complete.

_______ UNSAT STANDARD:

EVALUATORS NOTE:

• Acknowledge the completion of the task.

COMMENTS:

END OF JPM STOP TIME_____:

Surry Examiners Key Determine CTMT Partial Pressure 138.2 DEGF 131.8 DEGF 138.4 DEGF 103.4 DEGF 128.0 DEGF 137.6 DEGF 122.3 DEGF 111.4 DEGF 125.6 DEGF 119.6 DEGF 119.7 DEGF 109.0 DEGF 116.5 DEGF 112.7 DEGF 92.5 DEGF 128.2 DEGF 132.3 DEGF 109.3 DEGF 113.0 DEGF 128.0 DEGF

Surry Examiners Key Determine CTMT Partial Pressure OUTLET TEMP OUTLET TEMP OUTLET TEMP OUTLET TEMP 101.0 DEGF 101.0 DEGF 100.0 DEGF 101.0 DEGF INLET TEMP INLET TEMP INLET TEMP INLET TEMP 98.0 DEG 98.0 DEG 98.0 DEG 98.0 DEG

Snapshot of TS FIG. 3.8-1

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Both Units are at 100% power.

• Today is 08/25/2021, 2200 and this is the 4th day in a row with ambient temperatures above 100 oF.

• Containment Cooling was being supplied by Chilled Water with Chiller 1-CD-REF-1A in operation. 1-CD-REF-1B is non-functional due to breaker maintenance.

• Approximately 30 minutes ago the operating chilled water system chiller tripped. As a result, annunciators 1B-A6 (CTMT PART PRESS -0.1 PSI CH 1) and 1B-B6 (CTMT PART PRESS -0.1 PSI CH 2) were received.

• The Containment Partial pressure indicators were declared inoperable 15 minutes ago.

• The operating team has implemented ARP-1B-A6 up to the point of implementing Attachment 2.

• Maintenance has determined that the chiller will not be returned to service until tomorrow.

• Air has NOT been bled into Containment, AND Containment Vacuum pumps have not been run in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• No Containment sample has been taken.

Initiating Cue:

• Here is a copy of Attachment 2 of Annunciator Response Procedure (ARP) 1B-A6, Containment Pressure -0.1 PSI Channel 1, Attachment 3, PCS Screen shots, AND the latest PT-36 Operator Log excerpts.

• I need you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B-A6, steps 1-7, to Determine Containment Partial Pressure and Technical Specification Compliance. Write your answers on the attached Answer sheet.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Both Units are at 100% power.

• Today is 08/25/2021, 2200 and this is the 4th day in a row with ambient temperatures above 100 oF.

• Containment Cooling was being supplied by Chilled Water with Chiller 1-CD-REF-1A in operation. 1-CD-REF-1B is non-functional due to breaker maintenance.

• Approximately 30 minutes ago the operating chilled water system chiller tripped. As a result, annunciators 1B-A6 (CTMT PART PRESS -0.1 PSI CH 1) and 1B-B6 (CTMT PART PRESS -0.1 PSI CH 2) were received.

• The Containment Partial pressure indicators were declared inoperable 15 minutes ago.

• The operating team has implemented ARP-1B-A6 up to the point of implementing Attachment 2.

• Maintenance has determined that the chiller will not be returned to service until tomorrow.

• Air has NOT been bled into Containment, AND Containment Vacuum pumps have not been run in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• No Containment sample has been taken.

Initiating Cue:

• Here is a copy of Attachment 2 of Annunciator Response Procedure (ARP) 1B-A6, Containment Pressure -0.1 PSI Channel 1, Attachment 3, PCS Screen shots, AND the latest PT-36 Operator Log excerpts.

• I need you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B-A6, steps 1-7, to Determine Containment Partial Pressure and Technical Specification Compliance. Write your answers on the attached Answer sheet.

NAME:_________________________

Partial Pressure (Pair2) = ____________psia Applicable Tech Spec Section________.

Tech Spec Required Actions (if any):

CONT PARTIAL PRESS CH1

• 08/25/2021 21:00 10.25 Barttels, Joshua 08/25/2021 15:00 10.25 Dunlevy, James 08/25/2021 09:00 10.20 Goodman, Ian Blake 08/24/2021 03:00 10.20 Shcroth, John CONT PARTIAL PRESS CH2

• 08/25/2021 21:00 10.25 Barttels, Joshua 08/25/2021 15:00 10.20 Dunlevy, James 08/25/2021 09:00 10.19 Goodman, Ian Blake 08/24/2021 03:00 10.19 Shcroth, John U0091 PCS WEIGHTED AVG CONT TEMP 08/25/2021 21:00 118.38 Barttels, Joshua 08/25/2021 15:00 117.50 Dunlevy, James 08/25/2021 09:00 117.05 Goodman, Ian Blake 08/24/2021 03:00 116.20 Shcroth, John

138.2 DEGF 131.8 DEGF 138.4 DEGF 103.4 DEGF 128.0 DEGF 137.6 DEGF 122.3 DEGF 111.4 DEGF 125.6 DEGF 119.6 DEGF 119.7 DEGF 109.0 DEGF 116.5 DEGF 112.7 DEGF 92.5 DEGF 128.2 DEGF 132.3 DEGF 109.3 DEGF 113.0 DEGF 128.0 DEGF

OUTLET TEMP OUTLET TEMP OUTLET TEMP OUTLET TEMP 101.0 DEGF 101.0 DEGF 100.0 DEGF 101.0 DEGF INLET TEMP INLET TEMP INLET TEMP INLET TEMP 98.0 DEG 98.0 DEG 98.0 DEG 98.0 DEG

Surry 2021-301 Determine PAR U.S. Nuclear Regulatory Commission Surry Power Station SR19301 Administrative Job Performance Measure G2.4.44 TIME CRITICAL Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title DETERMINE REQUIRED PAR ACTIONS K/A: G2.4.44 - Knowledge of emergency plan protective action recommendations. (2.4/4.4)

Applicability Validation Time Actual Time SRO ONLY 15 Minutes (Time Critical) ___________

Conditions

• Task is to be PERFORMED in the CLASSROOM.

Standards

• Determine PAR+ Evacuate 2 mile radious, and 2-5 miles downwind in sectors A, B, and C.

• Completes Attachment 3 correctly by including the following:

o Check mark in Evacuate box. Fills in 2 mile radius and 2-5 miles downwind in sectors A, B, C.

o Check mark in Recommend KI.

o Signs for approval to transmit.

Initiating Cues

• PAR part: A GE has just been declared.

Terminating Cues

• EPIP-1.06, Step 4 Completed.

Procedures

• EPIP-1.06, Protective Action Recommendations, Revision 11.

Tools and Equipment

• SEM EP Notebooks (3)

• Digital clock.

Page 1 of 9

Surry 2021-301 Determine PAR Performance Checklist Notes to the Evaluator.

• Task critical elements are bolded.

• The JPM will be read aloud to the whole group. Ask for questions, and use same start time for everyone.

• TIME CRITICAL REQUIREMENT:

The PAR must be determined within 15 minutes after the applicant indicated he/she is ready.

• Use the Digital clock to record start and stop times.

• START TIME:

STEP 1

_______ SAT Obtains and Initiates EPIP-1.06. (Step 1)

_______ UNSAT STANDARD:

a) Acknowledges NOTE before Step 1 that Attachments 4 and 5 may be used for reference.

b) Initiates procedure by filling out name, date, and time.

EVALUATORS NOTE:

COMMENTS:

STEP 2 CRITICAL STEP

_______ SAT USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION FLOWCHART SPS, TO DETERMINE INITIAL PAR. (Step 2) _______ UNSAT STANDARD:

a) Applicant uses Attachment 1 (flowchart) to determine the initial PAR.

b) Severe Accident = NO c) Hostile Action = NO d) Dose Assessment Available = Yes e) PAR = Evacuate: 2 mile radius and 2-5 miles downwind miles downwind.

CRITICAL STEP EVALUATORS NOTE:

COMMENTS:

Page 2 of 9

Surry 2021-301 Determine PAR STEP 3 CRITICAL STEP

_______ SAT IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP. (Step 3)

_______ UNSAT STANDARD:

a) Acknowledges NOTE before Step 3 that Attachment 2 is used for EPIP-1.06 PARs only, not EPIP-4.07 PARs.

b) Applicant implements Attachment 2 to determine affected sector(s). Applicant will round up 191.5 to 192.

- Acknowledges NOTE regarding rounding of wind direction up or down.

- Records time data acquired.

- Records wind direction from 192°.

- Records wind speed of 15 mph.

- Uses table to determine that the affected sectors are A, B, C and records on attachment. CRITICAL STEP

- Marks the affected sectors on map using pen, pencil, highlighter, etc.

EVALUATORS NOTE:

COMMENTS Page 3 of 9

Surry 2021-301 Determine PAR STEP 4 CRITICAL STEP

_______ SAT COMPLETE ATACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION.

(Step 4 and Attachment 3) _______ UNSAT STANDARD:

Applicant completes Attachment 3:

- Records #1 in PAR MESSAGE space.

- Acknowledges NOTES to transmit PAR to Virginia EOC only using ARD, autodial, or direct dial. Only use Insta-Phone if all other methods of contacting VEOC are non-functional.

- Places check mark in Drill Message box, or Emergency Message for Protective Actions box.

- Places check mark in EVACUATE box. Fills in (0-2) Mile radius 360° and 5 (2-

5) miles downwind in the following sectors: A, B, C. CRITICAL STEP

- Places check mark in Recommend implementation of Potassium Iodide (KI) for general public. CRITICAL STEP

- Acknowledges NOTE in REMARKS block regarding Shelter-in-Place recommendations.

- Record Notes (Optional).

- Signs for approval to transmit. CRITICAL STEP Records current date and time.

EVALUATORS NOTE:

This step must be complete within 15 minutes of start of task.

Record STOP Time: ________

COMMENTS COMMENTS Page 4 of 9

EXAMINER KEY EXAMINER KEY Time 191.5 A, B, C

EXAMINER KEY Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER )

Initial Conditions

• A General Emergency has just been declared (use current date/time).

• CETC temperature is 580 oF.

• The State and Local Communicator has determined wind direction to be from 191.5° and wind speed to be 15 mph.

• On site and Off site Dose Assessment teams have been dispatched.

The RAD reports the following dose at the Site boundary and 2 mile locations from the Dose monitoring teams:

Site Boundary 2 miles TEDE 1.05 REM 0.9 REM Adult Thyroid CDE 3.4 REM 2.2 REM Child Thyroid CDE 5.1 REM 3.3 REM Initiating Cues

• This JPM is TIME CRITICAL.

• You are to determine the Protective Action Recommendations, by performing steps 1-4 of EPIP-1.06, Report of Protective Action Recommendations.

• IMMEDIATELY Raise your hand when you have completed step 4 of EPIP-1.06.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A General Emergency has just been declared (use current date/time).

• CETC temperature is 580 oF.

• The State and Local Communicator has determined wind direction to be from 191.5° and wind speed to be 15 mph.

• On site and Off site Dose Assessment teams have been dispatched.

The RAD reports the following dose at the Site boundary and 2 mile locations from the Dose monitoring teams:

Site 2 miles Boundary TEDE 1.05 REM 0.9 REM Adult Thyroid CDE 3.4 REM 2.2 REM Child Thyroid CDE 5.1 REM 3.3 REM Initiating Cues

• This JPM is TIME CRITICAL.

• You are to determine the Protective Action Recommendations, by performing steps 1-4 of EPIP-1.06, Report of Protective Action Recommendations.

• IMMEDIATELY Raise your hand when you have completed step 4 of EPIP-1.06.

IMMEDIATELY RAISE YOUR HAND WHEN YOU HAVE COMPLETED ATTACHMENT 3.

U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure 2.3.13 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Perform Containment Entry Checklist K/A: G2.3.13 - Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (3.4/3.8)

Applicability Estimated Time Actual Time SRO(I)/SRO(U) 17 minutes Initial Conditions

• Task is PERFORMED in the CLASSROOM.

Standards

• Determines Incore detectors are not tagged out as required.

• Determines next Containment entry will exceed Tech Spec 3.8.B.1.b. limits due to exceeding 60 cumulative minutes within a year.

Initiating Cues Given simulated plant conditions, perform Attachment 1 of VPAP-0106, Subatmospheric Containment Entry, to evaluate preparation for Containment Entry and Technical Specification Compliance.

Terminating Cues

• VPAP-0106, attachment 1 assessment complete.

Procedures

• VPAP-0106, Subatmospheric Containment Entry.

• Tech Spec 3.8 Tools and Equipment Safety Considerations

• Laptop to access procedures

• None

• Tech Specs

Terminating Cues

• Applicant has completed the attachment, discussed results and problems with examiner, and determined the next Containment entry cannot be performed as stated.

Tools and Equipment

• VPAP-0106, Attachment 1

• Technical Specifications

• RWP 1012 Safety Considerations

• None Notes

PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and noted by the words Critical Step at the end of the step.

• The Applicant is given an initiated copy of VPAP-0106 Attachment 1.

• A laptop will be Available for the Applicant.

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME: _________________

STEP 1:

_______ SAT Review of Part 1 of VPAP-0106 Attachment 1.

_______ UNSAT STANDARD:

(a) Starts review of Attachment 1, starting at Part 1.

(b) Identifies no discrepancies in Part 1.

EVALUATORS NOTE:

COMMENTS:

STEP 2: CRITICAL STEP _______ SAT Review of Part 2 of VPAP-0106 Attachment 1. _______ UNSAT STANDARD:

(a) Determines total Outer Door open time will be 62 minutes after the next entry.

(b) Based on the Note in the same section, determines the estimated Outer Door times for the next entry will exceed the cumulative limit of one hour per year per Tech Spec 3.8.B.1.b.

EVALUATORS NOTE:

• If notified that the cumulative Outer Door open time will exceed the one hour limit, inform the Applicant that the times for the next entry are being re-evaluated, and direct them to continue the review of Attachment 1 Parts 1 through 4.

COMMENTS:

STEP 3: CRITICAL STEP _______ SAT Review of Parts 3 and 4 of VPAP-0106 Attachment 1. _______ UNSAT STANDARD:

(a) Completes review of Part 3 of Attachment 1 with no discrepancies.

(b) Ensures no other actions are underway or scheduled which may change containment conditions during the entry.

(c) Identifies Tag-Out of incore detectors is NOT hung in accordance with OP-AA-200, Equipment Clearance, based on Initial conditions and the N/A entered for this item in Part 4.

EVALUATOR NOTES:

• If asked: there are no other activities underway or scheduled that may impact containment conditions.

• If asked: inform the Applicant the tag has been removed from the Unit 2 incore detector system to support Unit 2 flux mapping.

• When notified that the incore detectors are not properly tagged out, inform the Applicant that another SRO will pursue removal of the Temp Lift.

COMMENTS:

STEP 17: _______ SAT Reports to Shift Manager that review is complete _______ UNSAT STANDARD:

(a) Reports the Unit 2 Containment entry cannot be made at this time.

(b) Submits the list of discrepancies.

EVALUATOR NOTES:

• An answer key is provided in this JPM with the list of discrepancies.

COMMENTS:

STOP TIME________________________:

EXAMINER ANSWER KEY Unit 2 Containment Entry IS / IS NOT permitted (circle ONE)

If containment entry cannot be performed, provide the reason(s) and/or applicable Tech Spec requirements that prohibit entry:

1. Cumulative Outer door total accumulated open time will exceed 1 hour/year. Tech Spec 3.8.B.1.b will be exceeded if the containment entry was performed.

2. Incore detectors are not tagged out as required.

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Unit 2 is at 100% power.

• The Unit 2 containment personnel hatch is inoperable due to excessive inner door seal leakage.

• Multiple U2 Containment entries have been made this week, to support investigation and repair of the Inner Door seal.

• Procedure 2-NPT-RX-002, Reactor Core Flux Maps, is in progress to satisfy a Tech Spec requirement.

• Current Unit 2 Containment personnel hatch status is as follows:

o The last Unit 2 Containment entry was performed last shift.

o The Outer Door has been open this week for a cumulative time of 50 minutes.

• The projected Outer door open times are as follows for the next Containment entry:

o During Personnel Hatch entry, the Outer door will be open for 5 minutes.

o During Personnel Hatch exit, the Outer door will be open for 7 minutes.

• The SRO who had the roles of Responsible Supervisor/Shift Manager for the next Unit 2 Containment entry had to leave the station.

Initiating Cues

• Your task is to determine whether or not Unit 2 Containment entry is permitted. Completion of VPAP-0106, Attachment 1 is NOT required.

• If you identify containment entry can be performed, then inform the examiner.

• If you identify containment entry cannot be performed, provide ALL the reason(s) that prohibit entry.

• If applicable, include any Tech Spec requirements that prohibit entry.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Unit 2 is at 100% power.

• The Unit 2 containment personnel hatch is inoperable due to excessive inner door seal leakage.

• Multiple U2 Containment entries have been made this week, to support investigation and repair of the Inner Door seal.

• Procedure 2-NPT-RX-002, Reactor Core Flux Maps, is in progress to satisfy a Tech Spec requirement.

• Current Unit 2 Containment personnel hatch status is as follows:

o The last Unit 2 Containment entry was performed last shift.

o The Outer Door has been open this week for a cumulative time of 50 minutes.

• The projected Outer door open times are as follows for the next Containment entry:

o During Personnel Hatch entry, the Outer door will be open for 5 minutes.

o During Personnel Hatch exit, the Outer door will be open for 7 minutes.

• The SRO who had the roles of Responsible Supervisor/Shift Manager for the next Unit 2 Containment entry had to leave the station.

Initiating Cues

• Your task is to determine whether or not Unit 2 Containment entry is permitted. Completion of VPAP-0106, Attachment 1 is NOT required.

• If you identify containment entry can be performed, then inform the examiner.

• If you identify containment entry cannot be performed, provide ALL the reason(s) that prohibit entry.

• If applicable, include any Tech Spec requirements that prohibit entry.

Applicant name: ___________________________

Unit 2 Containment Entry IS / IS NOT permitted (circle ONE)

If containment entry cannot be performed, provide the reason(s) and/or applicable Tech Spec requirements that prohibit entry:

U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Administrative Job Performance Measure G2.1.7 Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title Perform a Quadrant Power Tilt Calculation.

K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. [4.4/4.7]

Applicability Validation Time Actual Time RO 30 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Calculates Tilt % for Upper channels between 7.40% - 7.50%.

• Calculates Tilt % for Lower channels between 9.35% - 9.45%.

• Reports a Tech Spec LCO (Clock) is in effect based on exceeding 2% Quadrant Power Tilt.

Initiating Cues

• A dropped rod has occurred on Unit 1.

• A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System Malfunction.

Terminating Cues

• Applicant has completed the QPTR calculation.

Procedures

• 0- AP-1.00, Rod Control System Malfunction Tools and Equipment Safety Considerations

• Calculator and Laptop

• None

• NI/RM Info book

PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• START TIME_______:

STEP 1:

_______ SAT Step 1 NOTE:

Calculations for QPTR should be carried out to four places to the right of the decimal place _______ UNSAT to provide for accuracy and consistency of results.

STANDARD:

a) Acknowledges NOTE.

EVALUATORS NOTE:

COMMENTS:

STEP 2:

_______ SAT RECORD THE FOLLOWING DATA (Step 2)

_______ UNSAT Reactor Power___________% Date____________ Time____________

STANDARD:

a) Enters 100% for Reactor power.

b) Enters todays date.

c) Enters current time.

EVALUATORS NOTE:

If Asked: Current Reactor Power is 100%.

If Asked: Use todays date.

If Asked: Use current time.

COMMENTS:

STEP 3:

_______ SAT RECORD THE FOLLOWING EXCORE DETECTOR DATA. (Step 2)

• Actual Excore Detector Readings. _______ UNSAT

• Expected Excore Detector Readings.

STANDARD:

a) Places PR NI currents and Normalized Currents (from NI/RM Info book) in appropriate location on Calculation of Excore Quadrant Power Tilt Ratios.

EVALUATORS NOTE:

COMMENTS:

STEP 4:

_______ SAT NORMALIZE THE UPPER DETECTOR READINGS. (Step 3)

_______ UNSAT STANDARD:

a) Divides Upper Detector currents by Normalized currents for each detector.

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 5:

_______ SAT SUM OF NORMALIZED VALUES FOR THE UPPER DETECTORS. (Step 3)

_______ UNSAT STANDARD:

a) Adds Upper Detector Normalized values for all Upper detectors.

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 6:

_______ SAT NORMALIZE THE LOWER DETECTOR READINGS. (Step 3)

_______ UNSAT STANDARD:

a) Divides Lower Detector currents by Normalized currents for each detector.

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 7:

_______ SAT SUM OF NORMALIZED VALUES FOR THE LOWER DETECTORS. (Step 3)

_______ UNSAT STANDARD:

a) Adds Lower Detector Normalized values for all Lower detectors.

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 8:

_______ SAT RECORD THE NUMBER OF DETECTORS IN USE. (Step 4)

_______ UNSAT STANDARD:

a) Records 4 EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 9:

_______ SAT CALCULATE AVERAGE UPPER AND LOWER DETECTOR CURRENT VALUES. (Step 5)

_______ UNSAT STANDARD:

a) Transcribes Upper and Lower detector Sum of Normalized Values from Step 3 of Attachment 6.

b) Divides each sum by the number of Detectors in use.

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 10:

_______ SAT RECORD THE MAXIMUM NORMALIZED UPPER AND LOWER DETECTOR CURRENTS.

(Step 6) _______ UNSAT STANDARD:

a) Records the Maximum Normalized Upper Detector Current from Step 3 (N42 value of 1.0135).

b) Records the Maximum Normalized Lower Detector Current from Step 3 (N42 value of 1.0176).

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 11:

_______ SAT CALCULATE MAXIMUM UPPER AND LOWER EXCORE QUADRANT POWER TILT RATIOS.

(Step 7) _______ UNSAT STANDARD:

a) Divides Maximum Upper channel current by the Average Upper Detector currents to determine the Upper Excore Quadrant Power Tilt Ratio (1.0745).

b) Divides Maximum Lower channel current by the Average Lower Detector currents to determine the Lower Excore Quadrant Power Tilt Ratio (1.0940).

EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 12: CRITICAL STEP

_______ SAT CALCULATE TILT%. (Step 8)

_______ UNSAT STANDARD:

a) Calculates Tilt % for Upper channels between 7.4% - 7.5% (7.45%). CRITICAL STEP b) Calculates Tilt % for Lower channels between 9.35% - 9.45% (9.40%). CRITICAL STEP EVALUATORS NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

STEP 13: CRITICAL STEP DETERMINES IF A TECH SPEC LCO IS IN EFFECT.

STANDARD:

• Determines QPT exceeds the 2% limit in Tech Specs.

• Reports a Tech Spec LCO (Clock) is in effect based on exceeding 2% Quadrant Power Tilt. CRITICAL STEP EVALUATORS NOTE:

• If desired, ask the Applicant to identify which Tech Spec LCO sections require Charging Pump operability. Answer: Tech Spec section 3.12 requires Quadrant Power Tilt to be within 2%.

• If Asked: Inform the Candidate another operator will be responsible for Step 10.

COMMENTS:

STEP 14:

_______ SAT NOTIFY UNIT SUPERVISOR. (Step 9)

_______ UNSAT STANDARD:

a) Turns in Attachment 1.

EVALUATORS NOTE:

If Asked: Inform the Candidate another operator will be responsible for Step 10.

COMMENTS:

STOP TIME:

EXAMINER KEY 118.8 118.7 119.1 1.0000 1.0000 118.7 119.1 3.7728 3.7206

EXAMINER KEY 3.7728 0.9432 3.7206 0.9302 1.0135 1.0176 1.0745 1.0940 7.45% (7.40-7.50%)

9.40% (9.35-9.45%)

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions:

• Unit 1 was operating at 100% power.

o Control Rod K-4, Control Bank B, dropped and is currently indicating 0 steps.

o The team is performing 0-AP-1.00, Rod Control Malfunction.

o Shutdown Margin has just been verified.

• You are provided a copy of the NI/RM Info book providing Normalized Values.

Initiating Cues

• Perform the Quadrant Power Tilt (QPT) Calculation in accordance with Steps 1 through 8 of 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

• The current date/time is to be used in Attachment 6 Step 1.

• When steps 1 through 8 are complete, you are to report the following:

o The results of Step 8.

o Based on these results, is a Tech Spec LCO in effect? (Yes/No, including the reason for your determination)

• Report your results to the examiner.

Actual current detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 94.0 N-41 Lower Detector Current 89.5 N-42 Upper Detector Current 120.1 N-42 Lower Detector Current 121.4 N-43 Upper Detector Current 115.3 N-43 Lower Detector Current 114.0 N-44 Upper Detector Current 118.7 N-44 Lower Detector Current 119.1

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

• Unit 1 was operating at 100% power.

o Control Rod K-4, Control Bank B, dropped and is currently indicating 0 steps.

o The team is performing 0-AP-1.00, Rod Control Malfunction.

o Shutdown Margin has just been verified.

• You are provided a copy of the NI/RM Info book providing Normalized Values.

Initiating Cues

• Perform the Quadrant Power Tilt (QPT) Calculation in accordance with Steps 1 through 8 of 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

• The current date/time is to be used in Attachment 6 Step 1.

• When steps 1 through 8 are complete, you are to report the following:

o The results of Step 8.

o Based on these results, is a Tech Spec LCO in effect? (Yes/No, including the reason for your determination)

• Report your results to the examiner.

Actual current detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 94.0 N-41 Lower Detector Current 89.5 N-42 Upper Detector Current 120.1 N-42 Lower Detector Current 121.4 N-43 Upper Detector Current 115.3 N-43 Lower Detector Current 114.0 N-44 Upper Detector Current 118.7 N-44 Lower Detector Current 119.1

Surry 2021-301 Review 1-OPT-CH-001 U.S. Nuclear Regulatory Commission Surry Power Station SR21301 Administrative Job Performance Measure Applicant________________________________ Start Time___________________

Examiner_______________________________ Stop Time___________________

Date ___________________________________ SAT _________ UNSAT ________

Title Review 1-OPT-CH-001, CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1A K/A: GEN2.2.37 Ability to determine operability and/or availability of safety related equipment. [3.6/4.6]

Applicability Validation Time Actual Time RO/SRO(I)/SRO(U) 40 Minutes ___ Minutes Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Identifies the open stroke test time for 1-CH-MOV-1286A exceeds the acceptable range.

• Identifies the Outboard Vibration Horizontal pt 22 exceeds the INOP range.

• Determines a Tech Spec LCO is NOT in effect, based on having an OPERABLE Charging Pump powered by each train of emergency bus power (two trains) per Technical Specifications.

Initiating Cues

• 1-OPT-CH-001 has just been performed and is ready for review before statusing as complete.

• After the OPT was performed, 1-CH-P-1C was placed back in service and 1-CH-P-1A is now secured in AUTO.

Terminating Cues

• Candidate submits list of discrepancies and determination if a Tech Clock LCO is in effect.

Procedures

• 1-OPT-CH-001

• Tech Specs Tools and Equipment Safety Considerations Page 1 of 15

Surry 2021-301 Review 1-OPT-CH-001

• Laptop

• None Page 2 of 15

Surry 2021-301 Review 1-OPT-CH-001 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted as a CRITICAL STEP.

• START TIME_______:

STEP 1:

_______ SAT REVIEW SECTIONS 1 THROUGH 5

_______ UNSAT STANDARD:

a) Reviews Section 1.0 (Purpose).

b) Reviews Section 2.0 (References).

c) Reviews Section 3.0 (Initial Conditions) and verifies all steps are initialed.

d) Reviews Section 4.0 (Precautions and Limitations) and verifies all steps are initialed.

e) Reviews Section 5.0 (Special Tools and Equipment).

EVALUATORS NOTE:

COMMENTS:

STEP 2:

_______ SAT REVIEWS WORK PREPARATION. (Section 6.1)

_______ UNSAT STANDARD:

a) Verifies proper place keeping on all steps, notes, and cautions.

b) Verifies associated information has been entered in Attachment 1.

c) Verifies by the table in step 6.1.4 that Subsections 6.6 and 6.7 were the correct ones to be performed.

EVALUATORS NOTE:

COMMENTS:

Page 3 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 3:

_______ SAT VERIFIES SECTIONS 6.2 THROUGH 6.5 NOT PERFORMED.

_______ UNSAT STANDARD:

a) Verifies all steps of subsections 6.2, 6.3, 6.4, and 6.5 are entered N/A.

EVALUATORS NOTE:

COMMENTS:

STEP 4: CRITICAL STEP

_______ SAT DISCHARGE CHECK VALVE TEST, MOV TIMING, LUBE OIL TCV TIMING AND STARTING 1-CH-P-1A. (Section 6.6) _______ UNSAT STANDARD:

a) Verifies proper place keeping on all steps, notes, and cautions.

b) Verifies all associated data recorded in Attachments 1 and 4.

c) Per step 6.6.1.f.3, identifies the open stroke test time (recorded in Attachment 4) for 1-CH-MOV-1286A exceeds the acceptable range. (CRITICAL STEP)

EVALUATORS NOTE:

• Note: The Candidate may identify the unacceptable stroke time during performance of step 7.1.1.

• If the Candidate reports the stroke time for 1-CH-MOV-1286A, direct the Candidate to complete the review of 1-OPT-CH-001 and inform you of their results afterward.

COMMENTS:

Page 4 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 5: CRITICAL TASK

_______ SAT 1-CH-P-1A PERFORMANCE TEST. (Section 6.7)

_______ UNSAT STANDARD:

a) Verifies proper place keeping on all steps, notes, and cautions.

b) Verifies all associated data is recorded in Attachment 1.

c) Verifies Attachment 2 used to record operating pump data.

d) Per step 6.7.14, identifies the Outboard Vibration Horizontal pt 22 (recorded in Attachment 2) exceeds the INOP range. (CRITICAL STEP)

EVALUATORS NOTE:

• Note: The Candidate may identify the INOP pt 22 vibration during performance of step 7.1.1.

• If the Candidate reports the INOP vibration for pt 22, direct the Candidate to complete the review of 1-OPT-CH-001 and inform you of their results afterward.

COMMENTS:

STEP 6:

_______ SAT VERIFIES SECTIONS 6.8 AND 6.9 NOT PERFORMED.

_______ UNSAT STANDARD:

a) Verifies all steps of subsections 6.8 and 6.9 are entered N/A.

EVALUATORS NOTE:

COMMENTS:

Page 5 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 7:

_______ SAT OBTAINING OIL SAMPLES. (Section 6.10)

_______ UNSAT STANDARD:

a) Verifies proper place keeping on all steps, notes, and cautions.

b) Verifies steps performed for 1-CH-P-1C.

EVALUATORS NOTE:

COMMENTS:

STEP 8:

VERIFIES SECTION 6.11 NOT PERFORMED.

STANDARD:

a) Verifies all steps of subsections 6.11 are entered N/A.

EVALUATORS NOTE:

COMMENTS:

Page 6 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 9:

_______ SAT EVALUATES ACCEPTANCE CRITERIA. (Step 7.1.1)

_______ UNSAT STANDARD:

a) Determines the following acceptance criteria are MET:

a. 1-CH-258 check valve open and closed tests.

b. 1-CH-256 open test.

c. 1-CH-230 open test.

d. 1-CH-MOV-1275A open and closed travel times.

e. 1-CH-MOV-1287A open and closed travel times.

f. 1-SW-TCV-108A test position and stroke time.

g. 1-SW-TCV-108A lube oil temperature below 160°F.

b) Places a check () at each of the substeps listed above.

c) Enters N/A at the substep for 1-CH-P-1C ALT FEED breaker interlock test.

EVALUATORS NOTE:

COMMENTS:

STEP 10: CRITICAL TASK

_______ SAT EVALUATES ACCEPTANCE CRITERIA. (Step 7.1.1, continued)

_______ UNSAT STANDARD:

a) Identifies on Attachment 2 that the value recorded for Outboard Vibration Horizontal (pt 22) is in the INOP range. (CRITICAL TASK) b) Determines the acceptance criteria substep for Charging Pump Vibration is NOT MET.

c) Identifies on Attachment 4 that the value recorded for 1-CH-MOV-1286A Open stroke time exceeds the Acceptable Range Time. (CRITICAL TASK) d) Determines the acceptance criteria substep for 1-CH-MOV-1286A open stroke time is NOT MET.

EVALUATORS NOTE:

• Note: The Candidate may identify the INOP pt 22 vibration during review of step 6.7.14.

• Note: The Candidate may identify the 1-CH-MOV-1286A stroke time during review of step 6.6.1.f.3.

COMMENTS:

Page 7 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 11:

_______ SAT DOCUMENTS TEST RESULTS. (Step 7.1.2)

_______ UNSAT STANDARD:

a) Places a check () at Unsatisfactory to document the test results.

b) Places a check () at each of the substeps listed above.

c) Enters N/A at the substep for 1-CH-P-1C ALT FEED breaker interlock test.

EVALUATORS NOTE:

COMMENTS:

STEP 12: CRITICAL TASK

_______ SAT EVALUATES ACCEPTANCE CRITERIA. (Step 7.1.1, continued)

_______ UNSAT STANDARD:

a) Identifies on Attachment 2 that the value recorded for Outboard Vibration Horizontal (pt 22) is in the INOP range. (CRITICAL TASK) b) Determines the acceptance criteria substep for Charging Pump Vibration is NOT MET.

c) Identifies on Attachment 4 that the value recorded for 1-CH-MOV-1286A Open stroke time exceeds the Acceptable Range Time. (CRITICAL TASK) d) Determines the acceptance criteria substep for 1-CH-MOV-1286A open stroke time is NOT MET.

EVALUATORS NOTE:

• Note: The Candidate may identify the INOP pt 22 vibration during review of step 6.7.14.

• Note: The Candidate may identify the 1-CH-MOV-1286A stroke time during review of step 6.6.1.f.3.

COMMENTS:

Page 8 of 15

Surry 2021-301 Review 1-OPT-CH-001 STEP 13:

_______ SAT REPORTS TO SHIFT MANAGER. (Step 7.2.1)

_______ UNSAT STANDARD:

a) Informs Shift Manager that 1-OPT-CH-001 result is UNSAT.

b) Evaluates Tech Specs for applicability.

EVALUATORS NOTE:

• If the Candidate only reports the status of 1-OPT-CH-001, direct the Candidate to review Tech Specs for applicability and record their result, along with the reason a Tech Spec LCO is/is not applicable, in the Comments section of Section 7.3.

COMMENTS:

STEP 14: CRITICAL TASK

_______ SAT REVIEWS TECH SPECS FOR APPLICABILITY.

_______ UNSAT STANDARD:

a) Determines the B and C Charging pumps are operable, with each Charging Pump aligned to one of the two emergency buses (i.e. two trains operable).

b) Determines a Tech Spec LCO is NOT in effect, based on having an OPERABLE Charging Pump powered by each train of emergency bus power (two trains) per Technical Specifications. (CRITICAL TASK) c) Records their Tech Spec determination in the Comments section of Section 7.3.

EVALUATORS NOTE:

• If desired, ask the Applicant to identify which Tech Spec LCO sections require Charging Pump operability. Answer: Tech Spec sections 3.2 and 3.3 require Charging Pump operability.

COMMENTS:

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Surry 2021-301 Review 1-OPT-CH-001 STOP TIME:

Page 10 of 15

Surry 2021-301 Review 1-OPT-CH-001 EXAMINER KEY Page 11 of 15

Surry 2021-301 Review 1-OPT-CH-001 EXAMINER KEY Page 12 of 15

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions

• Both Units are at 100% power.

• The Unit 1 team is performing 1-OPT-CH-001, Charging Pump Operability And Performance Test For 1-CH-P-1A.

• All applicable portions of Section 6.0, Instructions, have been performed.

• After Section 6.0 was completed, Charging Pump manipulations were made and the current lineup is as follows:

• 1-CH-P-1C is running.

• 1-CH-P-1A and 1-CH-P-1B are secured and in AUTO.

Initiating Cues

• You are to review the completed portions of 1-OPT-CH-001 and perform Subsection 7.1.

• If the OPT is Sat, then complete Subsection 7.1 and another operator will complete the OPT paperwork.

• If the OPT is Unsat, then determine if a Tech Spec Clock is currently in effect (YES / NO), and record this in the Subsection 7.3 comments section. Include in the comments section the reason for your determination.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Both Units are at 100% power.

• The Unit 1 team is performing 1-OPT-CH-001, Charging Pump Operability And Performance Test For 1-CH-P-1A.

• All applicable portions of Section 6.0, Instructions, have been performed.

• After Section 6.0 was completed, Charging Pump manipulations were made and the current lineup is as follows:

• 1-CH-P-1C is running.

• 1-CH-P-1A and 1-CH-P-1B are secured and in AUTO.

Initiating Cues

• You are to review the completed portions of 1-OPT-CH-001 and perform Subsection 7.1.

• If the OPT is Sat, then complete Subsection 7.1 and another operator will complete the OPT paperwork.

• If the OPT is Unsat, then determine if a Tech Spec Clock is currently in effect (YES / NO), and record this in the Subsection 7.3 comments section. Include in the comments section the reason for your determination.