Text

Feb-March Exam 05000280/2008301 Draft JPMs
	ML081260327
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: ML081260327 (265)
	v • d • e

Draft Submittal

(Pink Paper)

1. / ADMINISTRATIVE TOPICS OUTLINE (ES-301-1)

2. / CONTROL ROOM SYSTEMS & FACILITY WALK-THROUGH

TEST OUTLINE (ES-301-2)

3. ~ ADMINISTRATIVE JPMS

4. 1N-PLANT JPMS

5. /CONTROL ROOM JPMS (SIMULATOR JPMS)

S ueJLy c2 {)tJg- ~I

DeAFT

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Surry Date of Examination: March 2008

Examination Level: RO 0' SRO D Operating Test Number: 2008-301

Administrative Topic Type Describe activity to be performed

(see Note) Code*

Conduct of Operations

Conduct of Operations Title: Perform a Quadrant Power Tilt Ratio calculation (QPTR).

N,R

G2.1.7 (3.7/4.4) Description: Given plant conditions determine the QPTR in

accordance with QPTR worksheet.

Title: Perform Measurement of Macrofouling Blockage of

Equipment Control Component Cooling Heat Exchanger (CCHX) 1CC-E-1A

N,R Surveillance (RO only)

G2.2.12 (3.0/3.4) Description: Determine status of the CCHX given plant data and

associated graphs from 1-0SP-SW-002 to include completion of

procedure acceptance criteria and follow-on tasks.

Title: Calculate radiation exposure when performing task in

Radiation Control

containment (varying fields and use of personnel)

M,R

Description: Job to be performed in CTMT. Select number of

G2.3.2 (2.5/2.9) personnel to perform the job in accordance with ALARA practices

and determine the expected dose.

Title: Complete Report of Emergency to State and Local

Emergency Plan

Governments (RO only).

D,S

Description: Complete report per EPIP-2.01, Notification of State and

G2.4.43 (2.8/3.5) Local Governments (Met data and stability class determination

required).

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking

only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator or Class(R)oom

(D)irect from bank (3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (1)

(P)revious 2 exams (1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Surry Date of Examination: March 2008

Examination Level: RO D SRo0 Operating Test Number: 2008-301

Administrative Topic Type Describe activity to be performed

(see Note) Code*

Conduct of Operations Title: Evaluate Overtime Eligiblity. (SRO only)

M,R

G2.1.5 (2.3/3.4) Description: Given various Operator hours of work for previous

week, determine which operator is eligible to perform overtime.

Conduct of Operations Title: Perform a Quadrant Power Tilt Ratio calculation (QPTR).

N,R

G2.1.7 (3.7/4.4) Description: Given plant conditions determine the QPTR in

accordance with QPTR worksheet.

Title: Perform a review of a performance test to verify operability of

Equipment Control associated components. (SRO only)

N,R

G2.2.12 (3.0/3.4) Description: Review I-OPT-CS-006 (RWST Chemical Addition

Tank and Containment Spray System MOV Stroke Test) for

accuracy.

Title: Calculate radiation exposure when performing task in

Radiation Control

containment (varying fields and use of personnel)

M,R

Description: Job to be performed in CTMT. Select number of

G2.3.2 (2.5/2.9) personnel to perform the job in accordance with ALARA practices

and determine the expected dose.

Emergency Plan Title: Classify an event in accordance with EPIP-l.0 1 (SRO only).

M,S

G2.4.41 (2.3/4.1) Description: Facility JPM 88.05. Modified such that EPIP-l.0l will

be performed with requested approval of faulted EPIP-2.0 1 form.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking

only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator or Class(R)oom

(D)irect from bank (3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (1)

(P)revious 2 exams (1; randomly selected)

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) 15 Minutes

Conditions

Task is to be PERFORMED in the classroom.

Standards

Correctly calculates Quadrant Power Tilt for given core conditions on the Radial Tilt Calculation Worksheet. This

Worksheet constitutes the approved procedure for this task.

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 1000/0 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.

The Shift Manager directs you to perform the Quadrant Power Tilt Calculation on the attached "Radial Tilt

Calculation Worksheef'.

The Shift Manager directs you to perform these calculations to 4 significant digits.

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 11-9.4

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: 1.02 to 1.023 or 2.00/0 to 2.30/0 acceptable.

COMMENTS:

STOP TIME:

Page 5 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

Radial Tilt Calculation Worksheet

Unit

U er Flux Channels ANSWER KEY

Time Data NI-41 NI-42 NI-43 NI-44 Average NI Peak Radial Tilt

41+42+43+44 NI-_42_ PEAK

4 AVERAGE

Actual 109.8 123.4 100.2 117.8

Normalized 111.0 123.8 101.4 119.5

Actual-Normalized .9892 .9968 .9882 .9895

Actual

Normalized

Actual-Normalized

Actual

Normalized

Actual-Normalized

Lower Flux Channels

Time Data NI-41 NI-42 NI-43 NI-44 Average NI Peak Radial Tilt

41+42+43+44 NI-_42- PEAK

4 AVERAGE

Actual 122.4 119.4 118.3 122.0

Normalized 117.8 112.7 115.0 119.8

Actual-Normalized 1.0390 1.0595 1.0287 1.0184

Actual

Normalized

Actual-Normalized

Actual

Normalized

Actual-Normallzed

Page 6 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.

The Shift Manager directs you to perform the Quadrant Power Tilt Calculation on the attached "Radial Tilt

Calculation Worksheet".

The Shift Manager directs you to perform these calculations to 4 significant digits.

Also provided is a copy of the Power Range Currents from the NIS Data Book providing the 100% Normalized

Values.

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 9

Surry 2008-301 Quadrant Power Tilt Calculation

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 was at 1000/0 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.

The Shift Manager directs you to perform the Quadrant Power Tilt Calculation on the attached "Radial Tilt

Calculation Worksheef'.

The Shift Manager directs you to perform these calculations to 4 significant digits.

Also provided is a copy of the Power Range Currents from the NIS Data Book providing the 100% Normalized

Values.

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 8 of 9

Surry 2008-301 Quadrant Power Tilt Calculation

N41 N42 N43 N44

DATE %

Upper Lower Upper Lower Upper Lower Upper Lower

Channel Channel Channel Channel Channel Channel Channel Channel

02/07 100 111.0 117.8 123.8 112.7 101.4 115.0 119.5 119.8

2008

02/07 120 136.2 148.4 145.7 138.6 130.5 135.6 140.2 141.4

2008

100

120

100

120

100

120

100

120

100

120

G2.1.7 SR08301 9 of 9

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) 20 Minutes

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 lAW

VPAP-0103, Working Hours and Limitations (REV 9).

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.

A copy of VPAP-0103 is available for use during this JPM.

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 10

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.

Attached 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

All operators began their shift at the same time each day. (Day Shift)

The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

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, VPAP-0103 - Working Hours and Limitations, should be distributed to the applicant with

the directions.

Work History

8

Day 1 2 3 4 5 6 7

(Today)

Operator

12 0 12 12 12 12 8 14

1

Operator

0 12 12 12 12 12 0 12

2

Operator

0 12 12 12 0 0 12 12

3

Operator

12 0 12 12 12 12 0 13

4

Operator

12 12 12 12 0 0 0 15

5

Operator

0 12 12 12 12 8 8 8

6

Page 2 of 10

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.

COMMENTS:

STEPS CAN BE PERFORMED 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , but not exceed it. Day 7 and 8 will reach 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but not exceed it. Day

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

COMMENTS:

Page 3 of 10

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7-day period. The additional two hours would yield 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period. The additional two hours would yield 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months

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

COMMENTS:

Page 4 of 10

Surry 2008-301 Evaluate Overtime Eligibility

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 5: DETERMINES THE ELIGffiILITY 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 ELIGffiILITY 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 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period. The additional two hours would yield 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months in a 24

hour period, which would require management approval.

COMMENTS:

STEPS CAN BE PERFORMED IN ANY ORDER

_ _ _ SAT

STEP 7: DETERMINES THE ELIGffiILITY 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7-day period. The additional two hours would yield 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months in a

7-day period, whicli would require management approval.

COMMENTS:

Page 5 of 10

Surry 2008-301 Evaluate Overtime Eligibility

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

STANDARD: _ _ UNSAT

Applicant reports that Operators 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 10

Surry 2008-301 Evaluate Overtime Eligibility

ANSWER KEY

Work History

8

Day 1 2 3 4 5 6 7

(Today)

Operator

12 0 12 12 12 12 8 14

1

Operator

0 12 12 12 12 12 0 12

2

Operator

0 12 12 12 0 0 12 12

3

Operator

12 0 12 12 12 12 0 13

4

Operator

12 12 12 12 0 0 0 15

5

Operator

0 12 12 12 12 8 8 8

6

ALL BLOCKS OF THIS TABLE ARE CRITICAL STEPS

Eligible for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of Reason, if any, for NOT being eligible for overtime without prior

additional overtime management approval.

without management

approval?

Operator #1 *Yes

Operator #2 *No *Exceeds 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 day period

Operator #3 *No *Exceeds 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period

Operator #4 *Yes

Operator #5 *No *Exceeds 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

Operator #6 *No *Exceeds 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 day period

Page 7 of 10

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.

Attached 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

All operators began their shift at the same time each day. (Day Shift)

The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

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 10

Surry 2008-301 Evaluate Overtime Eligibility

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

Initial Conditions:

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

Attached 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

All operators began their shift at the same time each day. (Day Shift).

The computer program for calculating overtime eligibility is not available.

Initiating Cues

You have been directed to:

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 9 of 10

Surry 2008-301 Evaluate Overtime Eligibility

(TO BE GIVEN TO APPLICANT)

Work History

8

Day 1 2 3 4 5 6 7

(Today)

Operator

12 0 12 12 12 12 8 14

1

Operator

0 12 12 12 12 12 0 12

2

Operator

0 12 12 12 0 0 12 12

3

Operator

12 0 12 12 12 12 0 13

4

Operator

12 12 12 12 0 0 0 15

5

Operator

0 12 12 12 12 8 8 8

6

Eligible for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of Reason, if any, for NOT being eligible for overtime without prior

additional overtime management approval.

without management

approval?

Operator #1

Operator #2

Operator #3

Operator #4

Operator #5

Operator #6

G2.1.5 SR08301 10 of 10

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

Conditions

Task is to be PERFORMED in the classroom.

Standards

Completes 1-0SP-SW-002 (REV 18), Measurement of Macrofouling Blockage of Component Cooling Heat

Exchanger, 1-CC-E-1 A, 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-1 A), I need you to complete the procedure and turn it in to 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.

G2.2.12 SR08301 1 of 13

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

G2.2.12 SR08301 2 of 13

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 3 of 13

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 1-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.

EV ALUATOR 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:

G2.2.12 SR08301 4 of 13

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 per~ssion 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.

EVALUATOR NOTES:

If asked: HP was notified about SW valve manipulations.

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

COMMENTS:

G2.2.12 SR08301 5 of 13

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.

EV ALUATOR 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:

G2.2.12 SR08301 6 of 13

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 OF).

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:

G2.2.12 SR08301 7 of 13

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:

G2.2.12 SR08301 8 of 13

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 CUE:

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

complete Steps 7.2.3. Please continue with Step 7.2.4.

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:

G2.2.12 SR08301 9 of 13

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:

G2.2.12 SR08301 10 of 13

ANSWER KEY

'1*2::0

.f~~ n]:u:~'~~ D::eilt.a-P (i:f1.:c,h:e5 '~falter)

G2.2.12 SR08301 11 of 13

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-1 A), 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

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

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

PROCEDURE NO:

1-0SP-SW-002

REVISION NO:

SURRY POWER STATION 18

PROCEDURE TYPE: UNIT NO:

OPERATIONS SURVEILLANCE PROCEDURE 1

PROCEDURE TITLE:

MEASUREMENT OF MACROFOULING BLOCKAGE OF

COMPONENT COOLING HEAT EXCHANGER 1CC-E-1A

PMT LR

REVISION SUMMARY:

Made the following changes in response to PI S-2006-1372.

Added Commitment Document 2.4.5 on Page 4.

Revised Step 6.2.2 on Page 7.

Revised Note and Step 6.2.15 on Page 10.

Revised Step 6.2.17 on Page 11.

Revised Step 7.2.2 on Page 12.

Revised Step 7.2.3 on Page 13.

Added noun name for I-SW-39 in Step 6.2.2 on Page 7.

ON

Dominion 1-0SP-SW-002

Surry Power Station Revision 18

Page 2 of 21

TABLE OF CONTENTS

Section Page

1.0 PURPOSE 3

2.0 REFERENCES 3

3.0 INITIAL CONDITIONS 5

4.0 PRECAUTIONS AND LIMITATIONS 5

5.0 SPECIAL TOOLS AND EQUIPMENT 5

6.0 INSTRUCTIONS 6

6.1 Work Preparation 6

6.2 Measuring CC HX Flow 7

7.0 FOLLOW-ON 12

ATTACHMENTS

l-CC-E-1 A Macrofouling Data Sheet 15

2 l-CC-E-IA Operability Limits 16

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1.0 PURPOSE

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

Component Cooling Heat Exchanger I-CC-E-IA, and to use the flow readings

obtained to determine operability of the heat exchanger with respect to the amount

of tubesheet macro fouling. Determining the extent of tubesheet macrofouling

provides an aging management basis for License Renewal. (Ref. 2.4.4)

2.0 REFERENCES

2.1 Source Documents

2.1.1 EWR 89-152, Installation ofpermanent annubar

2.1.2 UFSAR 9.9,9.4,10.3

2.2 Technical Specifications - Surry Power Station Unit 1 and 2

2.2.1 Technical Specification Sections 3.13 and 3.14

2.3 Technical References

2.3.1 11448-FM-71A, Sheets 1 and 4

2.3.2 PES Calculation ME-028 1, RO

2.3.3 DCP 01-008, Instrument and Controls Upgrade Project, Unit I

2.3.4 ER-AA-AMP-101, Implementation of Activities Performed by License

Renewal Aging Management Coordinators

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Surry Power Station Revision 18

Page 4 of 21

2.4 Commitment Documents

2.4.1 CTS 89-1365-001

2.4.2 PI S-2001-0044

2.4.3 PI S-2004-0011, CC Temperature Change Effect on IX Train

2.4.4 NUREG-1766, Safety Evaluation Report Related to the License Renewal

of North Anna Power Station Units 1 and 2, and Surry Power Station

Units 1 and 2, January 28, 2003.

2.4.5 PI S-2006-1372, An extended duration flush is required when the CCHX

SW discharge valve is less than 1/3 open.

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Surry Power Station Revision 18

Page 5 of 21

Init Verif

3.0 INITIAL CONDITIONS

3.1 Shift Supervision has granted permission to perform this test.

4.0 PRECAUTIONS AND LIMITATIONS

4.1 Notify Health Physics prior to opening any SW instrument drain valves.

4.2 In order to limit undesired increases in CC temperature, isolation of SW flow

through a CC Heat Exchanger shall be minimized.

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.

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.

4.5 The amount of SW that is drained to the trough surrounding the CC HXs

shall be minimized.

5.0 SPECIAL TOOLS AND EQUIPMENT

None

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Surry Power Station Revision 18

Page 6 of 21

Init Verif

6.0 INSTRUCTIONS

6.1 Work Preparation

6.1.1 Personnel participating in this procedure shall initial, sign, and print name

in the space provided in Subsection 7.2.

6.1.2 IF test is performed to prove operability following maintenance, THEN

record Work Order Number and Mark Number. Otherwise, enter N/A.

WO Number: ,A,lA

Mark Number: dA

6.1.3 Verify open 1-CC-587, HX IB Outlet Valve (Component Cooling).

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Surry Power Station Revision 18

Page 7 of 21

6.2 Measuring CC HX Flow

6.2.1 IF desired for fine control of Component Cooling temperature,

THEN close l-CC-583, HX lA Outlet Valve (Component Cooling).

Otherwise, enter N/A.

6.2.2 Close 1-SW-39, CC HX A SW Outlet, and record numberoftums to

full closed. IF valve is found in the full open position, THEN enter

FULL OPEN. IF valve is found in the full closed position, THEN

enter FULL CLOSED.

J--J turns

As found less than or equal to 1/3 open. yes I~ (Circle one.)

6.2.3 Bleed entrapped air from 1-SW-FI-150A low side instrument line.

a. Open 1-SW-953, 1-SW-FI-150A Equalizer.

b. Open 1-SW-815, CC HX A SW Inlet FI-150A (L) IsoL

c. Verify open or open I-SW-949, 1-SW-FI-150A (L) Iso1.

d. Open 1-SW-947, 1-SW-FI-150A (L) Vent, to bleed off trapped air

(thirty seconds minimum).

e. Close 1-SW-947.

6.2.4 Bleed entrapped air from 1-SW-FI-150A high side instrument line.

a. Open 1-SW-814, CC HX A SW Inlet FI-150A (H) Isol.

b. Verify open or open 1-SW-950, 1-SW-FI-150A (H) Isol.

c. Open 1-SW-948, 1-SW-FI-150A (H) Vent, to bleed off trapped air

(thirty seconds minimum).

d. Close 1-SW-948.

e. Close 1-SW-953.

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Surry Power Station Revision 18

Page 8 of 21

6.2.5 Verify closed or close 1-SW-655, 1-SW-PDI-132A Equalizer Valve.

6.2.6 Bleed entrapped air from low side instrument lines...

M a. Close 1-SW-595, CC HX A SW Inlet DPI-132A (L) Vent.

1'1 b. Slowly open 1-SW-591, CC HX A SW Inlet DPI-132A (L) Iso1.

M c. Open 1-SW-595 to bleed off trapped air (thirty seconds minimum).

1'1 d. Re-close 1-SW-595.

6.2.7 Bleed entrapped air from high side instrument lines.

1'1 a. Close 1-SW-594, CC HX A SW Inlet DPI-132A (H) Vent.

1'1 b. Slowly open 1-SW-590, CC HX A SW Inlet DPI-132A (H) Iso1.

M c. Open 1-SW-594 to bleed off trapped air (thirty seconds minimum).

(l1 d. Re-close l-SW-594.

,A1 6.2.8 Open I-SW-39, to obtain 10 to 15 inches ~p on the Barton I-SW-PDI-132A.

6.2.9 Record the following on Attachment 1.

a. Barton M

b. Annubar gauge M, 1-SW-FI-150A

c. Circulating Water Inlet Temperature for any flowing waterbox, as read

on the PCS Computer.

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Surry Power Station Revision 18

Page 9 of 21

6.2.10 Continue to open 1-SW-39 to obtain an additional 10 to 20 inches L\P

on the Barton I-SW-PDI-132A.

a. Record data on Attachment 1.

b. Repeat until either Barton ~p exceeds 95 inches OR Annubar L\P

exceeds 4.0 inches.

6.2.11 Close 1-SW-815, CC HX A SW Inlet FI-150A (L) Iso1.

6.2.12 Close I-SW-814, CC HX A SW Inlet FI-150A (H) Iso1.

6.2.13 Close the following valves.

a. I-SW-590, CC HX A SW Inlet DPI-132A (H) Isol

b. I-SW-591, CC HX A SW Inlet DPI-132A (L) Isol

6.2.14 Perform the following steps to depressurize 1-SW-PDI-132A.

a. Open 1-SW-655, 1-SW-PDI-132A Equalizer Valve.

b. Slowly open I-SW-594, CC HX A SW Inlet DPI-132A (H) Vent.

c. Slowly open 1-SW-595, CC HX A SW Inlet DPI-132A (L) Vent.

d. WHEN ilP is reduced to zero, THEN re-close I-SW-655.

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 10 of 21

CAUTION

In order to prevent excessive CC cooldown during heat exchanger flushing, l-CC-583 should be closed

during seasons when SW temperature is low.

NOTE: The extended duration full flow flush is done to reduce tube fouling due

to sedimentation. The extended duration full flow flush is required when

the as found CCHX SW discharge valve position is less than or equal

to 1/3 open. (Step 6.2.2) (Ref. 2.4.5)

6.2.15 IF the as found SW discharge valve position is more than 1/3 open,

THEN start a 5 minute flush of the CC HX lAW the foIIowing instructions.

IF an extended duration full flow flush is required, THEN enter N/A in this

step and in Step 6.2.16. (Ref. 2.4.5)

a. IF desired to limit CC System cooldown, THEN verify closed or

close l-CC-583. Otherwise, enter N/A.

b. Fully open I-SW-39.

6.2.16 WHEN I-SW-39 has been open for at least five minutes, THEN

return I-SW-39 to the position recorded in Step 6.2.2, OR to the

position specified by Shift Supervision.

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 11 of 21

6.2.17 Start an extended duration full flow flush lAW the following instructions.

IF the extended full flow flush is NOT required, THEN enter NI A in this

step. (Ref. 2.4.3) (Ref. 2.4.5)

a. Verify Cation Bed is not in service on either Unit 1 or Unit 2.

b. Place 1-CH-TCV-1143, Letdown Line Divert, in DIVERTNCT.

c. Place 2-CH-TCV-2143, Letdown Line Divert, in DIVERT/VeT.

d. Verify closed or close 1-CC-583.

e. Fully open 1-SW-39.

f. WHEN 1-SW-39 has been open at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (2 hrs preferred),

THEN return 1-SW-39 to the position recorded in Step 6.2.2, OR

to the position specified by Shift Supervision.

g. Open l-CC-583.

h. Allow CC temperature to stabilize.

1. Place l-CH-TCV-1143, Letdown Line Divert, in AUTO/DEMIN.

J. Place 2-CH-TCV-2143, Letdown Line Divert, in AUTO/DEMIN.

6.2.18 IF 1-CC-583 was closed in Step 6.2.1 or Substep 6.2.15.a, THEN verify

open or open 1-CC-583. Otherwise, enter N/A.

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.

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.

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 12 of21

Init Verif

7.0 FOLLOW-ON

7.1 AcceptanceCriteria

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.

7.2 Follow-on Tasks

Test Result: (I)

( ) SATISFACTORY ( ) UNSATISFACTORY

7.2.1 IF the test was satisfactory in the OPERABLE Range, THEN check

SATISFACTORY AND enter N/A for Steps 7.2.2 and 7.2.3.

7.2.2 IF the test was satisfactory but in the ALERT Range, THEN check

SATISFACTORY AND perform the following. Enter N/A for Step 7.2.3.

a. Notify Shift Supervision.

b. Submit a Work Request to clean the heat exchanger and record the

number.

WR Number: _

c. Submit a Condition Report and record the number.

CRNumber: - - - - - - - - - - -

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 13 of 21

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:

System Engineer

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.

CRNumber: - - - - - - - - - - - -

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

SRO

are met.

f. Submit a Work Request (or note if one is outstanding) to clean the heat

exchanger and record the number.

WRNumber: - - - - - - - - - - -

7.2.4 Personnel participating in performance of this procedure shall complete the

table below.

Initials Signature Printed Name Date

,!ovA

O~AY

DOMINION 1-0SP-SW-002

Su rry Power Station Revision 18

Page 14 of 21

7.2.5 Notify Shift Supervision of test completion.

Comments: - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Completed by: - - - - - - - - - - - - - - - - - - - - Date:

7.3 Review

Comments:

Reviewed by: -------....,....--:--=-------:----------- Date:

Shift Supervision

Forward original procedure to Engineering Testing.

Comments: - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Reviewed by: -----::=---_--==----;;-- _ Date:

7.4 Records

Submit original procedure to Station Records in accordance with approved

Administrative procedures.

DOMJNION 1-0SP-SW-002

Surry Power Station Revision 18

Page 15 of 21

(Page 1 of 1)

Attachment 1

1-CC-E-1A MACROFOULING DATA SHEET

Transfer the highest flow point Barton and Annubar i\P readings to the Attachment 2 graph

illustrating the closest temperature that is equal to or higher than the current Circulating Water

Inlet Temperature to determine HX acceptability. Other points are gathered for information only.

IF the highest flow point Barton and Annubar AP readings are offscale to the right of the

graph, THEN the point is in the Operable Range.

HEAT EXCHANGER LiP ANNUBAR ilP

2.1 O.~

S-cP O,V5

7~ I. of)

9'1 1. 1 5

Circulating Water Inlet Temperature: 7.3 OF

Completed by: -'-- _ Date: r~()A,!

DOMINION 1-0SP-SW-002

Su rry Power Station Revision 18

Page 16of21

(Page 1 of 6)

Attachment 2

1-CC-E-1A OPERABILITY LIMITS

-++. -r- -=--:--t....H-++-++*t-f-,.-++-H-f +- H-

j.- _. i+

.-+~~++-f-l-.;. .t- .. *t* 'r' +-i+

j.*.;.*.;.*...**!***!*++*f**.j.***H* ***.-,***,:***;***1*++*..*+*.;.* ...+ ,+ . , t-~.... **.*+-.+.t-+++

-i.-t....-; ...:...:...:. .. ... -t :1::: +. . . :-f++* H.. r+ ..;.-+*..~,,'*.+-..**!~:;_*~:~I-*~l.*.j.**l-**I--,***,..*\- t::f.

INOP ERABLE -+-+-+--~+-f-'--+~l-l--+-+-+++-+~t-+-++--i--+-+-+--f-+-+--JII~+-+-+-t--t--t-H-t--:---;--t-I-t-i-~

M+.

I-j-- ... H**

.. [=~ =: ~:t::t: J.*;HH.*_*~-.+. H*.++_H..+.t.+

j.. .. .+. , ,.++.-

.. ~::t: .+.. ....++:}~ *:::1::: .rr

....... 'f-+- j.+*:'**+*";*+f*++*H***IH

'i

_. 'f+* .+-i***;*.*;*++.*!**.j.**,H**rj' -l- ._.-

0-t '" *t*.....H--HJ"t-+**;..+ ~.. .-t.

co

-+oJ

(j)

o .- '+-11 ,

L-

a>

H++* .

0>

c

co

.c

- H+ .......

.~++ f+++- . =~tt ., H*+

~++ .....

o

X . . H*+-

W

-+oJ

en I

Q) f+*

I

.-+._+..

-+++. ..+-. ...~ ...... .-

....;~

..~ ::~=tt .. - :::~::::~~

'-H-' .+++- . . -+++. H++- H-'" H** =:t-= ... :::t= ::l f=t-:: ..+.~.+ ..";"-I:= _.

-e- ++ .....+-+'.+,,; t:t: h"+" H*++-

o

o 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80

Annubar Delta-P (inches water)

CC HX

OPERABILITY LIMITS

(70) of

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 20 of 21

(Page 5 of 6)

Attachment 2

1-CC-E-1A OPERABILITY LIMITS

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Annubar Delta-P (inches water)

Graphics No: CB1743E

CC HX

OPERABILITY LIMITS

(90) of

(

DOMINION 1-0SP-SW-002

Surry Power Station Revision 18

Page 21 of 21

(Page 6 of 6)

Attachment 2

1-CC-E-1A OPERABILITY LIMITS

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1.10 1.30 1.50 1.70 1.90 2.10 2.30 2.50 2.70 2.90 3.10 3.30 3.50 3.70 3.90

Annubar Defta-P (inches water) Graphics No: CB1743F

CC HX

OPERABILITY LIMITS

(95) of

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

Conditions

Task is to be PERFORMED in the classroom.

Standards

Correctly identifies errors in 1-0PT-CS-006 (REV 9), 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, which has just been completed.

No maintenance has been performed on the Containment Spray system.

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

completeness and accuracy.

List ALL discrepancies noted on the ANSWER SHEET provided.

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

Page 1 of 24

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

Terminating Cues

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

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

If candidate wants to review Technical Specifications based on identified discrepancies, state that the Shift

Manager will review and be responsible for Technical Specification LCOs.

Page 2 of 24

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.

EVALUATOR 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 3 of 24

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.

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 I-CS-MOV-I0IA, 101C, and IOOA cannot be closed unless the breaker

for l-CS-P-IA is in TEST or CONNECT. MOVs I-CS-MOV-I0IB, 101D, and 100B

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

EV ALUATOR NOTES:

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

COMMENTS:

Page 4 of 24

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 5 of 24

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 Iso1.

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

COMMENTS:

Page 6 of 24

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

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

UNSAT

STANDARD:

6.2.6 Close 1-CS-MOY-102A.

SY

6.2.7 Throttle open 1-CS-120 one and one half turns.

6.2.8 Open 1-CS-38.

SY

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

required.

6.2.10 AFTER 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-MOY-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-MOY-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 MOY-102B

Isol,

COMMENTS:

Page 7 of 24

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 OPT was checked

SAT instead of UNSAT and that no comments were made regarding

These items.

COMMENTS:

Page 8 of 24

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 ReS 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: 3697

Stopwatch Cal Due Date: 12/16/07

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

Acceptable Range values. He should also identify the OPT was

checked SAT instead of UNSAT and that no comments were made

regarding these items. He should also identify that the stopwatch CAL

DATE is past due.

COMMENTS:

Page 9 of 24

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

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

STANDARD: UNSAT

_ _ _ 6.4.5 From the Control Room, close l-CS-MOV-I0IA from a full-open position. Using

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

following data. IF l-CS-MOV-I01A 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: 3697

Stopwatch Cal Due Date: 12/16/07

EVALUATOR NOTES: The candidate should also identify that the stopwatch CAL DATE is

past due.

_ _ _ 6.4.6 From the Control Room, open l-CS-MOV-I01B from a full-closed position. Using

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

following data. IF l-CS-MOV-I01B 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 10 of 24

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: 53.4

Reference Time: 55.9 seconds

Acceptable Range: 47.6 to 64.2 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

COMMENTS:

Page 11 of 24

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

STEP 9: 6.4 Cycle of l-CS-P-IA MOV s and Sample of Discharge Header (Continued) SAT

STANDARD: UNSAT

_ _ _ 6.4.9 Place l-CS-P-IA in AUTO AFTER STOP. Enter N/A if l-CS-P-IA is to be left in

PT~. (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 l-CS-P-IA discharge header IAW the following substeps. IF vent

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

_ _ _ a. Slowly open l-CS-57, CTMT Spray Pump lA Casing Vent.

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

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

ml.

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

_ _ _ e. Close l-CS-67.

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

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

for l-CS-P-IA 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 12 of 24

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 _ _ _ SAT

STANDARD: UNSAT

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

and 450 psig will start a Technical Specification LCO.

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

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

_ _ _ 6.5.2 Place l-CS-P-IB in PULL TO LOCK. (Ref. 2.4.3)

_ _ _ 6.5.3 Verify closed or close l-CS-MOV-I00B, CS PUMP B SUCTION.

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

_ _ _ 6.5.4 From the Control Room, open l-CS-MOV-I01C from a full-closed position. Using

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

followingdata. IF l-CS-MOV-I0IC 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

COMMENTS:

Page 13 of 24

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 1-CS-MOV-101D from a full-closed position. Using

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

following data. IF 1-CS-MOV-I01D 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

COMMENTS:

Page 14 of 24

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

_ _ _ 6.5.7 From the Control Room, close l-CS-MOV-I01D from a full-open position. Using

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

following data. IF l-CS-MOV-I0ID 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 l-CS-MOV-IOOB from a full-closed position. Using

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

following data, IF l-CS-MOV-I00B is NOT required to be tested, THEN enter N/A

for the following data.

Time to open in seconds: 64.2

Reference Time: 60 seconds

Acceptable Range: 51.0 to 69.0 seconds

Stopwatch SQC Number: 3698

Stopwatch Cal Due Date: 5/22/08

COMMENTS:

Page 15 of 24

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-1B in AUTO AFfER 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 l-CS-P-IB 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-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 l-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 l-CS-P-IB 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 0.94

COMMENTS:

Page 16 of 24

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.

___ l-CS-MOV-I02A, CHEM ADD TK OUTLT

___ I-CS-MOV-102B, CHEM ADD TK OUTLT

___ l-CS-MOV-1OOA, CS PUMP A SUCT

___ I-CS-MOV-100B, CS PUMP B SUCT

___ I-CS-MOV-101A, CS PUMP A DISCH

___ I-CS-MOV-101B, CS PUMP A DISCH

___ I-CS-MOV-101C, CS PUMP B DISCH

___ I-CS-MOV-101D, CS PUMPB DISCH

_ _ _ 7.1.2 Document the test results. ( )

__ Satisfactory __ Unsatisfactory

EVALUATOR NOTES: *Candidate should identify that the test was checked

Satisfactory instead of Unsatisfactory.

Candidate should also identify that the following valves were incorrectly checked as satisfactory:

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

l-CS-MOV-lOlA for open time being less than the Acceptable Range

COMMENTS:

Page 17 of 24

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.

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

actually Unsatisfactory and notifications should be made.

COMMENTS:

Page 18 of 24

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-001, containment spray System Chemistry Sample

as necessary.

_ _ _ f. Once l-OSP-CS-OO 1 has been performed satisfactorily then perform 1-

OPT-CS-OOl, 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 section 7.2.2 is marked N/A when chemistry

was actually Unsatisfactory and notifications should be made.

COMMENTS:

Page 19 of 24

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 Review

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 20 of 24

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

ANSWER KEY

1-0PT-CS-006 REVIEW

1. Step 6.3.5, 1-CS-MOV-102B exceeds open stroke time limits. (CRITICAL TASK)

2. Step 6.4.4, 1-CS-MOV-101A exceeds open stroke time limits. (CRITICAL TASK)

3. Step 6.4.4, stopwatch cal date is past due.

4. Step 6.4.5, stopwatch cal date is past due.

5. Sodium (Na) concentration exceeds limits.

6. Step 7.1.1, 1-CS-MOV-102B and CS-MOV-101A are checked as meeting the acceptance criteria.

7. 7.1.2, PT is marked as SAT versus UNSAT. (CRITICAL TASK)

8. Step 7.2.1, step marked N/A when notifications to engineering should be made and Condition Reports/Work

Requests should be submitted.

9. Step 7.2.2, step marked N/A when notifications to Chemistry should be made for OOS Sodium.

10. No comments made in the Operator Comments section.

Page 21 of 24

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, which has just been completed.

No maintenance has been performed on the Containment Spray system.

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

completeness and accuracy.

List ALL discrepancies noted on the ANSWER SHEET provided.

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

G2.2.12 SR08301 22 of 24

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

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

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, which has just been completed.

No maintenance has been performed on the Containment Spray system.

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

completeness and accuracy.

List ALL discrepancies noted on the ANSWER SHEET provided.

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

G2.2.12 SR08301 23 of 24

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

ANSWER SHEET

1-0PT-CS-006 REVIEW

G2.2.12 SR08301 24 of 24

PROCEDURE NO:

1-0PT-CS-006

REVISION NO:

SURRY POWER STATION 9

PROCEDURE TYPE: UNIT NO:

OPERATIONS PERIODIC TEST 1

PROCEDURE TITLE:

RWST CHEMICAL ADDITION TANK

AND CONTAINMENT SPRAY SYSTEM MOV STROKE TEST

1ST PMT PSA

REVISION SUMMARY:

Revised in response to Operations Feedback, OP FB 07-0348. Added P&L 4.4.

.:: -. :.;-':

.' .:.::.:'.,'.

co lNUO

Dominion 1-0PT-CS-006

Surry Power Station Revision 9

Page 2 of 24

TABLE OF CONTENTS

Section Page

1.0 PURPOSE 3

2.0 REFERENCES 4

3.0 INITIAL CONDITIONS 5

4.0 PRECAUTIONS AND LIMITATIONS 5

5.0 SPECIAL TOOLS AND EQUIPMENT 6

6.0 INSTRUCTIONS 7

6.1 Work Preparation 7

6.2 Cycle of l-CS-MOY-I02A 8

6.3 Cycle of l-CS-MOY-I02B 10

6.4 Cycle of 1-CS-P-1A MOVs and Sample of Discharge Header 12

6.5 Cycle of 1-CS-P-1B MOVs and Sample of Discharge Header 16

7.0 FOLLOW-ON 20

DOMINION 1-0PT-CS-006

Surry Power Station Revision 9

Page 3 of 24

1.0 PURPOSE

NOTE: If the reactor is shutdown and a test has not been performed within the

previous 92 days, a test must be performed within 92 days prior to

exceeding 350 degrees and 450 psig. (Reference 2.2.2)

1.1 To provide instructions for verifying the following on a quarterly basis when the

RCS is greater than or equal to 350 degrees and 450 psig.

To verify proper operation of the following MOYs.

I-CS-MOV-I02A, CHEM ADD TK OUTLT

I-CS-MOV-102B, CHEM ADD TK OUTL T

l-CS-MOV-IOOA, CS PUMP A SUeT

l-CS-MOV-IOOB, CS PUMP B suer

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

l-CS-MOV-IOIB, CS PUMP A DISCH

I-CS-MOV-IOIC, CS PUMP B DISCH

l-CS-MOV-IOID, CS PUMP B DISCH

To obtain a Chemistry sample of the Containment Spray system to ensure

chemical contamination has not occurred due to leakage through the Chemical

Addition Tank isolation MOVs.

1.2 To provide instructions to return Containment Spray valves to service following

maintenance.

DOMINION 1-0PT-CS-006

Surry Power Station Revision 9

Page 4 of24

2.0 REFERENCES

2.1 Source Documents

2.1.1 UFSAR 6.3.1, Spray Systems

2.2 Technical Specifications Surry Power Station Units 1 and 2

2.2.1 Technical Specification 3.4, Spray Systems

2.2.2 Technical Specification 4.5, Spray Systems Tests

2.2.3 Technical Specification 6.4, Inservice Testing Program

2.3 Technical References

2.3.1 11448-FM-084A, Containment Spray System

2.3.2 ASME OM Code, Section 1ST, Rules for Inservice Testing of Light-Water

Reactor Nuclear Power Plants

2.3.3 Inservice Testing Program Plan for Pumps and Valves

2.3.4 EWR 94-015, Revise valve stroke times to meet new Code Requirements

2.3.5 ET NAF 98-0174, Rev. 0, Containment Spray Discharge MOV Stroke Time

Limits

2.3.6 ET S-01-0087, Stroke Time Acceptance Criteria

for 1-CS-MOV-IOIA, B, C, D

DOMINrON 1-0PT-CS-006

Surry Power Station Revision 9

Page 5 of 24

2.4 Commitment Documents

2.4.1 QA Audit 87-01, Finding 2, Recording of Work Order and Mark Numbers

2.4.2 CTS 1438, Revised PT's to require performance prior to entry into the

applicable mode

2.4.3 DR S-97-0063, LHSI/CS pumps in PTL when suction source is isolated

2.4.4 CTS 4349, PMT Stamp and Review

2.4.5 CTS 4675, Maintenance activity was performed with no prior PSA

evaluation

2.4.6 PI S-2000-1953, CS Piping Chemistry Control

3.0 INITIAL CONDITIONS

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 2.4.5)

4.0 PRECAUTIONS AND LIMITATIONS

4.1 This procedure should be performed on only one MaY at a time.

4.2 The initials identification block in Subsection 7.3 must be completed before the

procedure is closed out.

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 [mal control panel light is

extinguished (i.e., if stroking an MOV closed, timing should be performed from the

time that the switch is moved to the "Close" position to the time that the red

indicating light goes out).

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4.4 MOVs I-CS-MOV-IOIA, IOlC, and lOOA cannot be closed unless the breaker

for I-CS-P-lA is in TEST or CONNECT. MOVs l-CS-MOV-IOIB, IOID,

and 100B cannot be closed unless the breaker for l-CS-P-IB is in TEST or

CONNECT.

5.0 SPECIAL TOOLS AND EQUIPMENT

5.1 Hoses and Sample Containers necessary to obtain Chemistry samples

5.2 SQC Stopwatch

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6.2 Cycle of l-CS-MOV-I02A

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.

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 MOYs and

manual isolation valve.

6.2.1 Connect the quick disconnect fitting of the hose to l-CS-120, Refueling Wtr

Chern Add Tk Otlt Hdr Drain, for l-CS-MOV-I02A.

6.2.2 Run hose from I-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 l-CS-38, Refueling Water Chern Add Tk Outlet

MOV-I02A Iso1.

NOTE: Refer to Precaution and Limitation 4.3 prior to stroking MOY.

6.2.5 From the Control Room, open l-CS-MOY-I02A 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: I~. 9

Reference Time: 19.6 seconds

Acceptable Range: 16.7 to 22.5 seconds

Stopwatch SQC Number: 3~ 'I <;

Stopwatch Cal Due Date: .; !J.J-/ofj

6.2.6 Close l-CS-MOY-I02A.

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6.2.7 Throttle open l-CS-120 one and one half turns.

6.2.8 Open l-CS-38.

6.2.9 Adjust flow to prevent overflowing the floor drain by throttling

open l-CS-120 as required.

6.2.10 AFTER 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 I-CS-120.

6.2.12 Stop Tech Spec clock. IF a Tech Spec clock was NOT started,

THEN enter N/A.

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6.3 Cycle of l-CS-MOV-I02B

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 l-CS-MOV-102B.

6.3.2 Run hose from l-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-I02B Isol.

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

6.3.5 From the Control Room, open l-CS-MOY-102B from a full-closed position.

U sing Control Room valve position indication, verify valve opens fully and

record the following data.

Time to open in seconds: l.3. ~

Reference Time: 19.87 seconds

Acceptable Range: 16.9 to 22.8 seconds

Stopwatch SQC Number: 3G:> 9~

Stopwatch Cal Due Date: S-/2:1./"1

6.3.6 Close l-CS-MOY-I02B.

6.3.7 Throttle open l-CS-112 one and one half turns.

6.3.8 Open l-CS-43.

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6.3.9 Adjust flow to prevent overflowing the floor drain by throttling

open l-CS-112 as required.

6.3.10 AFTER draining approximately 25 gallons OR flushing for approximately

five minutes, THEN close l-CS-112.

6.3.11 Remove the quick disconnect with the hose from l-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.

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6.4 Cycle of l-CS-P-IA MOVs and Sample of Discharge Header

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

and 450 psig will start a Technical Specification LCO.

6.4.I Declare 1-CS-P-IA 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 l-CS-MOV-100A, CS PUMP A SUCTION.

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

6.4.4 From the Control Room, open 1-CS-MOV-lOlA from a full-closed position.

Using Control Room valve position indication, verify valve opens fully and

record the following data. IF l-CS-MOV-I01A is NOT required to be tested,

THEN enter N/A.

Time to open in seconds: /3, 'I

Reference Time: 17.0 seconds

Acceptable Range: 14.5 to 19.5 seconds

Stopwatch SQC Number: 3"'91

Stopwatch Cal Due Date: ,J-/1f##1

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6.4.5 From the Control Room, close l-CS-MOV-IOIA from a full-open position.

Using Control Room valve position indication, verify valve closes fully and

record the following data. IF l-CS-MOY-I01A is NOT required to be tested,

THEN enter N/A.

Time to close in seconds: 1'1. <f

Reference Time: 17.1 seconds

Acceptable Range: 14.6 to 19.6 seconds

Stopwatch SQC Number: 3£.,97

Stopwatch Cal Due Date: /2/11,1,,?

6.4.6 From the Control Room, open 1-CS-MOY-I01B from a full-closed position.

Using Control Room valve position indication, verify valve opens fully and

record the following data. IF l-CS-MOY-I01B is NOT required to be tested,

THEN enter N/A.

Time to open in seconds: Il,. &>

Reference Time: 17.1 seconds

Acceptable Range: 14.6 to 19.6 seconds

Stopwatch SQC Number: 3" 't ~

Stopwatch Cal Due Date: S/22.JO~

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6.4.7 From the Control Room, close l-CS-MOY-1OlB from a full-open position.

U sing Control Room valve position indication, verify valve closes fully and

record the following data. IF l-CS-MOV-I01B is NOT required to be tested,

THEN enter N/A.

Time to close in seconds: / {" 1

Reference Time: 16.8 seconds

Acceptable Range: 14.3 to 19.3 seconds

Stopwatch SQC Number: 3~'l~

Stopwatch Cal Due Date: S" /).2./"r

6.4.8 From the Control Room, open 1-CS-MOV-1aOA from a full-closed position.

Using Control Room valve position indication, verify valve opens fully and

record the following data. IF 1-CS-MOV-1aDA is NOT required to be tested,

THEN enter N/A for the following data.

Time to open in seconds: S-'J. 'f

Reference Time: 55.9 seconds

Acceptable Range: 47.6 to 64.2 seconds

Stopwatch SQC Number: 1~'1t;

Stopwatch Cal Due Date: S-/'3-2./of

6.4.9 Place l-CS-P-IA in AUTO AFTER STOP. Enter N/A if l-CS-P-IA is to be

left in PTL. (Ref. 2.4.3)

6.4.10 Stop Tech Spec clock. IF a Tech Spec clock was NOT started,

THEN enter N/A.

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6.4.11 Vent and sample 1-CS-P-IA discharge header lAW the following

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

following substeps.

M a. Slowly open I-CS-57, CTMT Spray Pump lA Casing Vent.

t1 iZ b. WHEN vent is water solid, THEN close l-CS-57.

t1 c. Open l-CS-67, CS Pump lA Recirc Line Vent, and flush at least 500 ml.

.11 d. Obtain a 1000 ml sample from l-CS-67.

Ii e e. Close 1-CS-67.

f{ f. Label the sample l-CS-P-lA, and take to Chemistry for analysis.

t1 g. WHEN Chemistry analyzes the sample results, THEN record the results

for l-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, of( ."

F 0.15 ppm (),o1 ~

Na 500 ppm ~qo .v.

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6.5 Cycle of l-CS-P-IB MOVs and Sample of Discharge Header

NOTE: Isolating l-CS-P-IB when the RCS is equal to or greater than 350 degrees

and 450 psig will start a Technical Specification LCO.

6.5.1 Declare l-CS-P-IB inoperable and start the appropriate Tech Spec Clock.

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

6.5.2 Place l-CS-P-IB in PULL TO LOCK. (Ref. 2.4.3)

6.5.3 Verify closed or close l-CS-MOV-IOOB, CS PUMP B SUCTION.

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

6.5.4 From the Control Room, open l-CS-MOY-IOIC from a full-closed position.

Using Control Room valve position indication, verify valve opens fully and

record the following data. IF I-CS-MOY-IOIC is NOT required to be tested,

THEN enter N/A.

Time to open in seconds: ,S: '1

Reference Time: 16.1 seconds

Acceptable Range: 13.7 to 18.5 seconds

Stopwatch SQC Number: ~ ~ '18"

Stopwatch Cal Due Date: S-/t.2./Df

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6~5.5 From the Control Room, close l-CS-MOV-IOIC from a full-open position.

Using Control Room valve position indication, verify valve closes fully and

record the following data. IF l-CS-MOY-101C is NOT required to be tested,

THEN enter N/A.

Time to close in seconds: I s-. ~

Reference Time: 16.3 seconds

Acceptable Range: 13.9 to 18.7 seconds

Stopwatch SQC Number: 3fJ,9~

Stopwatch Cal Due Date: r/",,/of

6.5.6 From the Control Room, open 1-CS-MOY-101D from a full-closed position.

Using Control Room valve position indication, verify valve opens fully and

record the following data. IF l-CS-MOY-I0ID is NOT required to be tested,

THEN

- - enter N/A.

Time to open in seconds: I ~.1"

Reference Time: 15.8 seconds

Acceptable Range: 13.5 to 18.1 seconds

Stopwatch SQC Number: 1(,tj r

Stopwatch Cal Due Date: ~/2.:J./ 0 f

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6.5.7 From the Control Room, close l-CS-MOV-IOID from a full-open position.

Using Control Room valve position indication, verify valve closes fully and

record the following data. IF l-CS-MOY-I01D is NOT required to be tested,

THEN enter N/A.

Time to close in seconds: IS'". {,

Reference Time: 15.8 seconds

Acceptable Range: 13.5 to 18.1 seconds

Stopwatch SQC Number: 11.198'"

Stopwatch Cal Due Date: ~ J1.J./Of

6.5.8 From the Control Room, open l-CS-MOY-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: {, 'l2

Reference Time: 60 seconds

Acceptable Range: 51.0 to 69.0 seconds

Stopwatch SQC Number: "3 ~ 98'

Stopwatch Cal Due Date: ~/J.2-lo~

6.5.9 Place l-CS-P-IB in AUTO AFTER STOP. Enter N/A if l-CS-P-IB 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.

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6.5.11 Vent and sample l-CS-P-IB discharge header lAW the following substeps.

IF vent and sample are NOT required, THEN enter N/ A for the following

substeps.

a. Slowly open I-CS-60, CTMT Spray Pump IB Casing Vent.

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

c. Open l-CS-66, CS Pump IB Recirc Line Vent, and flush at least 500 m!.

d. Obtain a 1000 ml sample from l-CS-66.

e. Close I-CS-66.

f. Label the sample l-CS-P-IB, and take to Chemistry for analysis.

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

for l-CS-P-l B 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

Cl 0.15 ppm a. ()2.. -:

F 0.15 ppm 0." / ./

Na 500 ppm (),91;/ /

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7.0 FOLLOW-ON

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.

- ' - I-CS-MOV-I02A, CHEM ADD TK OUTLT (Step 6.2.5)

~ I-CS-MOV-I02B~ CHEM ADD TK OUTLT (Step 6.3.5)

.r. I-CS-MOV-IOOA, CS PUMP A SUCT (Step 6.4.8)

~ I-CS-MOV-IOOB, CS PUMP B SUCT (Step 6.5.8)

~ I-CS-MOV-IOIA, CS PUMP A DISCH (Step 6.4.4 and Step 6.4.5)

~ I-CS-MOV-IOIB, CS PUMP A DISCH (Step 6.4.6 and Step 6.4.7)

~ l-CS-MOV-IOIC, CS PUMP B DISCH (Step 6.5.4 and Step 6.5.5)

L l-CS-MOV-IOID~ CS PUMP B DISCH (Step 6.5.6 and Step 6.5.7)

7.1.2 Document the test results. (~)

~ Satisfactory _ _ Unsatisfactory

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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

d. Initiate a Condition Report and record the number.

eRNo.

e. Initiate a Work Request and record the number.

Work Request No. _

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

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d. Initiate a Condition Report and record the number.

eRNo.

e. Perform l-OSP-CS-OOl, containment spray System Chemistry Sample as

necessary.

f. Once l-OSP-CS-OO1 has been performed satisfactorily then

perform l-OPT-CS-OOl, 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.

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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 Narne.

Initials Printed Name

H BILL MAIZ.S;f4 J-l-

t? "~Av~p \-\ WH...a~V

~

Operator Comments: _

Completed by: _ Date: 7~ IJA.t

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7.4 Review

Shift Supervision Comments: _

Reviewed by: ~~;::____-__;__;_-------- Date:

Shift Supervision

Forward original procedure to Engineering Testing.

Engineering Comments: _

Reviewed by: -------~=-=--=----:------------

Date:

1ST Engineer

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 ALAR A program. (2.5/2.9)

Applicability Estimated Time Actual Time

RO/SRO(I)/SRO(U) 25 Minutes

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 9

Surry 2008-301 Radiation Exposure Calculation

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.

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

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

Initiating Cues

Given the travel times, times to pertorm 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. Two operators not wearing an SCBA

Page 2 of 9

Surry 2008-301 Radiation Exposure Calculation

Times to perform the task:

Two way travel time to 2-SI-MOV-2865B 12 minutes

without a SCBA

Two way travel time to 2-SI-MOV-2865B with 16 minutes

aSCBA

Time for two people without SCBAs to close 5 minutes

2-SI-MOV-2865B

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

SI-MOV-2865B

Dose rates for the Areas

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 9

Surry 2008-301 Radiation Exposure Calculation

PERFORMANCE CHECKLIST

Notes to the Evaluator

Task critical elements arebolded 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, with SCBA

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 [5 - 6 mrem]

Total Travel Time Dose: 5.33 mrem

b) Two operators, NO SCBAs

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

COMMENTS:

Page 4 of 9

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, with SCBA

Time to close the valve is 16 minutes.

Average External Dose Rate 70 mremlhr.

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

Total dose to close the valve: 18.67 mrem [18 - 19 mreml

b) Two operators, NO SCBAs

Time to close the valve is 5 minutes.

Average External Dose Rate 70 mremlhr.

Average Internal Dose Rate 60 mremlhr.

(70 mremlhr) x (1 hr /60 minutes) x (5 minutes) = 5.83 mrem external.

(60 mremlhr) x (1 hr / 60 minutes) x (5 minutes) =5 mrem internal.

(2 operators) x (5.83 mrem + 5 mrem) = 21.66 mrem

Total dose to close the valve: 21.66 mrem [21 - 22 mrem]

COMMENTS:

Page 5 of 9

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, with SCBA

Total dose to close the valve: 18.67 mrem [18 - 19 mrem]

Total Travel Time Dose: 5.33 mrem [5 - 6 mrem]

Total Job Dose: 24 mrem [23 - 25 mrem]

b) Two operators, NO SCBAs

Total dose to close the valve: 21.66 mrem [21 -22 mrem]

Total Travel Time Dose: 8 mrem

Total Job Dose: 29.66 mrem [29 - 30 mrem]

COMMENTS:

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 6 of 9

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

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.

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 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. Two operators not wearing an SCBA

G2.3.2 SR08301 7 of 9

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

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.

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 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. Two operators not wearing an SCBA

Times to perform the task:

G2.3.2 SR08301 8 of 9

Surry 2008-301 Radiation Exposure Calculation

Two way travel time to 2-SI-MOV-2865B 12 minutes

without a SCBA

Two way travel time to 2-SI-MOV-2865B with 16 minutes

aSCBA

Time for two people without SCBAs to close 5 minutes

2-SI-MOV-2865B

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

SI-MOV-2865B

Dose rates for the Areas

Average Dose Rate from while traveling to 20 mrem/hr

and 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)

G2.3.2 SR08301 9 of 9

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

Conditions

Task should be performed in the simulator.

Standards

Report of Emergency to State and Local Governments, EPIP-2.01 Attachment 2, form completed.

Initiating Cues

Nuclear Shift Manager direction.

Terminating Cues

EPIP-2.01 Attachment 2 completed.

Procedures

EPIP-2.01, NOTIFICATIONS OF STATE AND LOCAL GOVERNMENTS (REV 36)

Tools and Equipment

None

Safety Considerations

None

Page 1 of 12

Surry 2008-301 Transmit Report of Emergency

Initiating Cues

The Shift Manaqer 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 complete EPIP-2.01, Notification of State and Local Governments, including

filling out Attachment 2, Report of Emergency to State and Local Governments. Transmission of the report is

NOT required.

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 Manaqer has directed you to complete EPIP-2.01, Notification of State and Local Governments,

including filling out Attachment 2, Report of Emergency to State and Local Governments.

Transmission of trle report is NOT required.

You are in the Main Control Room.

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

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

mph.

Page 2 of 12

Surry 2008-301 Transmit Report of Emergency

PERFORMANCE CHECKLIST

Notes to the Evaluator

Task critical elements are balded 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 EMERGENCY 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 ofthe emergency.

Evaluator's Comments

Page 3 of 12

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHMENT 2 (REPORT OF E~RGENCY 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 CUE: Time SAE declared is 2 minutes before

present clock time. Provide this cue when

applicant is filling out Attachment 2.

Evaluator's Comments

Page 4 of 12

Surry 2008-301 Transmit Report of Emergency

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

Standards _ _ UNSAT

Fills out Attachment 2 (bolded below):

MESSAGE # 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)

[Xl Site Area Emergency *(CRITICAL TASK)

[] General Emergency

[] Emergency Terminated

Page 5 of 12

Surry 2008-301 Transmit Report of Emergency

STEP 3: RECORD INFORMATION ON ATTACHMENT 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;

AVE Wind Speed 10

_ - = - . ; . ._ _ mph

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.):

Unit 1 reactor failed to trip. The reactor is now tripped. (or words to this effect).

(CRITICAL TASK)

Page 6 of 12

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 7 of 12

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 8 of 12

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 [ ] TS'C [ ] LEOF [ ] CEOF

continuing the message.

Item 11: Recommended off-site protective actions are:

[X] None

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

sectors _

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

[ ] Beyond 10 Mile EPZ:

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

Width (feet)

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

Width feet)

[ ] Potassium Iodide: Recommend implementation of Potassium Iodide (Kl)

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 9 of 12

Surry 2008-301 Transmit Report of Emergency

STEP 4: CHECK EMERGENCY - 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

EVALUATOR CUE: Sign Approval for Candidate (upper right hand comer)

EVALUATOR CUE: If applicant does not recall this is the termination point

for the JPM, inform applicant that JPM is complete.

Evaluator's Comments

STOP TIME:

Page 10 of 12

Surry 2008-301 Transmit Report of Emergency

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

Task can be performed in the simulator or classroom.

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 complete EPIP-2.01, Notification of State and Local Governments, including

filling out Attachment 2, Report of Emergency to State and Local Governments.

Transmission of the report is NOT required.

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 complete EPIP-2.01, Notification of State and Local Governments,

including filling out Attachment 2, Report of Emergency to State and Local Governments.

Transmission of the report is NOT required.

You are in the Main Control Room.

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

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 complete EPIP-2.01, Notification of State and Local Governments, including

filling out Attachment 2, Report of Emergency to State and Local Governments. Transmission of the report is

NOT required.

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

G2.4.43 SR08301 11 of 12

Surry 2008-301 Transmit Report of Emergency

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

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 complete EPIP-2.01, Notification of State and Local Governments,

including filling out Attachment 2, Report of Emergency to State and Local Governments.

Transmission of the report is NOT required.

You are in the Main Control Room.

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

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 complete EPIP-2.01, Notification of State and Local Governments, including

filling out Attachment 2, Report of Emergency to State and Local Governments. Transmission of the report is

NOT required.

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

G2.4.43 SR08301 12 of 12

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

Conditions

Task may be PERFORMED in the simulator or classroom.

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 approval for transmitting EPIP-2.01.

Procedures

EPIP-1.01, EMERGENCY MANAGER CONTROLLING PROCEDURE (REV 51)

EPIP-2.01, NOTIFICATION OF STATE AND LOCAL GOVERNMENTS (REV 36)

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.

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. 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 you have reviewed and approved EPIP-2.01, Notification

of State and Local Governments.

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

mph.

If performed in the classroom, announcing classification (if required) out loud is not required.

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, Emergency Manager Controlling Procedure and approve EPIP-2.01, Notification of State and

Local Governments.

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: REVIEWS CAUTION AND NOTE PRIOR TO STEP 1 OF EPIP-1.0 1. _ _ 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 2: EVALUATEE:MERGENCY ACTION LEVELS: (Step 10fEPIP-1.01). _ _ SAT

Standards _ _ _ UNSAT

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

Index. .

Turns to EPIP-1.01, Attachment 1, Page 1, EAL Table Index.

b) Review EAL Tab associated with event category.

Determines event category to be SAFETY, SHUTDOWN OR ASSESS:MENT 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.

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

annunciator lE-G10 (STM GEN LO-LO LVL) is lit red.

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

event as a SITE AREA EMERGENCY. (CRITICAL TASK)

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 3: RECORD EAL TAB, TIME EMERGENCY 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 4: 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 5: CHECK - CONDITIONS ALLOW FOR NORMAL IMPLEMENTATION OF _ _ _ SAT

EMERGENCY 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 that could hinder the activation of

the emergency response organization.

Evaluator's Comments

Page 5 of 10

Surry 2008-301 Classify an Event

STEP 6: NOTIFY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION: (Step 5 of SAT

EPIP-l.Ol).

_ _ UNSAT

Standards

a) Check classification - ALERT OR HIGHER

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

Page 6 of 10

Surry 2008-301 Classify an Event

STEP 7: 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, NOTlFICATIONS OF STATE AND LOCAL

GOVERNMENTS

2) EPIP-2.02, NOTlFICATION OF NRC

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

Evaluator's Cue

Provide the previously completed EPIP-2.01 to the applicant. (Give applicant the

incorrect EPIP-2.01. If he classifies the event as SAE, give out the EPIP-2.01 marked

"ALERT". If he classifies the event as ALERT, give out the EPIP-2.01 marked "SAE". )

STATE "For purposes of this exam, I will not review this with you. Please review for

accuracy, completion and sign for approval."

Determines that EPIP-2.01 is incorrectly filled out. Alert is checked instead of Site

Area Emergency. (CRITICAL TASK)

Evaluator's Comments

Page 7 of 10

Surry 2008-301 Classify an Event

STEP 8: APPLICANT REPORTS CO:MPLETION OF TASK. _ _ _ SAT

Standards _ _ _ UNSAT

Applicant reports completion of the task.

Evaluator's Cue

If applicant continues in EPIP-l.Ol, if him that this is the end of the JPM.

Evaluator's Comments

STOP TIME:

Page 8 of 10

Surry 2008-301 Classify an Event

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMINER)

Task may be PERFORMED in the simulator or classroom.

Classify an event in accordance with EPIP-1.01, Emergency Manager Controlling Procedure and approve EPIP-

2.01, Notification of State and Local Governments.

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.

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. 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 you have reviewed and approved EPIP-2.01, Notification

otState and Local Governments.

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

mph.

If performed in the classroom, announcing classification (if required) out loud is not required.

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, Emergency Manager Controlling Procedure and approve EPIP-2.01, Notification of State and

Local Governments.

When yo~ 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)

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 La-La 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.

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. 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 you have reviewed and approved EPIP-2.01, Notification

of State and Local Governments.

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

mph.

If performed in the classroom, announcing classification (if required) out loud is not required.

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, Emergency Manager Controlling Procedure and approve EPIP-2.01, Notification of State and

Local Governments.

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

G2.4.41 SR08301 10 of 10

NUMBER ATIACHMENT TITLE ATTACHMENT

EPIP-2.01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 1of3

MESSAGE # _~_ i APPROVAL: ---- _

(Station Emergency Manager or RecoveryManaqor)

TIME NOTIFI(~ATJON STARTED:

This is Suny Power Station ~ Controt Room [ ] TSC [ ] LEOF [ ) CEOF. Standby fora roll-callfollowed

by an emergency message. Use a Reportof Emergency form to copy thtS message.

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

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

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

The emergency message is as follows: (READ SLOWLY)

Item 1: Emerg.3ncy Class:

[ ] Notification of Unusuat Event [ ] Sfte Area Emergency n"'e ~lfI

Declared atDccj..lIU"-" on II,;}[) ~

{)(J Alert [ J Generaf Emergency (24-hrtime) (date)

[ ] Emf~rgency Terminated

Item 2: Release of radioactive material:

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

[ J Related to the event is presentlyoccurring [Place release in context in Item5)

[ ] Related to the event has occurred and is now terminated [Place release in context in Itern 5]

[ ) Related to the event is projected to occur [Place projected release in context in Item 5]

Item 3: ( ] We wilt transmit a Reportof Radiological Conditions to the State EOC.

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

Item 4: Meteorological Data:

AVE Wind Direction from If> degrees (0° to 360 0 )1Compass Point ,A/F

.AVE Wind Speed ro _ mph

Based on: [)(J On-site Measurements [] Off-site Measurements [] Not available

Item 5: Rernerks I Description of event and release, as applicable. (Do not use abbreviations. mark

numbers and acroynms.): fhtJlr J ;2t'/lQ1)1{ FAILtl) 'Tu T~JI' F",z.t:¥"1

~f ('11"1/".1 CcMIril~L {?bIJM jA!Ht-.,..J J2r-6Jv"J2+(j,

(ATTACHMENT 2 CONTINUED ON NEXTPAGE)

g / 7. L Lg I - I c ~ - , c, 1\ J J n '-:: - :l).4 fl.1c n

NUMBER ATTACHMENT TITLE ATIACHMENT

EPIP-2.01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 2of3

MESSAGE # _1__

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

ernerqency class change, including emergency termination and maybe 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: [(I Excluded from this message

[ ] None .

__'_ (#) Fire Unitsfrom _ _ _ (#) Police Units from _

__ (#) Rescue Units from _ _____ (#) Other -

Item?: Emergency response actions underway; 1>4 Excluded from this message

[ ] None

[ 1Station monitoring teams dispatched off-site ( ] Station emergency personnel called in

l ] Other _

Item 8: Evacuation or Company Dismissal of on-site personnel: DC] Excfuded from this message

[ ) No

[ JYes, evacuated to:

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

l lOthe r -- --- ---

[ ) Company Dismissal of non-essential personnel:

[ ] is planned. [ 1is in progress. [ J has been completed.

Item 9: Prognosis of Situation~ 11<1 Excluded from this message

[ JImproving [ ] Stable

[ ] Worsening [ JOther -

Item 10: This is (name) IEmergency Communicator.

Please acknowledge receipt of this message. (Conduct roll-call and check boxes)

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

[ 1James City County (] Isle of Wight County [) Newport News

This is Surry Power station I)c) ControJ Room { ] TSC [ J LEOF [ ] CEOF out at on _

(24-hr time) (date)

(ATTACHMENT 2 (:ONTINUED ON NEXT PAGE)

Q/£ LLQ/-/C£-/CI ~JJn~ - ~WM~n

NUMBER ATTACHMENT TITLE AITACHMENT

EPIP-2.01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 30f3

MESSAGE # 1

NOTE: * When transmitted, the following information is for state use only. Transmitto State EOCusing

the [)EM ARD.

The remainder of this report is not transmitted when the message reports emergency

termination.

This is Surry Power Station [)(J Control Room ( ] TSC [ ] LEOF [ ] CEOF continuing the message.

Item 11: Recommended off-site protective actions are:

[)tJ None

[ ] Shelter-in..p lace: __ Mile radius (360 0 ) and __ Miles downwind in the follow;ng

sectors_ - - - - - - -

[ ] Evacuate: __ Mile radius (360 0 ) and __ Miles downwind in the foUowi 19

sectors: _

[ ] BHyond 10Mile EPZ;

[ ] Evacuate Area: _ _ Centerline (degrees); _ _ Distance (Miles);_ _ Width (f.~et)

( JShelter-in-place: _ _ Centertine {degrees}; _ _ Distance (Miles); _ _ Width fl~t)

[ ] Potassium Iodide: Recommend implementation of Potassium Iodide (Kf) strategies for

thf~ general public. The projected dose at the site boundary is ~ 5 Rem Thyroid CDE.

Item 12: U~atesched~e:( ]~minut~( ]Other ~~~ ~~~

Name of State EOC Duty Officer: _

This ;s Surry Power Station {)(J Control Room [ ] TSC [ 1LEOF [ ] CEOF out at on _

(24-hr time) (date;

Q / .., I I 0 I - I C ~ - I C I Ii. J J n ~ - 'i).l ~I cn

NUMBER ATTACHMENTTITLE AITACHM=NT

EPIP-2.01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 10f3

MESSAGE # 1 APPROVAL: ~ _

(Station Emergency Manageror Recovery Manager)

TIME NOTIFI{;ATION STARTED: _

This is Surry Power Station [xl Control Room [ ] TSC [ JLEOF I ] CEOF. Standbyfor a roll-call foflowod

by an emergency message. Use a Report of Emergency form to copy this message.

(Conduct a rell-cau and check boxes as each party answers)

[ JSurry County [ J state EOC [ JWilJiamsburg ( ] York County

I JJames City County [ J Isle of Wight County ( J Newport News

The emergency message is as follows: (READ SLOWLY)

Item 1: ErnerqencyClass:

[ ] Notification of Unusual Event [~ Site Area Emergency 'j/Mfi Ybv

Declared atOt:~.,~n on -roj.,~

[ ] Alert [, ] General Emergency (24-hr time) (datE)

[ ] Emorgency Terminated

Item 2: Release of radioactive materia':

rxJ Is within federal limits and NOT related to the event

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

( ] Related to the event has occurred and is now terminated [Place release in context in ltern 5J

[ ] Refutedto the event is projected to occur [Place projected release in context in Item5]

Item 3: [ ] We 'will transmit a Report of Radiological Conditions to the State EOC.

DtJ We .viII not issue a Report of Radiological Conditions.

Item 4; MeteorologicaJ Data:

AVEWind Direction from 'IS- degrees (0° to 36De>>, Compass Point .Alb .

AVE W'nd Speed jD mph

Based on: [)q On-site Measurements [J Off-site Measurements [] Not avaHable

Item 5: Remarks I Description of event and release, as applicable.(Do not use abbreviations, mark

numbers and acroynrns.): UN'" .1- ~tACT()K. EAIJ"eiJ f1I 7"'1' FJf2P(1

--1l:!l? /If.4/r"J C"ttff~()L. /(00/'1 Wtli(V /cE6>"'/~ctJ"

(ATTACHMENT 2 CONTINUED ON NEXT PAGE)

9/£ LL9L-L9£-L9L fiJJn~ - ~HM~n

NUMBER ATTACHMENT TITLE ATTACHtv1ENT

EPIP-2.01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 20f3

MESSAGE # --...1-==---_

NOTE: Items E... 9 are optional for a message reporting initial entry into the Emergency Plan or an

emergency class change. induding emergency termination and may be checked'Excluded from

this rnessaqe.' "Items 6 - 9 are excluded from this message" may be read in lieu of each item..

Item 6: Assistancerequested or being provided: [Xl Exduded from this message

[ ] None

__ (#) Fire Units from _ _ _ (#) Police Units from _

__ (#) Rescue Units from _ _ _ (#) Other _

Item 7: Emergency response actions underway: b(I Excluded from this message

[ ] None

( J Station monitoring teamsdjspatched off-site [ ] Station emergency personnel callE d in

[ ] Other _

(tam 8: Evacuation or Company Dismissal of on-site personnel: D(l Excluded from this message

[ JNo

[ ] Yes, evacuated to:

[ 1Primary Remote Assembly Area. [ ] Secondary Remote Assembly Area.

[ J Other __

[ ] Company Dismissal of non-essential personnel:

[ :I is planned. [ ] is in progress. [ ) has been completed.

Item 9: Prognosis of Situation: 00 Excluded from this message

[ ] Irnproving [ 1Stable

[ ] Worsening [ ] Other -----------

This is (name) IEmergency commurecaor.

I

Item 10:

Please acknowtedge receipt of this message. (Conduct rolf-call and check boxes)

[ ] Surry County [ JState EOC [ ] WiUlamsburg [ ] York County

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

This is Surry Power Station [xl Control Room [ ] TSC [ ] LEOF [ ] CEOF out at on _

(24-hr time) (date ~

(ATTACHMENT 2 (:ONTINUED ON NEXT PAGE)

9/9 LL9L-Lg£-LgL fiJJns - ~HN~n

NUMBER ATTACHMENT TITLE ° ATTACHMENT

EPIP-2a01 2

REPORT OF EMERGENCY TO

REVISION PAGE

STATE AND LOCAL GOVERNMENTS

36 30f3

MESSAGE# 1

NOTE: * When transmitted, the following information is for state use only. Transmitto State EOC using

the [)EM ARD.

The remainderof this report is not transmitted when the message reports emergency

terrnnation.

This is Surry Power Station [)tJ Control Room [ JTSC [ ] LEOF [ ] CEOF continuing the message.

Item 11: Recommended off-site protective actions are:

00 None

[ ] Shelter-in-place: __ Mile radius (360 0 ) and __ Miles downwind in the foHow;ng

sectors _

[ ] Evacuate: __ Mile radius (360 0

) and __ Miles downwind in the foUowilQ

sectors: . . . . . . -_ _

[ JBeyond 10 Mile EPZ:

[ ] Evacuate Area: _~ Centerline (degrees); _ _ Distance (Miles);_ _ Width (fl~et)

( ]! Shelter-tn-place: _ _ Centerline (degrees); _ _ Distance (Miles); _ _ Width fc~t)

[ ] Potassium Iodide: Recommend implementation of Potassium Iodide (Kr) strategiesfor

th.~ general public. The projected dose at the site boundary is ~ 5 Rem Thyroid CDE.

Item 12:

Name of State EOC Duty Officer: _

This ;s Surry Power Station [XJ Control Room [ ] TSC ( ] LEOF [ ] CEOF out at on _~_

(24~hr time) (date)

9ft LL9L-L~£-L~L ~JJns - ~HNsn r.Z:S:Z QOnZ/r.n/LL

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: ---=S.=UIT::..::..y.l-- _ Date of Examination: March, 2008

Exam Level: RO [{1 SRO-I D SRO-U D Operating Test No.: 2008-301

Control Room Systems'" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I lPM Title Type Code* Safety

Function

a. CVCS I Perform a blended flow make-up to the Unit 1 RWST in

SIN I

accordance with 1-0P-CS-004. KIA - 004A4.04 (3.2/3.6)

b. ESFAS I Transfer the SI System to Cold Leg Recirculation Mode

SlLlNENID II

(1-ES-1.3). KIA - 013A4.01 (4.5/4.8)

c. RHR I Initiate RHR alternate decay heat removal by forced feed SILID IV -P

cooling with a charging pump. KIA - 005A2.03 (2.9/3.1) and

APE25AA1.02 (3.8/3.9)

d. CS I Secure containment depressurization equipment. 026A2.08 SILINM V

(3.2/3.7)

e. NI I Remove a failure source range NI from service during a SILlAID VII

reactor startup. 015A4.03 (3.8/3.9)

f. CW I Respond to a low level transient. 075A2.02 (2.5/2.7) SID VIII

g. WGDS I Initiate the release of a waste gas decay tank. 071A4.26 SINN IX

(3.1/3.9)

h. PPC I Depressurize the RCS to minimize SGTR breakflow SID III

EPE038 EA1.04 (4.3/4.1)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. RC I Locally establish RCS and SG HIILO interface integrity. EID VIII

APE068.AA1.21 (3.9/4.1) I APE067.AA2.16 (3.3/4.0)

J. AFW I Establish make-up to the ECST in accordance with 2-ES- EILIAIRIN IV - S

3.1 Attachment 4. 061A1.04 (3.9/3.9)

k. EDG I Manually start an emergency diesel generator at the local EI AIM VI

panel. 064A4.01 (4.0/4.3)

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems

and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U

(A)Iternate path 4-6 / 4-6 / 2-3

(C)ontrol room

(D)irect from bank s-9 / s 8 / s 4

(E)mergency or abnormal in-plant 2:...1/~1/~1

(EN)gineered safety feature - /- /~1

(L)ow-Power / Shutdown 2:...1/~1/~1

(N)ew or (M)odified from bank including 1(A) 2:...2 / ~ 2 / ~ 1

(P)revious 2 exams S-3/ s 3 / s 2 (randomly selected)

(R)CA 2:..1/~1/~

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: -=:::S...=.UIT:;..:;....L-y _ Date of Examination: March, 2008

Exam Level: RO D SRO-I D SRO-U 0 Operating Test No.: 2008-301

Control Room Systems" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System 1 JPM Title Type Code* Safety

Function

a. ESFAS 1 Transfer the SI System to Cold Leg Recirculation Mode

S/L/AIEN/D II

(1-ES-1.3). KIA - 013A4.01 (4.5/4.8)

b. RHR 1 Initiate RHR alternate decay heat removal by forced feed S/L/D IV -P

cooling with a charging pump. KIA - 005A2.03 (2.9/3.1) and

APE25AA1.02 (3.8/3.9)

c. CS 1 Secure containment depressurization equipment. 026A2.08 S/LIAIM V

(3.2/3.7)

d.

e.

f.

g.

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. RC 1 Locally establish RCS and SG HIILO interface integrity. E/D VIII

APE068.AA1.21 (3.9/4.1) 1 APE067.AA2.16 (3.3/4.0)

j. AFW 1 Establish make-up to the ECST in accordance with 2-ES- E/L/AIR/N IV - S

3.1 Attachment 4. 061A1.04 (3.9/3.9)

k.

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems

and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3

(C)ontrol room

(D)irect from bank ~9/ S8 / S 4

(E)mergency or abnormal in-plant ~1/2:.1/2:.1

(EN)gineered safety feature - / - /2:. 1

(L)ow-Power / Shutdown ~1/2:.1/2:.1

(N)ew or (M)odified from bank including 1(A) ~2 /2:.2/2:. 1

(P)revious 2 exams ~3/ S 3 / .s 2 (randomly selected)

(R)CA ~1/2:.1/2:.

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: ~S....;.;.;urr;;;..;;;;.,Y"l.-- _ Date of Examination: March, 2008

Exam Level: RO D SRO-I 0' SRO-U D Operating Test No.: 2008-301

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I JPM Title Type Code* Safety

Function

a. CVCS I Perform a blended flow make-up to the Unit 1 RWST in

SIN I

accordance with 1-0P-CS-004. KIA - 004A4.04 (3.2/3.6)

b. ESFAS I Transfer the SI System to Cold Leg Recirculation Mode

SIL/AIENID II

(1-ES-1.3). KIA - 013A4.01 (4.5/4.8)

c. RHR I Initiate RHR alternate decay heat removal by forced feed SILID IV - P

cooling with a charging pump. KIA - 005A2.03 (2.9/3.1) and

APE25AA1.02 (3.8/3.9)

d. CS I Secure containment depressurization equipment. 026A2.08 SILINM V

(3.2/3.7)

e. NI I Remove a failure source range NI from service during a SILl AID VII

reactor startup. 015A4.03 (3.8/3.9)

f. CW I Respond to a low level transient. 075A2.02 (2.5/2.7) SID VIII

g. WGDS I Initiate the release of a waste gas decay tank. 071A4.26 SlAIN IX

(3.1/3.9)

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. RC I Locally establish Res and SG HIILO interface integrity. EID VIII

APE068.AA1.21 (3.9/4.1) I APE067.AA2.16 (3.3/4.0)

j. AFW I Establish make-up to the ECST in accordance with 2-ES- EIL/AIR/N IV - S

3.1 Attachment 4. 061A1.04 (3.9/3.9)

(

k. EDG I Manually start an emergency diesel generator at the local EINM VI

panel. 064A4.01 (4.0/4.3)

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems

and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3

(C)ontrol room

(D)irect from bank ~9 / s 8 / ~4

(E)mergency or abnormal in-plant >1/>1/>1

(EN)gineered safety feature - /- /?1

(L)ow-Power / Shutdown ?-1 /?1 /?1

(N)ew or (M)odified from bank including 1(A) ?-2 / ? 2 / ? 1

(P)revious 2 exams ~3/ s 3 / s 2 (randomly selected)

(R)CA ?-1/?1/?

(S)imulator

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure 004A2.27

Applicant, _ Start Time _

Examiner _

Date _ Stop Time _

PERFORM A BLENDED FLOW MAKEUP TO THE UNIT 1 RWST.

KIA: 004A2.27 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and

(b) based on those predictions, use procedures to correct, control or mitigate the consequences of those .

malfunctions or operations: Improper RWST boron concentration. (3.5/4.2)

Applicability Estimated Time Actual Time

RO/SRO(I) 10 Minutes

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.

The Unit SRO has calculated and the STA verified the POT SETTINGS for a 2300 ppm boron concentration

makeup to be:

o PG - 80 gpm - 5.36 pot setting

o BA -15.75 gpm - 6.32 pot setting

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 Safeguards 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.

Terminating Cues

004A2.27 SR08301 1 of 11

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 (REV12)

DRP-003, Curve Book

Tools and Equipment Safety Considerations

Straight Edge * None

Calculator

004A2.27 SR08301 2 of 11

Simulator Setup

Call up 100% power IC and initialize.

Set BA pot to 1.8 and the PG pot for 6.67.

Initiating Cues

Unit 1 RWST level nee~s 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.

The Unit SRO has calculated and the STA verified the POT SETTINGS for a 2300 ppm boron concentration

makeup to be:

o PG - 80 gpm - 5.36 pot setting

o BA - 15.75 gpm - 6.32 pot setting

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 Safeguards 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.

004A2.27 SR08301 3 of 11

PERFORMANCE CHECKLIST

Notes to the Evaluator

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

An additional instructor may be needed to silence and acknowledge alarms 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:

004A2.27 SR08301 4 of 11

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.

EVALUATOR'S NOTE:

If asked: Emergency borate flowpath is available.

COMMENTS:

STEP 4:

_ _ _ SAT

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

THE RCS. (Step 5.1.4) _ _ _ 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-1113A (1.8)

b) Records present setting on Primary Grade Water Controller.1-CH-FC-1114 (6.67)

COMMENTS:

004A2.27 SR08301 5 of 11

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:

004A2.27 SR08301 6 of 11

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:

INSTRUCTOR NOTE: When directed to perform the above actions, open CH-208. Perform

a time compression and report all above valves have been positioned

as directed.

STEP 9:

_ _ _ SAT

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

_ _ _ UNSAT

STANDARD:

a) Sets Boric Acid Integrator for 500 gpm.

b) Sets Primary Grade Water Integrator for 5000 gpm.

EVALUATOR'S NOTE:

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

blended make-up can be performed.

If asked: Set the Boric Acid Integrator at 500 gallons and PG at 5000 gallons.

However, I want you to stop the makeup manually after adding 10/0 to the

RWST.

COMMENTS:

004A2.27 SR08301 7 of 11

STEP 10:

_ _ _ SAT

SET THE BA 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 15.75 gpm. (6.32 +/- .2 Pot Setting)

(15.3 to 16.3 gpm)

b) Sets Primary Grade Water Flow Controller for 80 gpm. (5.36 +/- .2 Pot Setting)

(78 to 84 gpm)

EVALUATOR'S NOTE:

Tolerance to be +/- .2 Pot Setting.

COMMENTS:

STEP 11:

_ _ _ SAT

PLACE THE MAKE-UP MODE SEL SWITCH TO THE MANUAL POSIT~ON (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:

004A2.27 SR08301 8 of 11

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.

c) Prior to completion, flow must be in the following ranges:

Boric Acid - 15.3 to 16.3 gpm

PG Water - 78 to 84 gpm

EVALUATOR'S NOTE:

If applicant identifies wrong flowrate, state "Please set flow rates as originally discussed".

Once the makeup has been initiated, the evaluator will indicate that the JPM has been

completed.

COMMENTS:

STOP TIME:

004A2.27 SR08301 9 of 11

Operator Directions Handout

(TO BE READ TO APPLICANT BY EXAMI,~ER)

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 10/ 0.

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.

The Unit SRO has calculated and the STA verified the POT SETTINGS for a 2300 ppm boron concentration

makeup to be:

o PG - 80 gpm - 5.36 pot setting

o BA - 15.75 gpm - 6.32 pot setting

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 Safeguards 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.

004A2.27 SR08301 10 of 11

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

Initial Conditions

Unit 1 is at 100% power.

Unit 1 RWST needs to be raised by approximately 10/ 0 *

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.

The Unit SRO has calculated and the STA verified the POT SETTINGS for a 2300 ppm boron concentration

makeup to be:

o PG - 80 gpm - 5.36 pot setting

o BA - 15.75 gpm - 6.32 pot setting

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 Safeguards 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.

004A2.27 SR08301 11 of 11

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

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. (REV 17)

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 (RC01 01).

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 pumps, two (2) HHSI pumps & all ISRS pumps, OSRS pumps and CS pumps should be running.

HHSI pumps should be on redundant flowpath alignment and charging pump mini-flow recirc valves should be

closed.

When RWST level is - 210/0, place the control switch for 1-CS-P-1A in PTL and rackout breaker 14H5

5

When RWST level is -150/0 (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 200/0.

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 20%. '

1-CS-P-1A is tagged out.

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 may be needed to silence and acknowledge alarms 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 3s)

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-106D (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 8Y 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-18 (associated wi 8 RSHX).

c) 1-RS-P-2A (associated wi C RSHX).

d) 1-RS-P-28 (associated wi D RSHX).

COMMENTS:

STEP 6:

_ _ _ SAT

VERIFIES LHSI PUMPS - 80TH 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-12758 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 13%.

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 B.

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-1863B 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-MOY-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-MOY-18858 by placing control switch to CLOSE.

d) Checks 1-SI-MOV-1885S closed by observing green light on & red off.

e) Closes 1-SI-MOY-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-MOY-1885D by placing control switch to CLOSE.

h) Checks 1-SI-MOV-1885D closed by observing green light on & red off.

EYALUATOR'S NOTE:

1-SI-MOV-1885A and D supply "A" LHSI pump, 1-SI-MOV-1885B and C supply "S" 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 BENCHSOARD - LIT. (Step 5d(1))

_ _ _ UNSAT

STANDARD:

a) Checks Phase 2 Amber Status light not lit.

b) Ensures 1minute elapsed 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 observing 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 observing 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 VALVES. (Step 5d(3))

UNSAT

STANDARD:

a) Closes1-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-1"1158 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 (B 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 20%.

1-CS-P-1A is tagged out.

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)

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 20%.

1-CS-P-1A is tagged out.

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 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) 25 Minutes

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 has had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

Here is a copy of AP-27.00, Attachment 6 & 7. I need you to initiate alternate decay heat removal by performing

forced feed cooling, using a Charging pump to a hot leqftow path by completing Attachment 6.

"A" and "B" Charging Pumps are tagged out.

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 SI flow established.

Procedures

1-AP-27.00, Loss of Decay Heat Removal Capability, Attachment 6 (REV 17)

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 8 = O. SIMOV869A and B_Rack in = T. Set

CSM101 to equate to -90% 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.

Close 1-CH-MOV-1287C, 1270B and 1275C.

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 has had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

Directions to the Applicant

The Plant is currently operating at mid-loop on RHR and has had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

Here is a copy of AP-27.00, Attachment 6 and 7. I need you to initiate alternate decay heat removal by

performing forced feed cooling, using a Charging pump to a hot leg flow path by completing Attachment 6.

"A" and "B" Charging Pumps are tagged out.

Both LHSI pumps are tagged out.

Pressurizer Safety Valves are not removed.

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 (*).

Core boiling will result in this JPM being declared Unsat. Core boiling occurs - 40 minutes after JPM begins.

An additional instructor may be needed to silence and acknowledge alarms 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: LHSI pumps are not available.

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-11158 control switch in the OPEN position until valve

position lights indicate valve is open.

b) Places 1-CH-MOV-1115Dcontrol switch in the OPEN position until valve

position lights indicate valve lsopen,

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-1115Ccontrol switch in the CLOSE position until valve

position lights indicate valve is closed.

b) Places 1-CH-MOV-1115Econtrol 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:

a) Checks IICII Charqinqpurnp 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

b) Identifies that 1-CH-MOV-1287C, 1270B and 127~C are not open and manually opens

valves.

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 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months , 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 and 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 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

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 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months 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. (A minimum flow of 310 gpm

must be achieved to successfully complete this JPM) Observe SI flow indicated

on the following flow transmitters:

1-SI-FI-1943 & 1943A (Total hdrflow), 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) If hot leg injection NOT controlling RCS temperature as indicated by increasing

pressurizer liquid and vapor space temperatures or by decreasing subcooling, then do

either of the following:

1. Increase SI flow rate (or)

2. Swap to cold leg injection

(If adequate flow exists temperatures will not be increasing)

g) GO TO Step 22

EVALUATOR'S NOTE:

If asked: Provide cue time since shutdown is 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

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 200/0, 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 has had a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

Here is a copy of AP-27.00, Attachment 6 and 7. I need you to initiate' alternate decay heat removal by

performing forced feed cooling, using a Charging pump to a hot leg flow path by completing Attachment 6.

"A" and "B" Charging Pumps are tagged out.

Both LHSI pumps are tagged out.

Pressurizer Safety Valves are not removed.

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)

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 has had "a non-recoverable loss of RHR cooling. The

reactor has been SID for 230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

Here is a copy of AP-27.00, Attachment 6 and 7. I need you to initiate alternate decay heat removal by

performing forced feed cooling, using a Charging pump to a hot leg flow path by completing Attachment 6.

"A" and "8" Charging Pumps are tagged out.

Both LHSI pumps are tagged out.

Pressurizer Safety Valves are not removed.

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

005A2.03 SR08301 12 of 12

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

Conditions

Task is to be PERFORMED in the Simulator.

A large break LOCA has occurred from 100% power. 1-E-0 has been performed and transition made to 1-E-1.

1-E-1 has been performed through Step 8. Power has been lost to the Low Level Intake Structure and all ESW

pumps are running.

Standards

Containment spray equipment secured lAW 1-E-1 Steps 9 through 12.

Initiating Cues

You are the Unit RO & I am the Nuclear Shift Manager. A loss of all power at the Low Level Intake Structure

occurred due to lightning striking 1G and 2G transformers.

We subsequently had a large-break LOCA. 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.

When Hi-Hi CLS initiated, 1-CS-P-1 8 tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator is performing ES-1.3, Transfer to

Cold Leg Recirculation, and is monitoring the operation of RMT.

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 (REV 29)

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.

De-energize 1G and 2G transformers

Start all 3 ESW Pumps

Initiate LBLOCA (RC0101) and perform E-O followed by E-1 up to step 9.

Run until RWST level is < 200/0.

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

Defeat ability to operate CS-MOV-101A and B

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. A loss of all power at the Low Level Intake Structure

occurred due to Ii~Jhtning striking 1G and 2G transformers.

We subsequently had a large-break LOCA. 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..

When Hi-Hi CLS initiated, 1-CS-P-1B tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator is performing ES-1.3, Transfer to

Cold Leg Recirculation, and is monitoring the operation of RMT.

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 will be needed to silence and acknowledge alarms 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 both emergency buses energized and continues step 9.

EVALUATOR'S NOTE:

If CLS reset is missed at this point, it is acceptable to reset later when manipulating

components.

COMMENTS:

Page 4 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 2:

_ _ _ SAT

VERIFY ALL SPRAY SYSTEM COMPONENTS ON THE SW 'A' HEADER OPERATING.

(Step 9d) _ _ _ UNSAT

STANDARD:

a) Verify all spray system components on the SW 'A' header operating by checking the

following components:

1-CS-P-1 B - Running

1-RS-P-1 A - Running

1-RS-P-2B - Running

1-RS-MOV-155B- Open

1-RS-MOV-156B - Open

1-SW-MOV-103A or B - Open

1-SW-MOV-104A and D - Open

1-SW-MOV-105A and D - Open

b) Identifies 1-CS-P-1 B is not running and GOES TO RNO column.

EVALUATOR'S NOTE:

Candidate may go straight to RNO after checking 1-CS-P-1 B not running.

COMMENTS:

Page 5 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 3:

_ _ _ SAT

VERIFY ALL SPRAY SYSTEM COMPONENTS ON THE SW '8' HEADER OPERATING.

(Step 9d RNO) _ _ _ UNSAT

STANDARD:

a) Verify all spray system components on the SW '8' header operating by checking the

following components:

1-CS-P-1A - Running

1-RS-P-18 - Running

1-RS-P-2A - Running

1-RS-MOV-155A- Open

1-RS-MOV-156A-Open

1-SW-MOV-103C or D - Open

1-SW-MOV-1048 and C - Open

1-SW-MOV-1058 and C - Open

b) If all SW '8' header components are operating, then do the following:

1) Stops the following pumps by taking the control switch to OFF:

1-SW-P-5A

1-SW-P-5D

2) Manually or locally close the following MOVs:

1-SW-MOV-104A and D - Close

1-SW-MOV-105A and D - Close

3) Stop the following pumps and put in PTL:

1-RS-P-1A

1-RS-P-28

4) GO TO Step 11

COMMENTS:

INSTRUCTOR NOTE: May need to add RWST leak (CS10) to expedite RWST drawdown.

When RS-P-1A and 8 are secured, implement CS10 @ 50% deg.

Set CS10 deg to 0 when RWST level is 30/0.

Page 6 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 4:

_ _ _ SAT

CHECK EMERGENCY SERVICE WATER PUMPS - THREE RUNNING. (Step 11)

_ _ _ UNSAT

STANDARD:

Recalls from initial directions 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 5:

_ _ _ SAT

CHECK IF CONTAINMENT SPRAY PUMPS CAN BE STOPPED (Step 12a)

_ _ _ UNSAT

STANDARD:

Checks the following:

RWST level less than 30/0 (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:

a) Secures 1-RS-P-2A ("A" OSRS pump) and returns switch to AUTO.

COMMENTS:

STEP 11

_ _ _ SAT

STOP CONTAINMENT SPRAY PUMP AND PUTS SWITCH IN AUTO. (Step 12d)

(Step 1) _ _ _ UNSAT

STANDARD:

Secures 1-CS-P-1A ("A" CS pump) and returns switch to AUTO.

EVALUATOR'S NOTE:

1-CS-P-18 ("8" CS pump) does not need to be secured due pump previously tripping.

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-1018

1-CS-MOV-101C

1-CS-MOV-101D

Identifies 1-CS-MOV-101A and 1-CS-MOV-1018 do not close and goes to RNO column.

COMMENTS:

Page 8 of 11

Surry 2008-301 Secure Containment Depressurization Equipment

STEP 13:

_ _ _ SAT

CLOSE SUCTION MOV ON CS PUMP(S) WITH AN OPEN DISCHARGE MOV.

(Step 12e RNO) _ _ _ UNSAT

STANDARD:

Closes the following valve by taking the control switch to the close position:

1-CS-MOV-100A

COMMENTS=

STEP 14:

_ _ _ 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

COMMENTS:

STEP 15:

_ _ _ 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.

1G and 2G transformers were lost due to lightning strikes. 3 ESW pumps are running.

A Large Break LOCA is in progress with the team performing 1-E-1, Lossot Reactor or Secondary Coolant.

When Hi-Hi CLS initiated, 1-CS-P-1B tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator will perform ES-1.3, Transfer to Cold

Leg Recirculation, and monitor the operation of RMT when the setpoint is reached.

Initiating Cues

You are the Unit RO & I am the Nuclear Shift Manager. A loss of all power at the Low Level Intake Structure

occurred due to lightning striking 1G and 2G transformers. .

We subsequently had a large-break LOCA. 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.

When Hi-Hi CLS initiated, 1-CS-P-1 B tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator is performing ES-1.3, Transfer to

Cold Leg Recirculation, and is monitoring the operation of RMT.

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)

Initial Conditions

Unit 1 was at 1000/0 power.

1G and 2G transformers were lost due to lightning strikes. 3 ESW pumps are running.

A Large Break LOCA is in progress with the team performing 1-E-1, Loss of Reactor or Secondary Coolant.

When Hi-Hi CLS initiated, 1-CS-P-1B tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator will perform ES-1.3, Transfer to Cold

Leg Recirculation, and monitor the operation of RMT when the setpoint is reached.

Initiating Cues

You are the Unit RO & I am the Nuclear Shift Manager. A loss of all power at the Low Level Intake Structure

occurred due to lightning striking 1G and 2G transformers.

We subsequently had a large-break LOCA. 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.

When Hi-Hi CLS initiated, 1-CS-P-1B tripped and could not be restarted.

Annunciator A-A-7, RWST LO LEVEL, was just received. Another operator is performing ES-1.3, Transfer to

Cold Leg Recirculation, and is monitoring the operation of RMT.

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 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 and/or monitor in the control room: Trip bypasses (3.8/3.9)

Applicability Estimated Time Actual Time

RO/SRO(I) 5 Minutes

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-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.

Terminating Cues

Completion of 1-AP-4.00, Nuclear Instrumentation Malfunction.

Procedures

1-AP-4.00, Nuclear Instrumentation Malfunction (REV 22)

Page 1 of 9

Surry 2008-301 Remove SR NI From Service

Tools and Equipment Safety Considerations

None * None

Page 2 of 9

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

(MNI0101, 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 Pushbuttons. 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 9

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 periormance of that task element.

An additional instructor may be needed to silence and acknowledge alarms 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 9

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 RNO

Column.

Page 5 of 9

Surry 2008-301 Remove SR NI From Service

STEP 5:

_ _ _ SAT

REMOVE FAILED SOURCE RANGE NI FROM OPERATION.

_ _ _ UNSAT

STANDARD:

a) Pushes 1I1/N 33A TR All pushbutton and "1/N 33B TR 8 pushbutton.

11

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 BYP" will be

received.

d) * Places LEVEL TRIP switch for N-31 in BYPASS.

e) * Removes INSTRUMENT POWER fuses for N-31.

f) * Places LEVEL T.RIP 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:

It is acceptable to place both SRNI in LEVEL TRIP BYPASS before removing the

INSTRUMENT POWER fuses.

It is acceptable to stop at i) (step 22 RNO steps 4 & 5). AP-4.00 may remain open until

repairs completed or shutdown performed.

CUES

Tell operator (or if asked): The SS will ensure that Tech Specs are checked and that

appropriate log entries will be made.

COMMENTS:

Page 6 of 9

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 9

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 wi'll 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 8 of 9

Surry 2008-301 Remove SR NI From Service

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

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

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

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. (REV 25)

Tools and Equipment Safety Considerations

None * None

075A2.02 SR08301 1 of 10

Simulator Setup

Call up 100% IC and initialize.

Implement EL0802 and place simulator in RUN.

Allow canal level to decrease to -25.5 feet.

Set CW MOV pots to 30 seconds.

Verify Canal Level trend on wide range scale.

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 resulting in loss of 2G Screenwell

Transformer. 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 2 of 10

PERFORMANCE CHECKLIST

Notes to the Evaluator

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

A reactor trip will result in this JPM being declared Unsat. Trip occurs at 23.5 feet canal level.

An additional instructor may be needed to silence and acknowledge alarms 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:

a) Acknowledges note that EPIPs may be applicable.

b) 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:

075A2.02 SR08301 3 of 10

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:

075A2.02 SR08301 4 of 10

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:

075A2.02 SR08301 5 of 10

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 (15G8) 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 CW pump by clicking on CW

pump ICON on PCS CW 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 (OP-48.1, Starting any CW Pump).

EVALUATOR'S NOTE:

If asked: Greater than 5 minutes have elapsed since loss of transformer.

If asked: All Circ Water Pumps are in REMOTE.

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:

075A2.02 SR08301 6 of 10

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 0-SW-OP-002.

If asked: Operator will perform Attachment 2.

If asked: Operator is performing OP-48.1.1.

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.

UNIT (2) CUE: If asked: F-G-1(Intake Canal Low Level) is not lit on Unit 2

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:

075A2.02 SR08301 7 of 10

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.

If asked: No load reduction occurred.

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.

EVALUATOR'S NOTE:

This is the end of the JPM. You may stop the candidate at this point.

COMMENTS:

STOP TIME:

075A2.02 SR08301 8 of 10

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 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 resulting in loss of 2G Screenwell

Transformer. 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 9 of 10

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

Initial Conditions

Both units are at 1000/0 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 resulting in loss of 2G Screenwell

Transformer. 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 10 of 10

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

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

rd

You are the 3 License 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 96%

Oxygen Concentration 0.05%

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.

The Maximum Release Rate from the Release Form is 7.5 scfm.

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

Page 1 of 10

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. (REV 14)

Tools and Equipment Safety Considerations

None * None

Page 2 of 10

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

rd

You are the 3 License 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 960/0

Oxygen Concentration 0.050/0

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.

The Maximum Release Rate from the Release Form is 7.5 scfm.

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

Page 3 of 10

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 may be needed to silence and acknowledge alarms 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.

If asked: The operations computer calculation program is not available.

COMMENTS:

Page 4 of 10

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-1 01, 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. (Step 5.3.2)

1-GW-24, WGDT 1B Release Isolation. (Step 5.3.3)

1-GW-21, WGDT 1A Recycle Isolation (Step 5.3.4)

c) Verifies the following valves open by dispatching an operator to locally check valve

postion:

1-GW-20, WGDT 1A Outlet Isolation. (Step 5.3.5)

1-GW-23, WGDT 1A Release Isolation (Step 5.3.6)

INSTRUCTOR NOTE: When directed to perform these manipulations, state that a time

compression has occurred and the valves have been positioned as

directed. (steps 5.3.2 thru 5.3.6)

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. (CRITICAL STEP)

b) Observes green light OFF and red light ON for 1-GW-FCV-1 01.

COMMENTS:

Page 5 of 10

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

EVALUATOR NOTE: Momentarily going above 0.5 scfm is allowable.

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 10

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 96% (or)

b) Calls chem istry to get Hydrogen Concentration

EVALUATOR'S NOTES:

If asked: Hydrogen concentration is 96%

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 800/0 limitations

b) Notes hydrogen concentration is greater than 80% and refers to Attachment 4 to

determine maximum flow rate from WGDT.

EVALUATOR'S NOTES:

If asked: Hydrogen concentration is 96%

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 3.5%

(CRITICAL STEP)

COMMENTS:

Page 7 of 10

Surry 2008-301 Release a Waste Gas Decay Tank

STEP 10:

_ _ _ SAT

ADJUST 1-GW-FCV-101 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.

(CRITICAL STEP)

EVALUATOR NOTE: AUTO control may be used on 1-GW-FCV-101.

Momentarily exceeding flowrate limit is acceptable.

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 10

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

rd

You are the 3 License and I am the Nuclear Shift Manager.

1-GW-T"K-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 96%

Oxygen Concentration 0.05%

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.

The Maximum Release Rate from the Release Form is 7.5 scfm.

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)

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

rd

You are the 3 License 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 96%

Oxygen Concentration 0.05%

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.

The Maximum Release Rate from the Release Form is 7.5 scfm.

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

071A4.26 SR08301 10 of 10

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

Simulator Job Performance Measure EPE038EA1.04

ALTERNATE PATH

Applicant _ Start Time _

Examiner _

Date _ Stop Time _

DEPRESSURIZE THE RCS TO MINIMIZE SGTR BREAKFLOW.

KIA: EPE038EA1.04Ability 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

Conditions

Task is to be PERFORMED in the simulator.

A SGTR in lie" 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 and 20.

Initiating Cues

I am the Nuclear Shift Manager. We have a SGTR in the "C" 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 the 1-E-3 depressurization steps; I want you to depressurize the RCS lAW 1-E-3.

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

Page 1 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Terminating Cues

Report received that RCS depressurization completed.

Procedures

1-E-3, Steam Generator Tube Rupture. (REV 36)

Tools and Equipment Safety Considerations

None * None

Page 2 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Simulator Setup

Call up 100 % power IC and initialize.

Enter malfunction for SGTR in "C" SG at -450 gpm (RC2403 @ 50% degradation).

Call up the "C" Main Steam line & close 1-MS-158.

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 & B 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.

Set the following switch overrides:

RCPC444J_AUTO, OFF

RCPC444J_MANUAL, ON

RCPC444J_LOWER, OFF

RCPC444J_RAISE, OFF

RCPC444G_AUTO,ON

RCPC444H_AUTO, ON

Set the following lamp overrides:

RCPC444J_RED, OFF

RCPC444J_WHITE, ON

Initiating Cues

There is a SGTR in the "C" 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

I am the Nuclear Shift Manager. We have a SGTR in the "C" 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 depressurization steps; I want you to depressurize the RCS.

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

Page 3 of 9

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 may be needed to silence and acknowledge alarms 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 attempts to increase demand to open the spray valves.

- AND/OR**

b) Attempts to place PZR Master Controller (1-CH-PC-1444J) in MANUAL.

c) Identifies that neither of the above methods work; goes to RNO and goes to step 20.

COMMENTS:

Page 4 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

STEP 3: (Step 20 CAUTIONS AND NOTE)

_ _ _ SAT

STANDARD: _ _ _ UNSAT

a) Acknowledges Caution that PRT may rupture if a pressurizer PORV is used for RCS

Depressurization, rupturing the PRT may result in abnormal containment conditions.

b) Acknowledges Caution that cycling of the pressurizer PORV should be minimized.

c) Acknowledges Note that the upper head region may void during RCS

depressurization if RCPs are not running. This will result in a rapidly increasing

pressurizer level.

COMMENTS:

STEP 4: (Step 20a and b)

_ _ _ SAT

DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL

PRESSURIZER. (Step 20) _ _ _ UNSAT

STANDARD:

a) Determines that at least one pressurizer PORV is available.

b) Open one pressurizer PORV until ANY of the following conditions satisfied:

See next page for criteria.

COMMENTS:

Page 5 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

STEP 5:

_ _ _ SAT

DETERMINES IF PORV CLOSING 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.

- OR**

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).

- OR**

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, maintains PORV open until one of the three

criteria are met.

e) When one of the criteria are met, closes the pressurizer PORV.

EVALUATOR'S NOTE:

Exceeding either of the following limits will result in an UNSAT JPM performance:

Pressurizer going solid (or)

RCS subcooling indicating saturated conditions in RCS

COMMENTS:

Page 6 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

STEP 6:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that ReS depressurization completed.

COMMENTS:

Page 7 of 9

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.

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 SGTR in "C" 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 IICII 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 the 1-E-3 depressurization steps; I want you to depressurize the RCS lAW 1-E-3.

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

EPE038EA1.04 SR08301 8 of 9

Surry 2008-301 Depressurize RCS to minimize SGTR breakflow

Operator Directions Handout

(TO BE GIVEN TO APPLICANT)

Initial Conditions

A SGTR in "C" 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 "C" 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 the 1-E-3 depressurization steps; I want you to depressurize the RCS lAW 1-E-3.

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

EPE038EA1.04 SR08301 9 of 9

Surry 2008-30-1 Establish HI/LO Interface Integrity

U.S. Nuclear Regulatory Commission

Surry Power Station

SR08301

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

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.

th

I am the Shift Manager. You are the 4 RO on shift. 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. (REV 40)

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.

th

I am the Shift Manager. You are the 4 RO on shift. 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.

Page 3 of 8

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:

Page 4 of 8

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 CUE:

If applicant identifies a label discrepancy for 1-RC-SOV-100A-1/2, 1-RC-SOV-101A-

1/2, 1-RC-SOV-100B-1/2, and/or 1-RC-SOV-101 B-1/2, direct the applicant to continue

with switch positioning as directed. The label discrepancy for the 1/2 at the end of

each valve number will be resolved by shift management.

EVALUATOR'S NOTE:

DO NOT allow candidate to manipulate any controls - Simulate Only.

COMMENTS:

Page 5 of 8

Surry 2008-301 Establish HI/La Interface Integrity

STEP 3:

_ _ _ SAT

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR).

_ _ _ UNSAT

STANDARD:

Verbal status report made that you have completed locally establishing RCS & SG HI/La

interface integrity for Unit 1 only lAW steps 4 and 5 of Attachment 1 of FCA-1.00

COMMENTS:

STOP TIME:

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.

th

I am the Shift Manager. You are the 4 RO on shift. 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)

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.

th

I am the Shift Manager. You are the 4 RO on shift. 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

u.s. Nuclear Regulatory Commission

Surry Power Station

SR08301

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

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 Unit 2 Above Ground ECST is below 200/0 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, Attachment 4. I need you to locally makeup to

the Unit 2 Above Ground 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.

061 A1.04 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. (REV 18)

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 Unit 2 Above Ground 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 20%.

Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, Attachment 4. I need you to locally makeup to

the Unit 2 Above Ground 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 CUES:

a) When candidate attempts to open 2-CN-150, report that the handwheel will not

turn regardless of how much force is used.

b) Direct the candidate to align both AFW Booster Pumps to the suction of the

AFW Pumps lAW 2-ES-3.1, Attachment 4, Step 2 - 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 (Underground ECST) 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) (CRITICAL TASK)

b) 2-FW-284 (for FW-P-3A) (CRITICAL TASK)

c) 2-FW-285 (for FW-P-3B) (CRITICAL TASK)

EVALUATOR'S NOTE:

If asked: All AFW pumps are available

If asked: (Prior to opening) valve stem is down (-~ 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

STEP 5:

_ _ _ 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. (CRITICAL TASK)

b) Starts FW-P-4B by taking control switch to START position. (CRITICAL TASK)

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). (CRITICAL TASK)

b) Closes 2-FW-168 (for FW-P-3A). (CRITICAL TASK)

c) Closes 2-FW-183 (for FW-P-3B). (CRITICAL TASK)

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.

If operator attempts to call the MCR to verify AFW flow, report that flow is 150 gpm to each

SG.

COMMENTS:

061A 1.04 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, Attachment 4. I need you to locally makeup to

the Unit 2 Above Ground 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 9 of 10

Operator Directions Handout

(TO BE GIVEN TO APP"LICANT)

Initial Conditions

A simulated loss of secondary heat sink is in progress. The ECST is below 200/0 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 200/0.

Here's a copy of 2-ES-3.1, Post-SGTR Cooldown using Backfill, Attachment 4. I need you to locally makeup to

the Unit 2 Above Ground 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

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

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

O-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. You are an extra RO on shift. We currently have a fire with a loss of offsite

power. #1 EDG failed to auto-start 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 1 of 16

Terminating Cues

Report received that O-FCA-12.00, Step 31 completed.

Procedures

O-FCA-12.00, Emergency Diesel Generator Operation. (REV 11)

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. You are an extra RO on shift. We currently have a fire with a loss of offsite

power. #1 EDG failed to auto-start 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.

'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 statements 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 EMERG 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) "H" 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

VERIFIES "AUTO/LOCAL" SELECTOR SWITCH ON ENGINE CONTROL CABINET IN

"AUTO". (Step 2) _ _ _ UNSAT

STANDARD:

Checks Engine Control Cabinet "AUTO/LOCAL" selector switch in the "AUTO" 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. (StepS)

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 8 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 I::DG OVERCURRENT NOT PRESENT. (Step 23)

_ _ _ UNSAT

STANDARD:

a) Proceeds to breaker 15H3.

b) Verifies no orange flag drops on 15H3.

EVALUATOR'S NOTI::

If asked: No orange flag drops exist on 15H3.

COMMENTS:

STEP 12:

_ _ _ SAT

LOCALLY VERIFY EMER GEN # 1 PUSH BUTTON RESET - RESET (AUX TRIP RELAY).

(Step 24) _ _ _ UNSAT

STANDARD:

a) Proceeds to #1 EDG-DIP in #1 ESGR.

b) Pushes EMEF~G 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) Cheek all six air bottle stop valves - open.

e) 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. (NOT AUTO alarm light is lit, all others are 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 IIH II bus.

EVALUATOR'S NOTE:

If asked: Breaker 15H3 indication shows red light on and green light off.

If asked: "HII 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

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. You are an extra RO on shift. We currently have a fire with a loss of offsite

power. #1 EDG failed to auto-start 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)

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. You are an extra RO on shift. We currently have a fire with a loss of offsite

power. #1 EDG failed to auto-start 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

ML081260327

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