Text

Initial Exam 2010-301 Draft Sim/In-Plant JPMs
	ML102780346
Person / Time
Site:	Surry ; (DPR-032, DPR-037)
Issue date:	09/14/2010
From:	; NRC/RGN-II
To:	; Virginia Electric & Power Co (VEPCO)
References
	50-280/10-301, 50-281/10-301
	Download: ML102780346 (232)
	v • d • e

APE022.AA1.01 SR10301 1 of 11 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Job Performance Measure APE022.AA1.01

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ________________________

___________

Stop Time___________________

Title ISOLATE CHARGING CROSSTIE IN ACCORDANCE WITH 2-ECA-0.2. K/A: APE022.AA1.01

Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup: CVCS letdown and Charging

.

Applicability Estimated Time Actual Time RO/SRO(I) 15 Minutes

Initial Conditions Task is to be SIMULATED in the plant

. A Loss of Offsite Power has occurred on Unit 2 and power has subsequently been restored to Uni t 2. The team has completed 2-ECA-0.0 (Loss of All A/C Power) and transitioned to 2-ECA-0.2 (Loss of All AC Power Recovery with SI Required) and are currently performing Step 15 (Check if Charging Crosstie Can Be Isolated) of 2-ECA-0.2. It has been determined that Charging Crosstie can be isolated. You are to complete Step 15 of 2

-ECA-0.2. Standards Candidate correctly manipulates valves as required by 2-ECA-0.2, step 1 5, to allow for isolation of Charging Crosstie.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. Unit 2 had experienced a loss of offsite power and charging crosstie from Unit 1 to Unit 2 was utilized for RCS makeup.

Following the restoration of power to Unit 2, the team transitioned to 2

-ECA-0.2, Loss of All AC Power Recovery with SI Required.

The team has reached step 1 5 of 2-ECA-0.2, Loss of All AC Power Recovery with SI Required.

You are to perform step 1 5 sub-steps d and e. When you finish the actions necessary to accomplish this, please inform me.

APE022.AA1.01 SR10301 2 of 11 Terminating Cues Completion of 2-ECA-0.2, Loss of All AC Power Recovery with SI Required, step 1 5. Procedures 2-ECA-0.2, Loss of All AC Power Recovery with SI Required (Revision 1 7). Tools and Equipment Safety Considerations None Standard Personal Safety Equipment Bump hazard s in Auxiliary Building Basement ALARA

APE022.AA1.01 SR10301 3 of 11 Notes to the Evaluator

. Task briefing should occur in the pre-determined location

.

This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

Task critical elements are bolded and noted by the words "Critical Step" at the end of the step.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Nuclear Shift Manager. Unit 2 had experienced a loss of offsite power and charging crosstie from Unit 1 to Unit 2 was utilized for RCS makeup.

Following the restoration of power to Unit 2, the team transitioned to 2

-ECA-0.2, Loss of All AC Power Recovery with SI Required.

The team has reached step 15 of 2

-ECA-0.2, Loss of All AC Power Recovery with SI Required.

You are to perform steps 15 sub

-steps d and e.

When you finish the actions necessary to accomplish this, please inform me.

Notes Expected RWP to be used for 08.

2 License Class is - RWP - 000 1 Dose ALARM

- 5 mr Dose RATE ALARM

- 20 mr/hr

APE022.AA1.01 SR10301 4 of 11 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: Reviews the NOTE prior to Step 15 and notes that Step 15 sub

-steps 'a' through 'c' are signed off.

STANDARD: Reads note regarding the fact that FRs may now be implemented. Notes that Step 15 sub

-steps 'a' through 'c' are complete.

EVALUATOR'S NOTE:

This item is not related to the task directed to be performed

. COMMENTS: _______ SAT

_______ UNSAT

APE022.AA1.01 SR10301 5 of 11 STEP 2: STEP 1 5 d- Locally close CHG crosstie valves:

1-C H-728 STANDARD: (a) Proceeds to Auxiliary Building Basement Unit 1 side of Aux Bldg.

(b) Locates 1-CH-728 (see location sketch).

(c) Places the ratchet selector in the DOWN position (rotates selector lever clockwise until bottom stop reached).

This is a Critical Step.

(d) Closes 1-CH-728 by "ratcheting" the valve handwheel to turn the valve handwheel in the clockwise direction.

This is a Critical Step.

EVALUATOR'S NOTE:

If asked:

The valve ratchet selector is in the UP position and the valve is currently open (valve stem is extended)

. Tell operator: If operator attempts to reposition valve with ratchet selector in the UP position, as he/she pushes up on handwheel, it will not move since valve is open. If the operator push es DOWN on handwheel, it will "click".

Tell operator:

AFTER moving ratchet selector to DOWN position, handwheel "clicks" as it is moved up & valve moves clockwise & begins closing as handwheel is pushed down. Tell operator:

When 1-CH-728 properly operated, tell operator that flow noise is no longer heard through the line.

When properly operated:

Valve stem retracts in, operator ratchets the valve until valve no longer travels and flow noise is no longer heard. Area location sketch:

In order to close 1

-CH-728, the ratchet selector must be in the DOWN position. The ratchet selector in the UP direction opens 1

-CH-728. COMMENTS:

_______ SAT

_______ UNSAT

APE022.AA1.01 SR10301 6 of 11 STEP 3: STEP 1 5d- Locally close CHG crosstie valves (continued)

2-CH-447 STANDARD: (a) Proceeds to Auxiliary Building Basement Unit 2 side.

(b) Locates 2-CH-447 (see location sketch).

(c) Closes 2-CH-447 (by turning valve handwheel in the clockwise direction).

This is a Critical Step.

EVALUATOR'S NOTE:

If asked:

The valve is currently open (valve stem is extended).

When correctly operated:

Handwheel rotates, stem retracts in and then the handwheel stops. Area location sketch:

COMMENTS:

_______ SAT

_______ UNSAT

APE022.AA1.01 SR10301 7 of 11 STEP 4: STEP 1 5e- Locally open CHG line valve:

2-CH-304 STANDARD: (a) Proceeds to Auxiliary Building Basement Unit 2 side.

(b) Locates 2-CH-304 (located near 2

-CH-LCV-2122) (c) Opens 2-CH-304 (by turning valve handwheel in the clockwise direction).

This is a Critical Step.

EVALUATOR'S NOTE:

If asked:

The valve is currently open (valve stem is extended).

When correctly operated:

Handwheel rotates, stem retracts in and then the handwheel stops.

COMMENTS:

_______ SAT

_______ UNSAT

APE022.AA1.01 SR10301 8 of 11 STEP 5: Reports completion of the Step to the Shift Manager.

STANDARD: Verbal status report that charging crosstie from Unit 1 to Unit 2 has been locally secured in accordance with 2

-ECA-0.2. EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

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APE022.AA1.01 SR10301 9 of 11 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be SIMULATED in the plant.

Secure Charging Crosstie in accordance with 2-ECA-0.2, Loss of All AC Power Recovery with SI Required, Step

15.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions A Loss of Offsite Power has occurred on Unit 2 and power has subsequently been restored to Unit 2. The team has completed 2

-ECA-0.0 (Loss of All A/C Power) and transitioned to 2

-ECA-0.2 (Loss of All AC Power Recovery with SI Required) and are currently performing Step 15 (Check if Charging Crosstie Can Be Isolated) of 2

-ECA-0.2.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. Unit 2 had experienced a loss of offsite power and charging crosstie from Unit 1 to Unit 2 was utilized for RCS makeup.

Following the restoration of power to Unit 2, the team transitioned to 2-ECA-0.2, Loss of All AC Power Recovery with SI Required.

The team has reached step 15 of 2

-ECA-0.2, Loss of All AC Power Recovery with SI Required.

You are to perform step 15 sub

-steps d and e.

When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions A Loss of Offsite Power has occurred on Unit 2 and power has subsequently been restored to Unit 2. The team has completed 2

-ECA-0.0 (Loss of All A/C Power) and transitioned to 2

-ECA-0.2 (Loss of All AC Power Recovery with SI Required) and are currently performing Step 15 (Check if Charging Crosstie Can Be Isolated) of 2

-ECA-0.2.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. Unit 2 had experienced a loss of offsite power and charging crosstie from Unit 1 to Unit 2 was utilized for RCS makeup.

Following the restoration of power to Unit 2, the team transitioned to 2

-E CA-0.2, Loss of All AC Power Recovery with SI Required.

The team has reached step 15 of 2

-ECA-0.2, Loss of All AC Power Recovery with SI Required.

You are to perform step 15 sub

-steps d and e.

When you finish the actions necessary to accomplish this, please inform me.

EPE029EA1.12 SR10301 1 of 11 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Job Performance Measure EPE029EA1.12 Alternate Path

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________

________________________

Stop Time___________________

Title Locally Trip Unit 1 Reactor

. K/A: EPE029EA1.12: Ability to operate and monitor the following as they apply to a ATWS: M/G set power supply and reactor trip breakers

.

Applicability Estimated Time Actual Time RO/SRO(I) 1 0 Minutes

Initial Conditions Task is to be SIMULATED in the plant

. An Anticipated Transient Without Scram (ATWS) is in progress on Unit 1 with a coincident failure of both bench board reactor trip push buttons

. The operating team has entered FR

-S.1, Response to Nuclear Power Generation/ATWS.

A local trip of the reactor is required. You have been directed to open Unit 1 reactor trip breakers locally in accordance with FR

-S.1 Step 8.a RNO.

Standards Candidate opens Unit 1 Motor Generator Breakers and de

-energizes power to the Rod Control System

.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. UNIT 1 is currently experiencing an ATWS and the control room reactor trip push buttons won't work.

I need you to locally trip the UNIT 1 reactor trip breakers in accordance with FR

-S.1 Step 8.a RNO.

When you finish the actions necessary to accomplish this, please inform me.

EPE029EA1.12 SR10301 2 of 11 Terminating Cues Unit 1 Motor Generator Breakers are open

. Procedures FR-S.1, Response to Nuclear Power Generation/ATWS (Revision 2 6). Tools and Equipment Safety Considerations None Standard Personal Safety Equipment

EPE029EA1.12 SR10301 3 of 11 Notes to the Evaluator

. Task briefing should occur in the pre-determined location

.

This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

Task critical elements are bolded and noted by the words "Critical Step" at the end of the step.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. UNIT 1 is currently experiencing an ATWS and the control room reactor trip push buttons won't work.

I need you to locally trip the UNIT 1 reactor trip breakers in accordance with FR

-S.1 Step 8.a RNO.

When you finish the actions necessary to accomplish this, please inform me.

Notes When the candidate attempts to open the Unit 1 Reactor Trip Breakers, the candidate will find that the reactor trip breakers cannot be manipulated. Upon report of this condition to the Control Room / Shift Manager, the evaluator will provide direction to open the MG set output breakers in accordance with FR

-S.1 Step 8.a RNO.

EPE029EA1.12 SR10301 4 of 11 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: Step 8.a RNO

- Send operator to locally trip Reactor

Open reactor trip and bypass breakers OR Open the MG set output breakers.

o GEN NO. 1 o GEN NO. 2 STANDARD: a) Locates Unit 1 Reactor Trip and Bypass Breakers.

b) Attempts to open Unit 1 Reactor Trip Breaker A (RTB A) by depressing the TRIP push button on the breaker. EVALUATOR'S NOTE:

a) Proceeds to Unit 1 Cable Spreading Area (between the Pzr Acc monitor cabinet and the ASC/RMP panels) and enters the Reactor Trip Breaker cubicle.

b) If asked:

Prior to breaker manipulation, the CLOSED indication is showing (i.e., the breaker is "as you see it").

Following the breaker manipulation, no breaker movement is seen or heard and the CLOSED indication is showing (i.e., the breaker is "as you see it").

The 'A' Reactor Trip Bypass Breaker has the OPEN indication showing (i.e.,

the breaker is "as you see it").

COMMENTS: _______ SAT

_______ UNSAT

EPE029EA1.12 SR10301 5 of 11 STEP 2: Step 8.a RNO

- (continued)

Send operator to locally trip Reactor

Open reactor trip and bypass breakers OR Open the MG set output breakers.

o GEN NO. 1 o GEN NO. 2 STANDARD: a) Attempts to open Unit 1 Reactor Trip Breaker B (RTB B) by depressing the TRIP push button on the breaker.

b) Acknowledges that both of the Reactor Trip Breakers will NOT open locally.

EVALUATOR'S NOTE:

a) If asked:

Prior to breaker manipulation, the CLOSED indication is showing (i.e., the breaker is "as you see it"

). Following the breaker manipulation, no breaker movement is seen or heard and the CLOSED indication is showing (i.e., the breaker is "as you see it").

The 'B' Reactor Trip Bypass Breaker has the OPEN indication showing (i.e., the breaker is "as you see it").

ADDITIONAL DIRECTION TO BE PROVIDED TO CANDIDATE:

b) Upon identification of the failure of the reactor trip breakers to be opened, provide the following direction to the candidate, as necessary.

I need you to locally trip the UNIT 1 MG SET OUTPUT BREAKERS in accordance with FR

-S.1 Step 8.a RNO.

When you finish the actions necessary to accomplish this, please inform me.

COMMENTS:

_______ SAT

_______ UNSAT

EPE029EA1.12 SR10301 6 of 11 STEP 3: Step 8.a RNO

- (continued)

Send operator to locally trip Reactor:

Open reactor trip and bypass breakers OR Open the MG set output breakers.

o GEN NO. 1 o GEN NO. 2 STANDARD: a) Locates Unit 1 MG Set Output Breakers.

b) Trips one of the Unit 1 MG Set Output Breakers by either of the following:

Operating the breaker mounted trip mechanism (pushes the TRIP push button) Rotates the Generator Control pistol

-grip switch to the TRIP position.

This is a Critical Step

. EVALUATOR'S NOTE:

a) Proceeds to the MG Set Control Panel (center of Unit 1 4160V Switchgear Room) and locates the MG Set Output Breakers (at bottom of panel).

b) If asked:

Both MG Sets are operating.

Prior to breaker manipulation, the CLOSED indication is showing (i.e., the breaker is "as you see it"

). When properly operated, the MG Set Output Breaker indication changes from CLOSED to OPEN and breaker opening noise is heard.

COMMENTS:

_______ SAT

_______ UNSAT

EPE029EA1.12 SR10301 7 of 11 STEP 4: Step 8.a RNO

- (continued)

Send operator to locally trip Reactor

Open reactor trip and bypass breakers OR Open the MG set output breakers.

o GEN NO. 1 o GEN NO. 2 STANDARD: a) Trips the other Unit 1 MG Set Output Breakers by either of the following:

Operating the breaker mounted trip mechanism (pushes the TRIP push button) Rotates the Generator Control pistol

-grip switch to the TRIP position.

This is a Critical Step

. EVALUATOR'S NOTE:

a) If asked:

Prior to breaker manipulation, the CLOSED indication is showing (i.e., the breaker is "as you see it").

When properly operated, the MG Set Output Breaker indication changes from CLOSED to OPEN and breaker opening noise is heard.

COMMENTS:

_______ SAT

_______ UNSAT

EPE029EA1.12 SR10301 8 of 11 STEP 5: Reports completion of the Step to the Shift Manager.

STANDARD: Verbal status report that Unit 1 MG Breakers have been opened.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

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EPE029EA1.12 SR10301 9 of 11 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be SIMULATED in the plant.

A local trip of the reactor is required. The Candidate has been directed to open Unit 1 reactor trip breakers locally in accordance with FR

-S.1 Step 8.a RNO.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions An Anticipated Transient Without Scram (ATWS) is in progress on Unit 1 with a coincident failure of both bench board reactor trip push buttons. The operating team has entered FR

-S.1, Response to Nuclear Power Generation/ATWS.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. UNIT 1 is currently experiencing an ATWS and the control room reactor trip push buttons won't work.

I need you to locally trip the UNIT 1 reactor trip breakers in accordance with FR

-S.1 Step 8.a RNO.

When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions An Anticipated Transient Without Scram (ATWS) is in progress on Unit 1 with a coincident failure of both bench board reactor trip push buttons. The operating team has entered FR

-S.1, Response to Nuclear Power Generation/ATWS.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. UNIT 1 is currently experiencing an ATWS and the control room reactor trip push buttons won't work.

I need you to locally trip the UNIT 1 reactor trip breakers in accordance with FR

-S.1 Step 8.a RNO.

When you finish the actions necessary to accomplish this, please inform me.

008.A2.02 SR10301 1 of 30 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Job Performance Measure 008.A2.02 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ____________________________

_______ Stop Time___________________

Title Fill the CC Head Tank using 1

-BC-P-2. K/A: 008.A2.02:

Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level

.

Applicability Estimated Time Actual Time RO/SRO(I) 15 Minutes

Initial Conditions Task is to be SIMULATED in the plant. An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated. The CC Head Tank level is low and needs to be filled; current level is 30%

. The Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

It is desired to fill the CC Head Tank to 50% using 1-BC-P-2 in accordance with 0

-OP-BC-001. Standards Candidate correctly manipulates valves, starts 1

-BC-P-2 in accordance with 0

-OP-BC-001 and fills the CC Head Tank.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Shift Manager. An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated.

The CC Head Tank level is low and needs to be filled; current level is 30%.

Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

You are to fill the CC Head Tank to 50% using 1

-BC-P-2 in accordance with 0

-OP-BC-001, Operation of 1

-BC-P-2. When you finish the actions necessary to accomplish this, please inform me.

008.A2.02 SR10301 2 of 30 Terminating Cues The CC Head Tank has been filled to the desired level (50%). Procedures 0-OP-BC-001, Operation of 1

-BC-P-2 (Revision 7), Subsections 5.1, 5.2, and 5.4

. Tools and Equipment Safety Considerations None Standard Personal Safety Equipment

008.A2.02 SR10301 3 of 30 Notes to the Evaluator

. Task briefing should occur in the pre-determined location

.

This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

Task critical elements are bolded and noted by the words "Critical Step" at the end of the step.

Initiating Cues This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

I am the Nuclear Shift Manager. An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated.

The CC Head Tank level is low and needs to be filled; current level is 30%.

Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

You are to fill the CC Head Tank to 50% using 1

-BC-P-2 in accordance with 0

-OP-BC-001, Operation of 1

-BC-P-2. When you finish the actions necessary to accomplish this, please inform me.

Not es

008.A2.02 SR10301 4 of 30 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: Reviews procedure Section 3.0, Initial Conditions, and Section 4.0, Precautions and Limitations

. 3.0 Initial Conditions

None

4.0 Precautions

and Limitations

4.1 Push button station 1

-BS-CS-P2, BC M/U Pump Control Switch, is mounted on the vertical beam near the pump.

4.2 Because

the LCVs for 1

-CD-TK-1A, 1-CD-TK-1B, and 2-CD-TK-1, Chilled Water Surge Tanks, are not reliable, makeup is done using the LCV Bypass.

4.3 The BC flow path is normally aligned from 1

-BC-P-2 to Unit 1 BC System and to Unit 2 BC System. Starting 1

-BC-P-2 will fill the head tanks if required.

4.4 The following equipment will be required if performing Subsection 5.9:

Red rubber hose (100 ft) with Chicago fittings on both ends Five gallon bucket

STANDARD: Reviews procedure Section 3.0, Initial Conditions, and Section 4.0, Precautions and Limitations

.

EVALUATOR'S NOTE:

The candidate will only utilize Subsection 5.1, 5.2, and 5.4

. If the candidate looks at the local CC Head Tank Level indication (by ESGR entry doors) indicate level at 30%.

COMMENTS:

_______ SAT

_______ UNSA T

008.A2.02 SR10301 5 of 30 STEP 2: Section 5.4

- Filling the CC Surge Tank

Step 5.4.1

- Verify started or start 1

-BC-P-2 IAW Subsection 5.1. Enter N/A if filling from the WT makeup header.

STANDARD: a) Proceeds to procedure Subsection 5.4 and performs Step 5.4.1 which directs performance of Section 5.1, if not already performed.

EVALUATOR'S NOTE:

a) If asked:

The WT makeup header is not available for makeup to the CC Head Tank, use 1

-BC-P-2. Based on the directions, it is acceptable for the candidate to commence with Subsection 5.1

.

COMMENTS:

_______ SAT

_______ UNSAT

008.A2.02 SR10301 6 of 30 STEP 3: Section 5.1

- Starting 1

-BC-P-2, BC Alternate M/U Pump

Step 5.1.1

- Verify that 1

-BC-253, BC Alt M/U Pump Discharge Hdr Drain, is closed.

STANDARD: a) Proceeds to Unit 1 Turbine Building Basement.

b) Verifies that 1

-BC-253 is closed.

EVALUATOR'S NOTE:

a) Proceeds to the west side of Unit 1 Turbine Building Basement between the outlet waterboxes and the Condensate Pumps b) If asked:

1-BC-253 is "as you see it".

COMMENTS: _______ SAT

_______ UNSAT

STEP 4:

Section 5.1

- Starting 1

-BC-P-2, BC Alternate M/U Pump

Step 5.1.2

- Open 1-BC-177, BC Alt M/U Pump Suct.

STANDARD: a) Opens 1-BC-177 by rotating the handwheel in the counter

-clockwise direction. This is a Critical Step EVALUATOR'S NOTE:

a) If asked: Prior to valve manipulation 1-BC-177 is "as you see it" (i.e., closed).

Following valve manipulation indicate that 1

-BC-177 is OPEN (i.e., valve stem exposed)

.

COMMENTS:

_______ SAT

_______ UNSAT

008.A2.02 SR10301 7 of 30 STEP 5: Section 5.1

- Starting 1

-BC-P-2, BC Alternate M/U Pump

Step 5.1.3

- Open 1-BC-180, BC Alt M/U Pump Recirc Line Isol.

STANDARD: a) Opens 1-BC-1 80 by rotating the handwheel in the counter

-clockwise direction. This is a Critical Step EVALUATOR'S NOTE: a) If asked: Prior to valve manipulation 1-BC-180 is "as you see it" (i.e., closed).

Following valve manipulation indicate that 1

-BC-180 is OPEN.

COMMENTS: _______ SAT

_______ UNSAT

STEP 6:

Caution prior to Step 5.1.4: Valve 1

-BC-179 may require throttling to prevent cavitation when condensate temperature is high.

STANDARD: a) Acknowledges the Caution.

EVALUATOR'S NOTE:

a) If asked: Throttle 1

-BC-179 2 turns open.

The operator may decide to throttle 1

-BC-179 open until cavitation occurs and then throttle closed on 1

-BC-179.

COMMENTS: _______ SAT

_______ UNSAT

008.A2.02 SR10301 8 of 30 STEP 7: Section 5.1

- Starting 1

-BC-P-2, BC Alternate M/U Pump

Step 5.1.4

- Throttle open or open 1

-BC-179, BC Alt M/U Pump Disch.

STANDARD: a) Throttles open or opens 1-BC-1 79 by rotating the handwheel in the counter-clockwise direction. This is a Critical Step EVALUATOR'S NOTE:

a) If asked: Prior to valve manipulation 1-BC-179 is "as you see it" (i.e., closed).

Following valve manipulation indicate that 1-BC-179 is OPEN or THROTTLED (stem fully or partially exposed).

Throttle 1

-BC-179 2 turns open.

The operator may decide to throttle 1

-BC-179 open until cavitation occurs and then throttle closed on 1

-BC-179. As long as 1

-BC-179 was opened to allow flow forward, it is not critical that 1

-BC-179 be fully open (i.e., it is acceptable for this valve to be throttled)

COMMENTS: _______ SAT

_______ UNSAT

STEP 8:

Section 5.1

- Starting 1

-BC-P-2, BC Alternate M/U Pump

Step 5.1.5

- Start 1-BC-P-2 and verify discharge pressure is stable at approximately 70 to 115 psig as indicated on 1

-BC-PI-117, BC Alternate M/U Pump Discharge Press Ind. STANDARD: a) Starts 1-BC-P-2 by depressing the start push button. This is a Critical Step

. b) Determines discharge pressure by reading 1

-BC-PI-117 to be approximately 95 psig. EVALUATOR'S NOTE:

a) If asked: Prior to pump start, the pump is "as you see it" Following pump start, pump noise is heard and the discharge pressure gage increases from 30 psig to approximately 95 psig.

COMMENTS: _______ SAT

_______ UNSAT

008.A2.02 SR10301 9 of 30 STEP 9: Section 5.4

- Filling the CC Surge Tank

Step 5.4.1

- Verify started or start 1

-BC-P-2 IAW Subsection 5.1. Enter N/A if filling from the WT makeup header.

STANDARD: a) Notes that 1

-BC-P-2 is running.

EVALUATOR'S NOTE:

a) If asked:

The WT makeup header is not available for makeup to the CC Head Tank, use 1

-BC-P-2. COMMENTS: _______ SAT

_______ UNSAT

STEP 10:

Section 5.4

- Filling the CC Surge Tank Step 5.4.2

- Notify an Operator in the Main Control Room to monitor CC Surge Tank Level Indicator.

STANDARD: a) Contacts the Main Control Room and notifies the MCR to monitor CC Surge Tank level.

EVALUATOR'S NOTE:

a) If asked/contacted:

Will acknowledge the need to monitor CC Head Tank Level.

Will contact the operator when level approaches 50%.

COMMENTS:

_______ SAT

_______ UNSAT

008.A2.02 SR10301 10 of 30 STEP 10: Section 5.4

- Filling the CC Surge Tank

Step 5.4.3

- Slowly open 1

-CN-800, CN M/U to CC Surge Tk Isol. STANDARD: a) Slowly opens 1

-CN-800 by rotating the valve in the counter

-clockwise direction. It is not necessary to fully open 1

-CN-800. This is a Critical Step.

EVALUATOR'S NOTE:

a) If asked/contacted:

Prior to valve manipulation 1-CN-800 is "as you see it" (i.e., closed).

Following valve manipulation indicate that 1

-CN-800 is OPEN or THROTTLED (stem fully or partially exposed)

. The MCR will note that CC Head Tank Level is increasing.

If after 1

-CN-800 is opened and the candidate looks at the local CC Head Tank Level indication (by ESGR entry doors) indicate level increasing.

If 1-CN-800 is in a contaminated are a, the candidate will NOT enter the contaminated area, but simulate the actions required and valve manipulations.

Contact HP or Supervisor Verify proper dosimetry requirements with HP or Supervisor Don the required anti

-contamination clothing as directed by HP.

COMMENTS:

_______ SAT

_______ UNSAT

008.A2.02 SR10301 11 of 30 STEP 11: Section 5.4

- Filling the CC Surge Tank

Step 5.4.4

- When the CC Surge Tank is at the desired level, then close 1

-CN-800. STANDARD: a) Closes 1-CN-800 by rotating the valve in the clockwise direction.

This is a Critical Step.

EVALUATOR'S NOTE:

a) If asked/contacted:

Contact the operator to indicate CC Head Tank Level is approximately 50%.

Following valve manipulation indicate that 1

-CN-800 is CLOSED or "as you see it" (valve stem retracted)

. The MCR will note that CC Head Tank Level is stable following the closure of 1

-CN-800. If after 1

-CN-800 is closed and the candidate looks at the local CC Head Tank Level indication (by ESGR entry doors) indicate level stable at approximately 50%

.

If 1-CN-800 is in a contaminated are, the candidate will NOT enter the contaminated area, but simulate the actions required and valve manipulations.

Remove the required anti

-contamination clothing as directed by HP.

Perform a frisk, as necessary.

COMMENTS:

_______ SAT

_______ UNSAT

STEP 12:

Section 5.4

- Filling the CC Surge Tank

Step 5.4.5

- Stop 1-BC-P-2 IAW Subsection 5.2. Enter N/A if filled from WT makeup header.

STANDARD: a) Proceeds to procedure Subsection 5.2 to secure 1

-BC-P-2. EVALUATOR'S NOTE:

N/A COMMENTS:

_______ SAT

_______ UNSAT

008.A2.02 SR10301 12 of 30 STEP 13: Section 5.2

- Stopping 1

-BC-P-2, BC Alternate M/U Pump

Step 5.2.1

- After pump run is done, then stop 1

-BC-P-2. STANDARD: a) Stops 1-BC-P-2 by depressing the stop push button.

EVALUATOR'S NOTE:

a) If asked:

Discharge pressure decreases to 30 psig after the pump is stopped.

COMMENTS: _______ SAT

_______ UNSAT

STEP 14:

Section 5.2

- Stopping 1

-BC-P-2, BC Alternate M/U Pump

Step 5.2.2

- Close 1-BC-179, BC Alt M/U Pump Disch.

STANDARD: a) Closes 1-BC-179 by rotating the handwheel in the clockwise direction.

EVALUATOR'S NOTE: a) If asked: Prior to valve manipulation 1-BC-179 is OPEN.

Following valve manipulation indicate that 1

-BC-179 is CLOSED or "as you see it" (valve stem retracted)

.

COMMENTS:

_______ SAT

_______ UNSAT

STEP 15:

Section 5.2

- Stopping 1

-BC-P-2, BC Alternate M/U Pump

Step 5.2.3

- Close 1-BC-180, BC Alt M/U Pump Recirc Line Isol.

STANDARD: a) Closes 1-BC-180 by rotating the handwheel in the clockwise direction.

EVALUATOR'S NOTE:

a) If asked: Prior to valve manipulation 1-BC-180 is OPEN. Following valve manipulation indicate that 1

-BC-180 is CLOSED or "as you see it".

COMMENTS: _______ SAT

_______ UNSAT

008.A2.02 SR10301 13 of 30 STEP 16: Section 5.2

- Stopping 1

-BC-P-2, BC Alternate M/U Pump Step 5.2.3

- Close 1-BC-177, BC Alt M/U Pump Suct.

STANDARD: a) Closes 1-BC-1 77 by rotating the handwheel in the clockwise direction.

EVALUATOR'S NOTE:

a) If asked: Prior to valve manipulation 1-BC-177 is OPEN.

Following valve manipulation indicate that 1

-BC-177 is CLOSED or "as you see it" (valve stem retracted)

.

COMMENTS: _______ SAT

_______ UNSAT

STEP 17:

Reports completion of the Step to the Shift Manager.

STANDARD: Verbal status report that the CC Head Tank was filled with 1

-BC-P-2. EVALUATOR'S NOTE:

Acknowledge the completion of the task. COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

____________________________________________________________________________________

___________________

_________________________________________________________________

____________________________________________________________________________________

_________________

___________________________________________________________________

____________________________________________________________________________________

_______________

_____________________________________________________________________

____________________________________________________________________________________

008.A2.02 SR10301 14 of 30 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be SIMULATED in the plant.

Fill the CC Head Tank to 50% using 1

-BC-P-2 in accordance with 0

-OP-BC-001.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated. The CC Head Tank level is low and needs to be filled; current level is 30%.

Initial Conditions The Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

Initiating Cues I am the Shift Manager. An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated.

The CC Head Tank level is low and needs to be filled; current level is 30%.

Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

You are to fill the CC Head Tank to 50% using 1

-BC-P-2 in accordance with 0

-OP-BC-001, Operation of 1-BC-P-2. When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated. The CC Head Tank level is low and needs to be filled; current level is 30%.

Initial Conditions The Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

Initiating Cues I am the Shift Manager. An adverse trend was identified on the CC Head Tank and a CC leak was identified and subsequently isolated. The CC Head Tank level is low and needs to be filled; current level is 30%.

Water Treatment (WT) makeup header is not available to supply water to the CC Head Tank.

You are to fill the CC Head Tank to 50% using 1

-BC-P-2 in accordance with 0

-OP-BC-001, Operation of 1-BC-P-2. When you finish the actions necessary to accomplish this, please inform me.

Surry 2010-301 Recover a Dropped Rod Page 1 of 12 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure APE003.AA1.02 (3.6/3.4)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title RECOVER A DROPPED ROD

. K/A: APE003.AA1.02 Ability to operate and/or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod.

Applicability Estimated Time Actual Time RO/SRO(I) 2 2 Minutes Conditions Task is to be PERFORMED in the simulator.

A single dropped RCCA (P

-10) has occurred. Reactor power has been reduced to approximately 65

-70% power and stabilized. AP

-1.00 has been performed through step 23 and transition made to AP

-1.01, step 5 where it has been performed through step 14.

Standards Rod P-10 fully withdrawn IAW 0

-AP-1.01, Control Rod Misalignment.

Initiating Cues 0-AP-1.01, Control Rod Misalignment, step 1 5 Shift Manager direction.

Terminating Cues 0-AP-1.01, Control Rod Misalignment, step 28 completed.

Procedures 0-AP-1.01, Control Rod Misalignment

Surry 2010-301 Recover a Dropped Rod Page 2 of 12 Tools and Equipment None None Safety Considerations Recall IC-322 Simulator Setup Call up 70% power IC and initialize

. OR Enter malfunctions for dropped RCCA P

-10 (RD1224), annuciator overrides (0ff) GC4 (UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT < 50%), GD4 (LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT < 50%) and GE4 (NIS PWER RGE CH1 AVG FLUX DEVIATION). Perform 0

-AP-1.00 through step 23 and transition to 0

-AP-1.01 step 5, perform through step 13 and stabilize plant.

Sign off copy of 0

-AP-1.01, Control Rod Misalignment, from step 5 through step 14.

Verify Tave/Tref recorder set on proper scale for current Tave/Tref.

REMOVE MALFUNCTION (RD1224) & freeze simulator until ready to perform JPM.

Place an Orange Magnet next to the Control Bank 'A' Rod Position Indicator for P

-10. Initiating Cues 0-AP-1.01, Control Rod Misalignment, step 15 Shift Manager direction.

Directions to the Applicant I am the Shift Manager. Control Rod P

-10 dropped about 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to a blown fuse. The unit has been stabilized and the Instrument Techs have repaired the fuse. Tech Spec 3.12.E has been reviewed by the Shift Manager and STA. A pre-job brief has been held and we are now ready to withdraw the rod. I&C is standing by for your instructions.

Here's a copy of AP

-1.01, I want you to recover the dropped control rod IAW steps 15 through and including step

28. When you finish the actions necessary to accomplish this and return the rods to MANUAL, please inform me.

Notes Surry 2010-301 Recover a Dropped Rod Page 3 of 12 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1:

CAUTION S PRIOR TO STEP 15 CAUTION: This procedure is NOT valid for realignment of a control rod if Reactor is subcritical.

Realignment SHALL be performed with Reactor power held less than or equal to 75%.

STANDARD: Acknowledges caution

s. EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 15 - TRANSFER ROD CONT MODE SEL SWITCH TO AFFECTED BANK STANDARD: Places ROD CONT MODE SEL SWITCH to CBA (Control Bank 'A') position.

This is a Critical Task.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 4 of 12 STEP 3: Step 16 - RECORD AFFECTED ROD AND ROD BANK:

Rod: ____________________

Rod Bank: _______________

STANDARD: Records rod P

-10 and CBA.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Step 17 - ALIGN LIFT COIL DISCONNECT SWITCHES FOR AFFECTED BANK Place all disconnect switches to DISCONNECTED position Place affected rod disconnect switch to CONNECTED position Have alignment switches independently verified.

STANDARD: Proceeds behind Vertical Board 1

-2 to Lift Coil Disconnect Switch Panel a nd opens panel door. NOTES SIGN REQUIRING REMOVAL OF JEWELRY PRIOR TO ENTRY. Places all 8 disconnect switches for Control Bank 'A' in the DISCONNECT position. This is a Critical Task.

Places disconnect switch for rod P

-10 in the CONNECT position. This is a Critical Task.

Asks for an independent verification of disconnect switches position.

EVALUATOR'S NOTE: If asked, Lift Coil Disconnect Switches have been independently verified. COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 5 of 12 STEP 5: Step 18 - RECORD BANK POSITION OF AFFECTED ROD:

Group 1 step counter: ____________________

Group 2 step counter: ____________________

STANDARD: Records group 1 & 2 step counters for CBA at 228 steps.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT STEP 6:

Cautions prior to Step 19 CAUTION: The affected withdrawal rate during realignment is limited to 2/P (P=fraction of 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or the duration of misalignment can NOT be determined.

The withdrawal rate limitation may be relaxed with the authorization from the Reactor Engineer or Nuclear Analysis and Fuels.

STANDARD: Acknowledges cautions.

EVALUATOR'S NOTE: If asked, Reactor Engineering has authorized that the 2/P rod speed limit be relaxed. No limit on rod speed is required.

COMMENTS: _______ SAT

_______ UNSAT

STEP 7:

Step 19 - RECORD THE FOLLOWING Reactor Power: ___________

Withdrawal Rate: __________

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 6 of 12 STANDARD: Records current reactor power level (will be approximately 65

-70%). Records withdrawal rate at 48 spm.

EVALUATOR'S NOTE: If asked, Reactor Engineering has authorized that the 2/P rod spee d limit be relaxed. No limit on rod speed is required.

If asked, Do not exceed 70% power, a 1 dpm SUR or temperature

>565F during dropped rod recovery.

COMMENTS: STEP 8:

Note prior to step 20

NOTE: Refer to Attachment 2 before resetting Group Step Counter.

STANDARD: Acknowledges note.

Refers to attachment 2 (trainee may wait and refer to attachment 2 before resetting group step counters).

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 9:

Step 20 - CHECK AFFECTED ROD

- ON BOTTOM STANDARD: Checks rod P

-10 indicating zero steps using digital and light indication.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 7 of 12 STEP 10: Step 21 - REFER TO TECH SPEC 3.12.E STANDARD: Trainee recalls from directions that Tech Spec 3.12.E has been reviewed.

EVALUATOR'S NOTE: If asked, Tech Spec 3.12.E has been reviewed.

COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

Step 22 - RESET AFFECTED GROUP STEP COUNTER TO 0. STANDARD: Trainee refers to attachment 2 to reset group step counter to zero steps.

Trainee resets group step counter CONT BANK A GP 2 by pressing reset button OR by pulsing the group step counter until it reads 0 steps. This is a Critica l Task. EVALUATOR'S NOTE: If asked, it is preferred to use the reset button.

COMMENTS:

_______ SAT

_______ UNSAT STEP 12:

Step 23 - HAVE I&C RESET AFFECTED BANK DEMAND TO 000.

STANDARD: Trainee calls I&C and requests they reset affected bank CONT BANK A demand to 000.

EVALUATOR'S NOTE: N/A BOOTH OPERATOR'S NOTE: When requested to reset bank demand, inform the trainee that a time compression has occurred and CONT BANK A has been reset to 000 by I&C.

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 8 of 12 COMMENTS: STEP 13:

Note prior to step 2 4 NOTE: Annunciator 1G

-A6, ROD CONT SYS URGENT FAILURE, will alarm when the affected rod is withdrawn indicating that the lift coils of the remaining rods in the bank are deenergized.

STANDARD: Acknowledges note. EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 14: Step 24 - REALIGN AFFECTED ROD TO ITS BANK POSITION RECORDED IN STEP 18.

STANDARD: Places SHUTDN AND CONT ROD CONT SWITCH to the OUT position.

This is a Critical Task. Verifies outward rod motion indicated by observing affected rod CERPI.

Acknowledges annunciator 1G

-A6 (ROD CONT SYS URGENT FAILURE).

Withdraws affected rod to 228 steps.

This is a Critical Task.

ave, group step counters, CERPI, rod speed, out indication light and TR 409A.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 9 of 12 STEP 15: Step 25 - PLACE AFFECTED BANK LIFT COIL DISCONNECT SWITCHES TO THE CONNECT POSITION.

STANDARD: Proceeds behind Vert Bd 1

-2 to Lift Coil Disconnect Switch Panel.

NOTES SIGN REQUIRING REMOVAL OF JEWELRY PRIOR TO ENTRY.

Closes disconnect switches for affected bank (F

-2, B-10, K-14, P-6, K-2, B-6 & F-14). This is a Critical Task.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 16:

Step 26 - HAVE ALIGNMENT OF DISCONNECT SWITCHES INDEPENDENTLY VERIFIED STANDARD: Trainee recalls from directions that Tech Spec 3.12.E has been reviewed.

EVALUATOR'S NOTE: If asked, Lift Coil Disconnect Switches have been independently verified.

COMMENTS:

_______ SAT

_______ UNSAT STEP 17:

Step 27 - RESET ROD CONTROL URGENT FAILURE Depress ROD CONT SYS INTERNAL ALARM RESET pushbutton STANDARD: Depresses ROD CONT SYS INTERNAL ALARM RESET pushbutton.

This is a Critical Task.

_______ SAT

_______ UNSAT

Surry 2010-301 Recover a Dropped Rod Page 10 of 12 EVALUATOR'S NOTE: N/A COMMENTS:

STEP 18:

Step 28 - TRANSFER ROD CONT MODE SEL SWITCH TO MANUAL STANDARD: Moves rod control mode selector switch from CBA to Manual.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that control rod P

-10 has been realigned with its control bank and steps 15

-28 of AP-1.01 have been completed.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME:

____________________________________________________________________________________

____________________________________________

________________________________________

____________________________________________________________________________________

__________________________________________

____________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Perform Steps 15 - 28 of 0-AP-1.01 , CONTROL ROD MISALIGNMENT, to align control rod P

-10 with its control bank.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions A single dropped RCCA (P

-10) has occurred. Reactor power has been reduced to approximately 65

-70% power and stabilized. AP

-1.00 has been performed through step 23 and transition made to AP-1.01, step 5 where it has been performed through step 14.

Initiating Cues I am the Shift Manager. Control Rod P

-10 dropped about 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to a blown fuse. The unit has been stabilized and the Instrument Techs have repaired the fuse. Tech Spec 3.12.E has been reviewed by the Shift Manager and STA. A pre

-job brief has been held and we are now ready to withdraw the rod. I&C is standing by for your instructions.

Here's a copy of AP

-1.01, I want you to recover the dropped control rod IAW steps 15 through and including step

28. 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 A single dropped RCCA (P

-10) has occurred. Reactor power has been reduced to approximately 65

-70% power and stabilized. AP

-1.00 has been performed through step 23 and transition made to AP

-1.01, step 5 where it has been performed through step 14.

Initiating Cue s I am the Shift Manager. Control Rod P

-10 dropped about 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to a blown fuse. The unit has been stabilized and the Instrument Techs have repaired the fuse. Tech Spec 3.12.E has been reviewed by the Shift Manager and STA. A pre

-job brief has been held and we are now ready to withdraw the rod. I&C is standing by for your instructions.

Here's a copy of AP

-1.01, I want you to recover the dropped control rod IAW steps 15 through and including step

28. When you finish the actions necessary to accomplish this and return the rods to MANUAL, please inform me.

SI

Surry 2010-301 Pressurizer Level Channel Fails Low Page 1 of 1 1 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 011.A2.11 (3.4/3.6)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ________

___________________________

Stop Time___________________

Title RESPOND TO A FAILED LOW PRESSURIZER LEVEL CHANNEL K/A: 011.A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of PZR level instrument

- low. Applicability Estimated Time Actual Time RO/SRO(I) 15 minutes

Conditions Task is to be PERFORMED in the simulator.

Unit is operating at 100% power with all systems normal and in automatic.

Standards 0-AP-53.00 complete up and not including step 14 (Failed channel defeated, pressurizer heaters energized as required, charging in Auto).

Initiating Cues AP-53.00 Immediate Actions Shift Manager direction.

Terminating Cues 0-AP-53.00, Loss of Vital Instrumentation/Controls completed up to step 14

.

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

Surry 2010-301 Pressurizer Level Channel Fails Low Page 2 of 1 1 Tools and Equipment None None Safety Considerations Recall IC-321 Simulator Setup Call up 100% power IC and initialize place in RUN, select position III/II on the Pressurizer level control selector switch. OR Place pressurizer level recorder on Channel 3, 1

-RC-LI-1461. Program malfunction for low failure of Pressurizer Level Channel III (RC

-LT-1461, RC4903), trigger 1.

Implement malfunctions to fail letdown auto isolation (CH62, CH63 to true)

After evaluation begins, activate trigger 1.

Initiating Cues AP-53.00 Immediate Actions Shift Manager direction.

Directions to the Applicant You are the Unit 1 RO and I am the Shift Manager. The unit is operating at 100% power with all systems in automatic.

You are to respond to a plant transient.

When you finish the actions necessary to stabilize the unit at pre

-event conditions, please inform me.

Notes Surry 2010-301 Pressurizer Level Channel Fails Low Page 3 of 1 1 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1: IDENTIFIES CHANNEL III PRESSURIZER LEVEL FAILED LOW.

STANDARD:

Identifies 1

-RC-LI-1461 failed low.

Acknowledges Annunciator E-H-6, PRZR LO LVL CH

-3. Enters 0-AP-53.00, Loss of Vital Instrumentation/Controls.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 1 - VERIF Y REDUNDANT INSTRUMENT CHANNEL(S) INDICATION

- NORMAL STANDARD: Verifies R C-LT-1459 and 1460 normal.

Acknowledges annunciator C

-E-8, PRZR LO LVL HTRS OFF & LETDOWN ISOL.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 4 of 1 1 STEP 3: Step 2 - PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION STANDARD: Places charging flow control in manual and reduces to pre

-event flow (80

-90 gpm). This is a Critical Task.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

STEP 4: IMMEDIATE ACTIONS OF 0-AP-53.00 COMPLETE.

STANDARD: Operator reports the immediate actions of AP

-53.00 are complete.

EVALUATOR'S NOTE: Once the operator has reported the immediate actions of 0

-AP-53.00 are complete, acknowledge the completion of the immediate action steps and inform the operator that you would like them to continue on and perform 0

-AP-53.00 up to and not including step 14 and hand them a copy of the procedure.

COMMENTS: _______ SAT

_______ UNSAT

STEP 5: Step 3 - VERIFY REACTOR POWER

- LESS THAN OR EQUAL TO 100%

(continuous action step)

. STANDARD: Verifies Reactor Power indicating less than or equal to 100% using PCS 10 minute and/or instantaneous power indications.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 5 of 1 1 STEP 6: NOTES PRIOR TO STEP 4 NOTE: 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

14. STANDARD: Acknowledges notes EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 7: Step 4 - DETERMINE THE FAILED INSTRUMENT/CONTROL AND GO TO APPROPRIATE STEP.

STANDARD: Determines PRZR Level Control to be the failed instrument and goes to step 12.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

STEP 8:

Step 12 a - CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL STANDARD: Determines that all pressurizer level channels are not normal and goes to 12 aRNO. EVALUATOR'S CUE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 6 of 1 1 STEP 9: Step 12 a RNO - a) Do the following, as necessary:

1) Place either of the following in MANUAL:

1-CH-FC-1122C, CHG FLOW CNTRL OR

1-CH-LC-1459G, PRZR LEVEL CNTRL

2) Control PRZR level at program level.

3) Move PRZR LVL

- CH SEL switch to defeat the failed channel.

4) Verify or place recorder 1-RC-LR-1459 on an operable channel. 5) Refer to Tech Spec 3.1.A.5 (if Pressurizer heaters deenergized), Table 3.7-1, Item 9 and Table 3.7

-6, Item 13.

6) Refer to Attachment 3.

STANDARD: Places either 1

-CH-FCV-1122C or 1

-CH-LC-1459G in manual to control pressurizer level at program level. Note: One of these may already have been placed in manual during the immediate action steps.

Moves PRZR LVL

- CH SEL switch to defeat channel III. The ch annel should be placed in postion 1 which selects channel I as the upper and channel II as the lower. This is a Critical Task.

Places 1-RC-LR-1459 on an operable channel.

Notifies SM to review Tech Specs.

Refers to attachment 3 in 0

-AP-53.00. EVALUATOR'S NOTE: If asked, Tech Specs will be reviewed by Unit Supervisor / Shift Manager.

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 7 of 1 1 STEP 10: Step 12b- Verify Pressurizer Heaters

- ENERGIZED STANDARD: Trainee determines that not all pressurizer heaters are energized as required and that "C" Group pressurizer proportional heaters will need to be reset. Goes to RNO.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT STEP 11:

Step 12bRNO

- Reset Pressurizer Heaters.

STANDARD: Resets Group "C" pressurizer proportional heaters and verifies all heaters ar e energized or in Auto as required.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT STEP 1 2:

Step 12c- Check letdown

- IN SERVICE.

STANDARD: Verifies letdown is in service by observing normal letdown flow indicated. Note:

The trainee may point out that auto letdown isolation failed when 1

-RC-LI-1461 failed low.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 8 of 1 1 STEP 1 3: Step 12 d- Check PRZR level control

- IN AUTOMATIC STANDARD: Determine s pressurizer level control is in manual by observing 1

-CH-FCV-1122C or 1

-CH-LC-1459G in manual. Goes to RNO.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT STEP 1 4:

Step 12dRNO- Check PRZR level control

- IN AUTOMATIC d) Do the following as required:

1) Verify PRZR level restored to program.

2) Unsaturate 1-CH-LC-1459G, PRZR LEVEL CNTRL, as required.

3) Return 1-CH-FCV-1122 to AUTOMATIC by verifying or placing the following in AUTOMATIC:

1-CH-FC-1122C, CHG FL OW CNTRL

1-CH-LC-1459G, PRZR LEVEL CNTRL STANDARD:

Checks pressurizer level at program level.

Unsaturates 1

-CH-LC-1459G if necessary.

Returns 1-CH-FCV-1122C and/or 1

-CH-LC-1459G to Auto.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Pressurizer Level Channel Fails Low Page 9 of 1 1 STEP 15:

IAW the Note prior to step 4, recovery actions should continue at step 14.

STANDARD: Transitions to step 14.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 1 6:

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that 0-AP-53.00 is complete up to but not including step 14.

EVALUATOR'S NOTE: N/A STOP TIME:

COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME:

___________________________________________

_________________________________________

____________________________________________________________________________________

_________________________________________

___________________________________________

____________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Perform Steps immediate action steps of AP

-53.00, Loss of Vital Instrumentation/Controls, and then perform AP

-53.00 up to but not including step 14.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions Unit is at 100% power and stable.

Initiating Cues You are the Unit 1 RO and I am the Shift Manager. The unit is operating at 100% power with all systems in automatic.

You are to respond to a plant transient.

When you finish the actions necessary to stabilize the unit at pre

-event conditions, please inform me

.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions Unit is at 100% power and stable.

Initiating Cues You are the Unit 1 RO and I am the Shift Manager. The unit is operating at 100% power with all systems in automatic.

You are to respond to a plant transient.

When you finish the actions necessary to stabilize the unit at pre

-event conditions, please inform me.

Surry 2010-301 Loss of RHR Pump Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 005.A4.01 (3.6/3.4)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ________

___________________________

Stop Time___________________

Title RESPOND TO A LOSS OF THE OPERATING RHR PUMP

. K/A: 005.A4.01 Ability to manually operate and/or monitor in the control room: Controls and indication for RHR pumps.

Applicability Estimated Time Actual Time RO/SRO(I)/SRO(U) 12 minutes

Conditions Task is to be PERFORMED in the simulator.

1-RH-P-1A was in service on "A" RHR HX. We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped.

Standards 1-RH-P-1B started and RHR flow restored in accordance with 1

-AP-27.00, Loss of Decay Heat Removal Capability.

Initiating Cues Trip of the operating RHR pump.

Shift Manager direction.

Terminating Cues 1-AP-27.00, Loss of Decay Heat Removal Capability, step 14 completed.

Procedures 1-AP-27.00, Loss of Decay Heat Removal Capability.

Surry 2010-301 Loss of RHR Pump Page 2 of 9 Tools and Equipment None None Safety Considerations Recall IC-323 Simulator Setup Call up RHR IC and initialize. Place simulator in RUN.

OR Verify "A" RHR pump running and "B" in AUTO.

Verify 1-RH-FCV-1605 in auto with flowrate set at 3400 gpm.

Implement malf for over

-current trip of 1

-RH-P-1A and allow annunciators B

-G-6 & B-G-7 to alarm.

Place simulator in FREEZE until ready to perform JPM. 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.

Initiating Cues Trip of the operating RHR pump.

Shift Manager direction.

Directions to the Applicant I am the Shift Manager and you are the Unit RO. The unit has been operating on RHR.

1-RH-P-1A, "A" RHR pump was in service on "A" RHR heat exchanger at 3400 gpm.

We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped. Here is a copy of 1

-AP-27.00, Loss of Decay Heat Removal Capability. I need you to perform the necessary steps to address this condition and restore RHR flow. No RCS draindown evolutions are in progress and inventory is stable, not decreasing.

When you complete 1-AP-27.00, please inform me.

Notes Surry 2010-301 Loss of RHR Pump Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1:

CAUTION S and NOTE PRIOR TO STEP 1 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 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 caution s and recognizes that a total loss of IA is not occuring

.

COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 1 - CHECKS RCS INVENTORY

- DECREASING.

PRZR level

- DECREASING Standpipe level

- DECREASING Reactor cavity level - DECREASING RCS Narrow Range level

- DECREASING CTMT sump level

- INCREASING Makeup rate

- INCREASING PRT level, pressure, or temperature

- INCREASING PDTT level

- INCREASING RWST level

- INCREASING

_______ SAT

_______ UNSAT

Surry 2010-301 Loss of RHR Pump Page 4 of 9 STANDARD: Notes that there are no draindown evolutions in progress and inventory is stable based on the directions given.

Checks Containment Sump level (1

-DA-LI-100) is stable and not increasing.

Checks PRT conditions (level, LI 470; pressure, PI 472; and temperature, TI-1-471) are stable and not increasing.

Checks PDTT level (1

-DG-LI-107) is stable and not increasing.

Checks RWST level stable.

Determines that RCS inventory is NOT decreasing and performs RNO to transition to procedure STEP 4.

EVALUATOR'S NOTE: If asked, all indications are as you see them. If asked, no personnel are in Containment.

If asked, cavity is not flooded up.

COMMENTS:

STEP 3:

Step 4 - VERIFY RHR PUMP

- ONE RUNNING

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. Goes to RNO.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Step 4RNO - IF Emergency Bus power is available, THEN do the following: a) Manually close RH control valves:

1-RH-FCV-1605

1-RH-HCV-1758 b) Start one RHR pump.

c) Adjust RH control valves to return flow to pre

-event rate:

1-RH-FCV-1605

1-RH-HCV-1758

_______ SAT

_______ UNSAT

Surry 2010-301 Loss of RHR Pump Page 5 of 9 STANDARD: Places 1-RH-FCV-1605 in manual and closes valve.

Notes setpoint on ten turn pot for 1

-RH-H CV-1758 (9.8) and then closes 1

-RH-HCV-1758 using ten turn pot.

Starts 1-RH-P-1B by taking control switch to the start position and verifying amp are indicated.

This is a Critical Task.

Opens 1-RH-FCV-1605 until flow is approximately 3400 gpm and then places in AUTO. This is a Critical Task.

Places ten turn pot for 1

-RH-FCV-1758 at pre

-event setpoint of 9.8.

EVALUATOR'S NOTE: N/A COMMENTS:

STEP 5: Step 5 - VERIFY RHR FLOW

- INDICATED ON RHR SYS FLOW

1-RH-FI-1605 STANDARD: Checks RHR flow at approximately 3400 gpm on 1

-RH-FI-1605.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 6:

Step 6 - CHECK RHR PUMP

- VORTEXING

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 6 RNO.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Loss of RHR Pump Page 6 of 9 STEP 7: Step 12 - CHECK RHR HEAT SINK:

a) Flow on 1

-RH-FI-1605 - NORMAL b) CC to RHR HX b)

1) RHR HX CC Outlet HDR Flow

- NORMAL

1-CC-FI-110A

1-CC-FI-110B OR

2) RHR HX CC Outlet HDR TEMP

- NORMAL

1-CC-TI-109A

1-CC-TI-109B OR STANDARD: Checks flow on 1

-RH-FI-1605 indicating normal about 3400 gpm.

Checks CC to RHR HX on 1

-CC-FI-110A normal.

Checks RHR HX CC Outlet Hdr Temp on 1

-CC-TI-109A normal.

EVALUATOR'S NOTE: If asked, pre

-event flow on 1-CC-FI-110A was 4700 and temperature on 1-CC-TI-109A was approximately 88 degrees.

COMMENTS:

_______ SAT

_______ UNSAT

STEP 8:

Step 13 - VERIFY RCS TEMPERATURE

- STABLE OR DECREASING

STANDARD: Checks RCS temperature and/or RHR temperature stable or decreasing.

EVALUATOR'S CUE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Loss of RHR Pump Page 7 of 9 STEP 9: Step 14 - RETURN TO PROCEDURE IN EFFECT STANDARD: Operator Exits 1

-AP-27.00. EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT STEP 10:

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that 1

-AP-27.00, Loss of Decay Heat Removal Capability is complete and RHR flow has been restored.

EVALUATOR'S NOTE: N/A STOP TIME:

COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

____________________________________________________________________________________

___________________________________________________

_________________________________

____________________________________________________________________________________

_________________________________________________

___________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Perform 0-AP-27.00, LOSS OF DECAY HEAT REMOVAL CAPABILITY, to restore RHR flow to the core by starting 1-RH-P-1B.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions 1-RH-P-1A was in service on "A" RHR HX. We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped.

Initiating Cues I am the Shift Manager and you are the Unit RO. The unit has been operating on RHR.

1-RH-P-1A, "A" RHR pump was in service on "A" RHR heat exchanger at 3400 gpm.

We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped. Here is a copy of 1

-AP-27.00, Loss of Decay Heat Removal Capability. I need you to perform the necessary steps to address this condition and restore RHR flow. No RCS draindown evolutions are in progress and inventory is stable, not decreasing.

When you complete 1

-AP-27.00, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions 1-RH-P-1A was in service on "A" RHR HX. We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped.

Initiating Cues I am the Shift Manager and you are the Unit RO. The unit has been operating on RHR.

1-RH-P-1A, "A" RHR pump was in service on "A" RHR heat exchanger at 3400 gpm.

We just received annunciator B

-G-6, RHR HX LO FLOW, and 1-RH-P-1A has tripped. Here is a copy of 1

-AP-27.00, Loss of Decay Heat Removal Capability. I need you to perform the necessary steps to address thi s condition and restore RHR flow. No RCS draindown evolutions are in progress and inventory is stable, not decreasing.

When you complete 1

-AP-27.00, please inform me.

Surry 2010-301 FR-H.1, Feed From Condensate Page 1 of 12 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure EPEE05.EA1.1 (4.1/4.0) Alternate Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title ESTABLISH FEED FLOW FROM THE CONDENSATE SYSTEM IN RESPONSE TO A LOSS OF SECONDARY HEAT SINK.

K/A: EPEE05.EA1.1 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat Sink): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Applicability Estimated Time Actual Time RO/SRO(I) 20 minutes Conditions Task is to be PERFORMED in the simulator.

Plant is shutdown following a trip.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, is in effect at step 8.

Standards Establishes feed flow from the main condensate system IAW 1

-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 8.

Initiating Cues 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 8.

Shift Manager direction.

Terminating Cues 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 8 completed.

Procedures 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

Surry 2010-301 FR-H.1, Feed From Condensate Page 2 of 12 Tools and Equipment None None Safety Considerations Recall saved IC

-328 Simulator Setup Call up 100% IC and initialize.

OR Enter the following malfunctions: FW0701 (1-FW-P-3A Overcurrent Trip), FW0702 (1

-FW-P-3B Overcurrent Trip), and MS16 (1

-FW-P-2 Trip Throttle Valve Failed Close) with a 0 second time delay, FW1701 (1

-FW-P-1A Impeller Degradation) and FW1702 (1

-FW-P-1B Impeller Degradation) with a 2 second time delay 100% degradation.

Place the simulator in run and implement the malfunctions, immediately trip to conserve SG level.

Depressurize the RCS to 1950# while cooling the plant to <540F, block Low Pressure and High Steam Flow SI signals, Trip the RCPs, ensure RCS temp and pressure are stable SG levels should be about 30-50% WR when the setup is completed. If needed, delete a MFW pump degradation malfunction and feed the SGs. After feeding stop the MFP and re

-insert the deleted MFW pump degradation.

below the SI block setpoints. Go to Bypass Interlock on the steam dumps.

Set up the following triggers:

Trigger #5 - Places 'A' MFP motor breakers in test (use remote functions FWP1A1_TEST and FWP1A2_TEST and set the final value to IN TEST)

Trigger #7 - Places 'B' MFP motor breakers in test (use remote functions FWP1B1_TEST and FWP1B2_TEST and set the final value to IN TEST)

Place the simulator in freeze. Save conditions if necessary.

Insert the following malfunctions to fail the steam dumps: MSPC464B_RAISE to OFF, MSPC464B_LOWER to OFF, MSPC464B_MANUAL to ON.

Make sure RCS pressure is low enough that SI will not unblock before the cooldown (depressurization of 1 SG) begine. Initiating Cues 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 8.

Shift Manager direction.

Directions to the Applicant You are the Unit RO and I am the Shift Manager. There is a loss of secondary heat sink in progress on Unit 1.

Unit conditions are as follows, Unit 1 tripped due to mechanical damage to both main feed pumps, none of the aux feed pumps are working on Unit 1 and crosstie attempts from unit 2 have proven unsuccessful.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been completed to step 8. RCPs are secured, low pressure and hi steam flow SI signals have been blocked.

Here is a copy of FR

-H.1 Step 8, I need you to ESTABLISH FEED FLOW FROM THE CONDENSATE SYSTEM IN RESPONSE TO A LOSS OF SECONDARY HEAT SINK in accordance with step 8.

When you finish the actions necessary to accomplish this, please inform me.

Notes Surry 2010-301 FR-H.1, Feed From Condensate Page 3 of 12 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITIAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee

. START TIME:

STEP 1:

NOTE PRIOR TO STEP 8 NOTE: Flow on each Main Steamline should be kept less than 1.0 x 10 6 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps. STANDARD: Acknowledges note.

COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 8a - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

a) Select one intact SG to depressurize

STANDARD: Selects one SG to depressurize (A, B, or C)

EVALUATOR'S NOTE: If asked, there is no preferred SG.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 FR-H.1, Feed From Condensate Page 4 of 12 STEP 3: Step 8b - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

b) Close MSTVs on the non

-selected SGs STANDARD: Closes MSTVs on the 2 non

-selected SGs by taking control switch to close and verifying green light on and red light off.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Step 8c - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

c) Align CHG pump suction to the RWST:

1) Verify open or open CHG pump suction from RWST MOVs

1-CH-MOV-1115B

1-CH-MOV-1115D

2) Verify closed or close CHG pump suction from VCT MOVs

1-CH-MOV-1115 C

1-CH-MOV-1115E STANDARD: Opens 1-CH-MOV-1115B and 1

-CH-MOV-1115D by taking control switch to open and verifying red light on and green light off.

Closes 1-CH-MOV-1115C and 1

-CH-MOV-1115E by taking control switch to close and verifying green light on and red light off.

EVALUATOR'S NOTE:

N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 FR-H.1, Feed From Condensate Page 5 of 12 STEP 5: Step 8d - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

d) Verify closed or close letdown isolation valves

1-CH-LCV-1460A

1-CH-LCV-1460B STANDARD: Closes 1-CH-LCV-1460A and 1

-CH-LCV-1460B by taking control swich to close and verifying green light on and red light off.

Verifies letdown flow goes to zero.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ S AT

_______ UNSAT

STEP 6: Step 8e - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

e) Control charging flow to maintain PRZR level

STANDARD: Verifies 1

-CH-FCV-1122 is controlling in automatic or places in manual to control pressurizer level.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 7:

Step 8f - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

f) Dump steam to condenser at maximum rate to depressurize one intact SG to less than 550 psig.

STANDARD: Attempts to use steam dumps to depressurize selected intact SG.

Notes that the steam dumps are not functioning and goes to RNO.

_______ SAT

_______ UNSAT

Surry 2010-301 FR-H.1, Feed From Condensate Page 6 of 12 EVALUATOR'S NOTE:

N/A COMMENTS: STEP 8: Step 8f RNO- TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

f) Dump steam from intact SG:

Manually use SG PORV.

OR

Locally use SG PORV IAW Attachment 6.

IF at least one SG can NOT be depressurized, THEN GO TO Step 10.

STANDARD: Selects intact SG PORV and depressurizes selected intact SG to less than 550 psig by either placing SG PORV in man ual and opening it OR lowering setpoint for SG PORV.

Does not go to step 10, goes to step 8g. EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STEP 9:

Step 8g - TRY TO ESTABLISH FEED FLOW FROM CONDENSATE SYSTEM BY DEPRESSURIZING ONE INTACT SG:

g) Establish condensate flow:

1) Locally put one set of feed pump breakers in test

2) Close feed pump breakers in test

3) Open appropriate feed pump discharge MOV

4) Control flow with SG FW bypass flow valve(s) or feed REG valve(s) as necessary

5) Depressurize SG as necessary to establish adequate Delta

-P for feeding _______ SAT

_______ UNSAT

Surry 2010-301 FR-H.1, Feed From Condensate Page 7 of 12 STANDARD: Directs operator to close either 'A' or 'B' MFP breakers in test.

Once MFP breakers are reported to be closed in test, takes the control switches to close for the selected MFPs.

Opens appropriate discharge MOV (1

-FW-MOV-150A or 1-FW-MOV-150B). Controls FW flow to selected SG using the FW bypass flow valve for that selected SG.

Operator may continue to depressurize SG using SG PORV.

Verifies positive indication of SG level increase for selected SG.

All the above are Critical Tasks.

EVALUATOR'S NOTE: N/A

COMMENTS:

STEP 11:

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that feed flow has been established to at least one intact SG.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

____________________________________________________________________________________

____________

________________________________________________________________________

____________________________________________________________________________________

__________

__________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Establish feed flow from the main condensate system IAW 1

-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 8.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned ta sk Initial Conditions Unit 1 tripped due to mechanical damage to both main feed pumps, none of the aux feed pumps are working on Unit 1 and crosstie attempts from unit 2 have proven unsuccessful.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been completed to step 8. RCPs are secured, low pressure and hi steam flow SI signals have been blocked.

Initiating Cues You are the Unit RO and I am the Shift Manager. There is a loss of secondary heat sink in progress on Unit 1.

Unit conditions are as follows, Unit 1 tripped due to mechanical damage to both main feed pumps, none of the aux feed pumps are working on Unit 1 and crosstie attempts from unit 2 have proven unsuccessful.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been completed to step 8. RCPs are secured, low pressure and hi steam flow SI signals have been blocked.

Here is a copy of FR

-H.1 Step 8, I need you to ESTABLISH FEED FLOW FROM THE CONDENSATE SYSTEM IN RESPONSE TO A LOSS OF SECONDARY HEAT SINK in accordance with step 8.

When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions Unit 1 tripped due to mechanical damage to both main feed pumps, none of the aux feed pumps are working on Unit 1 and crosstie attempts from unit 2 have proven unsuccessful.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been completed to step 8. RCPs are secured, low pressure and hi steam flow SI signals have been blocked.

Initiating Cues You are the Unit RO and I am the Shift Manager. There is a loss of secondary heat sink in progress on Unit 1.

Unit conditions are as follows, Unit 1 tripped due to mechanical damage to both main feed pumps, none of the aux feed pumps are working on Unit 1 and crosstie attempts from unit 2 have proven unsuccessful.

1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been completed to step 8. RCPs are secured, low pressure and hi steam flow SI signals have been blocked. Here is a copy of FR

-H.1 Step 8, I need you to ESTABLISH FEED FLOW FROM THE CONDENSATE SYSTEM IN RESPONSE TO A LOSS OF SECONDARY HEAT SINK in accordance with step 8.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2010-301 Spurious CS Actuation Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 026.A4.01 (4.5/4.3) Alternate Path

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title RESPOND TO A SPURIOUS CS ACTUATION

. K/A: 026.A4. 01 Ability to manually operate and/or monitor in the control room: CSS Controls.

Applicability Estimated Time Actual Time RO/SRO(I) 12 minutes

Conditions Task is to be PERFORMED in the simulator.

Spurious CS actuation has occurred at HSD.

Standards Applicant recognizes spurious Hi Hi CLS signal.

Applicant secures 1

-CS-P-1 A, closes discharge MOVs 1-CS-MOV-101 A , B from MCR. Applicant directs actions to secure 1

-CS-P-1 B, close discharge MOVs 1

-CS-MOV-101 C , D from field / MCR.

Initiating Cues 1B-A6/B6, CTMT PART PRESS

-0.1 PSI CH 1 / 2 remain locked in.

Shift Manager direction.

Terminating Cues 1B-A6 Attachment 1, steps 1-6 complete.

Procedures 1B-A6, CTMT PART PRESS

-0.1 PSI CH 1.

Surry 2010-301 Spurious CS Actuation Page 2 of 9 Tools and Equipment Safety Considerations None None Simulator Setup Recall IC-326 OR Call up HSD IC and initialize

. Start 1-CS-P-1A/1B, freeze simulator, green flag both pumps and then place simulator in run.

Open 1-CS-MOV-101A-D. Implement the following overrides to prevent 1

-CS-P-1B from being secured from MCR and 1

-CS-MOV-101C/D from closing with control switch: MOVCS101C_OPEN

& MOVCS101D_OPEN to ON, CSP1B_STOP & CSP1B_LOCK to OFF.

Place the following Remotes on triggers: CSMOV101C & CSMOV101D to rack

-out, CSMOV101C & CSMOV101D manual valves to 0% (closed).

Initiating Cues 1B-A6/B6, CTMT PART PRESS

-0.1 PSI CH 1 / 2 remain locked in. Shift Manager direction.

Directions to the Applicant

I am the Shift Manager and you are the Unit RO.

Unit 1 is at Hot Shutdown.

There are NO personnel in Unit 1 containment.

An inadvertent CS actuation occurred and we have received annunciators 1 B-A6 and 1B-B6. Annunciator response 1B

-A6 has been initiated.

Here's a copy of annunciator response 1B

-A6. I need you to perform attachment 1 of ARP 1B

-A6, steps 1-6 only. When you finish the actions necessary to complete attachment 1, please inform me.

Notes Surry 2010-301 Spurious CS Actuation Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1:

STEP 1 - Verify reset or reset HI HI CLS signal.

STANDARD: Verifies annunciators 1B

-C4 and 1B-C5 are not lit.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 2 - Place control switch(es) for running CS pump(s) in PTL.

1-CS-P-1A

1-CS-P-1B STANDARD: Places control switch 1

-CS-P-1A in PTL and verifies zero amps.

This is a Critical Task.

Places control switch for 1

-CS-P-1B in PTL. Recognizes 1

-CS-P-1B did NOT stop by observing red light on and amps indicated.

EVALUATOR'S NOTE: N/A Booth Operator:

When called to locally open 1

-EP-BKR-14J-5, implement trigger 9 and inform the candidate that a time compression has occurred and 1

-EP-BKR-14J-5 is open.

COMMENTS:

_______ S AT

_______ UNSAT

Surry 2010-301 Spurious CS Actuation Page 4 of 9 STEP 3: Step 3 - IF CS pump(s) will NOT stop from the MCR, THEN locally open supply breaker(s):

1-CS-P-1A, 14H-5

1-CS-P-1B, 14J-5 STANDARD: Directs Operator to locally open supply breaker 1

-CS-P-1B supply breaker 14 J-5. This is a Critical Task.

When local operator reports 14J

-5 is open, recognizes breaker for 1

-CS-P-1B is open (red light off).

This is a Critical Task.

EVALUATOR'S NOTE: N/A BOOTH OPERATOR'S NOTE: When directed to locally open 14J

-5, inform the candidate that a time compression has occurred and 14J

-5 is open.

COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Note prior to Step 4 NOTE: The CS Pump Discharge MOVs will not close if the HI HI CLS signal is present. STANDARD: Acknowledge s note.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Spurious CS Actuation Page 5 of 9 STEP 5: Step 4 - Verify closed or close CS PUMP DISCH MOV(s):

1-CS-MOV-101A

1-CS-MOV-101B

1-CS-MOV-101C

1-CS-MOV-101D STANDARD: Closes 1-CS-MOV-101A (red light off, green light on)

. This is a Critical Task.

Closes 1-CS-MOV-101B (red light off, green light on). This is a Critical Task.

Closes 1-CS-MOV-101C (red light off, green light on)

Recognizes 1

-CS-MOV-101C did NOT close Closes 1-CS-MOV-101D (red light off, green light on)

Recognizes 1

-CS-MOV-101D did NOT close

EVALUATOR'S NOTE:

N/A COMMENTS: _______ SAT

_______ UNSAT

STEP 6: Step 5 - IF CS PUMP DISCH MOV(s) will NOT close, THEN do the following:

a. Send an Operator to Unit 1 Cable Vault and an Operator to Unit 1 Safeguards.

b. Direct Operator in Unit 1 Cable Vault to open MOV supply breaker(s) for

MOV(s) which will not close.

1-CS-MOV-101A, 1H1-2S-1A

1-CS-MOV-101B, 1J1-2W-5A

1-CS-MOV-101C, 1H1-2S-2B

1-CS-MOV-101D, 1J1-2W-4A

c. WHEN breaker(s) open, THEN have Operator in Safeguards locally close affected MOV(s). _______ SAT

_______ UNSAT

Surry 2010-301 Spurious CS Actuation Page 6 of 9 STANDARD: Directs Operator to locally open breaker for 1

-CS-MOV-101C, 1H1-2S-2B. This is a Critical Task.

Directs Operator to locally open breaker for 1

-CS-MOV-101D, 1J1-2W-4A. This is a Critical Task.

Once breakers reported open, directs local closure of 1

-CS-MOV-101C and 1

-CS-MOV-101D. EVALUATOR'S NOTE: N/A Booth Operator: When called to locally open 1

-EP-BKR-1H1-2S-2B & 1-EP-BKR-1J1-2W-4A, implement triggers 3 & 5 and inform the candidate that a time compression has occurred and 1

-EP-BKR-1H1-2S-2B & 1-EP-BKR-1J1-2W-4A are open.

Booth Operator:

When called to locally close 1

-CS-MOV-101C & 1-CS-MOV-101D, implement trigger 7 and inform the candidate that a time compression has occurred and 1

-CS-MOV-101C & 1-CS-MOV-101D are closed.

COMMENTS:

STEP 7:

Step 6 - Verify closed or close CHEM ADD TK OUTLET MOVs:

1-CS-MOV-102A

1-CS-MOV-102B STANDARD: Verifies 1

-CS-MOV-102A and 1

-CS-MOV-102B closed by observing red light off and green light on.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Spurious CS Actuation Page 7 of 9 STEP 8: REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that Attachment 1 of Annunciator response 1B

-A6, steps 1

-6 are complete.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

___________________________________________________________________________________

_ ____________________________________________________________________________________

____________________________________________________________________________________

_________________________________________________________________________________

___

____________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Perform Attachment 1, steps 1-6, of ARP 1B-A6.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions Spurious CS actuation has occurred at HSD.

Initiating Cues

I am the Shift Manager and you are the Unit RO.

Unit 1 is at Hot Shutdown.

There are NO personnel in Unit 1 containment.

An inadvertent CS actuation occurred and we have received annunciators 1B

-A6 and 1B-B6. Here's a copy of annunciator response 1B

-A6. I need you to perform attachment 1 of ARP 1B

-A6, steps 1-6 only. When you finish the actions necessary to complete attachment 1, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions Spurious CS actuation has occurred at HSD.

Initiating Cues

I am the Shift Manager and you are the Unit RO.

Unit 1 is at Hot Shutdown.

There are NO personnel in Unit 1 containment.

An inadvertent CS actuation occurred and we have received annunciators 1B

-A6 and 1B-B6. Here's a copy of annunciator response 1B

-A6. I need you to perform attachment 1 of ARP 1B

-A6, steps 1-6 only. When you finish the actions necessary to complete attachment 1, please inform me.

Surry 2010-301 AP-10.07, Attachment 4 Page 1 of 1 0 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 064.A2.05 (3.1/3.2) Alternate Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title ALIGN THE EMERGENCY BUS IN ACCORDANCE WITH AP

-10.07 ATTACHMENT 4 K/A: 064.A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loading the ED/G.

Applicability Estimated Time Actual Time RO/SRO(I) 15 minutes

Conditions Task is to be PERFORMED in the simulator.

1-CH-P-1B is in service. 1

-CH-P-1A and 1C are in AUTO. 1

-VS-F-58A is in service on the fuel building. Breaker 15H8 spuriously opened and #1 EDG is supplying Unit 1 H Bus Loads

.

Standards 1-AP-10.07, LOSS OF UNIT 1 POWER, Attachment 4 completed.

Initiating Cues 1-AP-10.07, LOSS OF UNIT 1 POWER, Step 41. Shift Manager Direction.

Terminating Cues Attachment 4 of 1

-AP-10.07, LOSS OF UNIT 1 POWER, completed.

Procedures Attachment 4 of 1

-AP-10.07, LOSS OF UNIT 1 POWER.

Surry 2010-301 AP-10.07, Attachment 4 Page 2 of 1 0 Tools and Equipment None None Safety Considerations Recall IC-325 Simulator Setup Call up 100% power IC & initialize. Verify that 1

-CH-P-1B is running and 1

-CH-P-1A and 1-CH-P-1C are in auto after stop.

OR Place the 58A fan in service on the fuel building.

Implement the following malfunction to cause breaker 15H8 to open: EL4901 Implement the following override to automatically actuate when 1

-CH-P-1A or 1-CH-P-1C is started: EDG1_MW = 0.32 (this will cause the #1 EDG MWs to read approximately 1600kW).

Reset the stub bus and start 1

-CC-P-1A. Perform 1-AP-10.07 up to step 41 and place the simulator in freeze to await JPM performance.

Place an orange magnet on 15H8.

RED FLAG 1

-VS-F-58A. Initiating Cues 1-AP-10.07, Step

41. Shift Manager Direction.

Directions to the Applicant I am the Shift Manager and you are the Unit RO. 1

-VS-F-58A is in service on the fuel building at the request of the fuel handlers in preparations for upcoming activities in the fuel building.

1-EP-BKR-15H8 spuriously opened and we are performing 1

-AP-10.07, LOSS OF UNIT 1 POWER. #1 EDG is supplying the 1H Bus solely.

Here is a copy of Attachment 4 of 1

-AP-10.07 (EMERGENCY BUS LOAD ALIGNMENT). I need you to perform this attachment in its entiret

y. Inform the Shift Manager prior to performing any component manipulations.

When you finish the actions necessary to accomplish this, please inform me.

Notes Surry 2010-301 AP-10.07, Attachment 4 Page 3 of 1 0 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1:

CAUTION S AND NOTES PRIOR TO STEP 1 CAUTION: An EDG can NOT initially be loaded to greater than 1300 KW prior to an SI or HI HI CLS, with the exception of loads that will trip when a HI HI CLS occurs, or loads which are running yet assumed to start on a HI HI CLS.

CAUTION: Total EDG load shall not exceed 2750 KW.

NOTE: The purpose of this Attachment is to limit EDG loading so that a subsequent HI HI CLS actuation will not overload the EDG.

EDG load must be monitored closely during pump operations.

One CHG pump must be running on each Emergency Bus solel y supplied from an EDG.

The other CHG pump supplied from that Emergency Bus must remain in PTL.

A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non

- running CHG pump is in PTL. This Tech LCO is entered due to an inoperable Emergency Bus due to EDG loading.

STANDARD: Acknowledges caution s and notes. The candidate may inform the SRO of the tech spec clock.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 AP-10.07, Attachment 4 Page 4 of 1 0 STEP 2: STEP 1 a - IF EDG 1 is the sole source of power to Emergency Bus 1H, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.

a. Verify running or start 1

-CH-P-1A or 1-CH-P-1C on Emergency Bus 1 H IAW Shift Supervision direction.

STANDARD: Starts 1-CH-P-1A or 1-CH-P-1C by placing control switch to start and observing amps indicated.

This is a Critical Task.

EVALUATOR'S NOTE: If asked, you have no preference as to which charging pump is started. COMMENTS:

_______ SAT

_______ UNSAT

STEP 3:

Step 1 b - b. IF a CHG pump can NOT be started on Emergency Bus 1H, THEN do the following. Otherwise, enter N/A.

___ 1. Verify running or start a CHG pump on Emergency Bus 1J.

___ 2. Place CHG pumps supplied from Emergency Bus 1H in PTL. (A supplied by Emergency Bus 1H are in PTL) ___ 3. GO TO Step 2.

STANDARD: N/A step 1b.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Step 1 c - c. Verify or place the remaining CHG pump supplied from Emergency Bus 1H in PTL. (1

-CH-P-1C must remain running if pump is supplied by Emergency Bus 1J)

_______ SAT

_______ UNSAT

Surry 2010-301 AP-10.07, Attachment 4 Page 5 of 1 0 STANDARD: Places non-running charging pump (1

-CH-P-1A or 1-CH-P-1C) in PTL.

This is a Critical Task. EVALUATOR'S NOTE

If informed, acknowledge that the 6/30 hr TS clock can be stopped.

COMMENTS: STEP 5: Step 1 d -

d. IF Emergency Bus 1J is supplied by offsite power, and 1

-CH-P-1B is running, THEN stop 1-CH-P-1B and place in Auto.

STANDARD: Secures 1-CH-P-1B by taking control switch to stop and returning to auto.

Observes zero amps indicated.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 6: Step 1e -

e. Determine Emergency Bus 1H load limit IAW the following equation, where (x) equals the total of the KW ratings of all RUNNING equipment from the table below.

___________ + 1300 KW = _________________

(x) EDG Load Limit

KW LOAD 100 1-VS-F-1A 125 1-VS-F-58A (if supplied by 14H1-1) 310 1-FW-P-3A

_______ SAT

_______ UNSAT

Surry 2010-301 AP-10.07, Attachment 4 Page 6 of 1 0 STANDARD: Identifies that 1

-VS-F-1A & 1-VS-F-58A are in service and 1

-FW-P-3A is not running.

Places 225 kW on the line in step 1e above the letter (x).

Determines that the load limit is 1525 kW. Records load limit in step 1e.

EVALUATOR'S NOTE: N/A COMMENTS: STEP 7:

Step 1 f - f. IF existing EDG load is greater than the limit calculated in substep e.

above, THEN reduce EDG load to less than or equal to the calculated load. STANDARD: Identifies that the current EDG loading is approximately 1600 kW. This exceeds the current EDG load limit.

Informs the SM that the EDG is exceeding its load limit and the procedure states we should reduce load. This is a Critical Task.

EVALUATOR'S NOTE: If asked about EDG loading: Ask what the candidate recommends to reduce. Acknowledge and inform the candidate that you understand the EDG is exceeding its load limit and will have another operator

investigate what loads can be secured to reduce EDG loading; please continue this attachment.

COMMENTS: _______ SAT

_______ UNSAT

STEP 8:

Step 2 - IF EDG 3 is the sole source of power to Emergency Bus 1J, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.

STANDARD: N/A's step 2.

EVALUATOR'S NOTE: N/A

_______ SAT

_______ UNSAT

Surry 2010-301 AP-10.07, Attachment 4 Page 7 of 1 0 COMMENTS: STEP 9: Step 3 - Notify Auxiliary Building Operator to increase monitoring of CHG pump lube oil temperature.

STANDARD: Contacts the Auxiliary Building Operator and directs him to increase monitoring of the Charging Pump Bearing Temperatures.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT STEP 10:

Step 4 - Increasing monitoring of CHG pump bearing temperatures using the Plant Computer system.

STANDARD: Increases monitoring of Charging Pump Bearing Temperatures on the PCS with the CHARGING PUMP SCREEN or states that increased monitoring with the PCS i s required.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT STEP 11:

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that Attachment 4 of 1

-AP-10.07 is complete.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 AP-10.07, Attachment 4 Page 8 of 1 0 STOP TIME:

____________________________________________________________________________________

______________________________________________

______________________________________

____________________________________________________________________________________

____________________________________________

________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Perform Attachment 4 of 1

-AP-10.07, LOSS OF UNIT 1 POWER.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions 1-CH-P-1B is in service. 1

-CH-P-1A and 1C are in AUTO. 1

-VS-F-58A is in service on the fuel building. Breaker 15H8 spuriously opened and #1 EDG is supplying Unit 1 H Bus Loads.

Initiating Cues I am the Shift Manager and you are the Unit RO. 1

-VS-F-58A is in service on the fuel building at the request of the fuel handlers in preparations for upcoming activities in the fuel building.

1-EP-BKR-15H8 spuriously opened and we are performing 1

-AP-10.07, LOSS OF UNIT 1 POWER. #1 EDG is supplying the 1H Bus solely.

Here is a copy of Attachment 4 of 1

-AP-10.07 (EMERGENCY BUS LOAD ALIGNMENT). I need you to perform this attachment in its entirety.

Inform the Shift Manager prior to performing any component manipulations.

When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions 1-CH-P-1B is in service. 1

-CH-P-1A and 1C are in AUTO. 1

-VS-F-58A is in service on the fuel building. Breaker 15H8 spuriously opened and #1 EDG is supplying Unit 1 H Bus Loads.

Initiating Cues I am the Shift Manager and you are the Unit RO. 1

-VS-F-58A is in service on the fuel building at the request of the fuel handlers in preparations for upcoming activities in the fuel building.

1-EP-BKR-15H8 spuriously opened and we are performing 1

-AP-10.07, LOSS OF UNIT 1 POWER. #1 EDG is supplying the 1H Bus solely.

Here is a copy of Attachment 4 of 1

-AP-10.07 (EMERGENCY BUS LOAD ALIGNMENT). I need you to perform this attachment in its entirety.

Inform the Shift Manager prior to performing any component manipulations.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2010-301 WGDT Release Isolation Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 071.A3.03 (3.6/3.8) Alternate Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title WASTE GAS DECAY TANK RELEASE ISOLATION

. K/A: 071.A3.03 Ability to monitor automatic operation of the Waste Gas Disposal System including: Radiation monitoring system alarm and actuating signals.

Applicability Estimated Time Actual Time RO/SRO(I) 13 minutes

Conditions Task is to be PERFORMED in the simulator.

Release of 'B' Waste Gas Decay Tank is in progress. The team is making preparations to run #1 EDG for its monthly performance test.

Standards Release isolated.

1-GW-FCV-101 closed, 1

-GW-FCV-160 closed, and 2

-GW-FCV-260 closed IAW RMA

-C6 and/or RMA

-C7.

Initiating Cues Annunciators RMA

-C6, PROCESS VENT PART ALERT/HI, and/or 0

-RMA-C7, PROCESS VENT NORMAL RANGE GAS ALERT/HI.

Shift Manager direction.

Terminating Cues Steps 1-5 of RMA-C6 and/or RMA

-C7 completed.

Procedures 0-RMA-C6, PROCESS VENT PART ALERT/HI, and/or 0

-RMA-C7, PROCESS VENT NORMAL RANGE GAS ALERT/HI.

Surry 2010-301 WGDT Release Isolation Page 2 of 9 Tools and Equipment None None Safety Considerations Recall IC-329 Simulator Setup OR Call up 100% power IC and initialize.

Enter malfunctions for Disable AUTO CLOSURE for 1

-GW-FCV-101, 1-GW-FCV-160, 2-GW-FCV-260. Enter overrides for Process Vent Particulate and Gas RMs: RM0601 to 40% and RM0602 to 60% and place on trigger

1. Place simulator in run and implement trigger 1 when ready to perform JPM.

HAVE A SIGNED OFF COPY OF OP

-23.2.4, RELEASE OF WASTE GAS DECAY TANK 1B, AVAILABLE IN CASE THE RO ASKS TO REVIEW/LOOK AT PROCEDURE.

Initiating Cues Annunciators RMA

-C6, PROCESS VENT PART ALERT/HI, and/or 0

-RMA-C7, PROCESS VENT NORMAL RANGE GAS ALERT/HI.

Shift Manager direction.

Directions to the Applicant I am the Shift Manager. You are the 3 rd RO. The unit is at 100% power and stable. 'B" Waste Gas Decay Tank release is in progress and we are currently making preparations to run #1 EDG for its monthly surveillance test.

An event is about to occur and I need you to respond IAW applicable procedures

.

Notes Surry 2010-301 WGDT Release Isolation Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

Annunciators RMA

-C6, PROCESS VENT PART ALERT/HI, and RMA

-C7, PROCESS VENT NORMAL RANGE GAS ALERT/HI will alarm. Performing either ARP will satisfy performance of the JPM.

Steps 1-6 of either ARP are identical.

STEP 1:

NOTES PRIOR TO STEP 1 NOTE: The MGP Process Vent channel sensing high radiation will buzz with an audible alarm. Pressing the blue SEL key on the display unit will silence the alarm.

This annunciator does NOT have reflash capability. This MGP remote display unit indicating high radiation will buzz with an audible alarm.

STANDARD: Acknowledges notes. EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT

STEP 2:

STEP 1 - VERIFY ALARM

- READING ON MONITOR OR CHART RECORDER GREATER THAN OR EQUAL TO ALERT SETPOINT

1-GW-RI-130A

1-RM-RR-132, Ch 1

1-RM-RR-132, Ch 4 STANDARD: Checks readings on radiation monitors greater than alert setpoint or checks that chart recorder indication is greater than alert setpoint.

_______ SAT

_______ UNSAT

Surry 2010-301 WGDT Release Isolation Page 4 of 9 EVALUATOR'S NOTE: N/A COMMENTS: STEP 3:

Step 2 - VERIFY PROCESS VENT FLOW RATE DEVICE

- OPERABLE STANDARD: Checks that one process vent blower is in service by checking red light on and green light off for either 1

-GW-F-1A o r 1-GW-F-1B. Verifies process vent flow indicated.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Caution and Note prior to Step 3 CAUTION: When CTMT Vacuum Pump Discharge Isolation valve 1

-GW-FCV- 160 or 2-GW-FCV-260 is closed, the associated Vacuum Pumps must be placed in OFF.

NOTE: If a high alarm has actuated, the automatic functions associated with that monitor shall be verified or performed.

STANDARD: Acknowledges caution and note.

EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 WGDT Release Isolation Page 5 of 9

STEP 5: Step 3 - CONSULT SHIFT SUPERVISION TO DETERMINE IF GW SHOULD BE ISOLATED STANDARD: Asks SM if GW should be isolated.

EVALUATOR'S NOTE: If asked, respond by saying "I need you to perform the actions for a high radiation alarm

". COMMENTS:

_______ SAT

_______ UNSAT

STEP 6:

Step 4 - VERIFY OR PERFORM AUTO ACTIONS Decay Tank Bleed Isolation valve 1

-GW-FCV-101 - CLOSED CTMT Vacuum Pump Discharge Isolation valve 1

-G W-FCV-160 - CLOSED CTMT Vacuum Pump Discharge Isolation valve 2

-GW-FCV-260 - CLOSED STANDARD: Closes 1-GW-FCV-101 by taking control switch to close and observing green light on and red light off OR by pressing the auto/manual station close arrow to close the valve.

This is a Critical Task.

Closes 1-GW-FCV-160 by taking control switch to close and observing green light on and red light off.

This is a Critical Task.

Closes 2-GW-FCV-260 by taking control switch to close and observing green light on and red light off.

This is a Critical Task.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 WGDT Release Isolation Page 6 of 9 STEP 7: Step 5 - PLACE CTMT VACUUM PUMPS IN OFF

1-CV-P-1A

1-CV-P-1B

2-CV-P-1A

2-CV-P-1B STANDARD: Places control switches to the "off" position for 1

-CV-P-1A and 1-CV-P-1B. Requests Unit 2 to place control switches for 2

-CV-P-1A and 2-CV-P-1B to the "off" position. EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STEP 8:

Step 6 - NOTIFY HP TO DO THE FOLLOWING:

a) Verify area evacuated as necessary a) b) Control access as necessary b) c) Sample c) d) Contact HP to verify activity within limits e) Investigate cause STANDARD: NONE EVALUATOR'S NOTE: When candidate picks up phone or gaitronics to make notifications, inform the candidate that another RO will perform that action and complete the ARP.

This JPM is complete.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 WGDT Release Isolation Page 7 of 9 STOP TIME:

____________________________________________________

________________________________

____________________________________________________________________________________

__________________________________________________

__________________________________

____________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Isolate release by performing Steps 1-5 of RMA-C6 and/or RMA

-C7 (1-GW-FCV-101 closed, 1

-GW-FCV-160 closed, 2-GW-FCV-260 closed).

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions Release of 'B' Waste Gas Decay Tank is in progress. The team is making preparations to run #1 EDG for its monthly performance test.

Initiating Cues I am the Shift Manager. You are the 3 rd RO. The unit is at 100% power and stable. 'B" Waste Gas Decay Tank release is in progress and we are currently making preparations to run #1 EDG for its monthly surveillance test.

An event is about to occur and I need you to respond IAW applicable procedures.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions Release of 'B' Waste Gas Decay Tank is in progress. The team is making preparations to run #1 EDG for its monthly performance test.

Initiating Cues I am the Shift Manager. You are the 3 rd RO. The unit is at 100% power and stable. 'B" Waste Gas Decay Tank release is in progress and we are currently making preparations to run #1 EDG for its monthly surveillance test.

An event is about to occur and I need you to respond IAW applicable procedures.

Surry 201 0-301 AP-24.01, Depress Aux Spray Page 1 of 8 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Simulator Job Performance Measure 010.A4.01 (3.7/3.5)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date _________

__________________________

Stop Time___________________

Title DEPRESSURIZE THE RCS WITH AUX SPRAY DUE TO LOSS OF RCPS IN AP

-24.01. K/A: 010.A4.01 Ability to manually operate and/or monitor in the control room: PZR Spray Valve Applicability Estimated Time Actual Time RO 15 minutes

Conditions Task is to be PERFORMED in the simulator.

A steam generator tube leak of approximately 65 gpm has developed on "C" SG . Reactor has been tripped and 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress. The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

Standards RCS depressurized using Aux Spray until termination criteria satisfied (Step 29 complete).

Initiating Cues 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, step 29.

Shift Manager direction.

Terminating Cues RCS depressurized using Aux Spray until termination criteria satisfied (Step 29 complete).

Procedures 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK

Surry 201 0-301 AP-24.01, Depress Aux Spray Page 2 of 8 Tools and Equipment None None Safety Considerations Recall IC-324 Simulator Setup Call up 100% power IC and initialize

. OR Enter malfunctions for SG tube leakage (RC2403) at 7% deg.

Enter malfunctions to have RCPs trip spuriously trip on swapover (RC5601, RC5602, RC5603).

Defeat SG level alarms to avoid nuisance alarms (HG5, HG6, HG7).

Implement all malfunctions and perform AP

-16.00, E-0, and AP-24.01 through step 28 to cooldown the RCS to target temperature and stabilize.

Place the simulator until ready for JPM performance.

Place orange magnets on 1

-RC-P-1A/1B/1C control switches.

Initiating Cues 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, step 29.

Shift Manager direction.

Directions to the Applicant I am the Shift Manager. A steam generator tube leak of approximately 65 gpm has developed on "C" SG .

1-AP-16.00, RCS LEAKAGE, has been performed. The Reactor has been tripped IAW 1

-E-0, REACTOR TRIP OR SAFETY INJECTION, and 1

-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress.

All 3 RCPs tripped on swapover.

The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

I need you to perform step 29 of 1

-AP-24.01 in its entirety to depressurize the RCS to stop breakflow.

When you finish the actions necessary to accomplish this, please inform me.

Notes Surry 201 0-301 AP-24.01, Depress Aux Spray Page 3 of 8 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITI CAL STEP.

An additional instructor may be needed to silence and acknowledge alarms for the examinee.

START TIME:

STEP 1: STEP 29a - DEPRESSURIZE RCS TO STOP BREAKFLOW:

a) Normal PRZR spray

- AVAILABLE STANDARD: Notes that no RCPs are running and normal spray is not available.

Goes to the RNO.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 2:

STEP 29 a RNO - DEPRESSURIZE RCS TO STOP BREAKFLOW:

a) Do the following:

1) Verify or place normal letdown in service. 2) Close normal PRZR spray valves.

3) Open 1-CH-HCV-1311, CHG AUX spray valve.

4) Close 1-CH-HCV-1310A, CHG Line ISOL Valve.

5) Monitor PRZR level

_______ SAT

_______ UNSAT

Surry 201 0-301 AP-24.01, Depress Aux Spray Page 4 of 8 STANDARD: Verifies letdown in service by observing normal letdown flow and pressure.

Places 1-RC-PCV-1455A and 1

-RC-PCV-1455B in manual and closes valves

. This is a Critical Task.

Opens 1-CH-HCV-1311, CHG AUX spray valve by observing red light on and green light off.

This is a Critical Task.

Closes 1-CH-HCV-1310A, CHG Line ISOL Valve by observing green light on and red light off.

This is a Critical Task.

Monitors pressurizer level by observing level trend.

EVALUATOR'S NOTE: N/A COMMENTS: STEP 3: Step 29b - DEPRESSURIZE RCS TO STOP BREAKFLOW:

b) Spray PRZR with maximum available spray until ANY of the following satisfied:

PRZR level

- GREATER THAN 69%

OR

RCS subcooling based on CETCs

- LESS THAN 30°F OR

RCS Pressure

- LESS THAN AFFECTED SG PRESSURE STANDARD: Sprays with Aux Spray using 1-CH-HCV 1311 until pressurizer level reaches 69%, OR RCS subcooling is less the 30°F, OR RCS pressure is less than "C" SG pressure.

This is a Critical Task.

EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT

STEP 4:

Step 29c - DEPRESSURIZE RCS TO STOP BREAKFLOW:

c) Close spray valves

Normal spray valves OR

Auxiliary spray valve, 1

-CH-HCV-1311

_______ SAT

_______ UNSAT

Surry 201 0-301 AP-24.01, Depress Aux Spray Page 5 of 8 STANDARD: Closes 1-CH-HCV-1311 when termination criteria satisfied by observing green light on and red light off. EVALUATOR'S NOTE:

N/A COMMENTS: STEP 5: Step 29d - DEPRESSURIZE RCS TO STOP BREAKFLOW:

d) Verify open or open 1

-CH-HCV-1310A, CHG Line ISOL Valve.

STANDARD: Opens 1-CH-HCV-1310A by observing red light on and green light off

. EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 6: Step 29e - DEPRESSURIZE RCS TO STOP BREAKFLOW:

e) Check CHG pumps

- ONLY ONE RUNNING

STANDARD: Checks 1-CH-P-1C in service by observing red light indication and amps and the 1-CH-P-1A & 1B secure in AUTO.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 201 0-301 AP-24.01, Depress Aux Spray Page 6 of 8 STEP 7: REPORT TO SHIFT SUPERVISOR (EVALUATOR).

STANDARD: Verbal status report that the RCS is depressurized IAW step 29 of 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAKAGE.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME:

____________________________________________________________________________________

__________________________________

__________________________________________________

____________________________________________________________________________________

________________________________

____________________________________________________

____________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator

. Perform Step 29 of 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAKAGE.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions A steam generator tube leak of approximately 65 gpm has developed on "C" SG . Reactor has been tripped and 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress. The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

Initiating Cues I am the Shift Manager. A steam generator tube leak of approximately 65 gpm has developed on "C" SG .

1-AP-16.00, RCS LEAKAGE, has been performed. The Reactor has been tripped IAW 1

-E-0, REACTOR TRIP OR SAFETY INJECTION, and 1

-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress.

All 3 RCPs tripped on swapover.

The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

I need you to perform step 29 of 1

-AP-24.01 in its entirety to depressurize the RCS to stop breakflow.

When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions A steam generator tube leak of approximately 65 gpm has developed on "C" SG . Reactor has been tripped and 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress. The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

Initiating Cues I am the Shift Manager. A steam generator tube leak of approximately 65 gpm has developed on "C" SG .

1-AP-16.00, RCS LEAKAGE, has been performed. The Reactor has been tripped IAW 1

-E-0, REACTOR TRIP OR SAFETY INJECTION, and 1

-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, is in progress.

All 3 RCPs tripped on swapover.

The team has cooled down the RCS to target temperature and is currently at step 29 "Depressurize RCS to stop breakflow".

I need you to perform step 29 of 1

-AP-24.01 in its entirety to depressurize the RCS to stop breakflow.

When you finish the actions necessary to accomplish this, please inform me.

Person / Time
ML102780346
Site:	Surry (DPR-032, DPR-037)
Issue date:	09/14/2010
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-280/10-301, 50-281/10-301
Download: ML102780346 (232)
v • d • e

ML102780346

Text

4.0 Precautions

4.2 Because

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