ML081260335

Feb-March Exam 05000280/2008301 Final JPMs

ML081260335
Person / Time
Site:	Surry
Issue date:	03/31/2008
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-280/08-301, 50-281/08-301
Download: ML081260335 (207)

See also: IR 05000280/2008301

Text

Final Submittal

(Blue Paper)

FINAL JPMS

1. ADMINISTRATIVE JPMs

2. IN-PLANT JPMs

3. SIMULATOR JPMs (CONTROL ROOM)

Surry 2008-301 Quadrant Power Tilt Calculation

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.1.7

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

Perform a Quadrant Power Tilt Calculation.

KIA: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating

characteristics, reactor behavior, and instrument interpretation.

Applicability Estimated Time Actual Time

RO/SRO(D)/SRO(U) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Correctly calculates Quadrant Power Tilt for given core conditions.

Initiating Cues

• A dropped rod has occurred on Unit 1.

• A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System

Malfunction.

• When you have determined the Quadrant Power Tilt, inform the examiner.

Terminating Cues

• Applicant has completed the QPTR Calculation.

Tools and Equipment

• Calculator

• NIS Setpoints and Power Range Currents Data Sheet

Safety Considerations

• None

Page 1 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

Initial Conditions:

• Unit 1 was at 100% power when a dropped rod occurred.

Initiating Cues

• A dropped rod has occurred on Unit 1.

• A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System

Malfunction.

• When you have determined the Quadrant Power Tilt, inform the examiner.

Here are the actual detector currents taken from the Power Range Nls:

N-41 Upper Detector Current 109.8

N-41 Lower Detector Current 122.4

N-42 Upper Detector Current 123.4

N-42 Lower Detector Current 119.4

N-43 Upper Detector Current 100.2

N-43 Lower Detector Current 118.3

N-44 Upper Detector Current 117.8

N-44 Lower Detector Current 122.0

Page 2 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEP 1: Transcribes information from data sheets onto Quadrant Power Tilt Calculation _ _ _ SAT

Worksheet.

_ _ _ UNSAT

STANDARD:

Places PR NI currents and Normalized Currents in appropriate location on Quadrant Power Tilt

Calculation Worksheet.

COMMENTS:

STEP 2: Performs calculations to obtain normalized values for Upper Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

Divides Upper Detector current by Normalized currents for each detector. (See attached

Quadrant Power Tilt Calculation Worksheet for calculations.)

COMMENTS:

STEP 3: Performs calculations to obtain average normalized value for Upper Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

Adds Upper Detector Normalized currents for all detectors and divides by 4. (See attached

Quadrant Power Tilt Calculation Worksheet for calculations.)

COMMENTS:

Page 3 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

STEP 4: Calculates Radial Tilt for Upper Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

Divides highest PR NI normalized current (N-42) for upper detectors by average NI normalized

current for upper detectors. (See attached Quadrant Power Tilt Calculation Worksheet for

calculations.)

COMMENTS:

STEP 5: Performs calculations to obtain normalized values for Lower Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

• Divides Lower Detector current by Normalized currents for each detector. (See

attached Quadrant Power Tilt Calculation Worksheet for calculations.)

COMMENTS:

STEP 6: Performs calculations to obtain average normalized value for Lower Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

• Adds Lower Detector Normalized currents for all detectors and divides by 4. (See

attached Quadrant Power Tilt Calculation Worksheet for calculations.)

COMMENTS:

STEP 7: Calculates Radial Tilt for Lower Detectors. _ _ _ SAT

STANDARD: _ _ _ UNSAT

• Divides highest PR NI normalized current (N-42) for lower detectors by average NI

normalized current for lower detectors. (See attached Quadrant Power Tilt Calculation

Worksheet for calculations.)

COMMENTS:

Page 4 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

STEP 8: Determines final Quadrant Power Tilt Value. _ _ _ SAT

STANDARD: _ _ _ UNSAT

• Determines final Quadrant Power Tilt Value from above calculations to be 1.022 or 2.2%

Tilt.

EVALUATOR NOTES:

COMMENTS:

STOP TIME:

Page 5 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Perform a Quadrant Power Tilt calculation.

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 1 was at 100% power when a dropped rod occurred.

Initiating Cues

• A dropped rod has occurred on Unit 1.

• A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System

Malfunction.

• Here is a copy of the Power Range Currents from the NIS Data Book providing the 100% Normalized Values and

the Radial Tilt Calculation Worksheet.

• I need you to perform a Quadrant Power Tilt Calculation.

• When you have determined the Quadrant Power Tilt, inform the examiner.

Here are the actual detector currents taken from the Power Range Nls:

N-41 Upper Detector Current 109.8

N-41 Lower Detector Current 122.4

N-42 Upper Detector Current 123.4

N-42 Lower Detector Current 119.4

N-43 Upper Detector Current 100.2

N-43 Lower Detector Current 118.3

N-44 Upper Detector Current 117.8

N-44 Lower Detector Current 122.0

G2.1.7 SR08301 6 of 7

Surry 2008-301 Quadrant Power Tilt Calculation

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Perform a Quadrant Power Tilt calculation.

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 1 was at 100% power when a dropped rod occurred.

Initiating Cues

• A dropped rod has occurred on Unit 1.

• A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System

Malfunction.

• Here is a copy of the Power Range Currents from the NIS Data Book providing the 1000/0 Normalized Values and

the Radial Tilt Calculation Worksheet.

• I need you to perform a Quadrant Power Tilt Calculation.

• When you have determined the Quadrant Power Tilt, inform the examiner.

Here are the actual detector currents taken from the Power Range Nls:

N-41 Upper Detector Current 109.8

N-41 Lower Detector Current 122.4

N-42 Upper Detector Current 123.4

N-42 Lower Detector Current 119.4

N-43 Upper Detector Current 100.2

N-43 Lower Detector Current 118.3

N-44 Upper Detector Current 117.8

N-44 Lower Detector Current 122.0

G2.1.7 SR08301 7 of 7

Surry 2008-301 Evaluate Overtime Eligibility

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.1 .5

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

Evaluate Overtime Eligibility

KIA: G.2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities.

Applicability Estimated Time Actual Time

SRO(D)/SRO(U) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Correctly determines which operator(s) is/are able to stay over for two hours without prior overtime approval.

Initiating Cues

• Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for two

hours without prior overtime approval, and determine which operators CANNOT be held over for two hours

without prior overtime approval.

• When you are finished responding to the questions, inform an examiner.

Terminating Cues

• Applicant has evaluated all operators and determined their overtime eligibility.

Tools and Equipment

• Calculator

• Overtime History

Safety Considerations

• None

Page 1 of 9

Surry 2008-301 Evaluate Overtime Eligibility

Initial Conditions:

• A start-up is planned for the following shift. One Reactor Operator must be held over two hours for the start-up.

• The following is the work history (excluding shift turnover time) of the available Reactor Operators on shift. A

break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all work periods. All operators began their shift at the same time each

day.

• The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

1) Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for an

additional two hours without prior overtime approval and determine which operator(s), if any, CANNOT be held

over for two hours without prior overtime approval. State the reason the operators can or cannot be held over

for the additional two hours. All six operators have tomorrow (Day 9) off.

The applicable procedure will not be provided to the applicant initially. Once the candidate identifies the correct

procedure and where to get it, hand them a copy of VPAP-0103, Working Hours and Limitations.

At the evaluator's discretion the applicant may use a computer to locate VPAP-0103.

Work History

8

Day 1 2 3 4 5 6 7

(Today)

Operator

12 0 12 12 12 12 8 14

1. 1

Operator

0 12 12 12 12 12 0 12

1. 2

Operator

0 12 12 12 0 0 12 12

1. 3

Operator

12 0 12 12 12 12 0 13

1. 4

Operator

12 12 12 12 0 0 0 15

1. 5

Operator

0 12 12 12 12 8 8 8

1. 6

Page 2 of 9

Surry 2008-301 Evaluate Overtime Eligibility

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are balded and denoted by an asterisk (*).

• START TIME:

STEP 1: OBTAINS A CURRENT COpy OF VPAP-0103, WORKING HOURS AND _ _ _ SAT

LIMITATIONS.

_ _ _ UNSAT

STANDARD:

a) Obtains a copy ofVPAP-0103.

This can be accomplished by either requesting a copy of the procedure from the evaluator or by

logging on to a network computer and obtaining an electronic version of the procedure.

EVALUATOR NOTES:

Operator mayor may not request a copy ofVPAP-0103. Use ofthis procedure is not critical.

If asked, state that the Operations' Program to calculate Overtime Eligibility is not available.

If the computer is used, the applicant will log on to the network, sign on to 'Webtop' and locate the

procedure via a keyword or procedure number search.

COMMENTS:

STEPS CAN BE PERFORl\1ED IN ANY ORDER

_ _ _ SAT

STEP 2: DETERMINES THE ELIGIBILITY OF OPERATOR #1.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #1 would not exceed any overtime limits.

EVALUATOR NOTES:

Days 2-8 will reach 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, but not exceed it. Day 7 and 8 will reach 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, but not exceed it. Day

8 will reach 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, but not exceed it.

COMMENTS:

Page 3 of 9

Surry 2008-301 Evaluate Overtime Eligibility

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 3: DETERMINES THE ELIGIBILITY OF OPERATOR #2.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #2 would exceed hours limitations.

EVALUATOR NOTES:

Days 2 - 8 already have 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7-day period. The additional two hours would yield 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> in a

7-day period, which would require management approval.

COMMENTS:

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 4: DETERMINES THE ELIGIBILITY OF OPERATOR #3.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #3 would exceed hours limitations,

EVALUATOR NOTES:

Day 7 and 8 already have 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period. The additional two hours would yield 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />

in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, which would require management approval.

COMMENTS:

Page 4 of 9

Surry 2008-301 Evaluate Overtime Eligibility

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 5: DETERMINES THE ELIGIBILITY OF OPERATOR #4.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #4 would not exceed any overtime limits.

EVALUATOR NOTES:

No limits are exceeded.

COMMENTS:

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 6: DETERMINES THE ELIGIBILITY OF OPERATOR #5.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #5 would exceed hours limitations.

EVALUATOR NOTES:

Day 8 already has 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The additional two hours would yield 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> in a 24

hour period, which would require management approval.

COMMENTS:

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 7: DETERMINES THE ELIGIBILITY OF OPERATOR #6.

_ _ _ UNSAT

STANDARD:

• a) Identifies that Operator #6 would exceed hours limitations.

EVALUATOR NOTES:

Days 2 - 8 already have 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7-day period. The additional two hours would yield 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> in a

7-day period, which would require management approval.

COMMENTS:

Page 5 of 9

Surry 2008-301 Evaluate Overtime Eligibility

STEP 4: REPORTS ELIGffiILITY OF ALL OPERATORS. _ _ _ SAT

STANDARD: _ _ _ UNSAT

Applicant reports that Operator 1 and 4 are eligible to receive the overtime without prior management

approval and the others are not.

Table correctly filled out.

COMMENTS:

STOP TIME:

Page 6 of 9

Surry 2008-301 Evaluate Overtime Eligibility

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for an

additional two hours without prior overtime approval and determine which operator(s), if any, CANNOT be held

over for two hours without prior overtime approval. State the reason the operators can or cannot be held over for

the additional two hours. All six operators have tomorrow (Day 9) off.

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 start-up is planned for the following shift. One Reactor Operator must be held over two hours for the start-up.

• The following is the work history (excluding shift turnover time) of the available Reactor Operators on shift. A

break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all work periods. All operators began their shift at the same time each

day.

• The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

1) Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for an

additional two hours without prior overtime approval and determine which operator(s), if any, CANNOT be held

over for two hours without prior overtime approval. State the reason the operators can or cannot be held over

for the additional two hours. All six operators have tomorrow (Day 9) off.

G2.1.5 SR08301 7 of 9

Surry 2008-301 Evaluate Overtime Eligibility

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for an

additional two hours without prior overtime approval and determine which operator(s), if any, CANNOT be held

over for two hours without prior overtime approval. State the reason the operators can or cannot be held over for

the additional two hours. All six operators have tomorrow (Day 9) off.

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 start-up is planned for the following shift. One Reactor Operator must be held over two hours for the start-up.

• The following is the work history (excluding shift turnover time) of the available Reactor Operators on shift. A

break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all work periods. All operators began their shift at the same time each

day.

• The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

1) Evaluate the work history for all six (6) operators. Determine which operator(s), if any, can be held over for an

additional two hours without prior overtime approval and determine which operator(s), if any, CANNOT be held

over for two hours without prior overtime approval. State the reason the operators can or cannot be held over

for the additional two hours. All six operators have tomorrow (Day 9) off.

G2.1.5 SR08301 8 of 9

Surry 2008-301 Evaluate Overtime Eligibility

Work History

8

Day 1 2 3 4 5 6 7

(Today)

Operator

12 0 12 12 12 12 8 14

1. 1

Operator

0 12 12 12 12 12 0 12

1. 2

Operator

0 12 12 12 0 0 12 12

1. 3

Operator

12 0 12 12 12 12 0 13

1. 4

Operator

12 12 12 12 0 0 0 15

1. 5

Operator

0 12 12 12 12 8 8 8

1. 6

Eligible for overtime Reason, if any, for NOT being eligible for overtime without prior

without management management approval.

approval?

Operator #1

Operator #2

Operator #3

Operator #4

Operator #5

Operator #6

G2.1.5 SR08301 9 of 9

Surry 2008-301 PT Review (1-0SP-SW-002)

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.2.12

Applicant. _ Start Time _

Examiner _

Date _ Stop Time _

Periodic Test Review (1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger 1-CC-E-1A)

KIA: G.2.2.12 Knowledge of surveillance procedures. (3.0/3.4)

Applicability Estimated Time Actual Time

RO 20 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Completes 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger, 1-

CC-E-1A, and determines if the test was completed satisfactorily or not.

Initiating Cues

• Here is a copy of 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger (1-CC-E-1A), I need you to complete the procedure and turn it into me for review.

• The necessary data has been collected, but not analyzed or plotted.

• When you are finished, inform your examiner of the results of the surveillance procedure.

Terminating Cues

• Applicant has completed the procedure and informed the examiner of the results of the surveillance procedure.

Page 1 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

Tools and Equipment

• Calculator

• Straight Edge (ruler)

• Partially completed copy of 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger (1-CC-E-1A)

Safety Considerations

• None

Page 2 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

Initial Conditions:

• All data for 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger (1-

CC-E-1A), has been collected and the procedure requires analysis and completion.

Initiating Cues

• Here is a copy of 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger (1-CC-E-1A), I need you to complete the procedure and turn it into me for review.

• The necessary data has been collected, but not analyzed or plotted.

• When you are finished, inform your examiner of the results of the surveillance procedure.

Page 3 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are balded and denoted by an asterisk (*).

• START TIME:

STEP 1: Review the purpose of the procedure (Section 1.0) SAT

UNSAT

STANDARD:

• Reviews the following:

To provide instructions to monitor flow through the Service Water side of the Component

Cooling Heat Exchanger l-CC-E-1A, and to use the flow readings obtained to determine

operability of the heat exchanger with respect to the amount of tubesheet macrofouling.

Determining the extent of tubesheet macrofouling provides an aging management basis for

License Renewal.

EVALUATOR NOTES:

• If asked: No maintenance has been performed on the Component Cooling Heat Exchangers.

• Review of this section is not required, but may be performed.

COMMENTS:

STEP 2: Review the References section (Section 2.0) SAT

UNSAT

STANDARD:

• Reviews section 2.1, Source Documents, 2.2 Technical Specifications,

2.3 Technical References, and 2.4 Commitment Documents.

EVALUATOR NOTES:

• Review of this section is not required, but may be performed.

COMMENTS:

Page 4 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

STEP 3: Verifies the Initial Conditions are met (Section 3.0) SAT

UNSAT

STANDARD:

• Reviews the following:

Shift Supervision has granted permission to perform this test.

EVALUATOR NOTES:

• If asked: The procedure was performed on its scheduled day and permission to perform the test

was granted.

• Review of this section is not required, but may be performed.

COMMENTS:

STEP 4: Reviews the Precautions and Limitations (Section 4.0) SAT

UNSAT

STANDARD:

-- (Step 4.1) Notify Health Physics prior to opening any SW instrument drain valves.

-- (Step 4.2) In order to limit undesired increases in CC temperature, isolation of SW flow

through a CC Heat Exchanger shall be minimized.

-- (Step 4.3) To prevent excessive cooling of the CC System during seasons when SW

temperature is low, the CC outlet valve, on the heat exchanger being tested, may be closed as

allowed by this procedure.

-- (Step 4.4) Technical Specification 3.13 requires two operable Component Cooling Heat

Exchangers during one unit operation and three operable CC HXs for two unit operation.

-- (Step 4.5) The amount of SW that is drained to the trough surrounding the CC HXs shall be

minimized.

EV ALUATOR NOTES:

• If asked: HP was notified about SW valve manipulations .

• Review of this section is not required, but may be performed .

COMMENTS:

Page 5 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

STEP 5: Reviews Section 6.1, Work Preparation, and verifies all initials are signed, as required. SAT

UNSAT

STANDARD:

• This section is reviewed and applicant notes that Step 6.1.1 and 6.1.3 were initialed as

completed while step 6.1.2 is marked N/A.

EVALUATOR NOTES:

• If asked: No maintenance has been performed on the Component Cooling Heat Exchangers.

• A detailed review of this section is not required, but may be performed.

COMMENTS:

STEP 6: Reviews Section 6.2, Measuring CC HX Flow, and verifies all initials are signed, as SAT

required, up to and including step 6.2.18.

UNSAT

STANDARD:

• This section is reviewed and the applicant notes that Step 6.2.1 and Step 6.2.17 were marked

N/A, while all other steps (up to and including step 6.2.18) were initialed as completed.

EVALUATOR NOTES:

• If asked: No maintenance has been performed on the Component Cooling Heat Exchangers.

• If asked: An extended duration full flow flush was not required.

• A detailed review of this section is not required, but may be performed.

COMMENTS:

Page 6 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

• STEP 7: The applicant performs Step 6.2.19. _ _ _ SAT

_ _ _ UNSAT

STANDARD:

_ _ _ 6.2.19 Select an Attachment 2 graph illustrating the closest temperature that is equal to or

higher than the current Circulating Water Inlet Temperature recorded on Attachment

1.

• * Applicant selects the graph from Attachment 2 associated with 75°F (page 2 of 6

from Attachment 2 or Page 17 of 21 in the procedure).

• Applicant initials next to Step 6.2.19 upon completion of graph selection.

EVALUATOR NOTES:

• If asked: Circulating Water Temperature is listed on Attachment 1 (73 "F),

COMMENTS:

• STEP 8: The applicant performs Step 6.2.20. _ _ _ SAT

_ _ _ UNSAT

STANDARD:

_ _ _ 6.2.20 Using a straightedge, mark on the appropriate Attachment 2 graph the intersection of

the highest flow point Barton and Annubar M> readings from Attachment 1. IF the

highest flow point Barton and Annubar M> readings are offscale to the right of the

graph, THEN the point is in the operable range.

• * Applicant plots the highest flow point Barton and Annubar LW readings from

Attachment and identifies that the CC HX is inoperable.

• Applicant initials next to Step 6.2.20 upon completion of marking graph.

EVALUATOR NOTES:

• The applicant may plot all data, only the highest flow point Barton and Annubar M>

readings are required to be plotted.

COMMENTS:

Page 7 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

STEP 9: Reviews Section 7.1, Acceptance Criteria. _ _ _ SAT

STANDARD: _ _ _ UNSAT

• Reviews the following:

IF the stated Acceptance Criteria are met, THEN the test shall be considered satisfactory.

• The recorded parameters fall within the Operable or Alert band on Attachment 2.

COMMENTS:

• STEP 10: Performs Section 7.2, Follow-on Task _ _ _ SAT

STANDARD: _ _ _ UNSAT

• * Records the Test Result as UNSATISFACTORY by marking the test as unsatisfactory.

• Notes that Step 7.2.1 and 7.2.2 are not applicable, since the test was not satisfactory nor was the

Heat Exchanger in Alert.

EVALUATOR NOTES:

• If told, acknowledge that the test was unsatisfactory.

COMMENTS:

Page 8 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

STEP 11: Performs Follow-on Actions associated with Unsatisfactory Results _ _ _ SAT

STANDARD: UNSAT

_ _ _ 7.2.3 IF results fall in the Inoperable Range, THEN mark UNSATISFACTORY AND

perform the following:

a. Notify Shift Supervision

b. Notify System Engineering of the Inoperable condition and record the name of

the person notified.

c. For unacceptable testing results that are due to macrofouling, the System Engineer

will consider the potential material degradation effects (loss of material and

cracking) of macrofouling that affect the aging management basis of license

renewal.

d. Submit a Condition Report and record the number.

e. Verify the requirements of Technical Specifications 3.13A and 3.14A are met.

f. Submit a Work Request (or not if one is outstanding) to clean the heat exchanger

and record the number.

_ _ _ 7.2.4 Personnel participating in performance of this procedure shall complete the table

below.

• Applicant signs his name, prints his name and fills in the date in the table of step

7.2.4.

EVALUATOR NOTES:

• When informed of the Unsatisfactory test results, the examiner will state that he will

complete Steps 7.2.3 b through f.

COMMENTS:

STEP 12: Completes the Table in Step 7.2.4 _ _ _ SAT

STANDARD: UNSAT

_ _ _ 7.2.4 Personnel participating in performance of this procedure shall complete the table

below.

• Applicant signs and prints his name and fills in the date in the table of step 7.2.4.

COMMENTS:

Page 9 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

STEP 13: Completes Step 7.2.5, documenting procedure completion SAT

STANDARD: UNSAT

• Applicant signs his name and may state in the comment section the reason for the

procedure being unsatisfactory.

COMMENTS:

STEP 14: Submits paperwork to examiner/supervisor for review SAT

STANDARD: UNSAT

• Applicant submits the completed paperwork to the evaluator for review.

COMMENTS:

STOP TIME:

Page 10 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

Page 11 of 12

Surry 2008-301 PT Review (1-0SP-SW-002)

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Completes 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger, 1-

CC-E-1A, and determines if the test was completed satisfactorily or not.

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 1 is at 100% power.

• 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger, 1-CC-E-1A, is

partially completed and needs to be finalized.

Initiating Cues

• Here is a copy of 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger (1-CC-E-1A), I need you to complete the procedure and turn it into me for review.

• The necessary data has been collected, but not analyzed or plotted.

• When you are finished, inform your examiner of the results of the surveillance procedure.

G2.2.12 SR08301 12 of 13

Surry 2008-301 PT Review (1-0SP-SW-002)

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Completes 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger, 1-

CC-E-1A, and determines if the test was completed satisfactorily or not.

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 1 is at 100% power.

• 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat Exchanger, 1-CC-E-1A, is

partially completed and needs to be finalized.

Initiating Cues

• Here is a copy of 1-0SP-SW-002, Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger (1-CC-E-1A), I need you to complete the procedure and turn it into me for review.

• The necessary data has been collected, but not analyzed or plotted.

• When you are finished, inform your examiner of the results of the surveillance procedure.

G2.2.12 SR08301 13 of 13

Surry 2008-301 PT Review (1-0PT-CS-006)

U.S. Nuclear Regulatory Commission

Surry Power Station '

SR08301

Administrative Job Performance Measure G2.2.12

Applicant. _ Start Time _

Examiner _

Date _ Stop Time _

Periodic Test Review .(1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV

Stroke Test)

KIA: G2.2.12 Knowledge of surveillance procedures. (3.0/3.4)

Applicability Estimated Time Actual Time

SRO(I)/SRO(U) 30 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Correctly identifies errors in 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System

MOV Stroke Test.

Initiating Cues

• I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-0PT-CS-006, RWST Chemical

Addition Tank and Containment Spray System MOV Stroke Test, that has just been completed.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

• When you are finished, inform your examiner of ALL problems noted in the procedure.

Terminating Cues

• Applicant has completed the procedure review and discussed problems with examiner.

Page 1 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

Tools and Equipment

• Calculator

• Copy of completed 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke

Test.

Safety Considerations

• None

Page 2 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

Initial Conditions:

• 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test has just been

completed.

Initiating Cues

• I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-0PT-CS-006, RWST Chemical

Addition Tank and Containment Spray System MOV Stroke Test, that has just been completed.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

• When you are finished, inform your examiner of ALL problems noted in the procedure.

Page 3 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are balded and denoted by an asterisk (*).

• START TIME:

STEP 1: Review the purpose of the procedure (Section 1.0) SAT

UNSAT

STANDARD:

-- Reviews NOTE concerning procedure performance when the Unit is shutdown.

-- Reviews Step 1.1 to identify the procedure provides for verifying proper operation of

Containment Spray MOVs on a quarterly basis and to obtain chemistry samples to ensure

chemical contamination has not occurred due to valve leakage.

-- Reviews Step 1.2 to determine the OPT also provides instructions to return Containment

Spray valves to service following maintenance.

EV ALUATOR NOTES:

• If asked: No maintenance has been performed on the Containment Spray System.

• A detailed review of this section is not required (no sign-offs).

COMMENTS:

STEP 2: Review the References section (Section 2.0) SAT

UNSAT

STANDARD:

-- Reviews section 2.1, Source Documents, 2.2 Technical Specifications,

2.3 Technical References, and 2.4 Commitment Documents.

EVALUATOR NOTES:

• A detailed review of this section is not required (no sign-offs).

COMMENTS:

Page 4 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 3: Verifies the Initial Conditions are met (Section 3.0) SAT

UNSAT

STANDARD:

-- Reviews Step 3.1. This procedure has PSA significance. IF this procedure is being

performed on a day other than its POD scheduled date, THEN notify Shift

Supervision that a PSA evaluation is required for the performance of this procedure.

(Reference 2.4.3)

EVALUATOR NOTES:

• If asked: The procedure was performed on its scheduled day.

• A detailed review of this section is not required (no sign-offs).

COMMENTS:

STEP 4: Reviews the Precautions and Limitations (Section 4.0) SAT

UNSAT

STANDARD:

-- (Step 4.1) Notes that testing more than one MOV at a time is not permitted.

-- (Step 4.2) The initials identification block in Subsection 7.3 must be completed before the

procedure is closed out.

-- (Step 4.3) When stroking MOVs, timing should be performed from the time of the initiation

of the manual control panel switch to the time that the final control panel light is

extinguished.

-- (Step 4.4) MOVs l-CS-MOV-lOlA, 101C, and 100A cannot be closed unless the breaker

for l-CS-P-IA is in TEST or CONNECT. MOVs l-CS-MOV-lOlB, 101D, and 100B

cannot be closed unless the breaker for l-CS-P-lA is in TEST or CONNECT.

EVALUATOR NOTES:

• A detailed review of this section is not required (no sign-offs).

COMMENTS:

Page 5 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 5: 5.0 SPECIAL TOOLs AND EQUIPMENT (Section 5.0) _ _ _ SAT

_ _ _ UNSAT

STANDARD:

(Step 5.1) Needs hoses and sample containers.

(Step 5.2) Needs a stopwatch.

COMMENTS:

STEP 6: 6.0 INSTRUCTIONS (Section 6.0) _ _ _ SAT

_ _ _ UNSAT

STANDARD:

6.1 Work Preparation

NOTE: Subsections and steps may be performed out of sequence with Shift

Supervion permission.

6.1.1 IF this procedure is used to prove operability of equipment after maintenance,

THEN record the Work Order Number and Mark Number below or attach a copy of

the Work Order Tracking sheet to the completed procedure. Otherwise, enter N/A.

EVALUATOR NOTES: Maintenance has not been performed, therefore step will be marked N/A

and initialed.

COMMENTS:

Page 6 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 7: 6.2 Cycle of 1-CS-MOV-102A. _ _ _ SAT

_ _ _ UNSAT

STANDARD:

Reads NOTE: Isolating a Containment Spray Subsystem when the RCS is equal to or greater

than 350 degrees and 450 psig will start a Technical Specification LCO.

Reads NOTE: A proper hose with a quick disconnect fitting should be located on a rack in the

safeguards basement near the Auxiliary Feed Booster Pumps. This will be used to

back flush the caustic soda between the MOVs and manual isolation valve.

_ _ _ 6.2.1 Connect the quick disconnect fitting of the hose to 1-CS-120, Refueling Wtr Chern

Add Tk Otlt Hdr Drain, for 1-CS-MOV-102A.

_ _ _ 6.2.2 Run hose from 1-CS-120 to a floor drain.

_ _ _ 6.2.3 Declare a Containment Spray Subsystem inoperable and start the appropriate Tech

Spec Clock. IF Tech Spec Clock does NOT apply, THEN enter N/A.

_ _ _ _ _ _ 6.2.4 Verify closed or close 1-CS-38, Refueling Water Chern Add Tk Outlet SV

MOV-102A Isol.

Reads NOTE: Refer to Precaution and Limitation 4.3 prior to stroking MOV.

_ _ _ 6.2.5 From the Control Room, open 1-CS-MOV-102A from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data.

Time to open in seconds: ---:1:;;..;;:8:.;.::;.9 _

Reference Time: 19.6 seconds

Acceptable Range: 16.7 to 22.5 seconds

Stopwatch SQC Number: --.;;;3;...;;;.6~98.;:;;.....-_ _

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: Candidate identifies there are no issues with the above entries.

COMMENTS:

Page 7 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 7: 6.2 Cycle of 1-CS-MOV-102A. (Continued) SAT

UNSAT

STANDARD:

6.2.4 Close 1-CS-MOV-102A.

SV

6.2.7 Throttle open l-CS-120 one and one halftums.

6.2.8 Open 1-CS-38. I

SV

6.2.9 Adjust flow to prevent overflowing the floor drain by throttling open 1-CS-120 as ,

required.

6.2.10 AFfER draining approximately 25 gallons OR after flushing for approximately five

minutes, THEN close 1-CS-120.

6.2.11 Remove the quick disconnect with the hose from 1-CS-120.

6.2.12 Stop Tech Spec clock. IF a Tech Spec clock was NOT started, THEN enter N/A.

COMMENTS:

STEP 8: 6.3 Cycle of 1-CS-MOV-102B SAT

STANDARD: UNSAT

Reads NOTE: Isolating a Containment Spray Subsystem when the RCS is equal to or

greater than 350 degrees and 450 psig will start a Technical Specification

LCO.

6.3.1 Connect the quick disconnect fitting of the hose to 1-CS-112, Refueling Wtr Chern

Add Tk Otlt Hdr Drain, for 1-CS-MOV-102B.

6.3.2 Run hose from 1-CS-112 to a floor drain.

6.3.3 Declare a Containment Spray Subsystem inoperable and start the appropriate Tech

Spec Clock. IF Tech Spec Clock does NOT apply, THEN enter N/A.

6.3.4 Verify closed or close 1-CS-43, Refueling Water Chern Add Tk Outlet MOV-102B

Iso1.

COMMENTS:

Page 8 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 8: 6.3 Cycle of 1-CS-MOV-102B(Continued) _ _ _ SAT

STANDARD: UNSAT

_ _ _ Reads NOTE: Refer to Precaution and Limitation 4.3 prior to stroking MOV.

_ _ _ 6.3.5 From the Control Room, open 1-CS-MOV-102B from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data.

• Time to open in seconds: 23.6

Reference Time: 19.87 seconds

Acceptable Range: 16.9 to 22.8 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

_ _ _ _ _ _ 6.3.6 Close 1-CS-MOV-102B.

SV

_ _ _ 6.3.7 Throttle open 1-CS-112 one and one half turns.

_ _ _ _ _ _ 6.3.8 Open 1-CS-43.

_ _ _ 6.3.9 Adjust flow to prevent overflowing the floor drain by throttling open 1-CS-112 as

required.

_ _ _ 6.3.10 AFTER draining approximately 25 gallons OR flushing for approximately five

minutes, THEN close 1-CS-112.

_ _ _ 6.3.11 Remove the quick disconnect with the hose from 1-CS-112.

_ _ _ 6.3.12 Completely drain the hose into the floor drain.

_ _ _ 6.3.13 WHEN the draining is complete, THEN place hose neatly back on rack located in

safeguards basement near the Auxiliary Feed Booster Pumps.

_ _ _ 6.3.14 Stop Tech Spec clock. IF a Tech Spec clock was NOT started, THEN enter N/A.

EVALUATOR NOTES: *Candidate identifies that the stroke open time exceeds the

Acceptable Range values. He should also identify that no comments

were made regarding this and the OPT was checked SAT instead of

UNSAT.

COMMENTS:

Page 9 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 9: 6.4 Cycle of 1-CS-P-1A MOVs and Sample of Discharge Header _ _ _ SAT

STANDARD: UNSAT

_ _ _ Reads NOTE: Isolating 1-CS-P-1A when the RCS is equal to or greater than 350 degrees

and 450 psig will start a Technical Specification LCO.

_ _ _ 6.4.1 Declare 1-CS-P-1A inoperable and start the appropriate Tech Spec Clock. IF Tech

Spec Clock does NOT apply, THEN enter N/A.

_ _ _ 6.4.2 Place 1-CS-P-1A in PULL TO LOCK. (Ref. 2.4.3)

_ _ _ 6.4.3 Verify closed or close 1-CS-MOV-100A, CS PUMP A SUCTION.

_ _ _ Reads NOTE: Refer to Precaution and Limitation 4.3 prior to stroking MOV.

_ _ _ 6.4.4 From the Control Room, open 1-CS-MOV-101A from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data. IF 1-CS-MOV-101A is NOT required to be tested, THEN enter N/A.

• Time to open in seconds: 13.4

Reference Time: 17.0 seconds

Acceptable Range: 14.5 to 19.5 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: *Candidate identifies that the stroke open time exceeds the

Acceptable Range values. He should also identify that no comments

were made regarding this and the OPT was checked SAT instead of

UNSAT.

COMMENTS:

Page 10 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 9: 6.4 Cycle of 1-CS-P-1A MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.4.5 From the Control Room, close 1-CS-MOV-101A from a full-open position. Using

Control Room valve position indication, verify valve closes fully and record the

following data. IF 1-CS-MOV-101A is NOT required to be tested, THEN enter N/A.

Time to close in seconds: 14.8

Reference Time: 17.1 seconds

Acceptable Range: 14.6 to 19.6 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

_ _ _ 6.4.6 From the Control Room, open 1-CS-MOV-101B from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data. IF 1-CS-MOV-101B is NOT required to be tested, THEN enter N/A.

Time to open in seconds: 16.6

Reference Time: 17.1 seconds

Acceptable Range: 14.6 to 19.6 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

COMMENTS:

Page 11 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 9: 6.4 Cycle of 1-CS-P-1A MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.4.7 From the Control Room, close 1-CS-MOV-101B from a full-open position. Using

Control Room valve position indication, verify valve closes fully and record the

following data. IF 1-CS-MOV-101B is NOT required to be tested, THEN enter N/A.

Time to close in seconds: 16.7

Reference Time: 16.8 seconds

Acceptable Range: 14.3 to 19.3 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

_ _ _ 6.4.8 From the Control Room, open 1-CS-MOV-100A from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data. IF 1-CS-MOV-100A is NOT required to be tested, THEN enter N/A

for the following data.

• Time to open in seconds: 68.4

Reference Time: 55.9 seconds

Acceptable Range: 47.6 to 64.2 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: *Candidate identifies that the stroke open time exceeds the

Acceptable Range values. He should also identify that no comments

were made regarding this and the OPT was checked SAT instead of

UNSAT.

COMMENTS:

Page 12 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 9: 6.4 Cycle of 1-CS-P-1A MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.4.9 Place 1-CS-P-1A in AUTO AFfER STOP. Enter N/A if 1-CS-P-1A is to be left in

~. (Ref 2.4.3)

_ _ _ 6.4.10 Stop Tech Spec clock. IF a Tech Spec clock was NOT started, THEN enter N/A.

_ _ _ 6.4.11 Vent and sample 1-CS-P-1A discharge header IAW the following substeps. IF vent

and sample are NOT required, THEN enter N/A for the following substeps.

_ _ _ a. Slowly open 1-CS-57, CTMT Spray Pump 1A Casing Vent.

_ _ _ b. WHEN vent is water solid, THEN close 1-CS-57.

_ _ _ c. Open 1-CS-67, CS Pump 1A Recirc Line Vent, and flush at least 500

ml.

_ _ _ d. Obtain a 1000 ml sample from 1-CS-67.

_ _ _ e. Close 1-CS-67.

_ _ _ f. Label the sample 1-CS-P-1A, and take to Chemistry for analysis.

_ _ _ g. WHEN Chemistry analyzes the sample results, THEN record the results

for 1-CS-P-1A discharge header below AND indicate Sat if the results

were less than or equal to the Acceptance Criteria or Unsat if results

were greater than the Acceptance Criteria.

Acceptance

Chemical Criteria Results Sat Unsat

CI 0.15 ppm 0.08

F 0.15 ppm 0.04

Na 500 ppm 640

EVALUATOR NOTES: Candidate identifies that the chemistry results for Na exceeds the

Acceptable Criteria value. He should also identify that no

comments were made regarding this and Notifications were not

made to the System Engineer and Chemistry.

COMMENTS:

Page 13 of 23

Surry 2008-301 PT Review (1-0PT -CS-006)

STEP 10: 6.5 Cycle of 1-CS-P-1B MOVs and Sample of Discharge Header _ _ _ SAT

STANDARD: UNSAT

_ _ _ Reads NOTE: Isolating 1-CS-P-1B when the RCS is equal to or greater than 350 degrees

and 450 psig will start a Technical Specification LCO.

_ _ _ 6.5.1 Declare 1-CS-P-1B inoperable and start the appropriate Tech Spec Clock. IF Tech

Spec Clock does NOT apply, THEN enter N/A.

_ _ _ 6.5.2 Place 1-CS-P-1B in PULL TO LOCK. (Ref. 2.4.3)

_ _ _ 6.5.3 Verify closed or close 1-CS-MOV-100B, CS Pillv1PB SUCTION.

_ _ _ Reads NOTE: Refer to Precaution and Limitation 4.3 prior to stroking MOV.

_ _ _ 6.5.4 From the Control Room, open 1-CS-MOV-101C from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

followingdata. IF 1-CS-MOV-l01C is NOT required to be tested, THEN enter N/A.

Time to open in seconds: 15.9

Reference Time: 16.1 seconds

Acceptable Range: 13.7 to 18.5 seconds

Stopwatch SQC Number: 3698'

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: Candidate identifies there are no issues with the above entries.

COMMENTS:

Page 14 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 10: 6.5 Cycle of l-CS-P-IB MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.5.5 From the Control Room, close l-CS-MOV-I0IC from a full-open position. Using

Control Room valve position indication, verify valve closes fully and record the

following data. IF l-CS-MOV-I0IC is NOT required to be tested, THEN enter N/A.

Time to close in seconds: 15.8

Reference Time: 16.3 seconds

Acceptable Range: 13.9 to 18.7 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

_ _ _ 6.5.6 From the Control Room, open l-CS-MOV-I0ID from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data. IF l-CS-MOV-I0ID is NOT required to be tested, THEN enter N/A.

Time to open in seconds: 15.8

Reference Time: 15.8 seconds

Acceptable Range: 13.5 to 18.1 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: Candidate identifies there are no issues with the above entries.

COMMENTS:

Page 15 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 10: 6.5 Cycle of 1-CS-P-1B MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.5.7 From the Control Room, close 1-CS-MOV-101D from a full-open position. Using

Control Room valve position indication, verify valve closes fully and record the

following data. IF 1-CS-MOV-101D is NOT required to be tested, THEN enter N/A.

Time to close in seconds: 15.6

Reference Time: 15.8 seconds

Acceptable Range: 13.5 to 18.1 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

_ _ _ 6.5.8 From the Control Room, open 1-CS-MOV-100B from a full-closed position. Using

Control Room valve position indication, verify valve opens fully and record the

following data. IF 1-CS-MOV-100B is NOT required to be tested, THEN enter N/A

for the following data.

• Time to open in seconds: 72.6

Reference Time: 60 seconds

Acceptable Range: 51.0 to 69.0 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

EVALUATOR NOTES: *Candidate identifies that the stroke open time exceeds the

Acceptable Range values. He should also identify that no comments

were made regarding this and the OPT was checked SAT instead of

UNSAT.

COMMENTS:

Page 16 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 10: 6.5 Cycle of 1-CS-P-IB MOVs and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.5.9 Place 1-CS-P-IB in AUTO AFTER STOP. Enter N/A if 1-CS-P-1B is to be left in

PTL. (Ref. 2.4.3)

_ _ _ 6.5.10 Stop Tech Spec clock. IF a Tech Spec clock was NOT started, THEN enter N/A.

_ _ _ 6.5.11 Vent and sample 1-CS-P-1B discharge header lAW the following substeps. IF vent

and sample are NOT required, THEN enter N/A for the following substeps.

_ _ _ a. Slowly open l-CS-60, CTMT Spray Pump 1B Casing Vent.

_ _ _ b. WHEN vent is water solid, THEN close 1-CS-60.

_ _ _ c. Open 1-CS-66, CS Pump 1B Recirc Line Vent, and flush at least 500

mI.

_ _ _ d. Obtain a 1000 mI sample from 1-CS-66.

_ _ _ e. Close 1-CS-66.

_ _ _ f. Label the sample 1-CS-P-1B, and take to Chemistry for analysis.

_ _ _ g. WHEN Chemistry analyzes the sample results, THEN record the results

for 1-CS-P-1B discharge header below AND indicate Sat if the results

were less than or equal to the Acceptance Criteria or Unsat if results

were greater than the Acceptance Criteria.

Acceptance

Chemical Criteria Results Sat Unsat

CI 0.15 ppm 0.02

F 0.15 ppm 0.01

Na 500 ppm .940

EVALUATOR NOTES: Candidate identifies there are no issues with the above entries.

COMMENTS:

Page 17 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 11: 7.0 FOLLOW-ON _ _ _ SAT

_ _ _ UNSAT

STANDARD:

7.1 Acceptance Criteria

_ _ _ 7.1.1 Evaluate the test results by reviewing the Acceptance Criteria for the components

tested. ( )

Each valve tested traveled fully in each direction AND the time to travel full open

or full close was in the Acceptable Range.

_ _ _ 1-CS-MOV-102A, CHEM ADD TK OUTLT

_ _ _ *1-CS-MOV-I02B, CHEM ADD TK OUTLT

_ _ _ *1-CS-MOV-lOOA, CS PUMP A SUCT

_ _ _ *l-CS-MOV-IOOB, CS PUMP B SUCT

_ _ _ *l-CS-MOV-IOIA, CS PUMP A DISCH

_ _ _ 1-CS-MOV-101B, CS PUMP A DISCH

_ _ _ 1-CS-MOV-101C, CS PUMPB DISCH

_ _ _ l-CS-MOV-IOID, CS PUMPB DISCH

_ _ _ 7.1.2 Document the test results. ( )

• __ Satisfactory __ Unsatisfactory

EVALUATOR NOTES: Candidate should identify that the following valves were incorrectly

checked as satisfactory:

I-CS-MOV-I02B for open time exceeding Acceptable Range

I-CS-MOV-IOIA for open time being less than the Acceptable Range

I-CS-MOV-IOOA for open time exceeding Acceptable Range

I-CS-MOV-IOOB for open time exceeding Acceptable Range

Candidate should also identify that the test was checked

Satisfactory instead of Unsatisfactory.

COMMENTS:

Page 18 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 11: 7.0 FOLLOW-ON (Continued) _ _ _ SAT

STANDARD: _ _ _ UNSAT

7.2 Follow-On Tasks

7.2.1 IF the test was unsatisfactory as a result of valve performance, THEN perform the

following actions. Otherwise, enter N/A.

_ _ _ a. Document the reason for the unsatisfactory test in Operator Comments.

_ _ _ b. Notify the System Engineer and record the name.

System Engineer Date

_ _ _ c. Notify the 1ST Engineer and record the name.

1ST Engineer Date Date

_ _ _ d. Initiate a Condition Report and record the number.

CRNo. _

_ _ _ e. Initiate a Work Request and record the number.

Work Request No. _

EVALUATOR NOTES: Candidate identifies that trois section is marked N/A when the test

was actually Unsatisfactory and notifications should be made.

COMMENTS:

Page 19 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 11: 7.0 FOLLOW-ON (Continued) _ _ _ SAT

_ _ _ UNSAT

STANDARD:

_ _ _ 7.2.2 IF the chemical analysis performed for each Containment Spray Pump discharge

header are greater than the maximum values indicated, THEN perform the following

actions. Otherwise, enter N/A.

_ _ _ a. Document the reason for the unsatisfactory chemical analysis in

Operator Comments.

_ _ _ b. Notify the System Engineer and record the name. System Engineer Date

_ _ _ c. Notify the Chemistry Shift Leader and record the name. Chemistry Shift

Leader Date

_ _ _ d. Initiate a Condition Report and record the number.

CRNo.

_ _ _ e. Perform 1-0SP-CS-00l, containment spray System Chemistry Sample

as necessary.

_ _ _ f. Once 1-0SP-CS-001 has been performed satisfactorily then perform 1-

OPT-CS-OO 1, FLUSHING SENSITIZED PIPING FOR THE

CONTAINMENT SPRAY SYSTEM, Subsection 6.4 or 6.5 as

necessary.

_ _ _ 7.2.3 IF a partial test was performed, THEN document the reason for the partial test in

Operator Comments. Otherwise, enter N/A.

_ _ _ 7.2.4 Make or verify an entry in the M&TE Usage Log for each SQC device used during

this test.

EVALUATOR NOTES: Candidate identifies that this section is marked NIA when chemistry

was actually Unsatisfactory and notifications should be made.

COMMENTS:

Page 20 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

STEP 11: 7.0 FOLLOW-ON (Continued) _ _ _ SAT

STANDARD: _ _ _ UNSAT

7.3 Notification, Documentation, and Procedure Closeout

7.3.1 Notify Shift Supervision that the test is complete.

The Initials in this procedure will be identified by the Printed Name.

Operator Comments: _

Completed by: Date: _

7.4 Fteview

Shift Supervision Comments: _

Reviewed by: Date: _

Shift Supervision

Forward original procedure to Engineering Testing.

Engineering Comments: _

Reviewed by: Date: _

1ST Engineer

EVALUATOR NOTES: Candidate identifies that no Operator Comments were made even

though numerous Unsatisfactory conditions existed.

COMMENTS:

STOP TIME:

Page 21 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

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 1 is at 100% power.

• 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, has just been

completed.

Initiating Cues

• I am the Shift Manager and you are the Unit Supervisor.. Here is a copy of 1-0PT-CS-006, RWST Chemical

Addition Tank and Containment Spray System MOV Stroke Test, that has just been completed.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

• When you are finished, inform your examiner of ALL problems noted in the procedure.

G2.2.12 SR08301 22 of 23

Surry 2008-301 PT Review (1-0PT-CS-006)

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

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 1 is at 100% power.

• 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, has just been

completed.

Initiating Cues

• I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-0PT-CS-006, RWST Chemical

Addition Tank and Containment Spray System MOV Stroke Test, that has just been completed.

• Review 1-0PT-CS-006, RWST Chemical Addition Tank and Containment Spray System MOV Stroke Test, for

completeness and accuracy.

• When you are finished, inform your examiner of ALL problems noted in the procedure.

G2.2.12 SR08301 23 of 23

Surry 2008-301 Radiation Exposure Calculation

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.3.2

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

Calculate the radiation exposure when locally operating 2-SI-MOV-2865B.

KIA: G2.3.2 Knowledge of facility ALARA program. (2.5/2.9)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 25 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the classroom.

Standards

• Correctly calculates radiation exposure.

Initiating Cues

• You are to answer the radiation control question, placing your response on the paper containing the question.

• When you are finished responding to the questions, inform an examiner.

Terminating Cues

• Applicant informs the examiner that the answer to the question has been completed.

Tools and Equipment

• Calculator

• Survey Data

Safety Considerations

• None

Page 1 of 13

Surry 2008-301 Radiation Exposure Calculation

Initial Conditions:

• Unit 2 is in a refueling outage and leakage out of the 'B' Sl Accumulator has been noted.

• The operating team has attempted to close 2-SI-MOV-2865B; the valve cannot be closed from the MCR and

needs to be locally closed.

• You have been tasked with entering containment and locally closing 2-SI-MOV-2865B and then exiting

containment.

• HP has reported that there is airborne contamination in the area of 2-SI-MOV-2865B and have asked that the use

of SCBAs be considered, although they have not required it.

• HP has stated that if respirators are NOT worn, the internal dose rate while manipulating 2-SI-MOV-2865B is 60

mremlhr; this dose rate is in addition to the radiation field (external dose rate = 70 mrem/hr) where the valve is

located.

• HP has also stated that the average dose rate from the containment entry point to the valve is 20 mrem/hr and

there is no airborne contamination while traveling to and from 2-SI-MOV-2865B.

• Due to the conditions in containment, use of the main staircase is the only route available to reach 2-SI-MOV-

2865B.

• A second operator is available to aid you in performance of this task, if you deem it necessary.

• HP personnel are currently unavailable to provide assistance for dose determination.

Initiating Cues

Given the one way travel times, times to perform the task and dose rates on the attached table, calculate which one

of the following will result in the lowest total dose for this task (Travel to and from the valve and close the valve)?

a. One operator wearing an SCBA

b. One operator not wearing an SCBA

c. Two operators wearing an SCBA

d. Two operators not wearing an SCBA

Page 2 of 13

Surry 2008-301 Radiation Exposure Calculation

Times to perform the task:

One way travel time to 2-SI-MOV-2865B 6 minutes

without a SCBA

One way travel time to 2-SI-MOV-2865B with 8 minutes

aSCBA

Time for one person without a SCBA to close 10 minutes

2-SI-MOV-2865B

Time for two people without SCBAs to close 4 minutes

2-SI-MOV-2865B

Time for one person with a SCBA to close 2- 16 minutes

SI-MOV-2865B

Time for two people with SCBAs to close 2- 6 minutes

SI-MOV-2865B

Average Dose Rate while traveling to and 20 mrem/hr

from 2-SI-MOV-2865B

Average External Dose Rate while closing 2- 70 mrem/hr

SI-MOV-2865B

Average Internal Dose Rate while closing 2- 60 mrem/hr

SI-MOV-2865B (if applicable)

Page 3 of 13

Surry 2008-301 Radiation Exposure Calculation

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 1: APPLICANT CALCULATES THE TOTAL EXPOSURE FROM TRAVELING TO

AND FROM 2-SI-MOV-2865B. _ _ _ UNSAT

STANDARD:

a) One operator, NO SCBA

One way travel time is 6 minutes, therefore total travel time is 12 minutes.

Average Dose Rate during travel is 20 mrem/hr.

(20 mrem/hr) x (1 hr /60 minutes) x (12 minutes) = 4 mrem

Total Travel Time Dose: 4 mrem

• b) One operator, with SCBA

One way travel time is 8 minutes, therefore total travel time is 16 minutes.

Average Dose Rate during travel is 20 mremlhr.

(20 mremlhr) x (1 hr 160 minutes) x (16 minutes) =5.33 mrem

Total Travel Time Dose: 5.33 mrem

c) Two operators, NO SCBAs

One way travel time is 6 minutes, therefore total travel time is 12 minutes.

Average Dose Rate during travel is 20 mrem/hr.

(20 mrem/hr) x (1 hr /60 minutes) x (12 minutes) = 4 mrem

(2 operators) x (4 mrem) = 4 mrem

Total Travel Time Dose: 8 mrem

d) Two operators, with SCBAs

One way travel time is 8 minutes, therefore total travel time is 16 minutes.

Average Dose Rate during travel is 20 mrem/hr.

(20 mrem/hr) x (1 hr /60 minutes) x (16 minutes) = 5.33 mrem

(2 operators) x (5.33 mrem) = 10.67 mrem

Total Travel Time Dose: 10.67 mrem

COMMENTS:

Page 4 of 13

Surry 2008-301 Radiation Exposure Calculation

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 2: APPLICANT CALCULATES THE TOTAL EXPOSURE FROM CLOSING 2-SI-MOV-

2865B. _ _ _ UNSAT

STANDARD:

a) One operator, NO SCBA

Time to close the valve is 10 minutes.

Average External Dose Rate 70 mremJhr.

Average Internal Dose Rate 60 mremJhr.

(70 mremJhr) x (1 hr / 60 minutes) x (10 minutes) = 11.67 mrem external.

(60 mremJhr) x (1 hr / 60 minutes) x (10 minutes) = 10 mrem internal.

Total dose to close the valve: 21.67 mrem

• b) One operator, with SCBA

Time to close the valve is 16 minutes.

Average External Dose Rate 70 mremlhr.

(70 mremlhr) x (1 hr 160 minutes) x (16 minutes) = 18.67 mrem external.

Total dose to close the valve: 18.67 mrem

c) Two operators, NO SCBAs

Time to close the valve is 4 minutes.

Average External Dose Rate 70 mremJhr.

Average Internal Dose Rate 60 mremJhr.

(70 mremJhr) x (1 hr / 60 minutes) x (4 minutes) = 4.67 mrem external.

(60 mremJhr) x (1 hr / 60 minutes) x (4 minutes) = 4 mrem internal.

(2 operators) x (4.67 mrem + 4 mrem) = 17.33 mrem

Total dose to close the valve: 17.33 mrem

d) Two operators, with SCBAs

Time to close the valve is 6 minutes.

Average External Dose Rate 70 mremJhr.

(70 mremJhr) x (1 hr / 60 minutes) x (6 minutes) = 7 mrem external.

(2 operators) x (9.33 mrem) = 7 mrem

Total dose to close the valve: 14 mrem

COMMENTS:

Page 5 of 13

Surry 2008-301 Radiation Exposure Calculation

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 3: APPLICANT DETERMINES TOTAL JOB DOSE.

_ _ _ UNSAT

STANDARD:

a) One operator, NO SCBA

Total dose to close the valve: 21.67 mrem

Total Travel Time Dose: 4 mrem

Total Job Dose: 25.67 mrem

• b) One operator, with SCBA

Total dose to close the valve: 18.67 mrem

Total Travel Time Dose: 5.33 mrem

Total Job Dose: 24 mrem

c) Two operators, NO SCBAs

Total dose to close the valve: 17.33 mrem

Total Travel Time Dose: 8 mrem

Total Job Dose: 25.33 mrem

d) Two operators, with SCBAs

Total dose to close the valve: 14 mrem

Total Travel Time Dose: 10.67 mrem

Total Job Dose: 24.67 mrem

COMMENTS:

Page 6 of 13

Surry 2008-301 Radiation Exposure Calculation

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ SAT

STEP 4: TASK TEAM DETERMINATION.

_ _ UNSAT

STANDARD:

Applicant reports that one operator with a respirator is the team that will perform the task with the

minimum total dose.

COMMENTS:

STOP TIME:

Page 7 of 13

Surry 2008-301 Radiation Exposure Calculation

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Determine the number of operators and whether or not the use of an SCBA will be required to perform the task

(travel to and from 2-SI-MOV-2865B and then close 2-SI-MOV-2865B, and then exit containment) and yield the

lowest total dose.

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 2 is in a refueling outage and leakage out of the 'B' SI Accumulator has been noted.

• The operating team has attempted to close 2-SI-MOV-2865B; the valve cannot be closed from the MCR and

needs to be locally closed.

• You have been tasked with entering containment and locally closing 2-SI-MOV-2865B and then exiting

containment.

• HP has reported that there is airborne contamination in the area of 2-SI-MOV-2865B and have asked that the use

of SCBAs be considered, although they have not required it.

• HP has stated that if respirators are NOT worn, the internal dose rate while manipulating 2-SI-MOV-2865B is 60

mremlhr; this dose rate is in addition to the radiation field (external dose rate = 70 mrem/hr) where the valve is

located.

• HP has also stated that the average dose rate from the containment entry point to the valve is 20 mrem/hr and

there is no airborne contamination while traveling to and from 2-SI-MOV-2865B.

• Due to the conditions in containment, use of the main staircase is the only route available to reach 2-SI-MOV-

2865B.

• A second operator is available to aid you in performance of this task, if you deem it necessary.

• HP personnel are currently unavailable to provide assistance for dose determination.

Initiating Cues

Given the one way travel times, times to perform the task and dose rates on the attached table, calculate which one

of the following will result in the lowest total dose for this task (Travel to and from the valve and close the valve)?

a. One operator wearing an SCBA

b. One operator not wearing an SCBA

c. Two operators wearing an SCBA

d. Two operators not wearing an SCBA

G2.3.2 SR08301 8 of 10

Surry 2008-301 Radiation Exposure Calculation

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Determine the number of operators and whether or not the use of an SCBA will be required to perform the task

(travel to and from 2-SI-MOV-2865B and then close 2-SI-MOV-2865B, and then exit containment) and yield the

lowest total dose.

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 2 is in a refueling outage and leakage out of the 'B' SI Accumulator has been noted.

• The operating team has attempted to close 2-SI-MOV-2865B; the valve cannot be closed from the MCR and

needs to be locally closed.

• You have been tasked with entering containment and locally closing 2-SI-MOV-2865B and then exiting

containment.

• HP has reported that there is airborne contamination in the area of 2-SI-MOV-2865B and have asked that the use

of SCBAs be considered, although they have not required it.

• HP has stated that if respirators are NOT worn, the internal dose rate while manipulating 2-SI-MOV-2865B is 60

mrem/hr; this dose rate is in addition to the radiation field (external dose rate = 70 mrem/hr) where the valve is

located.

• HP has also stated that the average dose rate from the containment entry point to the valve is 20 mrem/hr and

there is no airborne contamination while traveling to and from 2-SI-MOV-2865B.

• Due to the conditions in containment, use of the main staircase is the only route available to reach 2-SI-MOV-

2865B.

• A second operator is available to aid you in performance of this task, if you deem it necessary.

• HP personnel are currently unavailable to provide assistance for dose determination.

Initiating Cues

Given the one way travel times, times to perform the task and dose rates on the attached table, calculate which one

of the following will result in the lowest total dose for this task (Travel to and from the valve and close the valve)?

a. One operator wearing an SCBA

b. One operator not wearing an SCBA

c. Two operators wearing an SCBA

d. Two operators not wearing an SCBA

G2.3.2 SR08301 9 of 10

Surry 2008-301 Radiation Exposure Calculation

Times to perform the task:

One way travel time to 2-SI-MOV-28658 6 minutes

without a SC8A

One way travel time to 2-SI-MOV-28658 with 8 minutes

aSC8A

Time for one person without a SC8A to close 10 minutes

2-SI-MOV-28658

Time for two people without SC8As to close 4 minutes

2-SI-MOV-28658

Time for one person with a SC8A to close 2- 16 minutes

SI-MOV-28658

Time for two people with SC8As to close 2- 6 minutes

SI-MOV-28658

Dose rates for the Areas

Average Dose Rate from while traveling to 20 mrem/hr

and from 2-SI-MOV-28658

Average External Dose Rate while closing 2- 70 mrem/hr

SI-MOV-28658

Average Internal Dose Rate while closing 2- 60 mrem/hr

SI-MOV-28658 (if applicable)

G2.3.2 SR08301 10 of 10

Surry 2008-301 Classify an Event

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.4.41

TIME CRITICAL

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

Classify an event in accordance with EPIP-1.01

KIA: G2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.3/4.1)

Applicability Estimated Time Actual Time

SRO(I)/SRO(U) 15 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

Standards

• "Site Area Emergency" declared lAW EPIP-1.01.

Initiating Cues

• Significant event notification.

• EPIP-1.01, Emergency Manager Controlling Procedure.

Terminating Cues

• Report received of event classification and initiation of EPIP-1.04.

Procedures

• EPIP-1.01, EMERGENCY MANAGER CONTROLLING PROCEDURE

• EPIP-1.04, RESPONSE TO A SITE AREA EMERGENCY

Safety Considerations

• None

Page 1 of 10

Surry 2008-301 Classify an Event

Initial Conditions:

• This is a TIME CRITICAL JPM.

• You are the Nuclear Shift Manager. While the unit was at 100% power, the 'A' and '8' Main Feed Pumps tripped.

Steam generator levels in all three steam generators (all channels) rapidly decreased off-scale low (Le., below

narrow range indication).

• The team identified a first out (1E-G10, STM GEN LO-LO LVL) due to the low steam generator levels with the

reactor trip breakers still closed. The team then attempted to manually trip the reactor. The reactor could not be

tripped from the main control room.

• I need you to perform EPIP-1.01 and determine if this event should be classified. If a classification is warranted,

complete EPIP-1.01 until the appropriate response procedure is initiated.

• When you finish the actions necessary to accomplish this, please inform me of your findings and classification, if

applicable.

Initiating Cues

• Perform EPIP-1.01 until the appropriate response procedure is initiated, if applicable.

Page 2 of 10

Surry 2008-301 Classify an Event

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are balded and denoted by an asterisk (*).

• START TIME:

STEP 1: OBTAINS A COPY OF EPIP-1.01, ElVlERGENCY MANAGER CONTROLLING SAT

PROCEDURE.

UNSAT

Standards

(a) Proceeds to Sm console bookrack.

(b) Obtains SEM emergency package (or STA classification package).

(c) Gets copy ofEPIP-1.01.

Evaluator's Comments

STEP 2: REVIEWS CAUTION AND NOTE PRIOR TO STEP 1 OF EPIP-1.01. SAT

Standards UNSAT

a) Reviews the following CAUTION: Declaration of the highest emergency class

for which an Emergency Action Level is exceeded shall be made.

b) Reviews the following NOTE: The PCS is potentially unreliable in the event of

an earthquake. Therefore, PCS parameters should be evaluated for accuracy

should an earthquake occur.

Evaluator's Comments

Page 3 of 10

Surry 2008-301 Classify an Event

STEP 3: EVALUATE EMERGENCY ACTION LEVELS: (Step lofEPIP-l.0l). _ _ _ SAT

Standards _ _ UNSAT

a) Determine event category using Attachment 1, Emergency Action Level Table

Index.

Turns to EPIP-l.01, Attachment 1, page 1, EAL Table Index.

b) Review EAL Tab associated with event category.

Determines event category to be SAFETY, SHUTDOWN OR ASSESSMENT SYSTEM

EVENT and turns to Tab A.

c) Use Control Room monitors, PCS, and outside reports to get indications of

emergency conditions listed in the EAL Table.

Ifasked, state that the reactor trip breakers are closed, the team is performing FR-S.l and

annunciator lE-GlO (SrM GEN LO-LO LVL) is lit red.

• Determines event is A-5, Failure of the reactor to trip (ATWT) and classifies the

event as a SITE AREA EMERGENCY.

d) Verify EAL - CURRENTLY EXCEEDED

e) Initiate a chronological log of events

Evaluator's Comments

The time criticality associated with this JPM ends upon declaration of the Site Area

Emergency.

DECLARATION TIME:

Page 4 of 10

Surry 2008-301 Classify an Event

STEP 4: RECORD EAL TAB, TIME EI\1ERGENCY DECLARED AND SMiSEM NAME: (Step SAT

2ofEPIP-l.Ol).

_ _ _ UNSAT

Standards

Completes the table below:

Emergency Classification EAL Time Declared SM/SEM

TAB Name

Notification of Unusual Event

Alert

Site Area Emergency

General Emergency

Evaluator's Comments

STEP 5: ANNOUNCES THE FOLLOWING DECLARATIONS: (Step 3 ofEPIP-l.Ol). _ _ SAT

Standards _ _ UNSAT

Announces the following information:

• Station Emergency Manager position

• Emergency Classification

• EAL Tab

• Time Declared

Evaluator's Comments

STEP 6: CHECK - CONDITIONS ALLOW FOR NORMAL IMPLEI\1ENTATION OF _ _ _ SAT

EI\1ERGENCY RESPONSE ACTIONS: (Step 4 ofEPIP-l.Ol).

_ _ UNSAT

Standards

Determines that plant conditions allow for normal implementation of the emergency

response organization

If asked, state that there are no other events in progress which could hinder the activation

ofthe emergency response organization.

Evaluator's Comments

Page 5 of 10

Surry 2008-301 Classify an Event

STEP 7: NOTIFY PLANT STAFF OF ALERT OR illGHER CLASSIFICATION: (Step 5 of SAT

EPIP-1.01).

_ _ UNSAT

Standards

a) Check classification- ALERT OR illGHER

b) Check if emergency assembly and accountability - PREVIOUSLY

CONDUCTED

If asked, accountability was not previously conducted.

c) Sound emergency alarm and make announcement on the station Gai-Tronics

system as follows:

"Site Area Emergency has been declared due to a failure of the reactor to trip" (or

words to this effect)

d) Repeat step 5.c.

If asked, as Unit 2 sound the emergency alarm for 15 seconds.

Evaluator's Comments

STEP 8: INITIATE SUPPORTING PROCEDURES: (Step 6 ofEPIP-1.01). _ _ SAT

Standards _ _ _ UNSAT

Reviews the following CAUTION: All further instructions should be continued unless

otherwise directed.

a) INITIATE SUPPORTING PROCEDURES:

1) EPIP-2.01, NOTIFICATIONS OF STATE AND LOCAL

GOVERNMENTS

2) EPIP-2.02, NOTIFICATION OF NRC

b) Check if classification announcement made using Gai-Tronics system

If asked, as State and Local Communicator and NRC Communicator, initiate EPIP-2.01

and EPIP-2.02.

Evaluator's Comments

Page 6 of 10

Surry 2008-301 Classify an Event

STEP 9: CHECK TSC - ACTNATED: (Step 7 ofEPIP-l.Ol). _ _ SAT

Standards _ _ UNSAT

Determines the TSC has not been activated.

If asked, the TSC has not been activated.

EPIP-l.Ol Step 7 RNO - IF TSC NOT activated, THEN do the following:

a) Have the STA report to the Control Room.

If asked, the STA is in the MCR ..

b) Notify the Operations Manager On Call (OMOC) or the Manager Nuclear

Operations.

If contacted, the OMOC will acknowledge the classification and report.

c) Evaluate having Radiological Assessment Director report to the Control Room.

If contacted, the RAD will report to the MCR if requested.

d) WHEN relief SEM arrives, THEN perform turnover using EPIP-l.Ol Attachment

3, Turnover Checklist.

If asked, reliefSEM is not present.

Evaluator's Comments

Page 7 of 10

Surry 2008-301 Classify an Event

STEP 10: INITIATE EPIP FOR ElVIERGENCY CLASSIFICATION IN EFFECT: (Step 8ofEPIP-

1.01).

Standards

Initiates the appropriate procedure

• Site Area Emergency - EPIP-1.04, RESPONSE TO A SITE AREA ElVIERGENCY

Applicant reports completion of the task.

STOP TIME:

Page 8 of 10

Surry 2008-301 Classify an Event

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the classroom.

• Classify an event in accordance with EPIP-1.01, Emergency Manager Controlling Procedure.

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:

• This is a TIME CRITICAL JPM.

• You are the Nuclear Shift Manager. While the unit was at 100% power, the 'A' and '8' Main Feed Pumps tripped.

Steam generator levels in all three steam generators (all channels) rapidly decreased off-scale low (Le., below

narrow range indication).

• The team identified a first out (1E-G10, STM GEN LO-LO LVL) due to the low steam generator levels with the

reactor trip breakers still closed. The team then attempted to manually trip the reactor. The reactor could not be

tripped from the main control room.

• I need you to perform EPIP-1.01 and determine if this event should be classified. If a classification is warranted,

complete EPIP-1.01 until the appropriate response procedure is initiated.

• When you finish the actions necessary to accomplish this, please inform me of your findings and classification, if

applicable.

Initiating Cues

• Perform EPIP-1.01 until the appropriate response procedure is initiated, if applicable.

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

G2.4.41 SR08301 9 of 10

Surry 2008-301 Classify an Event

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the classroom.

• Classify an event in accordance with EPIP-1.01, Emergency Manager Controlling Procedure.

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:

• This is a TIME CRITICAL JPM.

• You are the Nuclear Shift Manager. While the unit was at 100% power, the 'A' and '8' Main Feed Pumps tripped.

Steam generator levels in all three steam generators (all channels) rapidly decreased off-scale low (Le., below

narrow range indication).

• The team identified a first out (1E-G10, STM GEN LO-LO LVL) due to the low steam generator levels with the

reactor trip breakers still closed. The team then attempted to manually trip the reactor. The reactor could not be

tripped from the main control room.

• I need you to perform EPIP-1.01 and determine if this event should be classified. If a classification is warranted,

complete EPIP-1.01 until the appropriate response procedure is initiated.

• When you finish the actions necessary to accomplish this, please inform me of your findings and classification, if

applicable.

Initiating Cues

• Perform EPIP-1.01 until the appropriate response procedure is initiated, if applicable.

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

G2.4.41 SR08301 10 of 10

Surry 2008-301 Transmit Report of Emergency

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Administrative Job Performance Measure G2.4.43

TIME CRITICAL

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

Transmit Report of Emergency to State and Local Governments

KIA: G2.4.43 Knowledge of the emergency communications systems and techniques. (2.8/3.5)

Applicability . Estimated Time Actual Time

RO 15 Minutes - To be validated

Conditions

• Task should be performed in the simulator.

Standards

• Report of Emergency transmitted per EPIP-2.01 Attachment 2.

Initiating Cues

• Nuclear Shift Manager direction.

Terminating Cues

• Report transmitted.

Procedures

• EPIP-2.01, NOTIFICATIONS OF STATE AND LOCAL GOVERNMENTS

Tools and Equipment

• Telephone( s)

Safety Considerations

• None

Page 1 of 13

Surry 2008-301 Transmit Report of Emergency

Initiating Cues

• The Shift Manager has just declared a Site Area Emergency for a failure of the reactor to automatically or

manually trip from the main control room. The reactor has been tripped from outside the main control room. The

Shift Manager has directed you to perform EPIP-2.01, Notification of State and Local Governments, including

transmission of the report.

Directions to the Applicant

• This is a TIME CRITICAL JPM.

• The Unit 1 operator was unable to trip the reactor automatically or manually from the main control room.

• The reactor has been tripped from outside the main control room.

• The Shift Manager just declared a Site Area Emergency due to the failure.

• The Shift Manager has directed you to perform EPIP-2.01, Notification of State and Local Governments, including

transm ission of the report.

• This is the first report that will be made to the State and Local Governments

• You are in the Main Control Room.

• On-site weather instruments indicate wind is from the North East (45 degrees) with an average wind speed of 10

mph.

Page 2 of 13

Surry 2008-301 Transmit Report of Emergency

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEP 1: INITIATE PROCEDURE: SAT

Standards UNSAT

Completes Step 1 of EPIP-2.01

• By:

• Date:

• Time:

• Location:

Evaluator's Comments

STEP 2: CHECK FIRST REPORT OF El\1ERGENCY FOR EVENT - REQUIRED. SAT

Standards UNSAT

Recalls that this is the first report of the emergency (or asks).

If asked, state that this is the first report of the emergency.

Evaluator's Comments

Page 3 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHMENT 2 (REPORT OF ENIERGENCY TO _ _ SAT

STATE AND LOCAL GOVERNMENTS).

_ _ UNSAT

Standards

Reviews the following NOTES:

• The initial notification of any emergency classification must be made (meaning contact

initiated with the first agency) within 15 minutes of declaring the emergency class.

• Items 6 though 9 on Attachment 2 are optional for a message reporting initial entry

into the Emergency Plan or an emergency class change, including emergency

termination and may be check 'Excluded from this message.'

• Attachment 1, Instructions for Completing Report of Emergency to State and Local

Governments, may be referenced as needed.

Proceeds to Attachment 2 of EPIP-2.01

Evaluator's Comments

STEP 3: RECORD INFORMATION ON ATTACHMENT 2 (Continued) _ _ SAT

Standards _ _ UNSAT

Fills out Attachment 2 (bolded below):

NIESSAGE # _ _1~ _ APPROVAL: _

(Station Emergency Manager or Recovery Manager)

TIME NOTIFICATION STARTED: _

This is Surry Power Station [X] Control Room [ ] TSC [ ] LEOF [ ] CEOF. Standby for

a roll-call followed by an emergency message. Use a Report of Emergency form to copy

this message.

(Conduct a roll-call and check boxes as each party answers)

[ ] Surry County [ ] State EOC [ ] Williamsburg [ ] York County

[] James City County [ ] Isle of Wight County [ ] Newport News

The emergency message is as follows: (READ SLOWLY)

Item 1: Emergency Class:

[] Notification of Unusual Event Declared at on _

[] Alert (24- hr time) (date)

[X] Site Area Emergency

[] General Emergency

[] Emergency Terminated

Page 4 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHl\1ENT 2 (Continued) _ _ _ SAT

Standards _ _ _ UNSAT

Fills out Attachment 2 (bolded below):

Item 2: Release of radioactive material:

[X] Is within federal limits and NOT related to the event

[] Related to the event is presently occurring [Place release in context in Item 5]

[] Related to the event has occurred and is now terminated [Place release in context in

Item 5]

[] Related to the event is projected to occur [Place projected release in context in Item

5]

If asked, no radioactive release is in progress; however, a normal steam release is

ongoing through the TDAFW pump.

[] We will transmit a Report of Radiological Conditions to the State EOC.

[X] We will not issue a Report of Radiological Conditions.

If asked, a report of radiological conditions is not required..

Item 4: Meteorological Data:

AVE Wind Direction from 45 degrees (0 to 360 ), Compass Point: North East;

10 _ mph

AVE Wind Speed _--:;;;...;;.._

Based on: [X] On-site Measurements [ ] Off-site Measurements [ ] Not available

Item 5:

Remarks / Description of event and release, as applicable. (Do not use abbreviations,

marknumbers and acroynms.):

The reactor failed to shutdown automatically or manually from the main control

room. The reactor has been shutdown from outside the main control room. (or

words to this effect).

Page 5 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHMENT 2 (Continued) _ _ SAT

Standards _ _ _ UNSAT

Fills out Attachment 2 (balded below):

NOTE: Items 6 - 9 are optional for a message reporting initial entry into the

Emergency Plan or an emergency class change, including emergency

termination and may be checked 'Excluded from this message.' "Items 6 - 9 are

excluded from this message" may be read in lieu of each item.

Item 6: Assistance requested or being provided:

[X] Excluded from this message

[] None

_ _ _ _(#) Fire Units from _

_ _ _ _(#) Rescue Units from _

_ _ _ _(#) Police Units from _

_ _ _ _....(#) Other _

If asked, no off-site assistance is required.

Item 7: Emergency response actions underway:

[X] Excluded from this message

[] None

[] Station monitoring teams dispatched off-site

[] Other _

[] Station emergency personnel called in

If asked, no off-site assistance is required station emergency personnel called in.

Item 8: Evacuation or Company Dismissal of on-site personnel:

[X] Excluded from this message

[] No

[ ] Yes, evacuated to:

[] Primary Remote Assembly Area. [] Secondary Remote Assembly Area.

[] Other _

[] Company Dismissal of non-essential personnel:

[ ] is planned. [ ] is in progress. [ ] has been completed.

If asked, evacuation or dismissal is planned.

Page 6 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHMENT 2 (Continued) _ _ SAT

Standards _ _ UNSAT

Fills out Attachment 2 (balded below):

Item 9: Prognosis of Situation:

[X] Excluded from this message

[ ] Improving

[] Stable

[ ] Worsening

[] Other _

If asked, condition is stable.

Item 10:

This is (name) /Emergency

Communicator. Please acknowledge receipt of this message. (Conduct roll-

call and check boxes)

[ ] Surry County [ ] State EOC [ ] Williamsburg [ ] York County

[ ] James City County [ ] Isle of Wight County [ ] Newport News

This is Surry Power Station [X] Control Room [ ] TSC [ ] LEOF [ ] CEOF out at

_ _ _ _ on _

(24-hr time) (date)

Page 7 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHl\1ENT 2 (Continued) _ _ SAT

Standards _ _ UNSAT

Fills out Attachment 2 (balded below):

NOTE:

• When transmitted, the following information is for state use only.

Transmit to State EOC using the DEM ARD.

• The remainder of this report is not transmitted when the message

reports emergency termination.

This is Surry Power Station [X] Control Room [ ] TSC [ ] LEOF [ ] CEOF

continuing the message.

Item 11: Recommended off-site protective actions are:

[X] None

[ ] Shelter-in-place: Mile radius (360) and Mliles downwind in the following

sectors _

[ ] Evacuate: Mile radius (360) and Miles downwind in the following sectors:

[ ] Beyond 10 Mile EPZ:

[] Evacuate Area: _ _ Centerline (deqrees): _ _ Distance (Miles); _ _

Width (feet)

[] Shelter-in-place: _ _ Centerline (deqrees): _ _ Distance (Miles); _ _

Width feet)

[] Potassium Iodide: Recommend implementatlon of Potassium Iodide (KI)

strategies for the general public. The projected dose at the site boundary is > 5

Rem Thyroid CDE.

If asked, Protective Actions are not required..

Item 12: Update schedule:

Name of State EOC Duty Officer:

This is Surry Power Station [X] Control Room [ ] TSC [ ] LEOF [ ] CEOF out at

_ _ _ _ on _

(24-hr time) (date)

RETURNS TO STEP 4 IN BODY OF PROCEDURE.

Page 8 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 4: CHECK ElV1ERGENCY - REMAINS IN EFFECT SAT

Standards UNSAT

Determines the emergency remains in effect.

If asked, state that the emergency remains in effect.

Evaluator's Comments

STEP 5: HAVB SEM / RM APPROVE REPORT (initial/sign at top of Attachment 2) SAT

Standards UNSAT

Obtains SEM / RM signature

Sign Approval for Candidate

Evaluator's Comments

Page 9 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 6: SEND REPORT OF EMERGENCY TO STATE AND LOCAL GOVERmJENTS (i.e. _ _ _ SAT

Initial or Follow-up Report, as required)

_ _ UNSAT

Standards

Sends report to localities and state.

a) Check Instaphone - CLEAR OF CONFLICTING l\1ESSAGE TRAFFIC

b) Use Instraphone to contact State and Local Emergency Operation Centers

(EOCs).

c) Record time notification started on Attachment 2.

d) Perform initial roll-call (ckeck boxes as EOC(s) answer).

e) Read items 1 thourgh 10.

f) Check each EOC answers acknowledgement roll-call (check associated box as

EOC(s) answer).

g) Repeat any items upon request.

h) Record date and time transmittal of Items 1 through 10 completed.

i) Check message reports emergency - REMAINS IN EFFECT

j) Use DEM ARD phone to contact State EOC or DEM,.autodial (ask for Duty

Officer (Alternate: (804) 674-2400)

k) Check State EOC acknowledged message

1) Read items 11 and 12

m) Consult with State EOC Duty Officer to determine desired update message

schedule.

n) Record following at Item 12

• Update message schedule

• State EOC Duty Officer's name

Evaluator's Comments

Time Critical element ends upon initiation of report to the localities.

Page 10 of 13

Surry 2008-301 Transmit Report of Emergency

STEP 7: RECORD DATE AND TIME TRANSMITTAL OF ITEMS TO STATE EOC SAT

COMPLETE

UNSAT

Standards

Records date and time to the form

Evaluator's Comments

STEP 8: VERIFY ALL LOCAL EOCS ANSWERED ACKNOWLEDGEMENT ROLL CALL SAT

Standards UNSAT

Notes that all answered roll-call.

Goes to Step 11

Evaluator's Comments

STEP 9: NOTIFY SEM/RMTRANSMITTAL WAS SENT. SAT

Standards UNSAT

Notifies SEM the transmittal was sent

Evaluator's Comments

End JPM upon report

STOP TIME:

Page 11 of 13

Surry 2008-301 Transmit Report of Emergency

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• The Shift Manager has just declared a Site Area Emergency for a failure of the reactor to automatically or manually trip from

the main control room. The reactor has been tripped from outside the main control room. The Shift Manager has directed

you to perform EPIP-2.01, Notification of State and Local Governments, including transmission of the report.

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:

• This is a TIME CRITICAL JPM.

• The Unit 1 operator was unable to trip the reactor automatically or manually from the main control room.

• The reactor has been tripped from outside the main control room.

• The Shift Manager just declared a Site Area Emergency due to the failure.

• The Shift Manager has directed you to perform EPIP-2.01, Notification of State and Local Governments, including

transmission of the report.

• This is the first report that will be made to the State and Local Governments

• You are in the Main Control Room.

• On-site weather instruments indicate wind is from the North East (45 degrees) with an average wind speed of 10 mph.

Initiating Cues

• The Shift Manager has just declared a Site Area Emergency for a failure of the reactor to automatically or manually trip from

the main control room. The reactor has been tripped from outside the main control room. The Shift Manager has directed

you to perform EPIP-2.01, Notification of State and Local Governments, including transmission of the report.

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

G2.4.41 SR08301 12 of 13

Surry 2008-301 Transmit Report of Emergency

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• The Shift Manager has just declared a Site Area Emergency for a failure of the reactor to automatically or manually trip from

the main control room. The reactor has been tripped from outside the main control room. The Shift Manager has directed

you to perform EPIP-2.01, Notification of State and Local Governments, including transmission of the report.

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:

• This is a TIME CRITICAL*JPM.

• The Unit 1 operator was unable to trip the reactor automatically or manually from the main control room.

• The reactor has been tripped from outside the main control room.

• The Shift Manager just declared a Site Area Emergency due to the failure.

• The Shift Manager has directed you to perform EPIP-2.01, Notification of State and Local Governments, including

transmission of the report.

• This is the first report that will be made to the State and Local Governments

• You are in the Main Control Room.

• On-site weather instruments indicate wind is from the North East (45 degrees) with an average wind speed of 10 mph.

Initiating Cues

• The Shift Manager has just declared a Site Area Emergency for a failure of the reactor to automatically or manually trip from

the main control room. The reactor has been tripped from outside the main control room. The Shift Manager has directed

you to perform EPIP-2.01, Notification of State and Local Governments, including transmission of the report.

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

G2.4.41 SR08301 13 of 13

Surry 2008-301 Perform blended makeup to Unit 1 RWST

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 004A4.40

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

PERFORM A BLENDED FLOW MAKEUP TO THE UNIT 1 RWST.

KIA: 004A4.04 Ability to manually operate and/or monitor in the control room: Calculation of boron

concentration changes. (3.213.6)

Applicability Estimated Time Actual Time

RO/SRO(l) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

• Unit 1 RWST level needs to be raised by approximately 10/0.

Standards

• 1-0P-CS-004, Refueling Water Storage,Tank Makeup

Initiating Cues

• I am the Nuclear Shift Manager. Unit 1 RWST level needs to be raised by approximately 10/0.

• Here's a copy of 1-0P-CS-004, Refueling Water Storage Tank Makeup, Section 5.1. I need you to initiate a

blended flow makeup from the Unit 1 blender at '2300 ppm boron concentration. The present RWST boron

concentration is 2470 ppm.

• I need you .~g.g:~~r~in~~n~r~9Mir~.g~g~~g\~cid* flowrate to achieve 2300 ppm boric acid concentration for a PG

flowrate of tf.)::;t:'jl:lllsr:rrii91'1**~:~nimm"alila~i;C)m gpm.

• No personnel are at the bottom of the Unit 1 Safeguards Valve Pit and HP is restricting access/work to the area.

• Another operator has verified that Unit 1 Safeguard Building Ventilation System is in the UNFILTER mode in

accordance with O-OP-VS-005

• The STA has been notified that Unit 1 RWST will be filled.

• Field operators are available, if required.

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

Page 1 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

Terminating Cues

• Initiate makeup to Unit 1 RWST by completing up to.Step 5.1.18 of 1-0P-CS-004, Refueling Water Storage Tank

Makeup.

Procedures

• 1-0P-CS-004, Refueling Water Storage Tank Makeup

• DRP-003, Curve Book

Tools and Equipment Safety Considerations

• Straight Edge * None

• Calculator

Page 2 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

Simulator Setup

• Call up 100% power IC and initialize.

Initiating Cues

• Unit 1 RWST level needs to be raised by approximately 10/0.

Directions to the Applicant

• I am the Nuclear Shift Manager. Unit 1 RWST level needs to be raised by approximately 1%.

• Here's a copy of 1-0P-CS-004, Refueling Water Storage Tank Makeup, Section 5.1. I need you to initiate a

blended flow makeup from the Unit 1 blender at 2300 ppm boron concentration. The present RWST boron

concentration is 2470 ppm.

• I need YOu.~~r~.;~i~~~t~~7~R~iX~ij~~:.~~!~iM~g~!~p~Cid flowrate to achieve 2300 ppm boric acid concentration for a PG

flowrate of ~~~*:;:*tll:~:~st.I.:ime~;:;;;lIw;;~imj*;:::*I.li:Ba~imm gpm.

• No personnel are at the bottom of the Unit 1 Safeguards Valve Pit and HP is restricting access/work to the area.

• Another operator has verified that Unit 1 Safeguard Building Ventilation System is in the UNFILTER mode in

accordance with 0-OP-VS-005.

• The STA has been notified that Unit 1 RWST will be filled.

• Field operators are available, if required.

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

Page 3 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

_ _ _ SAT

NOTIFY THE STA THAT UNIT 1 RWST WILL BE FILLED. (Step 5.1.1)

_ _ _ UNSAT

STANDARD:

Notifies STA that Unit 1 RWST will be filled.

EVALUATOR'S NOTE:

• If asked: The STA has been informed that the Unit 1 RWST will be filled.

COMMENTS:

STEP 2:

_ _ _ SAT

VERIFY THAT THE VCT IS AT DESIRED LEVEL AND BLENDER IS NOT NEEDED FOR

MAKEUP. (Step 5.1.2) _ _ _ UNSAT

STANDARD:

• Checks VCT level at approximately 40%

• Determines blender is not needed for makeup to VCT.

EVALUATOR'S NOTE:

• If asked: Blender is not needed for makeup at this time.

COMMENTS:

Page 4 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

STEP 3:

_ _ _ SAT

VERIFY EMERGENCY BORATE FLOWPATH IS AVAILABLE. (Step 5.1.3)

_ _ _ UNSAT

STANDARD:

• Notes flowpath is available by observing CH-MOV-1350 energized.

COMMENTS:

STEP 4:

_ _ _ SAT

VERIFY THAT THE BLENDER IS NOT NEEDED FOR NORMAL BORIC ACID CONTROL OF

THE RCS. (Step5.1.4) _ _ _ UNSAT

STANDARD:

• Determines blender is not needed by noting Tave and Tref matched and stable.

EVALUATOR'S NOTE:

• If asked: Blender is not needed for makeup at this time.

COMMENTS:

STEP 5:

_ _ _ SAT

RECORD PRESENT BLENDER SETPOINTS FOR A RETURN TO SERVICE REFERENCE.

(Step 5. 1.5) _ _ _ UNSAT

STANDARD:

a) Records present setting on Boric Acid Controller 1-CH-FC-113A

b) Records present setting on Primary Grade Water Controller 1-CH-FC-1114

COMMENTS:

Page 5 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

STEP 6:

_ _ _ SAT

PLACE MAKEUP MODE CONTROL SWITCH TO STOP. (Step 5.1.6)

_ _ _ UNSAT

STANDARD:

• Places Makeup Mode Control Switch to STOP.

COMMENTS:

STEP 7:

_ _ _ SAT

PLACE THE CONTROL SWITCHES FOR BLENDER VALVES IN CLOSE. (Step 5.1.7)

_ _ _ UNSAT

STANDARD:

• a) Places control switch for 1-CH-FCV-1113A in CLOSE and verifies green light ON and

red light OFF.

• b) Places control switch for 1-CH-FCV-1113B in CLOSE and verifies green light ON

and red light OFF.

• c) Places control switch for 1-CH-FCV-1114B in CLOSE and verifies green light ON

and red light OFF.

COMMENTS:

Page 6 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

STEP 8:

_ _ _ SAT

DIRECTS OPENING VARIOUS VALVES TO PROVIDE ALIGNMENT OUTSIDE THE MCR.

(Steps 5.1.8 thru 5.1.11) _ _ _ UNSAT

STANDARD:

a) Directs operator to open or verify open 1-CH-208, Boric Acid Blender 1 Outlet Isol.

b) Directs operator to open or verify open 1-CH-210, Boric Acid Blender 1 Outlet Hdr Isol.

c) Directs operator to open or verify open 1-CH-391, B.A. Blender 1 Outlet to RWST.

d) Directs operator to close or verify closed 1-FC-71, Unit 1 RWST Return Isol.

EVALUATOR'S NOTE:

• If asked: Field operators are available for valve manipulations.

• If asked: Field operators have been briefed for the task.

• If contacted, the field operators will manipulate the valves as directed and report back

that the valves have been manipulated as directed.

COMMENTS:

STEP 9:

_ _ _ SAT

SET THE BORIC ACID AND PRIMARY WATER BATCH INTEGRATORS. (Step 5.1.12)

_ _ _ UNSAT

STANDARD:

a) Sets Boric Acid Integrator for gpm.

b) Sets Primary Grade Water Integrator for gpm.

EVALUATOR'S NOTE:

• Actual values entered into the integrators are not of consequences, as long as a

blended make-up can be performed.

COMMENTS:

Page 7 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

STEP 10:

_ _ _ SAT

SET THE SA FLOW CONTROLLER AND PRIMARY WATER FLOW CONTROLLER FOR

THE REQUIRED CONCENTRATION OF MAKEUP. (Step 5.1.13) _ _ _ UNSAT

STANDARD:

• a) Sets Boric Acid Flow Controller for Ili:!~!.!i~ill'* *i:II.!:i:llllliBli:l:ill:llaliill gpm.

• b) Sets Primary Grade Water Flow Controller for tS:;:jllii:illlelllilimlll!:i:illii.lllimliiilijiiiliililJl

gpm.

EVALUATOR'S NOTE:

Tolerance to be determined during validation.

COMMENTS:

STEP 11

_ _ _ SAT

PLACE THE MAKE-UP MODE SE'L SWITCH TO THE MANUAL POSITION (Step 5.1.14)

_ _ _ UNSAT

STANDARD:

• *Places Makeup Mode Selector Switch to the MANUAL position.

COMMENTS:

STEP 12:

_ _ _ SAT

IF THE UNIT IS IN CSD OR RSD (Step 5.1.15)

_ _ _ UNSAT

STANDARD:

a) Reads NOTE before step about CSD and RSD. Determines plant is at 100% power

and the NOTE is Not Applicable.

b) Reads step about CSD and RSD. Determines plant is at 100% power and the Step is

Not Applicable.

COMMENTS:

Page 8 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

STEP 13:

_ _ _ SAT

PLACE THE CONTROL SWITCH FOR 1-CH-FCV-1113A, BORIC ACID TO BLENDER, TO

AUTO (Step 5.1.16) _ _ _ UNSAT

STANDARD:

• *Places control switch for 1-CH-FCV-1113A to the AUTO position

COMMENTS:

STEP 14:

_ _ _ SAT

START THE MAKEUP BY PLACING THE MAKEUP MODE CONTROL SWITCH TO THE

START POSITION (Step 5.1.17) _ _ _ UNSAT

STANDARD:

• a) Places Makeup Mode Control Switch to the START position.

b) Observes that blender makeup begins by noting boric acid and PG flow.

EVALUATOR'S NOTE:

Once the makeup has been initiated, the evaluator will indicate that the JPM has been

completed.

COMMENTS:

STOP TIME:

Page 9 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Perform a blended flow makeup to Unit 1 RWST.

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 1 is at 100% power.

• Unit 1 RWST needs to be raised by approximately 1%.

Initiating Cues

• I am the Nuclear Shift Manager. Unit 1 RWST level needs to be raised by approximately 1%.

• Here's a copy of 1-0P-CS-004, Refueling Water Storage Tank Makeup, Section 5.1. I need you to initiate a

blended flow makeup from the Unit 1 blender at 2300 ppm boron concentration. The present RWST boron

concentration is 2470 ppm.

• I need you~g ..~~1=~[:~:.iD~.~D~.r~9~.!~~~~g~~.g~cid flowrate to achieve 2300 ppm boric acid concentration for a PG

flowrate of tc>:.::..melef!.:im~m. ::Gti1li£immh:~alima~iC)m gpm.

• No personnel are at the bottom of the Unit 1 Safeguards Valve Pit and HP is restricting access/work to the area.

• Another operator has verified that Unit 1 Safeguard Building Ventilation System is in the UNFILTER mode in

accordance with 0-OP-VS-005

• The STA has been notified that Unit 1 RWST will be filled.

• Field operators are available, if required.

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

004A4.04 SR08301 10 of 11

Surry 2008-301 Perform blended makeup to Unit 1 RWST

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Perform a blended flow makeup to Unit 1 RWST.

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 1 is at 100% power.

• Unit 1 RWST needs to be raised by approximately 1%.

Initiating Cues

• I am the Nuclear Shift Manager. Unit 1 RWST level needs to be raised by approximately 10/0.

• Here's a copy of 1-0P-CS-004, Refueling Water Storage Tank Makeup, Section 5.1. I need you to initiate a

blended flow makeup from the Unit 1 blender at 2300 ppm boron concentration. The present RWST boron

concentration is 2470 ppm.

• I need you~g~~1~r~i~~.~~:~.. :r~9.~ir;g:~8ri~ .: ~cid flowrate to achieve 2300 ppm boric acid concentration for a PG

flowrate of tm:~*CJetenm:im~::*CJ.Lllirnm::Nla.liEJa~imm gpm.

• No personnel are at the bottom of the Unit 1 Safeguards Valve Pit and HP is restricting access/work to the area.

• Another operator has verified that Unit 1 Safeguard Building Ventilation System is in the UNFILTER mode in

accordance with 0-OP-VS-005

• The STA has been notified that Unit 1 RWST will be filled.

• Field operators are available, if required.

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

004A4.04 SR08301 11 of 11

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 005A2.03

Alternate Path

Applicant. _ Start Time _

Examiner _

Date _ Stop Time _

INITIATE RHR ALTERNATE DEACY HEAT REMOVAL BY FORCED FEED COOLING WITH A CHARGING

PUMP.

KIA: 005A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS,

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of

those malfunctions or operations: RHR pump/motor malfunction (2.9/3.1)

KIA: APE 025AA1.02 Ability to operate and/or monitor the following as they apply to the Loss of Residual

Heat Removal System: RCS inventory (3.8/3.9)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

• Plant is at mid-loop with RHR cooling lost and non-recoverable.

• 1-AP-27.00, Loss of Decay Heat Removal Capability, in progress.

Standards

• Feed & Bleed cooling established lAW 1-AP-27.00, Attachment 6.

Initiating Cues

• The Plant is currently operating at mid-loop on RHR and have had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

• Here is a copy of AP-27.00, Attachment 6. I need you to initiate alternate decay heat removal by performing

forced feed cooling, using a Charging pump to a hot leg flow path.

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

Page 1 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

Terminating Cues

• 1-AP-27.00, Attachment 6, step 23 completed, and hot leg 81 flow established.

Procedures

• 1-AP-27.00, Loss of Decay Heat Removal Capability, Attachment 6.

Tools and Equipment Safety Considerations

• None * None

Page 2 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

Simulator Setup

• Call up mid-loop RHR IC and initialize. Set SIMOV869A and B = O. SIMOV869A and B_Rack in = T. Set

CSM101 to equate to -900/0 RWST level.

• On VCT Float makeup (No charging pumps operating); Place red magnets on A & B Chg pumps; Rack in C Chg

pp normal bkr & ensure C Chg pp alt bkr racked out, with red magnets.

• Drain to ~ 12.0 feet; Lock out both RHR pumps; Verify RMT key switches are in the RMT position. Insert Hot Leg

SI MOV keys into respective key switches.

• Freeze simulator for JPM performance.

Initiating Cues

• The Plant is currently operating at mid-loop on RHR and have had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

Directions to the Applicant

• The Plant is currently operating at mid-loop on RHR and have had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

• Here is a copy of AP-27.00, Attachment 6. I need you to initiate alternate decay heat removal by performing

forced feed cooling, using a Charging pump to a hot leg flow path.

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

Page 3 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

_ _ _ SAT

READS AP-27.00, ATTACHMENT 6 CAUTIONS:

_ _ _ UNSAT

• PERSONNEL WORKING IN CTMT SHOULD BE WARNED BEFORE THE RCS IS

FILLED TO AVOID INADVERTENT CONTAMINATION OF PERSONNEL WORKING

NEAR RCS OPENINGS.

• ONLY BORATED WATER SHOULD BE ADDED TO THE RCS TO MAINTAIN

ADEQUATE SHUTDOWN MARGIN.

• THE INTENT OF THIS ATTACHMENT IS TO MAINTAIN SUBCOOLED

CONDITIONS IN THE RCS.

(Step 1 CAUTIONS)

STANDARD:

Reads and acknowledges cautions.

EVALUATOR'S NOTE:

• If asked: No personnel are in CTMT.

COMMENTS:

Page 4 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 2:

SAT

READS AP-27.00 NOTE: THE HOT LEG FLOW PATH IS PREFERRED FOR RCS FEED

AND BLEED, THE COLD LEG SHOULD BE USED IF THE HOT LEG IS NOT AVAILABLE OR UNSAT

THE PRZR CANNOT BE FILLED DUE TO MAINTENANCE. (Step 1 Note)

STANDARD:

a) Reads and acknowledges note.

b) Determines that hot leg flow path is available by checking HHSI to hot leg valves,

1-SI-MOV-1869A and B, available.

c) Determines from SS that PRZR is also available.

EVALUATOR'S NOTE:

• If asked: Provide cue MOV-1869A and B indicates GREEN on and RED off.

• If asked: Provide cue no maintenance is being conducted on the PRZR. Hot leg flow

path is available.

COMMENTS:

STEP 3:

SAT

READS STEP 1, AP-27.00, ATTACHMENT 6, AND TRANSITIONS TO STEP 13. (Step 1)

UNSAT

STANDARD:

a) Reads step 1.

b) Determines that Chg pump is to be used based on initial directions, and transitions to

step 13.

EVALUATOR'S NOTE:

• If asked: Chg pump is to be used.

COMMENTS:

Page 5 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 4:

_ _ _ SAT

OPENS CHARGING PUMP SUCTION VALVES FROM RWST. (Step 13a)

_ _ _ UNSAT

STANDARD:

• a) Places 1-CH-MOV-1115Bcontrol switch in the OPEN position until valve

position lights indicate valve is open.

• b) Places 1-CH-MOV-1115D control switch in the OPEN position until valve

position lights indicate valve is open.

EVALUATOR'S NOTE:

• Since the RWST suction valves are parallel flowpaths, only one of these are necessary

to satisfy the critical step requirement.

COMMENTS:

STEP 5:

_ _ _ SAT

CLOSES CHARGING PUMP SUCTION VALVES FROM VCT. (Step 13b)

_ _ _ UNSAT

STANDARD:

• a) Places 1-CH-MOV-1115C control switch in the CLOSE position until valve

position lights indicate valve is closed.

• b) Places 1-CH-MOV-1115E control switch in the CLOSE position until valve

position lights indicate valve is closed.

EVALUATOR'S NOTE:

• Since the VCT suction valves are series isolations, only one of these are necessary to

satisfy the critical step requirement.

COMMENTS:

Page 6 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 6:

SAT

DETERMINES WHICH CHG PUMP IS TO BE STARTED. (Step 14)

UNSAT

STANDARD:

a) Verifies 1-CH-P-1 C (Normal) is available by determ ining 1-CH-P-1 A, 1B, and 1C

(Alternate) are tagged out by observing the RED magnets placed beside the pump

control switches.

EVALUATOR'S NOTE:

• If asked: Provide cue 1-CH-P-1C (Normal) is available, with its breaker racked in.

COMMENTS:

STEP 7:

SAT

VERIFIES VALVES ASSOCIATED WITH 1-CH-P-1C (NORMAL) OPEN. (Step 15)

UNSAT

STANDARD:

Checks "C" Charging pump valves open:

• 1-CH-MOV-1270A

• 1-CH-MOV-1270B

• 1-CH-MOV-1275C

• 1-CH-MOV-1286C

• 1-CH-MOV-1287C

• 1-CH-MOV-1373

COMMENTS:

Page 7 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 8:

_ _ _ SAT

STARTS ONE CHARGING PUMP. (Step 16)

_ _ _ UNSAT

STANDARD:

• a) Starts 1-CH-P-1C (normal) by removing control switch from PTL position.

b) Verifies pump start by observing breaker status lights (RED light lit and GREEN

light off) and pump amp meter.

COMMENTS:

STEP 9:

_ _ _ SAT

ESTABLISHES RCS BLEED PATH. (Step 17)

_ _ _ UNSAT

STANDARD:

a) Determines the required minimum SI flow for decay heat removal from Attachment 7 is

320 gpm (+/- 10 gpm)

b) Determines that PRZR Safety Valve not removed, by consulting initial directions or

asking SM.

c) Determines time after shutdown is 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, by consulting initial directions or asking

SM, and that one PORV and associated Block MOVs is required for adequate bleed

path.

d) Verifies both Przr block valves open by observing valve position indicating lights show

RED on and GREEN off for both 1-RC-MOV-1535 or 1-RC-MOV-1536.

e) Verifies both PORVs open by observing valve position indication lights show RED on

and GREEN off.

EVALUATOR'S NOTE:

• If asked: Provide cue PRZR Safety Valves are installed.

• If asked: Provide cue Time since shutdown is 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

COMMENTS:

Page 8 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 10:

_ _ _ SAT

ESTABLISHES SI FLOW PATH BY LOCAL THROTTLING OF SELECTED MOVS. (Step 18)

_ _ _ UNSAT

STANDARD:

a) Reads note that the hot leg flow path is preferred for RCS feed and bleed.

b) Directs Auxiliary Building Operator to go to Auxiliary Building basement.

c) Directs Service Building Operator to open breaker for MOV-1869A, (1H1-1 3C)

or MOV-1869B (1J1-1 9A), depending on which is selected.

d) Determines, using attachment 7, flow rate necessary for adequate decay heat

removal to be 320.gpm (allowable 310-330 gpm) based on 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> since shutdown.

• e) Directs the Auxiliary Building Operator to throttle open MOV-1869A or B until

flow rate determined in 9(a) above is achieved. Observe SI flow indicated on

the following flow transmitters:

• 1-SI-FI-1943 & 1943A (Total hdr flow), if MOV-1869B selected, or

• 1-SI-FI-1940 & 1940A (Total alt flow), if MOV-1869A selected

• 1-SI-FI-1933 (A loop flow)

• 1-SI-FI-1960 (B loop flow)

• 1-SI-FI-1932 (C loop flow)

f) GO TO Step 22

EVALUATOR'S NOTE:

• If asked: Provide cue time since shutdown is 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

Booth will open breakers and manipulate valves as directed by candidate.

COMMENTS:

Page 9 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

STEP 11:

_ _ _ SAT

MONITORS RWST LEVEL. (Step 22 & 23)

_ _ _ UNSAT

STANDARD:

a) Identify that when RWST level decreases to 20%, a transition is made to Step 24.

b) Identify that when RHR system is available, must return to procedure Step 23.

COMMENTS:

STEP 12:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that forced feed cooling established with 1 charging pump.

COMMENTS:

Page 10 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Perform Attachment 6 of AP-27.00 to initiate alternate decay heat removal by performing forced feed cooling,

using a Charging pump to a hot leg flow path

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

• Plant is at mid-loop with RHR cooling lost and non-recoverable.

• 1-AP-27.00, Loss of Decay Heat Removal Capability, in progress.

Initiating Cues

• The Plant is currently operating at mid-loop on RHR and have had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

• Here is a copy of AP-27.00, Attachment 6. I need you to initiate alternate decay heat removal by performing

forced feed cooling, using a Charging pump to a hot leg flow path.

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

005A2.03 SR08301 11 of 12

Surry 2008-301 Initiate RHR Alternate Decay Heat Removal

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Perform Attachment 6 of AP-27.00 to initiate alternate decay-heat removal by performing forced feed cooling,

using a Charging pum p to a hot leg flow path

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

• Plant is at mid-loop with RHR cooling lost and non-recoverable.

• 1-AP-27.00, Loss of Decay Heat Removal Capability, in progress.

Initiating Cues

• The Plant is currently operating at mid-loop on RHR and have had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

• Here is a copy of AP-27.00, Attachment 6. I need you to initiate alternate decay heat removal by performing

forced feed cooling, using a Charging pump to a hot leg flow path.

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

005A2.03 SR08301 12 of 12

Surry 2008-301 Transfer to Cold Leg Recirc

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 013A4.01

Alternate Path

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

TRANSFER THE SI SYSTEM TO COLD LEG RECIRCULATION MODE

KIA: 013A4.01 Ability to manually operate and/or monitor in the control room: ESFAS-initiated equipment

which fails to actuate (4.5/4.8)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

• A LBLOCA has occurred on Unit 1. The RWST is near the RMT swapover point.

Standards

• 1-ES-1.3, Transfer to Cold Leg Recirculation, Steps 1-5.

Initiating Cues

• 1-E-1, Loss of Reactor or Secondary Coolant, Step 21.

• Nuclear Shift Manager direction.

Terminating Cues

• Completion of 1-ES-1.3, Transfer to Cold Leg Recirculation, Steps 1-5.

Procedures

• 1-ES-1.3, Transfer to Cold Leg Recirculation.

Tools and Equipment Safety Considerations

• None * None

Page 1 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

Simulator Setup

• Call up 1000/0 power IC and initialize. Place simulator in RUN.

• Initiate the following annunciator overrides:

V1AE2 to OFF.

• Initiate the following switch overrides:

CSRMTA_REFUEL to REFUEL,

CSRMTB_REFUEL to REFUEL.

• Initiate malfunction for A loop cold leg rupture (RC0101).

• Perform E-O & transition to 1-E-1. Perform 1-E-1 through Step 21, which checks for transition to ES-1.3.

• Two (2) LHSI two (2) HHSI pumps & two (2) ISRS should be running (no CS pumps should be running). HHSI

pumps should be on redundant flowpath alignment and charging pump mini-flow recirc valves should be closed.

5

• When RWST level is -15% (CSM101 of 6.0 x 10 ) , freeze simulator for performance.

Initiating Cues

• A Large-Break LOCA has occurred on Unit 1. RWST level is less than 20%.

• The team has just transitioned to 1-ES-1.3.

Directions to the Applicant

• I am the Nuclear Shift Manager. A Large-Break LOCA has occurred on Unit 1. RWST level is less than 200/0.

• Here's a copy of 1-ES-1.3, Transfer to Cold Leg Recirculation. I need you to perform Steps 1-5.

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

Page 2 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• . An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

SAT

STEP 1, CAUTIONS and NOTES (Step 1)

UNSAT

STANDARD:

a) Reads caution that SI recirc flow to RCS must be maintained at all times.

b) Reads caution that transfer to recirculation may cause high radiation in the Auxiliary

Building.

c) Notes that Steps 1 through 5 should be performed without delay and FRs should not

be implemented before completion of these steps.

d) Notes that if sump blockage or a complete loss of sump suction capability occurs,

FRs should NOT be implemented until directed in Attachment 1, or in 1-ECA-1.1,

LOSS OF EMERGENCY COOLANT RECIRCULATION.

e) Verifies BOTH RMT Transfer Switches in RMT position.

COMMENTS:

STEP 2:

SAT

RESETS SAFETY INJECTION. (Step 2)

UNSAT

STANDARD:

Depresses both SI Reset Pushbuttons on Benchboard 1-1.

EVALUATOR'S NOTE:

If SI previously reset, verification of SI reset by noting annunciators A-F-3 & 4 (SI Initiated)

clear will suffice.

COMMENTS:

Page 3 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 3:

SAT

CHECKS SW FLOW ESTABLISHED TO AT LEAST TWO RSHXs. (Step 3a)

UNSAT

STANDARD:

Checks the following flow indications for SW flow to at least two RS HXs:

a) 1-SW -FI-106A (SW flow to "A" RSHX).

b) 1-SW-FI-106B (SW flow to "B" RSHX).

c) 1-SW -FI-106C (SW flow to "C" RSHX).

d) 1-SW -FI-1060 (SW flow to "0" RSHX).

COMMENTS:

STEP 4:

SAT

VERIFIES AC EMERGENCY BUSES - ENERGIZED BY OFF-SITE POWER. (Step 3b)

UNSAT

STANDARD:

a) Checks "H" Bus voltage indicated (between 4000 and 4400 volts).

b) Checks "H" Bus normal supply breaker, 15H8, closed (red light on & green off).

c) Checks "J" Bus voltage indicated (between 4000 and 4400 volts).

d) Checks "J" Bus normal supply breaker, 15J8, closed (red light on & green off).

COMMENTS:

Page 4 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 5:

_ _ _ SAT

CHECKS RS PUMPS ASSOCIATED WITH RS HXs SUPPLIED BY SW AT LEAST TWO

RUNNING. (Step 3c) _ _ _ UNSAT

STANDARD:

Checks if the following pumps are running (breaker indication red light on and amps

indicated):

a) 1-RS-P-1A (associated wi A RSHX).

b) 1-RS-P-1B (associated wi B RSHX).

COMMENTS:

STEP 6:

_ _ _ SAT

VERIFIES LHSI PUMPS - BOTH RUNNING. (Step 4)

_ _ _ UNSAT

STANDARD:

a) Checks 1-SI-P-1A breaker indication red light on and amps indicated.

b) Checks 1-SI-P-1B breaker indication red light on and amps indicated.

COMMENTS:

Page 5 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 7:

_ _ _ SAT

ALIGNS SI SYSTEM FOR RECIRC. (Step 5a & b)

_ _ _ UNSAT

STANDARD:

a) Notes CAUTION that if suction source is lost to any SI or CS pump, the pump should

be stopped.

b) Checks 1-CH-MOV-1275A closed by observing green light on and red light off.

c) Checks 1-CH-MOV-1275B closed by observing green light on and red light off.

d) Checks 1-CH-MOV-1275C closed by observing green light on and red light off.

e) Checks RWST level less than 13% on the following indicators:

• 1-CS-LI-100A

• 1-CS-LI-100B

• 1-CS-LI-100C

• 1-CS-LI-100D

f) If RWST level not less than 13%, waits for level to reach 130/0.

EVALUATOR'S NOTE:

If annunciators 1A-A2, 1A-B2, 1A-C2, and 1A-D2 are lit, the operator should identify auto

RMT failure and proceed to Step 5c.

COMMENTS:

Page 6 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 8:

_ _ _ SAT

ATTEMPTS INITIATION OF RECIRC MODE TRANSFER - PHASE 1. (Step 5e(1))

_ _ _ UNSAT

STANDARD:

a) Checks Phase 1 White Status light not lit. (Goes to RNO)

b) Pushes both RMT actuation pushbuttons for Train A.

c) Pushes both RMT actuation pushbuttons for Train 8.

EVALUATOR'S NOTE:

• Phase 1 White Status light is not lit.

• RMT actuation pushbuttons will not function when pushed.

COMMENTS:

STEP 9:

_ _ _ SAT

ALIGNS LHSI PUMP DISCHARGE TO THE HHSI PUMP SUCTION. (Step 5e(2))

_ _ _ UNSAT

STANDARD:

• a) Opens 1-SI-MOV-1863A by placing control switch to OPEN.

b) Checks valve open by observing red light on & green off.

• c) Opens 1-SI-MOV-1863B by placing control switch to OPEN.

d) Checks valve open by observing red light on & green off.

EVALUATOR'S NOTE:

• 1-SI-MOV-1863A or 1-SI-MOV-18638 will provide sufficient head to the HHSI pumps,

therefore only one needs to be performed.

COMMENTS:

Page 7 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 10:

_ _ _ SAT

CLOSE THE LHSI PUMP RECIRCULATION PATH TO THE RWST. (Step 5c(3))

_ _ _ UNSAT

STANDARD:

• a) Closes 1-SI-MOV-1885A by placing control switch to CLOSE.

b) Checks 1-SI-MOV-1885A closed by observing green light on & red off.

• c) Closes 1-SI-MOV-1885B by placing control switch to CLOSE.

d) Checks 1-SI-MOV-1885B closed by observing green light on & red off.

• e) Closes 1-SI-MOV-1885C by placing control switch to CLOSE.

f) Checks 1-SI-MOV-1885C closed by observing green light on & red off.

• g) Closes 1-SI-MOV-1885D by placing control switch to CLOSE.

h) Checks 1-SI-MOV-1885D closed by observing green light on & red off.

EVALUATOR'S NOTE:

1-SI-MOV-1885A and D supply IIAII LHSI pump, 1-SI-MOV-1885B and C supply IIB" LHSI

pump. Only one valve per pump is required to be closed to satisfy the intent of this step.

COMMENTS:

STEP 11:

_ _ _ SAT

CHECK PHASE 2 AMBER STATUS LIGHT ON BENCHBOARD - LIT. (Step 5d(1))

_ _ _ UNSAT

STANDARD:

a) Checks Phase 2 Amber Status light not lit.

b) Ensures 1 minute elapses prior to continuing.

COMMENTS:

Page 8 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 12:

SAT

OPENS LHSI PUMP CONTAINMENT SUMP SUCTION ISOLATION VALVES. (Step 5d(2))

UNSAT

STANDARD:

• a) Opens 1-SI-MOV-1860A by placing control switch to OPEN.

b) Checks 1-SI-MOV-1860A open by observinq red light on & green off.

• c) Opens 1-SI-MOV-1860B by placing control switch to OPEN.

d) Checks 1-SI-MOV-1860B open by observinq red light on & green off.

EVALUATOR'S NOTE:

These valves take approximately 1 minute to open.

COMMENTS:

STEP 13:

SAT

CLOSES LHSI PUMP RWST SUCTION ISOLATION VA,LVES. (Step 5d(3))

UNSAT

STANDARD:

• a) Closes 1-SI-MOV-1862A by placing control switch to CLOSE.

b) Checks 1-SI-MOV-1862A closed by observing green light on & red off.

• c) Closes 1-SI-MOV-1862B by placing control switch to CLOSE.

d) Checks 1-SI-MOV-1862B closed by observing green light on & red off.

EVALUATOR'S NOTE:

COMMENTS:

Page 9 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 14:

SAT

CLOSES CHG PUMP RWST SUCTION ISOLATION VALVES. (Step 5d(4))

UNSAT

STANDARD:

• a) Closes 1-CH-MOV-1115B by placing control switch to CLOSE.

b) Checks 1-CH-MOV-1115B closed by observing green light on & red off.

• c) Closes 1-CH-MOV-1115D by placing control switch to CLOSE.

d) Checks 1-CH-MOV-1115D closed by observing green light on & red off.

COMMENTS:

STEP 15:

SAT

VERIFIES RECIRCULATION FLOW ESTABLISHED. (Step 5e)

UNSAT

STANDARD:

Verifies SI flow to the Rx core via both cold leg flowpaths by checking the following flow

instrumentation:

• 1-SI-FI-1945 (A LHSI FT),

• 1-SI-FI-1946 (8 LHSI FT),

• 1-SI-FI-1961 (A Loop FT),

• 1-SI-FI-1962 (B Loop FT),

• 1-SI-FI-1963 (C Loop FT),

• 1-SI-FI-1943 (Total flow normal hdr),

• 1-SI-FI-1943A (Total flow normal hdr),

• 1-SI-FI-1940 (Total flow alt hdr),

• 1-SI-FI-1940A (Total flow alt hdr).

COMMENTS:

Page 10 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

STEP 16:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that cold leg recirculation established.

COMMENTS:

STOP TIME:

Page 11 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Perform Steps of 1-ES-1.3, Transfer to Cold Leg Recirculation, to establish cold leg recirculation flow.

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 Large-Break LOCA has occurred on Unit 1. RWST level is less than 20%.

• The team has just transitioned to 1-ES-1.3, Transfer to Cold Leg Recirculation.

Initiating Cues

• I am the Nuclear Shift Manager. A Large-Break LOCA has occurred on Unit 1. RWST level is less than 200/0.

• Here's a copy of 1-ES-1.3, Transfer to Cold Leg Recirculation. I need you to perform Steps 1-5.

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

013A4.01 SR08301 12 of 13

Surry 2008-301 Transfer to Cold Leg Recirc

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Perform Steps of 1-ES-1.3, Transfer to Cold Leg Recirculation, to establish cold leg recirculation flow.

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 Large-Break LOCA has occurred on Unit 1. RWST level is less than 20%.

• The team has just transitioned to 1-ES-1.3, Transfer to Cold Leg Recirculation.

Initiating Cues

• I am the Nuclear Shift Manager. A Large-Break LOCA has occurred on Unit 1. RWST level is less than 200/0.

• Here's a copy of 1-ES-1.3, Transfer to Cold Leg Recirculation. I need you to perform Steps 1-5.

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

013A4.01 SR08301 13 of 13

Surry 2008-301 Remove SR NI From Service

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 015A4.03

Alternate Path

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

REMOVE A FAILED SOURCE RANGE NI FROM SERVICE DURING A REACTOR STARTUP

KIA: 015A4.03 Ability to manually operate andlor monitor in the control room: Trip bypasses (3.8/3.9)

Applicability Estimated Time Actual Time

RO/SRO(I) 5 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

10

• N-31 has failed low with reactor power at 1.3 x 10- amps during a startup, and the SR high voltage cannot be

removed from either N-31 or N-32.

Standards

• 1-AP-4.00, Nuclear Instrumentation Malfunction.

Initiating Cues

• During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-338 TR 8 to de-

energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from

either detector (N-31 or N-32).

• I need you to respond to a failure of both Source Range Nls, lAW 1-AP-4.00, so the reactor startup can continue.

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

Terminating Cues

• Completion of 1-AP-4.00, Nuclear Instrumentation Malfunction.

Procedures

• 1-AP-4.00, Nuclear Instrumentation Malfunction

Page 1 of 5

Surry 2008-301 Remove SR NI From Service

Tools and Equipment Safety Considerations

• None * None

Page 2 of 5

Surry 2008-301 Remove SR NI From Service

Simulator Setup

• Call up Reactor Startup IC and initialize.

10

• Perform the startup to obtain power at ::::::1.3 x 10- amps (or slightly greater), then implement malfunction

(MN101 01, 1 sec, 50 to 0%), N-31 failure in the low direction. Implement switch overrides (SRTRP_BLK_TRA_PB

AND SRTRP_BLK_TRB_PB, ACTIVE), Flux Level Trip Cutout Pushbutlons. Freeze the simulator until ready for

operator to perform JPM.

• Do not allow the SUR to be greater than +0.1 dpm. (0 DPM preferred)

Initiating Cues

• During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-33B TR B to de-

energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from

either detector (N-31 or N-32).

Directions to the Applicant

• During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-33B TR B to de-

energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from

either detector (N-31 or N-32).

• I need you to respond to a failure of both Source Range Nls, lAW 1-AP-4.00, so the reactor startup can continue.

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

Page 3 of 5

Surry 2008-301 Remove SR NI From Service

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*). If substeps of a critical element also are bolded

and have an asterisk (*), then only those substeps are critical to performance of that task element.

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

SAT

DETERMINES PROCEDURAL STEPS TO RESPOND TO SRNI FAILURE.

UNSAT

STANDARD:

a) Enters 1-AP-4.00 at Step 1.

b) Determines failure not in Power Range NI and goes to step 10.

c) Determines failure not in Intermediate Range NI and goes to step 19.

d) Identifies failure in the SRNls.

COMMENTS:

STEP 2:

SAT

STABILIZES UNIT CONDITIONS

UNSAT

STANDARD:

a) Verifies unit conditions stable with a zero startup rate.

b) Maintains power with approximately zero startup rate.

EVALUATOR'S NOTE:

A manual reactor trip is NOT an acceptable action.

COMMENTS:

Page 4 of 5

Surry 2008-301 Remove SR NI From Service

STEP 3:

SAT

10

CHECKS REACTOR POWER - GREATER THAN P- 6 (1 X 10- AMPS)

UNSAT

STANDARD:

Checks reactor power level by observing INT RNG FLUX meters NI-1-35B and NI-1-36B (on

Benchboard 1-2) or the meters on the IR NIS cabinets. (Reactor power should be above 1 x

-10

10 amps).

COMMENTS:

STEP 4:

SAT

VERIFY BOTH SOURCE RANGE CHANNEL- HIGH VOLTAGE OFF

UNSAT

STANDARD:

Checks both SR channels, determines that both are still energized and goes to the RNa

Column.

Page 5 of 5

'Surry 2008-301 Remove SR NI From Service

• STEP 5:

_ _ _ SAT

REMOVE FAILED SOURCE RANGE NI FROM OPERATION.

_ _ _ UNSAT

STANDARD:

11

a) Pushes 1I1/N 33A TR All pushbutton and 1I1/N 338 TR 8 pushbutton.

b) Notes that N-31 and N-32 still have high voltage applied to the detectors.

c) Informs operator that annunciator G-D-1, "Source or INT RNG NIS TRIP 8YP" will be

received.

d) * Places LEVEL TRIP switch for N-31 in BYPASS.

e) * Removes INSTRUMENT POWER fuses for N-31.

f) * Places LEVEL TRIP switch for N-32 in BYPASS.

g) * Removes INSTRUMENT POWER fuses for N-32.

h) Notes requirement to refer to Tech Spec Table 3.7-1 Item 4.

i) Notes requirement to make entry in PSL and shift turnover to reinstall fuses.

j) Goes to step 38 of 1-AP-4.00.

EVALUATOR'S NOTE:

• When the 1/N 33A TR A or 1/N 338 TR 8 buttons are pressed, annunciator G-A-3, "NIS

SOURCE RNG LOSS OF DET VOL" is received but clears when acknowledged.

• It is acceptable to place both SRNI in LEVEL TRIP 8YPASS before removing the

INSTRUMENT POWER fuses.

CUES

• Tell operator (or if asked): The S8 will ensure that Tech Specs are checked and that

appropriate log entries will be made.

COMMENTS:

Page 6 of 5

Surry 2008-301 Remove SR NI From Service

STEP 6:

_ _ _ SAT'

REPORT TO SHIFT SUPERVISOR (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report that N-31 and N-32 have been removed from service lAW AP-4.00.

EVALUATOR'S NOTE:

• Candidate may make notifications to the Instrument Shop and OMOC before terminating

JPM.

STOP TIME:

COMMENTS:

Page 7 of 5

Surry 2008-301 Remove SR NI From Service

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Perform Steps of 1-AP-4.00, Nuclear Instrumentation Malfunction, to allow reactor startup to continue.

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

10

• N-31 has failed low with reactor power at 1.3 x 10- amps during a startup, and the SR high voltage cannot be

removed from either N-31 or N-32.

Initiating Cues

• During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-338 TR 8 to de-

energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from

either detector (N-31 or N-32).

• I need you to respond to a failure of both Source Range Nls, lAW 1-AP-4.00, so the reactor startup can continue.

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

015A4.03 SR06301 8 of 9

Surry 2008-301 Remove SR NI From Service

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Perform Steps of 1-AP-4.00, Nuclear Instrumentation Malfunction, to allow reactor startup to continue.

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

10

• N-31 has failed low with reactor power at 1.3 x 10- amps during a startup, and the SR high voltage cannot be

removed from either N-31 or N-32.

Initiating Cues

• During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-33B TR B to de-

energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from

either detector (N-31 or N-32).

• I need you to respond to a failure of both Source Range Nls, lAW 1-AP-4.00, so the reactor startup can continue.

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

015A4.03 SR06301 9 of 9

Surry 2008-301 Secure Containment Depressurization Equipment

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 026A2.08

ALTERNATE PATH

Applicant. _ Start Time _

Examiner _

Date _ Stop Time _

SECURE CONTAINMENT DEPRESSURIZATION EQUIPMENT.

KIA: 026A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and

(b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those

malfunctions or operations: Safe securing of containment spray(when it can be done). (3.213.6)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the Simulator.

• LOOP occurred from 100 % power followed by large-break LOCA. The #1 EDG failed to load and the "H" bus is

de-energized. 1-E-0 has been performed, transition made to 1-E-1. 1-E-1 has been performed through Step 8,

all ESW pumps are running & Ctmt pressure is < 12 psia.

Standards

• 1-RS-P-28 and 1-CS-P-1 8 secured lAW 1-E-1 Steps 9 through 12.

Initiating Cues

• You are the Unit RO & I am the Nuclear Shift Manager. We have had a loss of offsite power followed by a large-

break LOCA. The #1 EDG failed to load and the "H" bus is de-energized. 1-E-0 has been performed and we

have performed 1-E-1 through Step 8 where the Outside Operator has started all Emergency Service Water

Pumps.

• Here's a copy of 1-E-1 Steps 9 through 12. I need you to secure the Containment depressurization equipment

lAW Steps 9 through 12.

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

Page 1 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

Terminating Cues

• Report received that 1-E-1 Step 12 completed.

Procedures

• 1-E-1, Loss of Reactor or Secondary Coolant.

Tools and Equipment Safety Considerations

• None * None

Page 2 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

Simulator Setup

• Call up 100 % power IC and initialize.

Initiating Cues

• 1-E-1, Loss of Reactor or Secondary Coolant, Step 9.

Directions to the Applicant

• You are the Unit RO & I am the Nuclear Shift Manager. We have had a loss of offsite power followed by a large-

break LOCA. The #1 EDG failed to load and the "H" bus is de-energized. 1-E-0 has been performed and we

have performed 1-E-1 through Step 8 where the Outside Operator has started all Emergency Service Water

Pumps.

• . Here's a copy of 1-E-1 Steps 9 through 12. I need you to secure the Containment depressurization equipment

lAW Steps 9 through 12.

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

Page 3 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

_ _ _ SAT

CHECK IF SW FLOW TO RS HXs CAN BE REDUCED. (Step 9)

_ _ _ UNSAT

STANDARD:

a) Acknowledges CAUTION 1 prior to Step 9 that if only one train of ESF is operating,

SW flow should not be isolated on the operating train.

b) Acknowledges CAUTION 2 prior to Step 9 that operation of an OSRS pump without an

operating CS pump could cause cavitation.

c) Acknowledges NOTE prior to Step 9 about isolating SW to inoperable components on

each SW header.

d) Checks containment pressure less than 14 psia by observing:

• 1-LM-PI-100A,

• 1-LM-PI-100B,

• 1-LM-PI-100C and/or

• 1-LM-PI-100D.

• e) Resets CLS by depressing both Train A and Train B CLS Reset Pushbuttons.

h) Checks AC emergency buses both energized by observing voltage indicated on:

• 1H Emerg Bus voltmeter (#1 EDG panel),

• 1J Emerg Bus voltmeter (#3 EDG panel).

i) Notes "H" Bus is de-energized and GOES TO Step 10

COMMENTS:

Page 4 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 2:

_ _ _ SAT

CHECK EMERGENCY BUS 1H - ENERGIZED. (Step 10a)

_ _ _ UNSAT

STANDARD:

a) 1H Emerg Bus voltmeter (#1 EDG panel) - Notes Zero voltage

b) Checks breakers 15H8 and 15H3 - Notes both open

c) Determines "H" Bus de-energized and GOES TO RNO column.

COMMENTS:

STEP 3:

_ _ _ SAT

STOP RS HX RAD MONITOR PUMPS. (Step 10a RNO step 1)

_ _ _ UNSAT

STANDARD:

Stops the following pumps by taking the control switch to OFF:

• 1-SW-P-5A

• 1-SW-P-5C

COMMENTS:

STEP 4:

_ _ _ SAT

LOCALLY CLOSE SW TO RSHX INLET VALVE. (Step 10a RNO step 2)

_ _ _ UNSAT

STANDARD:

Directs an operator to locally close ONE of the following valves:

• a) 1-SW-MOV-105A (may choose to open supply breaker 1H1-2N-7C first)

• b) 1-SW-MOV-104A (may choose to open supply breaker 1H1-2N-7B first)

EVALUATOR'S NOTE:

Only one valve needs to be closed to meet the critical step requirement.

COMMENTS:

Page 5 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 5:

_ _ _ SAT

LOCALLY CLOSE SW TO RSHX INLET VALVE. (Step 10a RNO step 3)

_ _ _ UNSAT

STANDARD:

Directs an operator to locally close ONE of the following valves:

• a) 1-SW-MOV-10SC (may choose to open supply breaker 1H1-2N-8C first)

• b) 1-SW-MOV-104C (may choose to open supply breaker 1H1-2N-8B first)

EVALUATOR'S NOTE:

Only one valve needs to be closed to meet the critical step requirement.

COMMENTS:

STEP 6:

_ _ _ SAT

PLACES "A" TRAIN RECIRC SPRAY PUMPS IN PULL-TO-LOCK. (Step 10a RNO step 4)

_ _ _ UNSAT

STANDARD:

Places the following pum p control switches in PTL:

• 1-RS-P-1 A ("A" Inside Recirc Spray),

• 1-RS-P-2A ("A" Outside Recirc Spray)

GOES TO Step 11

COMMENTS:

Page 6 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 7:

_ _ _ SAT

CHECK EMERGENCY SERVICE WATER PUMPS - THREE RUNNING. (Step 11)

_ _ _ UNSAT

STANDARD:

Recall from initial direction that three ESW pumps are running (or)

Asks Shift Manager status of ESW pumps

EVALUATOR'S NOTE:

• If asked: Three Emergency Service Water Pumps are running

COMMENTS:

STEP 8:

_ _ _ SAT

CHECK IF CONTAINMENT SPRAY PUMPS CAN BE STOPPED (Step 12a)

_ _ _ UNSAT

STANDARD:

Checks the following:

• RWST level less than 3% (and)

• CS Pump amps - FLUCTUATING

Notes both conditions exist and continues with Step 12b

COMMENTS:

STEP 9:

_ _ _ SAT

VERIFY BOTH TRAINS OF CLS RESET. (Step 12b)

_ _ _ UNSAT

STANDARD:

a) Recalls that CLS was reset in a previous step (or)

b) Resets CLS by pushing both CLS RESET pushbuttons

COMMENTS:

Page 7 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 10:

_ _ _ SAT

STOP OUTSIDE RECIRC SPRAY PUMP AND PUTS SWITCH IN AUTO. (Step 12c)

_ _ _ UNSAT

STANDARD:

• Secures 1-RS-P-2B ("B" OSRS pump) and returns switch to AUTO.

EVALUATOR'S NOTE:

1-RS-P-2A ("N' OSRS pump) does not need to be secured due to no power to the pump.

COMMENTS:

STEP 11

_ _ _ SAT

STOP CONTAINMENT SPRAY PUMP AND PUTS SWITCH IN AUTO. (Step 12d)

(Step 1) _ _ _ UNSAT

STANDARD:

• Secures 1-CS-P-1B ("B" CS pump) and returns switch to AUTO.

EVALUATOR'S NOTE:

1-CS-P-1 A ("A" CS pum p) does not need to be secured due to no power to the pump.

COMMENTS:

STEP 12

_ _ _ SAT

CLOSE CONTAINMENT SPRAY DISCHARGE VALVES. (Step 12e)

_ _ _ UNSAT

STANDARD:

Closes the following valves by taking the control switch to the close position:

• 1-CS-MOV-101A

• 1-CS-MOV-101B

• 1-CS-MOV-101C

• 1-CS-MOV-101D

Directs local closure of 1-CS-MOV-101A & C or 1-CS-MOV-100A & B.

COMMENTS:

Page 8 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 13:

_ _ _ SAT

CLOSE CHEMICAL ADDITION TANK OUTLET VALVES. (Step 12f)

_ _ _ UNSAT

STANDARD:

Closes the following valves by taking the control switch to the close position:

• 1-CS-MOV-102A

• 1-CS-MOV-1028

Directs local closure of 1-CS-MOV-102A

COMMENTS:

STEP 14:

_ _ _ SAT

REPORT TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that depressurization equipment secured.

COMMENTS:

STOP TIME:

Page 9 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Secure Containment Depressurization Equipment.

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 1 was at 100 % power when a loss of off-site power occurred.

• #1 EDG failed to load and the 'H' bus is de-energized.

• A Large Break LOCA is in progress with the team perform ing 1-E-1, Loss of Reactor or Secondary Coolant.

Initiating Cues

• You are the Unit RO & I am the Nuclear Shift Manager, We have had a loss of offsite power followed by a large-

break LOCA. The #1 EDG failed to load and the "IH" bus is de-energized. 1-E-0 has been performed and we

have performed 1-E-1 through Step 8 where the Outside Operator has started all Emergency Service Water

Pumps.

• Here's a copy of 1-E-1 Steps 9 through 12. I need you to secure the Containment depressurization equipment

lAW Steps 9 through 12.

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

026A2.08 SR08301 10 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Secure Containment Depressurization Equipment.

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 1 is at 100 % power.

• #1 EDG failed to load and the 'H' bus is de-energized.

• A Large Break LOCA is in progress with the team perform ing 1-E-1, Loss of Reactor or Secondary Coolant.

Initiating Cues

• You are the Unit RO & I am the Nuclear Shift Manager. We have had a loss of offsite power followed by a large-

break LOCA. The #1 EDG failed to load and the "H" bus is de-energized. 1-E-0 has been performed and we

have performed 1-E-1 through Step 8 where the Outside Operator has started all Emergency Service Water

Pumps.

• Here's a copy of 1-E-1 Steps 9 through 12. I need you to secure the Containment depressurization equipment

lAW Steps 9 through 12.

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

026A2.08 SR08301 11 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 071 A4.26

ALTERNATE PATH

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

RELEASE A WASTE GAS DECAY TANK (WGDT).

KIA: 071A4.26 Ability to manually operate and/or monitor in the control room: Authorized waste gas release,

conducted in compliance with radioactive gas discharge permit. (3.1/3.9)

Applicability Estimated Time Actual Time

RO/SRO(I) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the Simulator.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

Standards

• OP-23.2.3 - Release of Waste Gas Decay Tank 1A.

Initiating Cues

• You are the Unit BOP Operator and I am the Nuclear Shift Manager.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

• The following are the results of the sample on "A" WGDT

Hydrogen Concentration 90%

Oxygen Concentration 1.1 %

• Here's a copy of OP-23.2.3 - Release of Waste Gas Decay Tank 1A. I need you to initiate release of the "A"

WGDT in accordance with Section 5.3 and 5.4.

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

Page 1 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

Terminating Cues

• OP-23.2.3, Release of Waste Gas Decay Tank 1A, section 5.4 complete.

Procedures

• OP-23.2.3 - Release of Waste Gas Decay Tank 1A.

Tools and Equipment Safety Considerations

• None * None

Page 2 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

Simulator Setup

• Call up 100% power IC and initialize.

Initiating Cues

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

Directions to the Applicant

• You are the Unit BOP Opeartor and I am the Nuclear Shift Manager.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

• The following are the results of the sample on "A" WGDT

Hydrogen Concentration 90%

Oxygen Concentration 1.1%

• Here's a copy of OP-23.2.3 - Release of Waste Gas Decay Tank 1A. I need you to initiate release of the "A"

WGDT in accordance with Section 5.3

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

Page 3 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

_ _ _ SAT

REVIEWS INITIAL CONDITIONS AND PRECAUTIONS AND LIMITATIONS (SECTION 3 & 4)

_ _ _ UNSAT

STANDARD:

a) Reads Initial Conditions.

b) Reads Precautions and Limitations

c) Goes to Section 5.3

EVALUATOR'S NOTES:

• If asked: All channels of the Surry Radioactive Gaseous Effluent Monitoring

Instrumentation for the Process Vent System are in service.

• If asked: Both WGDT Gas Analyzers are in service.

COMMENTS:

Page 4 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

STEP 2:

_ _ _ SAT

WASTE GAS DECAY TANK 1A VALVE ALIGNMENT FOR RELEASE. (Step 5.3)

_ _ _ UNSAT

STANDARD:

a) Verifies closed 1-GW-FCV-101, Process Vent WGDT Effluent Flow Controller by

checking zero demand on Demand Signal output meter.

b) Verifies the following valves closed by dispatching an operator to locally check valve

postion:

• 1-GW-19, WGDT 1A Inlet Isolation.

• 1-GW-24, WGDT 1B Release Isolation.

• 1-GW-21, WGDT 1A Recycle Isolation

c) Verifies the following valves open by dispatching an operator to locally check valve

postion:

• 1-GW-20, WGDT 1A Outlet Isolation.

• 1-GW-23, WGDT 1A Release Isolation

COMMENTS:

STEP 3:

_ _ _ SAT

TURN 1-GW-FCV-101, DECAY, TANK BLEED ISOLATION SWITCH TO OPEN. (Step 5.4.1)

_ _ _ UNSAT

STANDARD:

• a) Places switch for 1-GW-FCV-101 in the OPEN position.

b) Observes green light OFF and red light ON for 1-GW-FCV-1 01.

COMMENTS:

Page 5 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

STEP 4:

SAT

SLOWLY OPENS 1-GW-FCV-101 TO ESTABLISH LESS THAN .5 SCFM FLOW. (Step 5.4.2)

UNSAT

STANDARD:

a) Reads NOTE about allowing pressure and flow to stabilize after opening

1-GW-FCV-101.

b) Slowly opens 1-GW-FCV-1 01 by slowly turning the dial on the controller clockwise.

c) Monitors WGDT flow on 1-GW-FI-101 to achieve < 0.5 scfm flow

COMMENTS:

STEP 5:

SAT

CHECK WGDT PRESSURE. (Step 5.4.3)

UNSAT

STANDARD:

a) Checks that WGDT pressure on 1-GW-PI-103 indicates between 4.5 and 6.5 psig

b) Notes that pressure is between 4.5 and 6.5 psig and that no adjustments are

necessary.

COMMENTS:

STEP 6:

SAT

MONITOR INDICATIONS FOR PROPER OPERATION. (Step 5.4.4)

UNSAT

STANDARD:

Monitor the following indications for proper operation:

• 1-RM-RR-132, Process Vent Radiation Monitor Recorder

• 1-RM-RR-133, Vent #2 Radiation Monitor Recorder

• 1-GW-FI-101, WGDT Effluent Flow

• 1-GW-FR-1 01, WGDT to Process Vent

COMMENTS:

Page 6 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

STEP 7:

_ _ _ SAT

RECORD WGDT HYDROGEN CONCENTRATION. (Step 5.4.5)

_ _ _ UNSAT

STANDARD:

a) Recalls from initial conditions that Hydrogen concentration is 90% (or)

b) Calls chernistry to get Hydrogen Concentration

EVALUATOR'S NOTES:

• If asked: Hydrogen concentration is 90%

COMMENTS:

STEP 8:

_ _ _ SAT

REFERS TO TABLE IN ATTACHMENT 4 TO DETERMINE MAXIMUM INDICATED

FLOWRATE FROM WGDT. (Step 5.4.6) _ _ _ UNSAT

STANDARD:

a) Reads CAUTION about Hydrogen concentration greater than 80% limitations

b) Notes hydrogen concentration is greater than 800/0 and refers to Attachment 4 to

determine maximum flow rate from WGDT.

EVALUATOR'S NOTES:

• If asked: Hydrogen concentration is 90%

COMMENTS:

STEP 9:

_ _ _ SAT

DETERMINES MAXIMUM WGDT FLOWRATE FROM ATTACHMENT 4 (Attachment 4)

_ _ _ UNSAT

STANDARD:

• Refers to Attachment 4 and determines maximum WGDT flowrate is 5.6%

COMMENTS:

Page 7 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

STEP 10:

_ _ _ SAT

ADJUST 1-GW-FCV-1 01 TO ACHIEVE DESIRED FLOWRATE. (Step 5.4.7)

_ _ _ UNSAT

STANDARD:

a) Reads NOTE about calculating actual flowrate.

b) Determines flow limit on Attachment 4 is less than the Release Form limit.

• c) Adjusts 1-GW-FCV-101 to achieve a flowrate less than limit on Attachment 4.

COMMENTS:

STEP 14:

_ _ _ SAT

REPORT TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that WGDT is being released.

COMMENTS:

STOP TIME:

Page 8 of 11

Surry 2008-301 Release a Waste Gas Decay Tank

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Release a Waste Gas Decay Tank.

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 1 is at 100% power.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

Initiating Cues

• You are the Unit BOP Operator and I am the Nuclear Shift Manager.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

• The following are the results of the sample on "A" WGDT

Hydrogen Concentration 90%

Oxygen Concentration 1.1%

• Here's a copy of OP-23.2.3 - Release of Waste Gas Decay Tank 1A. I need you to initiate release of the "A"

WGDT in accordance with Section 5.3 and 5.4.

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

071A4.26 SR08301 9 of 10

Surry 2008-301 Release a Waste Gas Decay Tank

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Release a Waste Gas Decay Tank.

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 1 is at 100 % power.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

Initiating Cues

• You are the Unit BOP Operator and I am the Nuclear Shift Manager.

• 1-GW-TK-1A ("A" WGDT) has been sampled, analyzed and is ready for release.

• The following are the results of the sample on "A" WGDT

Hydrogen Concentration 900/0

Oxygen Concentration 1.1%

• Here's a copy of OP-23.2.3 - Release of Waste Gas Decay Tank 1A. I need you to initiate release of the "A"

WGDT in accordance with Section 5.3 and 5.4.

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

071A4.26 SR08301 10 of 10

Surry 2008-301 Respond to a Low Level Transient

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 075A2.02

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

RESPOND TO A LOW LEVEL TRANSIENT (CW)

KIA: 075A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the

circulating water system; and (b) based on those predictions, use procedures to correct, control, or

mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps (2.5/2.7)

Applicability Estimated Time Actual Time

RO/SRO(I) 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

• Both units are at 100% power when a lightning strike trips 2G screenwell transformer.

Standards

• Circ Water Pumps restored in accordance with AP-12.01, Loss of Intake Canal Level.

Initiating Cues

• LLIS TROUBLE annunciator.

• Unit Two Circ Water Pumps secured.

Terminating Cues

• 0-AP-12.01, Loss of Intake Canal Level, completed.

Procedures

• 0-AP-.12.01, Loss of Intake Canal Level.

Tools and Equipment Safety Considerations

• None * None

Page 1 of 13

Surry 2008-301 Respond to a Low Level Transient

Simulator Setup

• Call up 100% IC and initialize.

• Implement EL0802 and place simulator in RUN.

• Acknowledge all annunciators and place simulator in FREEZE.

Initiating Cues

• LLIS TROUBLE annunciator.

• Unit Two Circ Water Pumps secured.

Directions to the Applicant

• You .are the third license and I am the Unit One Unit Supervisor. Alarm VSP L-7 "LLIS TROUBLE" has alarmed

and security reports a lightning strike in the vicinity of the low level intake. All Unit 2 Circulating Water Pumps

were running.

• Unit One and Unit Two Reactor Operators are currently throttling CW MOVs to conserve intake canal level.

• Here's a copy of AP-12.01. You are to perform AP-12.01 in its entirety in response to the loss of 2G screenwell

transformer.

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

Page 2 of 13

Surry 2008-301 Respond to a Low Level Transient

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

_ _ _ SAT

CHECKS ENTRY INTO THIS PROCEDURE -FROM AN EOP OR AN AP TO RESTORE SW

FLOW TO THE CCHXs (Step 1) _ _ _ UNSAT

STANDARD:

Determines, based on initial conditions, that AP was entered due to loss of screenwell

transformer and goes to step 3..

EVALUATOR'S NOTE:

If asked: No actions have been taken in regard to CCHX SW flow.

COMMENTS:

Page 3 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 2:

_ _ _ SAT

TRIES TO MAINTAIN INTAKE CANAL LEVEL. (Step 3)

_ _ _ UNSAT

STANDARD:

a) Acknowledges CAUTION prior to step 3 regarding turbine stall flutter and reference to

AP-14, if vacuum cannot be maintained

b) Acknowledges note prior to step 3 regarding potential need to trip one unit to reduce

rate of intake canal drawdown.

c) Recalls that initial conditions revealed that Unit ROs were throttling waterboxes as

required.

EVALUATOR'S NOTE:

• If asked: Both units are currently throttling waterbox outlet MOVs as required due to

loss of circ water pumps.

• If asked: Unit SRO will direct unit ramping as required.

COMMENTS:

STEP 3:

_ _ _ SAT

CHECKS INTAKE CANAL LEVEL- DECREASING. (Step 4)

_ _ _ UNSAT

STANDARD:

a) Trainee identifies that 3 CW pumps are insufficient to supply two units CW flow

requirements.

b) Trainee reads intake canal level indicator and determines downward trend.

COMMENTS:

Page 4 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 4:

_ _ _ SAT

STARTS CIRC WATER PUMPS AS REQUIRED FROM THE MCR lAW ATTACHMENT 3.

(Step 5) _ _ _ UNSAT

STANDARD:

Trainee goes to attachment 3

COMMENTS:

Page 5 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 5:

_ _ _ SAT

ATTACHMENT 3- REMOTE START OF CIRCULATING WATER PUMPS. (Att 3 Step 1)

_ _ _ UNSAT

STANDARD:

a) Trainee acknowledges NOTE prior to step (a) that requires 5-minute coastdown of CW

pumps prior to starting.

b) Trainee verifies 1G-2G Bus Tie Bkr Closed using "LLIS Electrical" PCS screen.

c) Trainee verifies that CW pumps are not in local by noting no white box around Unit 2

CW pumps on CW Pump PCS screen.

• d) Trainee calls up soft control box pumps to start ew pump by clicking on ew

pump ICON on pes ew screen.

• e) Trainee enables soft control box for pump to be started by clicking on mark

number box and verifies red border.

• f) Trainee hits "Start" button for pump to control that is active.

g) Trainee verifies proper amp indication for pump started.

• h) Trainee completes steps (c) through (e) of attachment 3 for remaining pumps to

be started.

i) Trainee directs outside operator to perform post-start checks lAW respective OP

procedure.

EVALUATOR'S NOTE:

• If asked: Greater than 5 minutes have elapsed since loss of transformer.

• If asked: 2A, 2B, 2C and 2D circ water pumps were previously in service.

• *Only six Circulating Water Pumps running are required to meet critical task.

COMMENTS:

Page 6 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 6:

_ _ _ SAT

SENDS OPERATOR TO LOW LEVEL INTAKE TO PERFORM THE FOLLOWING

PROCEDURES. (Step 6) _ _ _ UNSAT

STANDARD:

a) Trainee acknowledges Note prior to step 6 regarding a key is required for entry into the

Low Level Switchgear Room and statement regarding CW pump restrictions when

1G-2G busses are crosstied.

b) Sends an Operator to Low Levels to perform Attachment 2 and OP-48.1.1.

c) May direct an operator to perform 0-OP-SW-002.

EVALUATOR'S NOTE:

• If asked: Operator is performing O-SW-OP-002.

COMMENTS:

STEP 7:

_ _ _ SAT

CHECKS INTAKE CANAL LEVEL - GREATER THAN TRIP SETPOINT. (Step 7)

_ _ _ UNSAT

STANDARD:

Trainee determines that Intake canal level is greater than 23.5 feet and annunciator F-G-1

not lit.

COMMENTS:

STEP 8:

_ _ _ SAT

CHECK CW LOSS - SUSTAINED WITH NO EXPECTATION OF RECOVERY

(Step 8) _ _ _ UNSAT

STANDARD:

Identifies that CW pumps have been restarted and canal level is recovering

RNO - Goes to Step 10

COMMENTS:

Page 7 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 9:

_ _ _ SAT

CONTINUES TO REDUCE UNIT LOAD AS NECESSARY TO MAINTAIN VACUUM.

(Step 10) _ _ _ UNSAT

STANDARD:

Trainee determines that no actions are required based on number of CW pumps running.

EVALUATOR'S NOTE:

• If asked: Both unit's Reactor Operators have stopped throttling CW MOVs.

COMMENTS:

STEP 10:

_ _ _ SAT

CHECKS INTAKE CANAL LEVEL - STABLE OR INCREASING. (Step 11)

_ _ _ UNSAT

STANDARD:

a) Trainee evaluates canal level indication and/or trend recorder to verify canal level

increasing.

b) Trainee then goes to Step 27.

COMMENTS:

STEP 11:

_ _ _ SAT

NOTIFIES THE FOLLOWING. (Step 27)

_ _ _ UNSAT

STANDARD:

Notifies plant personnel. (OMOC, Manager Nuc Ops, STA)

COMMENTS:

Page" 8 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 12:

_ _ _ SAT

VERIFIES INTAKE CANAL LEVEL- INCREASING. (Step 28)

_ _ _ UNSAT

STANDARD:

a) Trainee acknowledges note regarding minimum canal level for RS System.

b) Trainee evaluates canal level indication and/or trend recorder to verify canal level

increasing.

COMMENTS:

STEP 13:

_ _ _ SAT

CHECKS INTAKE CANAL LEVEL - GREATER THAN 17.2 FT. (Step 29)

_ _ _ UNSAT

STANDARD:

Trainee identifies canal level greater than 17.2 feet.

COMMENTS:

STEP 14:

_ _ _ SAT

THROTTLES OPEN CC HX SW OUTLET VALVES AS NECESSARY TO LOWER CC

TEMPERATURE. (Step 30) _ _ _ UNSAT

STANDARD:

a) Acknowledges note regarding restoration of CCHX SW flow.

c) Trainee recognizes that no throttling of CCHW SW flow was performed, so no actions

required on this step.

EVALUATOR'S NOTE:

• If asked: No actions were taken to reduce CCHX SW flow.

COMMENTS:

Page 9 of 13

Surry 2008-301 Respond to a Low Level Transient

STEP 15:

_ _ _ SAT

VERIFIES CAUSE OF LEVEL DECREASE - CORRECTED. (Step 31)

_ _ _ UNSAT

STANDARD:

Trainee identifies that restoration of CW pumps corrects cause of level decrease.

EVALUATOR'S NOTE:

• Trainee may direct troubleshooting to commence on 2G screenwell transformer, if

directed, state that control ops group will be notified.

COMMENTS:

STEP 16:

_ _ _ SAT

RESTOREs CW AND SW COMPONENTS (INCLUDING CW CHEMICAL INJECTION BY

OPENING 1-SA-285 AND 2-SA-274) TO SUPPORT PLANT CONDITIONS. (Step 32) _ _ _ UNSAT

STANDARD:

a) Trainee reports that CW MOVs may be returned to previous position.

b) Trainee recognizes that chemical injections systems require no action

COMMENTS:

STEP 16:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that he has completed AP-12.01 and restarted Unit 2 CW Pumps.

COMMENTS:

STOP TIME:

Page 10 of 13

Surry 2008-301- Respond to a Low Level Transient

Page 11 of 13

Surry 2008-301 Respond to a Low Level Transient

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Perform AP-12.01 in its entirety in response to the loss of 2G screenwell transformer.

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

• Both units are at 1000/0 power when a lightning strike trips 2G screenweHtransformer.

Initiating Cues

• You are the third license and I am the Unit One Unit Supervisor. Alarm VSP L-7 "LLIS TROUBLE" has alarmed

and security reports a lightning strike in the vicinity of the low level intake. All Unit 2 Circulating Water Pumps

were running.

• Unit One and Unit Two Reactor Operators are currently throttling CW MOVs to conserve intake canal level.

• Here's a copy of AP-12.01. You are to perform AP-12.01 in its entirety in response to the loss of 2G screenwell

transformer.

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

075A2.02 SR08301 12 of 13

Surry 2008-301 Respond to a Low Level Transient

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Perform AP-12.01 in its entirety in response to the loss of 2G screenwell transformer.

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

• Both units are at 100% power when a lightning strike trips 2G screenwell transformer.

Initiating Cues

• You are the third license and I am the Unit One Unit Supervisor. Alarm VSP L-7 "LLIS TROUBLE" has alarmed

and security reports a lightning strike in the vicinity of the low level intake. All Unit 2 Circulating Water Pumps

were running.

• Unit One and Unit Two Reactor Operators are currently throttling CW MOVs to conserve intake canal level.

• Here's a copy of AP-12.01. You are to perform AP-12.01 in its entirety in response to the loss of 2G screenwell

transform er.

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

075A2.02 SR08301 13 of 13

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure EPE038EA1.04

Applicant _ Start Time _

Examiner _

Date _ Stop Time ""'""""-- _

DEPRESSURIZE THE RCS TO MINIMIZE SGTR BREAKFLOW.

KIA: EPE038EA1.04 Ability to operate and monitor the following as they apply to a SGTR: PZR spray, to

reduce coolant system pressure (4.3/4.1)

Applicability Estimated Time Actual Time

RO 10 Minutes - To be validated

Conditions

• Task is to be PERFORMED in the simulator.

11

• A SGTR in 118 SG has been identified and isolated, SI has been blocked and the RCS cooled down to the target

temperature. 1-E-3 has been performed up to Step 19 and the team is ready to perform the RCS

depressurization to minimize SGTR breakflow.

Standards

• 1-E-3, Steam Generator Tube Rupture, Step 19.

Initiating Cues

11

• I am the Nuclear Shift Manager. We have a SGTR in the 118 SG. The SG has been identified and isolated, SI

has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to

perform the RCS depressurization to minimize the SGTR breakflow.

• Here's a copy of 1-E-3 Step 19; I want you to depressurize the RCS lAW Step 19.

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

Page 1 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Terminating Cues

• Report received that RCS cooldown (1-E-3 Step 19) completed.

Procedures

• 1-E-3, Steam Generator Tube Rupture.

Tools and Equipment Safety Considerations

• None * None

Page 2 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Simulator Setup

• Call up 100 % power IC and initialize.

• Enter malfunction for SGTR in "B" SG at -450 gpm (RC2402 @ 50% degradation).

• Call up the "BII Main Steam line & close 1-MS-120.

• Place sim in RUN, trip Unit, perform 1-E-0 and transition to 1-E-3. Perform 1-E-3 up to Step 19, (incl SI blocks).

RCPs should still be running & subcooling greater than 50°F. Throttle AFW flow to A & C SGs down to -175

gpm.

• Verify SR NIS detectors are energized and the SR scale is indicated on 1-NI-NR-A/B.

• Freeze simulator until ready for JPM performance.

Initiating Cues

• There is a SGTR in the "B" SG. The SG has been identified and isolated, SI has been blocked and the RCS

cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to perform the RCS

depressurization to minimize the SGTR breakflow.

Directions to the Applicant

II

• I am the Nuclear Shift Manager. We have a SGTR in the "B SG. The SG has been identified and isolated, SI

has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to

perform the RCS depressurization to minimize the SGTR breakflow.

• Here's a copy of 1-E-3 Step 19; I want you to depressurize the RCS lAW Step 19.

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

Page 3 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor/operator may be needed to operate the control boards for the examinee.

• START TIME:

STEP 1:

SAT

CHECKS NORMAL PRESSURIZER SPRAY AVAILABLE. (Step 19a)

UNSAT

STANDARD:

a) Checks RCP-C and 1-RC-PCV-1455B ('C' Spray Valve) - Both Available.

OR

b) RCPs A and B, AND 1-RC-PCV-1455A ('A' Spray Valve) - Both Available

COMMENTS:

STEP 2:

SAT

SPRAYS PRESSURIZER WITH MAXIMUM AVAILABLE SPRAY. (Step 19b)

UNSAT

STANDARD:

• a) Places PZR spray valve controllers (1-RC-PC-1444G and 1-RC-PC-1444H) in

MANUAL and increases valve demand to open both for maximum available

spray,

• • OR**

• b) Places PZR Master Controller (1-CH-PC-1444J) in MANUAL and increases

demand to open both spray valves for maximum available spray (keeps MC

demand < 750/0 to prevent PORV from opening).

NOTE - Performing either of the above actions satisfies the critical task.

COMMENTS:

Page 4 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

STEP 3:

_ _ _ SAT

DETERMINES IF SPRAY TERMINATION CRITERIA SATISFIED. (Step 19c)

_ _ _ UNSAT

STANDARD:

• a) Determines if PZR level is greater than 69% by observing 1-RC-LI-1459A,

1-RC-LI-1460 and/or 1-RC-LI-1461.

• b) Determines if RCS subcooling is less than 30°F by observing ICCM Train A

(1-RC-ICCM-A) and/or Train B (1.-RC-ICCM-B).

• c) Determines if:

1) RCS pressure is less than ruptured SG pressure by comparing RCS

pressure (1-RC-PI-1402-1, PI-1-402, 1-RC-ICCM-A and/or 1-RC-ICCM-B) to SG

pressure (1-MS-PI-1484, 1-MS-PI-1485 and/or 1-MS-PI-1486)

AND

2) PZR level is greater than 22% by observing 1-RC-LI-1459A, 1-RC-LI-1460

and/or

1-RC-LI-1461.

d) If none of these criteria are met, continues to spray the PZR until one of the three

criteria are met.

• e) When one of the criteria are met, proceeds to the next step.

COMMENTS:

Page 5 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

STEP 4:

SAT

CLOSES PZR NORMAL SPRAY VALVES. (Step 19d)

UNSAT

STANDARD:

• a) Decreases spray valve controllers (1-RC-PC-1444G and 1-RC-PC-1444H) demand

until both valves indicate closed (zero demand)

• • OR**

• b) Decreases PZR Master Controller (1-CH-PC-1444J) demand until any opened

spray valve indicates closed (zero demand).

COMMENTS:

STEPS:

SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

UNSAT

STANDARD:

Verbal status report made that RCS depressurization completed.

COMMENTS:

Page 6 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be performed in the simulator.

• Depressurize the RCS to minimize SGTR breakflow lAW 1-E-3 Step 19.

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 assiqned task.

Initial Conditions

• A SGTR in "8" SG has been identified and isolated, Sl has been blocked and the RCS cooled down to the target

temperature. 1-E-3 has been performed up to Step 19 and the team is ready to perform the RCS

depressurization to minimize SGTR breakflow.

Initiating Cues

11

• I am the Nuclear Shift Manager. We have a SGTR in the "8 SG. The SG has been identified and isolated, 81

has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to

perform the RCS depressurization to minimize the SGTR breakflow.

• Here's a copy of 1-E-3 Step 19; I want you to depressurize the RCS lAW Step 19.

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

EPE038EA1.04 SR08301 7 of 8

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be performed in the simulator.

• Depressurize the RCS to minimize SGTR breakflow lAW 1-E-3 Step 19.

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

II

A SGTR in IIB SG has been identified and isolated, SI has been blocked and the RCS cooled down to the target

temperature. 1-E-3 has been performed up to Step 19 and the team is ready to perform the RCS

depressurization to minimize SGTR breakflow.

Initiating Cues

• I am the Nuclear Shift Manager. We have a SGTR in the IIB II SG. The SG has been identified and isolated, SI

has been blocked and the RCS cooled down to the target temperature. We are at Step 19 of 1-E-3 and ready to

perform the ReS depressurization to minimize the SGTR breakflow.

• Here's a copy of 1-E-3 Step 19; 1want you to depressurize the RCS lAW Step 19.

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

EPE038EA1.04 SR08301 8 of 8

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 061A1.04

ALTERNATE PATH

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

ESTABLISH MAKEUP TO THE EMERGENCY CONDENSATE STORAGE TANK.

KIA: 061A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding limits)

associated with operating the AFW controls including: AFW source tank level (3.9/3.9)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 20 Minutes - To be validated

Conditions

• Task is to be SIMULATED in the plant beginning in Unit 2 Computer Room.

• A simulated loss of secondary heat sink is in progress. The ECST is below 20% level and it is desired to makeup

to the tank using 2-CN-150.

Standards

• 2-ES-3.1, Post-SGTR Cooldown using Backfill.

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 is currently experiencing a SGTR. The AFW pumps are aligned to the

ECST, which has gone below 20%.

• Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, FR-H.1, Attachment 4. I need you to locally

makeup to the Emergency Condensate Storage Tank from 2-CN-TK-2 using 2-CN-150.

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

061A1.04 SR08301 1 of 10

Terminating Cues

• Completion of 2-ES-3.1 Attachment 4 step 2g.

Procedures

• 2-ES-3.1, Post-SGTR Cooldown using Backfill.

Tools and Equipment Safety Considerations

• None * Standard Personal Safety Equipment

061A1.04 SR08301 2 of 10

Initiating Cues

• A simulated loss of secondary heat sink is in progress. The ECST is below 20% level and it is desired to makeup

to the tank using 2-CN-150.

Notes to the Evaluator.

• Task briefing should occur in the Unit 2 Computer Room.

• 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 denoted by an asterisk (*).

Directions to the Applicant

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

• I am the Nuclear Shift Manager. Unit 2 is currently experiencing a SGTR. The AFW pumps are aligned to the

ECST, which has gone below 200/0.

• Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, FR-H.1, Attachment 4. I need you to locally

makeup to the Emergency Condensate Storage Tank from 2-CN-TK-2 using 2-CN-150.

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

061A1.04 SR08301 3 of 10

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEP 1:

SAT

LOCALLY OPEN 2-CN-150. (Attachment 4, Step 1)

UNSAT

STANDARD:

a) Proceeds to Turbine Building basement and locates 2-CN-150 in South West corner.

b) Attempts to open 2-CN-150.

EVALUATOR'S NOTE:

a) When candidate attem pts to open 2-CN-150, report that the handwheel will not turn

regardless of how much force is used.

b) Direct candidate to fill the Emergency Condensate Storage Tank by Alignment of the

AFW Booster Pumps.

COMMENTS:

STEP 2:

SAT

VERIFY 2-CN-TK-3 LEVEL GREATER THAN 20%. (Attachment 4, Step 2a)

UNSAT

STANDARD:

Checks 2-CN-TK-3 level greater than 20% by either:

• requesting information from control room operator,

• reading MCR meter for 2-CN-TK-3 or

• checking TK-3 local meter.

EVALUATOR'S NOTE:

• If asked: Control room level indication reads 100 %.

• If asked: Local meter reads 17 feet 10 inches.

COMMENTS:

061A1.04 SR08301 4 of 10

STEP 3:

_ _ _ SAT

LOCALLY OPEN BOOSTER PUMP DISCHARGE ISOLATION TO AFW PUMPS.

(Attachment 4, Step 2b) _ _ _ UNSAT

STANDARD:

Proceeds to AFW pumps area and opens the following valves (by turning handwheel in the

counter-clockwise direction):

• a) 2-FW-283 (for FW-P-2),

• b) 2-FW-284 (for FW-P-3A),

• c) 2-FW-285 (for FW-P-3B),

EVALUATOR'S NOTE:

• If asked: All AFW pumps are available

• If asked: (Prior to opening) valve stem is down (- Y2 inch showing).

• If asked: (If properly operated) valve stem rises.

COMMENTS:

STEP 4:

_ _ _ SAT

LOCALLY VERIFY BOOSTER PUMP SUCTION VALVES OPEN. (Attachment 4, Step 2c)

_ _ _ UNSAT

STANDARD:

Proceeds to the basement of Safeguards, and

a) Verifies 2-FW-277 open (for FW-P-4A),

b) Verifies 2-FW-280 open (for FW-P-4B).

EVALUATOR'S NOTE:

• If asked: It is desired to start both Booster Pumps, 2-FW-P-4A and 2-FW-P-4B.

COMMENTS:

061A1.04 SR08301 5 of 10

STEPS:

_ _ _ SAT

LOCALLY OPEN BOOSTER PUMP DISCHARGE VALVES. (Attachment 4, Step 2d)

_ _ _ UNSAT

STANDARD:

a) Opens or verifies 2-FW-279 open (for FW-P-4A).

b) Opens or verifies 2-FW-282 open (for FW-P-4B).

COMMENTS:

STEP 6:

_ _ _ SAT

LOCALLY START THE ALIGNED BOOSTER PUMPS. (Attachment 4, Step 2e)

_ _ _ UNSAT

STANDARD:

• a) Starts FW-P-4A by taking control switch to START position.

• b) Starts FW-P-4B by taking control switch to START position.

EVALUATOR'S NOTE:

It is only necessary to start one of the two pumps to satisfy the critical component of this step.

• If asked: It is desired to start both Booster Pumps, 2-FW-P-4A and 2-FW-P-4B.

• Tell operator: (When pumps started,) pump running noise is heard.

• If asked: Booster pump disch pressures read -45#.

• If asked: When switch to START, green light goes out & red light on.

COMMENTS:

061A1.04 SR08301 6 of 10

STEP 7:

_ _ _ SAT

LOCALLY VERIFY AFW PUMP SUCTION PRESSURE AVAILABLE. (Attachment 4, Step 2f)

_ _ _ UNSAT

STANDARD:

Returns to AFW pump area and checks AFW pump suction pressure gauges to verify

pressure available:

a) 2-FW-PI-256A (for FW-P-2),

b) 2-FW-PI-256B (for FW-P-3A),

c) 2-FW-PI-256C (for FW-P-3B).

EVALUATOR'S NOTE:

• If asked: Point to 30 psi on the gauges.

COMMENTS:

STEP 8:

_ _ _ SAT

LOCALLY CLOSE THE NORMAL AFW PUMP SUCTION VALVES. (Attachment 4, Step 2g)

_ _ _ UNSAT

STANDARD:

Closes the normal AFW pump suction paths (by turning handwheels in the clockwise

direction):

• a) Closes 2-FW-153 (for FW-P-2).

• b) Closes 2-FW-168 (for FW-P-3A).

• c) Closes 2-FW-183 (for FW-P-3B).

EVALUATOR'S NOTE:

When the valves are operated properly, valve stem inserts until handwheel will not turn.

If asked (after the valves are closed), state that the AFW pumps are continuing to

operate normally.

COMMENTS:

061A1.04 SR08301 7 of 10

STEP 9:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that the ECST is being filled using the Booster Pumps.

COMMENTS:

STOP TIME:

061A1.04 SR08301 8 of 10

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be SIMULATED in the plant.

• Establish makeup to the Emergency Condensate Storage Tank.

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 simulated loss of secondary heat sink is in progress. The ECST is below 20% level and it is desired to makeup

to the tank using 2-CN-150.

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 is currently experiencing a SGTR. The AFW pumps are aligned to the

ECST, which has gone below 20%.

• Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, FR-H.1, Attachment 4. I need you to locally

makeup to the Emergency Condensate Storage Tank from 2-CN-TK-2 using 2-CN-150.

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

061A 1.04 SR08301 9 of 10

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be SIMULATED in the plant.

• Establish makeup to the Emergency Condensate Storage Tank.

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 simulated loss of secondary heat sink is in progress. The ECST is below 20% level and it is desired to makeup

to the tank using 2-CN-150.

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 is currently experiencing a SGTR. The AFW pumps are aligned to the

ECST, which has gone below 20%.

• Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, FR-H.1, Attachment 4. I need you to locally

makeup to the Emergency Condensate Storage Tank from 2-CN-TK-2 using 2-CN-150.

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

061A1.04 SR08301 10 of 10

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 064A4.01

ALTERNATE PATH

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

MANUALLY START AN EMERGENCY DIESEL GENERATOR AT THE LOCAL PANEL.

KIA: 064A4.01 Ability to manually operate and/or monitor in the Control Room: Local and remote operation of

the EDG. (4.0/4.3)

Applicability Estimated Time Actual Time

RO/SRO(I) 30 Minutes - To be* validated

Conditions

• Task is to be SIMULATED in the plant beginning in #1 ESGR at the Aux SID Panel.

• A Safe Shutdown Area fire has resulted in a loss of Offsite power, evacuation of the MCR to the ESGR, and

failure of #1 EDG to start.

Standards

• 0-FCA-12.00, Emergency Diesel Generator Operation.

Initiating Cues

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

• I am the Nuclear Shift Manager. We currently have a fire with a loss of offsite power. #1 EDG failed to autostart

and the MCR has been evacuated.

• Here is a copy of 0-FCA-12.00. I need you to manually start the #1 Emergency Diesel Generator at the local

panel. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is

loaded on the bus.

• Since I am going to accompany you, we won't be using radio headsets.

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

064A4.01 SR08301 1 of 16

Terminating Cues

• Report received that O-FCA-12.00, Step 31 completed.

Procedures

• O-FCA-12.00, Ernerqency Diesel Generator Operation.

Tools and Equipment Safety Considerations

• None * Standard Personal Safety Equipment

064A4.01 SR08301 2 of 16

Initiating Cues

• A Safe Shutdown Area fire has resulted in a loss of Offsite power, evacuation of the MCR to the ESGR, and

failure of #1 EDG to start.

Notes to the Evaluator.

• Task briefing should occur in the #1 ESGR at the Aux SID Panel.

• 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 denoted by an asterisk (*).

Directions to the Applicant

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

• I am the Nuclear Shift Manager. We currently have a fire with a loss of offsite power. #1 EDG failed to autostart

and the MCR has been evacuated.

• Here is a copy of O-FCA-12.00. I need you to manually start the #1 Emergency Diesel Generator at the local

panel. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is

loaded on the bus.

• Since I am going to accompany you, we won't be using radio headsets.

• Whe~ you finish the actions necessary to accomplish this, please inform me.

'B'Charging pump running

064A4.01 SR08301 3 of 16

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEP 1:

_ _ _ SAT

REVIEWS CAUTION AND NOTE PRIOR TO STEP 1. (Step 1 Cautions and Notes)

_ _ _ UNSAT

STANDARD:

Reads CAUTION statement covering portable radio and radio head set usage, and SPEED

DROOP control dial setting if paralleling EDG with the grid.

Reads the note about what will require the EM ERG GEN PUSH BUTTON RESET to be

rest.

COMMENTS:

STEP 2:

_ _ _ SAT

VERIFIES SWITCH POSITIONS AT THE #1 EDG ROOM DIESEL ISOL PANEL. (Step 1)

_ _ _ UNSAT

STANDARD:

Proceeds to #1 EDG room diesel isolation panel and verifies switches are in the desired

positions as follows:

(a) 15H8 sync switch - OFF

(b) 15H3 sync switch - OFF

(c) EDG isolation switch - OFF

(d) 15H8 normal feed control switch - AFTER CLOSE (red flag)

(e) 15H3 Emergency feed control switch - AFTER TRIP (green flag)

(f) IIH II Emergency Bus voltmeter switch - Any position other than OFF

(g) Fast start defeat switch - OFF

(h) Generator Field Flash switch - OFF

COMMENTS:

064A4.01 SR08301 4 of 16

STEP 3:

_ _ _ SAT

II

VERIFIES IIAUTO/LOCAL SELECTOR SWITCH ON ENGINE CONTROL CABINET IN

IIAUTOII. (Step 2) _ _ _ UNSAT

STANDARD:

Checks Engine Control Cabinet IIAUTO/LOCALII selector switch in the IIAUTOII position.

COMMENTS:

STEP 4:

_ _ _ SAT

OBTAINS DIP ISOLATION SWITCH KEY. (Step 3 Note)

_ _ _ UNSAT

STANDARD:

a) Reads NOTE prior to step 3 concerning EDG isolation lockout relays and which control

and indication functions are transferred to the local EDG panel.

b) Locates storage box on wall (on left behind DIP).

c) Breaks storage box front glass or break-away lock.

d) Obtains the DIP isolation switch key.

COMMENTS:

064A4.01 SR08301 5 of 16

STEP 5:

_ _ _ SAT

TRANSFERS EDG TO LOCAL CONTROL. (Step 3)

_ _ _ UNSAT

STANDARD:

• a) Inserts key into Isolation Switch.

• b) Rotates switch to the ON position.

c) Verifies all three isolation lockout relays - red trip light off and they rotate approximately

45°.

EVALUATOR'S NOTE:

• If asked: All isolation relays move 45° and red trip lights out.

COMMENTS:

STEP 6:

_ _ _ SAT

CHECK CHARGING PUMPS - AT LEAST ON RUNNING (Step 4)

_ _ _ UNSAT

STANDARD:

a) Reads CAUTION about Seal Injection being lost and seal isolation

b) Determines '8' Charging pump is running by asking Shift Manager.

EVALUATOR'S NOTE:

• If asked: '8' Charging pump is running on Unit 1

COMMENTS:

064A4.01 SR08301 6 of 16

STEP 7:

SAT

CHECKS OFF-SITE POWER AVAILABLE. (Step 5)

UNSAT

STANDARD:

a) Recalls from initial conditions that a loss of off-site power has occurred, (OR),

b) Asks Nuclear Shift Manager for status of off-site power.

c) Step 5 RNO directs operator to Step 8.

EVALUATOR'S NOTE:

• If asked: Off-site power is not available.

COMMENTS:

STEP 8:

SAT

VERIFIES THAT #1 EDG HAS FAILED TO AUTO START. GOES TO STEP 22 OF

0-FCA-12.00. (Step 8) UNSAT

STANDARD:

a) No RPM indicated.

b) No engine or start noise heard.

c) RNO Step 7 directs operator to Step 22.

EVALUATOR'S NOTE:

• If asked: Point to an RPM indication of zero (0) and no change in room noise level.

COMMENTS:

064A4.01 SR08301 7 of 16

STEP 9:

_ _ _ SAT

OBSERVES NOTES PRIOR TO STEP 22. (Step 22 Notes)

_ _ _ UNSAT

STANDARD:

a) Observes NOTE that if EDG has failed to start after three auto-start attempts, a start

failure alarm will occur. It should be investigated and reset.

b) Observes NOTE that an overspeed condition will immediately shutdown the EDG and

lockout the EDG until reset.

c) Observes NOTE for which signals will place the EDG into the cooldown cycle.

d) Observes NOTE that the operator should check the EDG Annunciator Panel to aid in

determining cause of EDG failures.

EVALUATOR'S NOTE:

• If asked: No annunciators are lit that would indicate the cause of the EDG failing to

start.

COMMENTS:

STEP 10:

_ _ _ SAT

VERIFIES THE EDG DIFFERENTIAL LOCKOUT RELAY IS NOT TRIPPED. (Step 22)

_ _ _ UNSAT

STANDARD:

Checks EDG differential lockout relay. Notes that the black flag is indicated and red light is

on.

EVALUATOR'S NOTE:

• If asked: Black flag is indicated on differential lockout relay.

• If asked: Red light is on for differential lockout relay.

COMMENTS:

064A4.01 SR08301 8 of 16

STEP 11:

_ _ _ SAT

LOCALLY VERIFIES EDG OVERCURRENT NOT PRESENT. (Step 23)

_ _ _ UNSAT

STANDARD:

a) Proceeds to breaker 15H3.

b) Verifies no orange flag drops on 15H3.

EVALUATOR'S NOTE:

• If asked: No orange flag drops exist on 15H3.

COMMENTS:

STEP 12:

_ _ _ SAT

LOCALLY VERIFY EMER GEN # 1 PUSH BUnON RESET - RESET (AUX TRIP RELAY).

(Step 24) _ _ _ UNSAT

STANDARD:

a) Proceeds to #1 EDG-DIP in #1 ESGR.

b) Pushes EMERG GEN #1 PUSH BUTTON RESET.

c) Verifies amber light for Auto Start Disabled is off.

EVALUATOR'S NOTE:

• If asked: Amber light for Auto Start Disabled is off.

COMMENTS:

064A4.01 SR08301 9 of 16

STEP 13:

SAT

VERIFIES BREAKER POSITIONS AT REMOTE EXCITATION CABINET. (Step 25)

UNSAT

STANDARD:

Proceed to remote excitation cabinet and verify following breakers closed:

a) CB alarm

b) CB start 1

c) CB start 2

d) AC control

e) DC control

EVALUATOR'S NOTE:

• If asked: Indicate that all breakers are closed .

COMMENTS:

STEP 14:

SAT

CHECKS EDG BATTERY VOLTAGE NORMAL. (Step 26)

UNSAT

STANDARD:

Observe battery voltage on EDG battery charger meter between 120 - 124 volts.

EVALUATOR'S NOTE:

• If asked: Point to a battery voltage indication of 122 volts.

COMMENTS:

064A4.01 SR08301 10 of 16

STEP 15:

_ _ _ SAT

VERIFIES STARTING AIR AVAILABLE. (Step 27)

_ _ _ UNSAT

STANDARD:

a) Observes NOTE that lister diesel may be operated to provide starting air.

b) Check all six air bottle stop valves - open.

c) Verify pressure in both banks greater than 175 PSIG at Engine Control Cabinet (ECC).

EVALUATOR'S NOTE:

• If asked: All six air bottle stop valves are in line with piping.

• If asked: Point to an air pressure in both banks of 185 PSIG at ECC.

COMMENTS:

STEP 16:

_ _ _ SAT

CHECKS ENGINE BASE TANK LEVEL GREATER THAN OR EQUAL TO 100 GALLONS.

(Step 28) _ _ _ UNSAT

STANDARD:

Verify engine base tank greater than 100 gallons by observing level gauge (below lube oil

eire. pump motor on base plate).

EVALUATOR'S NOTE:

• If asked: Point to an engine base tank level of ,. . 3/4 full.

COMMENTS:

064A4.01 SR08301 11 of 16

STEP 17:

SAT

CHECKS ELECTRIC FUEL PUMP - RUNNING. (Step 29)

UNSAT

STANDARD:

a) Observes NOTE about using fuel prime button when starting EDG if electric fuel oil

pump not running prior to pushing fuel prime pushbutton.

b) Observe Fuel System 1 filter inlet pressure < 10 PSIG at ECC.

• c) Push the fuel prime pushbutton and verify FO pressure indicates> 10 PSIG.

EVALUATOR'S NOTE:

• If asked: Point to a fuel system 1 filter pressure of zero (0) PSIG.

• If asked: After fuel prime pushbutton pushed, point to a fuel system 1 filter pressure of

15 PSIG.

COMMENTS:

STEP 18:

SAT

PREPARES FOR LOCAL START AT THE ENGINE CONTROL CABINET. (Step 30)

UNSAT

STANDARD:

a) Places the AUTO/LOCAL selector switch to the LOCAL position.

b) Verifies NO FIELD alarm is clear.

c) Positions personnel to observe the exhaust from air start motors.

EVALUATOR'S NOTE:

• If asked: NO FIELD alarm is clear .

• If asked personnel are stationed to observe air start motor exhaust.

COMMENTS:

064A4.01 SR08301 12 of 16

STEP 19:

_ _ _ SAT

DEPRESSES START PUSHBUTTON. (Step 31a)

_ _ _ UNSAT

STANDARD:

a) Reads CAUTION that personnel in the EDG Room should be wearing hearing

protection.

b) Reads NOTE that a local EDG start will cause both start circuits to actuate

sim ultaneously.

• c) Momentarily depresses the ENGINE START pushbutton on ECC.

EVALUATOR'S NOTE:

• Tell operator: Engine starter noise heard followed by engine running noise.

COMMENTS:

STEP 20:

_ _ _ SAT

ADJUSTS ENGINE SPEED TO 900 RPM. (Step 31b)

_ _ _ UNSAT

STANDARD:

a) Checks EDG RPM meter.

b) Takes governor control to RAISE and brings engine speed to 900 RPM.

EVALUATOR'S NOTE:

• If asked prior to adjusting governor control: Point to an engine speed of 850 RPM.

• If asked after adjusting governor control: Point to an engine speed of 900 RPM.

COMMENTS:

064A4.01 SR08301 13 of 16

STEP 21:

_ _ _ SAT

VERIFIES EDG OUTPUT BREAKER CLOSED. (Step 31d)

_ _ _ UNSAT

STANDARD:

a) Checks EDG output breaker (15H3) is closed by noting red light on, green light off and

4300 volts on ItH It bus.

EVALUATOR'S NOTE:

• If asked: Breaker 15H3 indication shows red light on and green light off.

It

• If asked: ItH bus voltage indicates 4300 volts.

COMMENTS:

STEP 22:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that #1 EDG started and loaded on the bus.

COMMENTS:

STOP TIME:

064A4.01 SR08301 14 of 16

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be SIMULATED in the plant.

• Manually start the #1 Emergency Diesel Generator at the local panel.

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 Safe Shutdown Area fire has resulted in a loss of Offsite power, evacuation of the MCR to the ESGR, and

failure of #1 EDG to start.

Initiating Cues

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

• I am the Nuclear Shift Manager. We currently have a fire with a loss of offsite power. #1 EDG failed to autostart

and the MCR has been evacuated.

• Here is a copy of O-FCA-12.00. I need you to manually start the #1 Emergency Diesel Generator at the local

panel. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is

loaded on the bus.

• Since I am going to accompany you, we won't be using radio headsets.

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

064A4.01 SR08301 15 of 16

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be SIMULATED in the plant.

• Manually start the #1 Emergency Diesel Generator at the local panel.

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 Safe Shutdown Area fire has resulted in a loss of Offsite power, evacuation of the MCR to the ESGR, and

failure of #1 EDG to start.

Initiating Cues

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

• I am the Nuclear Shift Manager. We currently have a fire with a loss of offsite power. #1 EDG failed to autostart

and the MCR has been evacuated. .

• Here is a copy of O-FCA-12.00. I need you to manually start the #1 Emergency Diesel Generator at the local

panel. The Service Bldg operator will close the stub bus breaker and complete the procedure once the EDG is

loaded on the bus.

• Since I am going to accompany you, we won't be using radio headsets.

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

064A4.01 SR08301 16 of 16

Surry 2008-301 Establish HI/LO Interface Integrity

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure APE068.AA1.21

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

LOCALLY ESTABLISH RCS AND SG HIILO INTERFACE INTEGRITY.

KIA: APE068.AA1.21 Ability to operate and/or monitor the following as they apply to the Control Room

Evacuation: Transfer of controls from control room to shutdown panel or local control (3.9/4.1)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 5 Minutes - To be validated

Conditions

• Task is to be SIMULATED in the plant.

• A limiting MCR fire has occurred and forced MCR evacuation. 0-FCA-1.00 is in progress at step 4.

Standards

• FCA-1.00, Limiting MCR Fire, Attachment 1.

Initiating Cues

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

• I am the Shift Manager. A fire has forced evacuation of the control room.

• Here is Attachment 1 of FCA-1.00. I need you to locally establish RCS & SG HI/LO interface integrity for Unit 1

only lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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

Page 1 of 8

Surry 2008-301 Establish HI/LO Interface Integrity

Terminating Cues

• Locally establish RCS & SG HI/LO interface integrity for Unit 1 lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

Procedures

• FCA-1.00, Limiting MCR Fire, Attachment 1.

Tools and Equipment Safety Considerations

• None * Standard Personal Safety Equipment

Page 2 of 8

Surry 2008-301 Establish HI/La Interface Integrity

Initiating Cues

• A limiting MCR fire has occurred and forced MCR evacuation. 0-FCA-1.00 is in progress at step 4.

Notes to the Evaluator.

• Task briefing should occur in the Unit 2 Computer Room.

• 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 denoted by an asterisk (*).

Directions to the Applicant

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

• I am the Shift Manager. A fire has forced evacuation of the control room.

• Here is Attachment 1 of FCA-1.00. I need you to locally establish RCS & SG HI/La interface integrity for Unit 1

only lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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

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Surry 2008-301 Establish HI/LO Interface Integrity

PERFORMANCE CHECKLIST

Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• START TIME:

STEP 1:

_ _ _ SAT

OPEN UNIT 1 AUXILIARY SHUTDOWN PANEL DOOR. (Attachment 1 Step 4)

_ _ _ UNSAT

STANDARD:

a) Proceeds to Unit 1 Emergency Switchgear Room and goes to the Auxiliary Shutdown

Panel (ASDP).

b) Obtains Key to unlock door of ASDP from box on the panel, unlocks and opens the

door.

(SIMULATES unlocking and opening door)

EVALUATOR'S NOTE:

• DO NOT allow candidate to unlock ASDP door - Simulate Only

COMMENTS:

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Surry 2008-301 Establish HI/LO Interface Integrity

STEP 2:

_ _ _ SAT

ESTABLISH RCS AND SG HIGH/LOW INTERFACE INTEGRITY ON UNIT 1.

(Attachment 1 Step 5) _ _ _ UNSAT

STANDARD:

a) Acknowledges NOTE concerning primary and secondary high/low pressure boundary

valve operation under SS direction after evaluation of system integrity.

b) Acknowledges NOTE that 1-CH-LCV-1460A will require a CTMT entry or MCR access

to be operated after isolation.

• c) Places the following HI/LO control switches to the DISABLE position:

• 1-RC-SOV-100A-1/2 and RC-SOV-101A-1/2, Reactor/PRZR Vent Valves.

• 1-RC-PCV-1455C, PRZR PORV.

• 1-CH-LCV-1460A, Letdown Line Isolation.

• 1-RC-SOV-100B-1/2 and RC-SOV-101B-1/2, Reactor/PRZR Vent Valves.

• 1-RC-PCV-1456, PRZR PORV.

• 1-CH-HCV-1137, Excess Letdown Flow.

EVALUATOR'S NOTE:

• DO NOT allow candidate to manipulate any controls - Simulate Only.

COMMENTS:

STEP 3:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that you have completed locally establishing RCS & SG HI/LO

interface integrity for Unit 1 only lAW steps 4 and 5 of Attachment 1 of FCA-1.00

COMMENTS:

STOP TIME:

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Surry 2008-301 Establish HI/LO Interface Integrity

Page 6 of 8

Surry 2008-301 Establish HI/LO Interface Integrity

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

• Task is to be SIMULATED in the plant.

• Locally establish RCS & SG HI/LO interface integrity for Unit 1 lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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 limiting MCR fire has occurred and forced MCR evacuation. 0-FCA-1.00 is in progress at step 4.

Initiating Cues

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

• I am the Shift Manager. A fire has forced evacuation of the control room.

• Here is Attachment 1 of FCA-1.00. I need you to locally establish RCS & SG HI/LO interface integrity for Unit 1

only lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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

APE068.AA1.21 SR08301 7 of 8

Surry 2008-301 Establish HI/LO Interface Integrity

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

• Task is to be SIMULATED in the plant.

• Locally establish RCS & SG HI/LO interface integrity for Unit 1 lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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 limiting MCR fire has occurred and forced MCR evacuation. 0-FCA-1.00 is in progress at step 4.

Initiating Cues

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

• I am the Shift Manager. A fire has forced evacuation of the control room.

• Here is Attachment 1 of FCA-1.00. I need you to locally establish RCS & SG HI/LO interface integrity for Unit 1

only lAW steps 4 and 5 of Attachment 1 of FCA-1.00.

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

APE068.AA1.21 SR08301 8 of 8