Text

Surry Initial Exam 2010-301 Draft Administrative JPMs
	ML102780342
Person / Time
Site:	Surry
Issue date:	09/14/2010
From:	; NRC/RGN-II
To:	; Virginia Electric & Power Co (VEPCO)
References
	50-280/10-301, 50-281/10-301
	Download: ML102780342 (397)
	v • d • e

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 1 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.

1.20 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Determine Partial Pressure following a Loss of Containment Cooling K/A: G2.1.20

- Ability to interpret and execute procedure steps. (4.6/4.6) Applicability Est Completion Time Actual Time

SRO(I) 30 Minutes ___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Standards Correctly determine partial pressure in accordance with ARP

-1B-A6 and verifies Tech Spec compliance.

Initiating Cues Given simulated plant conditions, perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 2 of 319 Initia l Conditions I am the Nuclear Shift Manager. I have assigned you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

Approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago Unit 1 was at 100% power when the operating chilled water system chiller tripped. As a result, annunciators 1B-A6 (CTMT PART PRESS

-0.1 PSI CH 1) and 1B

-B6 (CTMT PART PRESS

-0.1 PSI CH 2) were received.

The operating team has implemented ARP

-1B-A6 up to the point of implementing Attachment 2.

Maintenance has determined that the chiller will not be returned to service until tomorrow.

Applicable Plant conditions are located below and as attachments to this JPM

Previous PT

-36.00 data:

Date: Today Time: 0000 CTMT Air Partial Pressure:

10.4 1 psia Here is a copy of Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1. I need you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

When you have completed this task please inform me of the results

. Terminating Cues Steps 1-13 of Attachment 2 of ARP 1B

-A6 are complete.

Procedures Attachment 2 of procedure 1B

-A6 , CTMT PRESS

-0.1 PSI CH 1 Tech Spec 3.8 Tools and Equipment Safety Considerations Calculator Steam Tables Tech Specs DRP-003 None Notes PCS Screen Shots are provide to facilitate classroom performance.

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 3 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: Notes prior to Step 1 of Attachment 2

This calculation is required at a minimum of every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to satisfy Tech Spec 3.8. However, if CTMT cooling conditions change adversely, this calculation should be performed more frequently, at the discretion of Shift Supervision.

Performance of this calculation immediately after loss of CTMT cooling is not required; however, it must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of the last satisfactory surveillance. (typically within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of the last valid 1

-PT-36 log reading)

Air partial pressure (P air) is obtained from the formula Ptot

- Psat = Pair Ptot is CTMT pressure from one of the following:

o The highest of 1

-CV-PI-101A or 1-CV-PI-101B o The highest of Unit 1 PCS points P1LM002A, P1LM003A, P1LM001A, or P1LM004A Psat is the saturation pressure of the minimum CTMT temperature obtained in Step 3 (using steam tables). This conservatively assumes that the lowest CTMT ambient temperature is at the CTMT saturation temperature. A more precise determination of Psat is allowed in Step 8. This alternative relies on measurement of relative humidity, since the actual saturation temperature is a function of both dry-bulb temperature and relative humidity.

STANDARD: (a) Acknowledges the notes EVALUATOR'S NOTE:

If asked, it is desired to perform this calculation now.

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 4 of 319 STEP 2: Step 1 of Attachment 2:

1. Record the Date, Time, and CTMT Air Partial Pressure from the last valid 1

-PT-36 log reading in the first row of the CTMT Pressure Data Table at the end of this attachment.

STANDARD: a) Obtains required data from supplied PT

-36 and records it on LINE 1 of CTMT PRESSURE DATA TABLE of

. EVALUATOR NOTES:

Page 3 of Attachment 2 will be filled out as follow s: Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI COMMENTS: _______ SAT

_______ UNSAT STEP 3: Step 2 of Attachment 2:

2. Record the Date and Time in the CTMT Pressure Data Table.

STANDARD: a) Records the current Date and Time on Line 2 of CTMT PRESSURE DATA TABLE of attachment 2.

EVALUATOR NOTES:

Page 3 of Attachment 2 will be filled out as follow s: Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI Today/Now COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 5 of 319 STEP 4: Step 3 of Attachment 2:

3. Obtain the minimum CTMT air temperature from Unit 1 PCS Containment Temperatures (Elev) and record in the Tmin column in the CTMT Pressure Data Table. STANDARD: a) Utilizing the PCS Screen Shot for CTMT Air Temperatures

- chooses the reading of 88 °F This is a critical step.

EVALUATOR NOTES:

This PCS Screen Shot is located at the end of this JPM. Page 3 of Attachment 2 will be filled out as follows:

Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI Today/Now 88 °F COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 6 of 319 STEP 5: Step 4 of Attachment 2:

4. Obtain Ptot from one of the following sources and record in the Ptot column in the CTMT Pressure Data Table.

o The highest of 1

-CV-PI-101A or 1-CV-PI-101B o The highest of Unit 1 PCS points P1LM002A, P1LM003A, P1LM001A, or P1LM004A STANDARD: a) Utilizing the highest (in accordance with note prior to step 1) of either 1

-CV-PI-101A/B or PCS points P1LM002A, P1LM003A, P1LM001A, or P1LM004A. This is a critical step.

EVALUATOR NOTES:

This PCS Screen Shot is located at the end of this JPM.

Page 3 of Attachment 2 will be filled out as follows (using PCS data)

Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI Today/Now 88 °F 11.29 (PCS) Answer: If CV-PI-101A/B chosen

- highest reading should be 11.2 7 psia [range 11.20

- 11.3 0] If PCS points are utilized

- highest reading should be 11.2 9 psia COMMENTS:

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 7 of 319 STEP 6: Step 5 of Attachment 2

5. Use Steam Tables to determine Psat corresponding to the minimum CTMT temperature obtained in Step 3 and record in the Psat column in the CTMT Pressure Data Table.

STANDARD: a) Utilizing minimum temperature obtained in Step 3, determines Psat and records on Line 2 of CTMT PRESSURE DATA TABLE of Attachment 2

- Psat data field.

This is a critical step.

EVALUATOR NOTES:

Should determine Psat to be 0.65551 [0.65

- 0.66] Page 3 of Attachment 2 will be filled out as follows (using PCS data):

Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI Today/Now 88 °F 11.29 (PCS) 0.65551 Answer: 0.65551 [Acceptable Range 0.65

- 0.66] COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 8 of 319 STEP 7: Step 6 of Attachment 2:

6. Calculate Pair by subtracting Psat from Ptot and record in the Pair column in the CTMT Pressure Data Table.

STANDARD:

a) Determines Pair by subtracting Psat from Ptot.

EVALUATOR NOTES:

Page 3 of Attachment 2 will be filled out as follows (using PCS data):

Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.4 1 SI Today/Now 88 °F 11.29 (PCS) 0.65551 10.63449 SI Answer: If CV-PI-101A/B Used

- should calculate Pair to be 10.61449 [range 10.

5 4 - 10.6 5] If PCS used

- should calculate Pair to be 10.

63449 [range 10.

6 3 - 10.6 4] COMMENTS: _______ SAT

_______ UNSAT STEP 8: Note prior to step 7: A more precise measurement of Pair may be obtained by performing the following steps with STA or System Engineering assistance.

STANDARD: (a) Acknowledges the notes EVALUATOR NOTES:

If asked, it is NOT desired to perform this calculation

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 9 of 319 STEP 9: Step 7 of Attachment 2:

7. IF a more precise measurement of Pair is required, THEN perform the remainder of this attachment with STA or Engineering assistance. Otherwise, enter N/A for Steps 8 through 12, AND GO TO Step 13.

STANDARD:

a) Enters N/A on steps 8 through 1 2 and goes to step 1

2. EVALUATOR NOTES:

If asked, it is NOT desired to perform this calculation COMMENTS: _______ SAT

_______ UNSAT STEP 10:

Step 1 3 of Attachment 2

13. Verify CTMT Air Partial Pressure is within Tech Spec 3.8

-1 limits.

STANDARD: a) Obtains a copy of Tech Specs and refers to table 3.8

-1 and determines that partial pressure is NOT within acceptable Tech Spec limits.

This is a critical step.

EVALUATOR NOTE S: Trainee to obtain CW temperature from PCS Screen Shots located at the end of this JPM - CW inlet temp will be 9 4 If report is given that partial pressure is outside of Table 3.8-1 limits, ask the trainee to determine and report applicable LCO limits and actions required.

o Should determine 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months clock to restore to within limits or be in HSD in next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and CSD in following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

COMMENTS:

Surry 2010-301 Calculate Partial Pressure G2.1.20 SR10301 10 of 319 STEP 11: Reports task is complete

. STANDARD: a) Verbal or written status report that the task is complete and that Partial Pressure is outside the limits of TS Table 3.8

-1. This is a Critical Step if not already performed.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

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

Task Task may be PERFORMED in the simulator or classroom.

Correctly determine partial pressure in accordance with ARP

-1B-A6 and verifies Tech Spec compliance

. 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:

I am the Nuclear Shift Manager. I have assigned you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

Approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago Unit 1 was at 100% power when the operating chilled water system chiller tripped. As a result, annunciators 1B-A6 (CTMT PART PRESS

-0.1 PSI CH 1) and 1B

-B6 (CTMT PART PRES S -0.1 PSI CH 2) were received.

The operating team has implemented ARP

-1B-A6 up to the point of implementing Attachment 2.

Maintenance has determined that the chiller will not be returned to service until tomorrow.

Applicable Plant conditions are located below and as attachments to this JPM:

Previous PT

-36.00 data:

Date: Today Time: 0000 CTMT Air Partial Pressure:

10.41 psia Initiating Cues:

Here is a copy of Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure -0.1 PSI Channel 1. I need you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

When you have completed this task please inform me of the results

.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

I am the Nuclear Shift Manager. I have assigned you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

Approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago Unit 1 was at 100% power when the operating chilled water system chiller tripped. As a result, annunciators 1B-A6 (CTMT PART PRESS

-0.1 PSI CH 1) and 1B

-B6 (CTMT PART PRESS

-0.1 PSI CH 2) were received.

The operating team has implemented ARP

-1B-A6 up to the point of implementing Attachment 2.

Maintenance has determined that the chiller will not be returned to service until tomorrow.

Applicable Plant conditions are located below and as attachments to this JPM:

Previous PT

-36.00 data:

Date: Today Time: 0000 CTMT Air Partial Pressure:

10.41 psia

Initiating Cues:

Here is a copy of Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1. I need you to perform Attachment 2 of Annunciator Response Procedure (ARP) 1B

-A6, Containment Pressure

-0.1 PSI Channel 1, to calculate Containment Partial Pressure and Technical Specification Compliance.

When you have completed this task please inform me of the results

.

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 1 of 319 Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 2 of 319 P1LM 001A CNTMT IR PRESSURE (BL) 11.2 9 PSIA P1LM002A CNTMT I R PRESSURE (RD) 11.2 7 PSIA P1LM 003A CNTMT IR PRESSURE (WT) 11.2 3 PSIA P1LM 004A CNTMT IR PRESSURE (YW) 112 5 PSIA Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 3 of 319 88.0 DEG 89.3 DEG 108.2 DEG 96.5 DEG 88.7 DEG 95.6 DEG 92.3 DEG 103.4 DEG 111.8 DEG 97.6 DEG 108.4 DEG F 98.2 DEG 92.7 DEG 98.0 DEG 89.6 DEG 91.4 DEG 93.0 DEG 102.3 DEG 92.5 DEG F 98.0 DEG Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 4 of 319 94.0 DEG INLET TEMP 94.0 DEG INLET TEMP 94.0 DEG INLET TEMP 94.0 DEG INLET TEMP OUTLET TEMP 101.0 DEGF OUTLET TEMP 101.0 DEGF OUTLET TEMP 101.0 DEGF OUTLET TEMP 101.0 DEGF Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 5 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.1.37 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title COMPLETE A REACTIVITY

SUMMARY

SHEET K/A: G 2.1.37 - Knowledge of procedures, guidelines, or limitations associated with reactivity management. (4.3/4.6) Applicability Est Completion Time Actual Time

RO 45 Minutes ___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM

. Performance of 1

-OP-RX-010, Documentation of Reactivity Parameters during Power Operations, is required

. Standards Completes the calculations, within tolerances, that allow for completion of the Reactivity Summary Sheet located in 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations

. Initiating Cues

Given simulated plant conditions, perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1-OP-RX-010, Reactivity Summary Sheet.

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 6 of 319 Initia l Conditions It is mid shift on Saturday. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

The following is reactivity information was supplied by the Reactor Engineer today: Core burnup: 13 0 90 MWD/MTU Isothermal temperature coefficient:

-26.48 pcm/ F Target delta flux:

-0.5% The following are the Unit conditions:

Reactor power: 100%

RCS boron concentration: 4 68 ppm Control Bank 'D' is at 228 steps

'A' BAST is in

-service on Unit 1 with a boron concentration of 13952 ppm

. A power reduction has not occurred and is not planned.

Here is a copy of 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

When you are ready to have your work independently verified, please inform me, as this will end the JPM

. Terminating Cues Reactivity Summary Sheet calculations performed and the candidate is ready for their work to be independently verified

. Procedures 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations (Revision 11)

Tools and Equipment Safety Considerations

Calculator None Notes Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 7 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: 3.0 INITIAL CONDITIONS

3.1 Unit is operating at greater than 50% power (see P&L 4.1).

4.0 PRECAUTIONS AND LIMITATIONS

4.1 The Unit should be at steady state conditions, i.e., constant power (+/

- 5%) for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If the unit is not stable or not above 50% power, then this procedure should be carried daily on the PT schedule until the Unit is at equilibrium condition.

4.2 This procedure should be performed every two weeks as directed by the Operations PT schedule. If RCS boron concentration is less than 200 ppm, this procedure should be done weekly.

STANDARD: (a) Acknowledges Initial Conditions and Precautions and Limitations.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT STEP 2: Note prior to Step 5.1.1: _______ SAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 8 of 319 The items listed in Step 5.1.1 will be updated every 2 weeks by Reactor Engineering.

STANDARD: (a) Acknowledges the Note. EVALUATOR'S NOTE:

None COMMENTS: _______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 9 of 319 STEP 3: Step 5.1.1

5.1.1 The following items have been provided by Reactor Engineering, and will be used for calculations:

Core burn-up Isothermal Temperature Coefficient (ITC)

STANDARD: (a) Acknowledges that this information was provided by Reactor Engineering in the initial conditions.

EVALUATOR'S NOTE: None. COMMENTS: _______ SAT

_______ UNSAT STEP 4: Notes prior to Step 5.2.1:

The following guidelines should be used when performing calculations:

o Do no round numbers until the final value. Then round Boric Acid calculations to the nearest tenth of a gallon and round PG calculations to the nearest gallon. Review Attachment 4 before performing calculations.

o Use the last known reported boron from Chemistry. It is not necessary to interpolate or obtain a sample if one has not been taken for the day.

The following form is located on the Operations network drive in S:/Surry Power Station/3/Data1/OPS/Forms/Reactivity Reactivity1, Unit 1 Form Once calculated, this procedure will remain in effect for two weeks if RCS boron concentration is greater than or equal to 200 ppm. If RCS boron concentration is less than 200 ppm, this calculation should be performed weekly.

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 10 of 319 The Unit 1 Reactor Operator will have the results of this procedure verified by either the Shift Technical Advisor or another licensed Reactor Operator.

STANDARD: (a) Acknowledges the Notes.

EVALUATOR'S NOTE:

None COMMENTS:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 11 of 319 STEP 5: Step 5.2.1

5.2.1 Perform Attachment 1 to calculate reactivity parameters.

STANDARD: (a) Proceeds to Attachment 1 to commence reactivity calculations.

EVALUATOR'S NOTE

None. COMMENTS: _______ SAT

_______ UNSAT

STEP 6: Note prior to Step 1 of Attachment 1:

Unless a specific value is given, the most recent Core Burn

-up value from the Reactor Engineers should be used. This value is listed on the bench board. Do not interpolate for daily burn

-up. STANDARD: (a) Acknowledges the Note.

EVALUATOR'S NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 12 of 319 STEP 7 Attachment 1, Step 1:

1. Using data from Reactor Engineering, the Curve Book, and Chemistry, determine the following parameters:

a. Core Burn-up: (MWD/MTU) b. ITC: (PCM/°F) c. Differential Boron Worth (DBW):

(PCM/PPM) d. Boron Concentration of in

-service BAST (Cb BAST):

ppm STANDARD: Completes Step 1 as indicated below:

1. Using data from Reactor Engineering, the Curve Book, and Chemistry, determine the following parameters:

a. Core Burn-up: 13 0 90 (MWD/MTU) b. ITC: -26.48 (PCM/°F) c. Differential Boron Worth (DBW):

-8.3 0 (PCM/PPM) d. Boron Concentration of in

-service BAST (Cb BAST):

13952 ppm EVALUATOR'S NOTE

a. Core Burn-up was provided as an initial condition.

b. ITC was provided as an initial condition.

c. Is read from a graph in DRP

-0003, Curve Book.

The curve is located at Section 27 (page 53) of DRP

-0003. Answer: -8.3 0 pcm/ppm ACCEPTABLE RANGE: [

-8.28 to -8.3 3] _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 13 of 319 d. BAST Boron Concentration was provided as an initial condition.

COMMENTS:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 14 of 319 STEP 8: Attachment 1, Step 2:

2. Calculate the amount of boron to make a +1 ppm change.

-50813 x LN(1 + 1 / (Current Boron

- Step 1d)) -50813 x LN(1 + 1 / ( - )) =

gal (Reactivity Summary Line 7)

STANDARD: Completes Step 2 as indicated below:

2. Calculate the amount of boron to make a +1 ppm change.

a. -50813 x LN(1 + 1 / (468 - 13952)) b. -50813 x LN(1 + 1 / (-13484)) c. -50813 x LN(1 + (-0.000074162

) [may round to

-0.00007] d. -50813 x LN(0.999925838

) [based on previous rounding 0.99993] e. -50813 x -0.000074165

[based on previous rounding

-0.00007] f. 3.768 gals

[based on previous rounding 3.55 gals]

g. Answer: 3.8 gallons [acceptable range: 3.6

- 3.8 gallons]

This is a critical step.

EVALUATOR'S NOTE:

Candidate may transfer this value to Attachment 2 (Reactivity Summary Sheet) line #7 at this time (or may wait until all calculations are complete).

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 15 of 319 Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 16 of 319 STEP 9: Note prior to Step 3 of Attachment 1:

When RCS Boron Concentration is less than 12 ppm, the equation in Step 3 will yield invalid results. By decreasing the assumed charging line Boron concentration at low RCS Boron Concentration, a value of 35221 gallons of dilution is obtained.

STANDARD: (a) Acknowledges the Note. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 17 of 319 STEP 10: Attachment 1, Step 3:

3. IF RCS Boron concentration is greater than or equal to 12 ppm, THEN calculate the amount of dilution to make a

-1 ppm change in accordance with the following. Otherwise, enter N/A

-50813 x LN(1

- 1 / (Current Boron

- 10)) -50813 x LN(1

- 1 / (

- 10)) =

gal (Reactivity Summary Line 8)

STANDARD: Completes Step 3 as indicated below:

3. Calculate the amount of boron to make a +1 ppm change.

a. -50813 x LN(1

- 1 / (468 - 10)) b. -50813 x LN(1

- 1 / (458)) c. -50813 x LN(1

- (0.002183406

)) [may round to 0.00218] d. -50813 x LN(0.99781659

) [based on previous rounding 0.99782] e. -50813 x -0.002185797

[based on previous rounding

-0.00218] f. 111.07 gals [based on previous rounding 110.77 gals]

g. Answer: 111 gallons [acceptable range: 110.7

-111.1 gallons]

This is a critical step.

EVALUATOR'S NOTE:

Candidate may transfer this value to Attachment 2 (Reactivity Summary Sheet) line #8 at this time (or may wait until all calculations are complete).

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 18 of 319 Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 19 of 31 9 STEP 11: Attachment 1, Step 4:

4. IF RCS Boron concentration is less than or equal to 12 ppm, THEN the amount of dilution to make a

-1 ppm change is calculated by the following. Otherwise, enter N/A

-50813 x LN(1

- (1 / 2)) =

35221 gal (Reactivity Summary Line 8)

STANDARD: 4. Marks Step as Not Applicable (N/A). EVALUATOR'S NOTE:

None. COMMENTS:

_______ SAT

_______ UNSAT

STEP 12: , Step 5: 5. Calculate the boron concentration change to cause a 1 °F temperature change. / = ppm / °F (ITC, Step 1b)

(DBW, Step 1c)

STANDARD: Completes Step 5 as indicated below:

5. Calculate the boron concentration change to cause a 1 °F temperature change. -26.48 / -8.3 = 3.190361 ppm / °F (ITC, Step 1b)

(DBW, Step 1c)

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 20 of 319 a. ITC was provided as an initial condition.

b. DBW was read from a graph in DRP

-0003, Curve Book.

c. Answer: 3.

19 ppm/°F ACCEPTABLE RANGE: [3.17 to 3.20]

This is a critical step.

EVALUATOR'S NOTE:

None COMMENTS:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 21 of 319 STEP 13: Attachment 1, Step 6:

6. Calculate the amount of boron to make a

-1 °F Tave change. -50813 x LN(1 + Step 5 / (Current Boron

- Step 1d)) -50813 x LN(1 + / ( - )) =

gal (Reactivity Summary Line

4)

STANDARD: Completes Step 6 as indicated below:

6. Calculate the amount of boron to make a +1 ppm change.

a. -50813 x LN(1 +

3.19 / (468 - 13952)) b. -50813 x LN(1 +

3.19 / (-13484)) c. -50813 x LN(1 + (-0.000 236577) [may round to

-0.000 24] d. -50813 x LN(0.999 763423) [based on previous rounding 0.999 76] e. -50813 x -0.000 236605 [based on previous rounding

-0.000 24] f. 12.0 2 gals [based on previous rounding 12.18 gals] g. Answer: 12.0 gallons [acceptable range: 11.7 - 12.2 gallons] This is a critical step.

EVALUATOR'S NOTE:

Candidate may transfer this value to Attachment 2 (Reactivity Summary Sheet) line #4 at this time (or may wait until all calculations are complete).

Range incorporates rounding and bounding values from previous step.

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 22 of 319 Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 23 of 319 STEP 14: Notes prior to Step 7 of Attachment 1:

When RCS Boron Concentration is less than 1 6 ppm, the equation in Step 7 will yield invalid results.

When RCS Boron Concentration is less than 1 6 ppm, the amount of dilution to make a 1 °F Tave change will be greater than 50,000 gallons

. STANDARD: (a) Acknowledges the Notes.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 24 of 319 STEP 15: Attachment 1, Step 7:

7. IF RCS Boron concentration is greater than or equal to 16 ppm, THEN calculate the amount of dilution to make a +1 °F Tave change. Otherwise, enter N/A for this step and Step 5 on Attachment 2.

-50813 x LN(1

- Step 5 / (Current Boron

- 10)) -50813 x LN(1

- / (

- 10)) =

gal (Reactivity Summary Line

5)

STANDARD: Completes Step 7 as indicated below:

7. Calculate the amount of boron to make a +1 ppm change.

a. -50813 x LN(1

- 3.19 / (468 - 10)) b. -50813 x LN(1

- 3.19 / (458)) c. -50813 x LN(1

- (0.0 06965066)) [may round to 0.00 69 7] d. -50813 x LN(0.99 3034934 [based on previous rounding 0.99 30 3] e. -50813 x -0.006986435 [based on previous rounding

-0.00699] f. 355.1 gals [based on previous rounding 355.4 gals]

g. Answer: 35 5 gallons [acceptable range 35 3 - 357] This is a critical step.

EVALUATOR'S NOTE:

Candidate may transfer this value to Attachment 2 (Reactivity Summary Sheet) line #5 at this time (or may wait until all calculations are complete).

Range incorporates rounding and bounding values from previous steps

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 25 of 319 COMMENTS:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 26 of 319 STEP 16: Notes prior to Step 8 of Attachment 1:

If the value of ITC is between rod steps listed in the Curve Book, select the rod height with the highest rod worth. Interpolation to an unlisted rod height is not necessary. STANDARD: (a) Acknowledges the Notes.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 27 of 319 STEP 17 Attachment 1, Step 8:

8. Determine the number of rod steps from the fully withdrawn position that equates to a 1 °F Tave change by performing the following calculations:

a. Current Rod Height:

Steps b. Value of ITC:

(+) pcm (record as + value)

c. Rod height associated with b:

Steps d. Subtract a

- c: Steps (Reactivity Summary line 6) STANDARD: Completes Step 8 as indicated below:

8. Determine the number of rod steps from the fully withdrawn position that equates to a 1 °F Tave change by performing the following calculations:

a. Current Rod Height:

228 Steps b. Value of ITC:

(+) 26.48 pcm (record as + value)

c. Rod height associated with b:

217 Steps d. Subtract a

- c: 11 Steps EVALUATOR'S NOTE

a. Current Rod Height was provided as an initial condition.

b. ITC was provided as an initial condition.

c. Is read from a table in DRP-0003, Curve Book.

The curve is located at Section 2 9 (page 62) of DRP-0003. Answer: 217 steps

[217 to 218

] d. 228 - 217 = 11 Steps [11

- 10 Steps]. Answer: 11 Steps [10

- 11 steps] _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 28 of 319 This is a critical step.

Candidate may transfer this value to Attachment 2 (Reactivity Summary Sheet) line #6 at this time (or may wait until all calculations are complete).

The candidate may sign step 5.2.1 as complete at this time.

COMMENTS:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 29 of 319 STEP 18 Step 5.2.2 Transfer appropriate values to Attachment 2, Reactivity Summary Sheet.

STANDARD: Transfer appropriate values to Attachment 2, Reactivity Summary Sheet, as indicated below: 1. Reactor Operators will discuss Items 4

- 8 with the Unit SRO following turnover.

2. See Subsection 5.2 for directions to complete Items 4 through 8.

3. Reactor Power 100 % 4. Boron for 1 °F decrease 11.7 - 12.2 GAL BA 5. Dilution for 1 °F increase 35 3 - 357 GAL PG 6. Rod steps for 1 °F change 10 - 11 Steps 7. Gallons of boric acid for 1 ppm change 3.6 - 3.8 GAL BA 8. Gallons of PG for 1 ppm change 111 GAL PG EVALUATOR'S NOTE

This is a summary sheet for easy reference. Critical Steps (4

- 8) are bolded and the details on the calculation are provided earlier in the JPM

. The candidate may sign step 5.2.2 as complete and 5.2.3 as not applicable at this time. COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 30 of 319 Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 31 of 319 STEP 5: Reports completion of 1

-OP-RX-010 and that the calculations are ready to be independently verified. STANDARD: (a) Verbal or written status report that a 1-OP-RX-010 is ready to be independently verified. EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS: _______ SAT

_______ UNSAT

STOP TIME:

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 32 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Performance of 1

-OP-RX-010, Documentation of Reactivity Parameters during Power Operations, is 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 It is mid shift on Saturday. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

The following is reactivity information was supplied by the Reactor Engineer today:

Core burnup: 13 090 MWD/MTU Isothermal temperature coefficient:

-26.48 pcm/ F Target delta flux:

-0.5% The following are the Unit conditions:

Reactor power: 100%

RCS boron concentration: 468 ppm Control Bank 'D' is at 228 steps

'A' BAST is in

-service on Unit 1 with a boron concentration of 13952 ppm.

A power reduction has not occurred and is not planned.

Initiating Cues:

Here is a copy of 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

When you are ready to have your work independently verified, please inform me, as this will end the JPM

.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions It is mid shift on Saturday. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

The following is reactivity information was supplied by the Reactor Engineer today:

Core burnup: 13 090 MWD/MTU Isothermal temperature coefficient:

-26.48 pcm/ F Target delta flux:

-0.5% The following are the Unit conditions:

Reactor power: 100%

RCS boron concentration: 468 ppm Control Bank 'D' is at 228 steps

'A' BAST is in

-service on Unit 1 with a boron concentration of 13952 ppm.

A power reduction has not occurred and is not planned.

Initiating Cues:

Here is a copy of 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 1-OP-RX-010, Documentation of Reactivity Parameters during Power Operations and complete Attachment 2 of 1

-OP-RX-010, Reactivity Summary Sheet.

When you are ready to have your work independently verified, please inform me, as this will end the JPM

.

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 1 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 2 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 3 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 4 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 5 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 6 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 7 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 8 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 9 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 10 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 11 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 12 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 13 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 14 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 15 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 16 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 17 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 18 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 19 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 20 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 21 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 22 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 23 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 24 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 25 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.1.23 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title COMPLETE 1-OPT-R C-10.0, REACTOR COOLANT LEAKAGE

- COMPUTER CALCULATED K/A: G 2.1.23 - Ability to perform specific system and integrated plant procedure during all modes of plant operation. (4.3/4.4) Applicability Est Completion Time Actual Time S RO(I) 3 0 Minutes ___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM

. Performance of 1

-OP T-RC-10.0 , Reactor Coolant Leakage

- Computer Calculated, is required

. Standards Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 26 of 319 Completes the remaining portions of 1

-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and determines that the procedure was unsatisfactory.

Standards for Part 2 (after completion of 1

-OPT-RC-10.0) Determines that the primary to secondary leakage from the completed copy of 1

-OPT-RC-10.0 violates Technical Specification requirement and notes that the actions contained within Technical Specification 3.1.C.3 are applicable.

Initiating Cues Given simulated plant conditions, perform the remainder of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and submitted the procedure for review by the Unit Supervisor.

Initiating Cues for Part 2 (after completion of 1

-OPT-RC-10.0) Given a completed copy of 1

-OPT-RC-10.0 determine if the results are within the bounds of the Technical Specifications, and if not, what actions are necessary.

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 27 of 319 Initia l Conditions It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated

. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review. The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic

. One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed.

Containment Sump Data: Initial containment sump level was 47% as indicated on 1

-DA-LI-100 Final containment sump level was 6 2% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 1 5 - 25 gpd range per steam generator for the past week. Today the N-16 monitors are slightly elevated and indicate the following:

SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:

\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need you to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM

. Initial Conditions for Part 2 (after completion of 1

-OPT-RC-10.0) Now that you have completed 1

-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, I need you to determine if the results are within the bounds of the Technical Specifications, and if not, what actions are necessary.

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 28 of 319 Terminating Cues 1-OPT-RC-10.0 has been completed and is ready to be reviewed.

Terminating Cues for Part 2 (after completion of 1

-OPT-RC-10.0) 1-OPT-RC-10.0 has been completed and is ready to be reviewed.

Procedures 1-OPT-RC-10.0, Reactor Coolant Leakage - Computer Calculated (Revision

33) Tools and Equipment Safety Considerations Calculator RCS Leakrate Spreadsheet Large Stapler None Notes Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 29 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: 3.0 INITIAL CONDITIONS

Notes prior to Step 3.1 Reactor Coolant System (RCS) temperature and pressure stability for the purposes of this procedure shall be determined by Shift Supervision.

An RCS water inventory balance must be performed once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance requirement specified time intervals may be adjusted plus or minus 25% to accommodate normal test schedules.

If required RCS pressure conditions cannot be met, 1

-OPT-RC-10.01, Reactor Coolant Leakage

- Manually Calculated, must be performed.

3.1 Verify that the Reactor Coolant System is being maintained at stable temperature and pressure.

3.2 Verify that Reactor Coolant System Pressure is greater than 2100 psig and less than 2500 psig.

STANDARD: (a) Acknowledges/Reviews the Initial Conditions.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 30 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 31 of 319 STEP 2: 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The RCS leak rate program on the PCS plant computer will halt if VCT level increases by 2.0%, if PDTT level decreases by 1.0%, or if PRZR level changes (increases or decreases) by 2.0% during the performance of the program.

4.2 Routine daily leak rate determinations should be performed over a minimum time period of two hours, when a computer calculation of the RCS leak rate is performed.

4.3 Reactor Coolant System sampling should not take place during the performance of this procedure.

4.4 RCS temperature and pressure should be maintained as stable as possible when a RCS leak rate calculation is being performed during a pause in a Reactor Coolant System (RCS) heat up or cool down.

4.5 A leak rate based on an RCS water inventory balance is required once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but is not required to be completed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. (stable pressure, temperature, power level, Pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flow) Refer to Tech Spec 4.13, SR 4.13.A.

4.6 The initials identification block in Subsection 7.3 must be completed before this procedure is closed out.

4.7 If any one data point from the leakrate printout or the final leakrate results are marked with POOR or BAD, or has any reason code, (for example, L, H, or S) the leakrate should be considered unreliable.

4.8 The RCS leak rate calculation should not be performed until 10 minutes have passed following pumping the PDTT.

4.9 The RCS must be maintained at steady state during the performance of the leak rate.

Steady state is defined as:

Power change less than one percent of rated Thermal Power RCS temperature change less than 2°F RCS pressure change less than 5 psig No change in letdown or makeup systems PRZR level change less than 2%

No RCP standpipe fills

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 32 of 319 4.10 Any evolution that changes level in the PDTT (for example, draining the PRT, making up to the RCP Vapor Seal Tank, or cycling of the Gas Stripper) may negate the validity of this OPT.

STANDARD: (a) Acknowledges/Reviews the Precautions and Limitations.

EVALUATOR'S NOTE:

None COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 33 of 319 STEP 3: Reviews completed procedure Section 6.1 and procedure Section 6.12 up to Step 6.2.12.

STANDARD: (a) Acknowledges procedure status up to Step 6.2.12.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 4: Step 6.2.12:

6.2.12 Evaluate unidentified RCS leak rate result and perform the actions indicated in the table below. Enter N/A for the condition that does not exist, or if the unidentified RCS leak rate is positive Evaluation of RCS Leakrate Unidentified RCS Leakrate:

Actions to be taken:

Initials With a negative Unidentified leakrate greater than

-0.08 gpm a. REPEAT steps 6.2.7 through 6.2.12 to obtain valid unidentified RCS Leak Rate Calculation.

b. IF a valid Unidentified RCS Leak Rate calculation cannot be obtained, THEN perform a manual leak rate IAW 1-OPT-RC-10.0 With a negative Unidentified leakrate less than or equal to

-0.08 gpm a. Enter zero for unidentified RCS leak rate. b. Adjust total leak rate fto equal to the identified leak rate.

c. Make a comment in the Operator Comments in Subsection 7.3.

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 34 of 319 STANDARD: (a) Marks the Initial Column Lines as "N/A"

. EVALUATOR'S NOTE

None. COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 35 of 319 STEP 5: Step 6.2.13 6.2.13 Record the Total, Unidentified, and Identified RCS leak rates (gpm) in Attachment 1. Use results from Step 6.2.12 if performed, otherwise use computer printout results.

STANDARD: (a) Proceeds to Attachment 1 to record data from RCS Leak Rate Printout.

EVALUATOR'S NOTE

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from the LAST (most recent previously calculated leak rate data) performance of 1

-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate Current values:

Total OTHER Identified Leakage:

0 (gpm) 0 (gpm) Total Unidentified RCS Leak Rate:

0.13 (gpm) Identified RCS Leak Rate: 0.15 (gpm) Total RCS Leak Rate:

0.28 (gpm) COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 36 of 319 STEP 6: Step 6.2.14

6.2.14 Print and attach the PCS computer printout leak rate program results to this procedure as a permanent record of the derivation of the RCS Leak rates recorded in Step 6.2.13.

STANDARD: (a) Acknowledges and signs this Step. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 7: Step 6.2.1 5 6.2.1 5 Verify one PDTT pump is in AUTO.

STANDARD: (a) Recalls from initial conditions that one PDTT pump is in Automatic

.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 37 of 319 STEP 8: Step 6.2.16

6.2.16 IF charging flow control was placed in Manual in Step 6.2.4, THEN do the following. Otherwise, enter N/A.

a. Verify or adjust CHG flow to maintain PRZR level at programmed setpoint. b. Place 1-CH-FCV-1122, CHG FLOW CNTRL, in Auto.

STANDARD: (a) Recalls from initial conditions that charging flow control is in Automatic and marks this step as N/A.

EVALUATOR'S NOTE:

Candidate will proceed to Section 6.3.

COMMENTS: _______ SAT

_______ UNSAT

STEP 9:

Reviews procedure Section 6.3 up to Step 6.3.2.

STANDARD: (a) Acknowledges procedure status up to Step 6.3.2 and that these steps have been signed off as completed.

EVALUATOR'S NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 38 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 39 of 319 STEP 10: Step 6.3.3 6.3.3 Record the required initial data for calculating the Containment Sump in-leakage rate (Attachment 4, Table 1

- Containment Sump In Leakage Rate, Column 3).

STANDARD: (a) Recalls from initial conditions that initial containment sump level was 47%.

(b) Records initial containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes) CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level

(% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1

-DRP-003 (gallons) (gallons) 34.6465 (gallons) Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 34.6465 [range 34.6465

- 35 gallons]

If candidate uses graph to determine containment volume:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 40 of 31 9 Answer: 35 gallons [range 34

- 36 gallons]

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 41 of 319 STEP 11: Step 6.3.4 6.3.4 Record the required final data for calculating the Containment Sump in-leakage rate (Attachment 4, Table 1

- Containment Sump In Leakage Rate, Column 2).

STANDARD: (a) Recalls from initial conditions that final containment sump level was 62%. (b) Records final containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes)

CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1

-DRP-003 (gallons) 39.439 (gallons) 34.6465 (gallons)

Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 39.439 [range 39

- 39.439 gallons]

If candidate uses graph to determine containment volume:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 42 of 319 Answer: 39 gallons [range 38

- 40 gallons]

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 43 of 319 STEP 12: Step 6.3.5 6.3.5 Calculate the change in parameter from the initial start conditions to the final end conditions and record the elapsed time in Table 2

- Containment Sump In

-leakage Rate. (Attachment 4).

STANDARD: (a) Calculated the difference in containment sump volume.

This is a critical step.

(b) Records difference in containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes)

CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1-DRP-003 (gallons) 39.439 (gallons) 34.6465 (gallons) 4.7925 Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 4.7925 [range 4

- 5 gallons] If candidate uses graph to determine containment volume:

Answer: 4 gallons [range 2 - 6 gallons] _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 44 of 319 Table 2 - Containment Sump In Leakage rate Change in Parameter (+/

-) (final value

- initial value)

Divided by Elapsed Time Sump In Leakage rate CTMT Sump Volume Change 4.7925 (gallons) (minutes) 60 (gpm) Elapsed time will be filled in as an initial condition.

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 45 of 319 STEP 13: Step 6.3.6 6.3.6 Calculate the total Containment Sump In Leakage Rate in gallons per minute. (Attachment 4, Table 2

- Containment Sump In Leakage Rate).

STANDARD: (a) Calculates the containment sump in leakage rate in gallons per minute.

This is a critical step.

(b) Records containment sump in leakage rate in Attachment 4.

EVALUATOR'S NOTE:

Table 2 - Containment Sump In Leakage rate Change in Parameter (+/

-) (final value

- initial value)

Divided by Elapsed Time Sump In Leakage rate CTMT Sump Volume Change 4.7925 (gallons) (minutes) 60 (gpm) 0.08 If candidate uses chart to determine containment volume:

Answer: 0.079875 4 gpm [range 0.0 6 - 0.0 83 gpm]

If candidate uses graph to determine containment volume:

Answer: 0.06667 gpm [range 0.0 3 - 0.1 gallons] COMMENTS: _______ SAT

_______ UNSA T

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 46 of 319 STEP 14: Step 6.3.7 6.3.7 Transfer the Containment Sump In Leakage Rate from Attachment 4, Table 2

- Containment Sump In Leakage Rate, to Attachment 1.

STANDARD: (a) Records containment sump in leakage rate on Attachment 1.

EVALUATOR'S NOTE:

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from the LAST (most recent previously calculated leak rate data) performance of 1

-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate Current values:

Total OTHER Identified Leakage:

0 (gpm) 0 (gpm) Total Unidentified RCS Leak Rate:

0.13 (gpm) Identified RCS Leak Rate: 0.15 (gpm) Total RCS Leak Rate:

0.28 (gpm) CTMT Sump In Leakage CTMT Sump In Leakage Rate:

0.08 (gpm) If candidate uses chart to determine containment volume:

Answer: 0.0798754 gpm [range 0.06

- 0.083 gpm]

If candidate uses graph to determine containment volume:

Answer: 0.06667 gpm [range 0.03

- 0.1 gallons]

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 47 of 319 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 48 of 319 STEP 15: Step 6.3.8 6.3.8 Verify or place one CTMT sump pump is in AUTO.

STANDARD: (a) Recalls from initial conditions that one CTMT sump pump is in Automatic

. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 16: Step 6.4 Note prior to Step 6.4.1:

This Subsection is not required if performing a backup leak rate.

STANDARD: (a) Acknowledges the note

.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 49 of 319 STEP 17: Step 6.4.1 6.4.1 Verify primary to secondary leakage through SG A and SG C is less than or equal to 100 gallons per day AND less than or equal to 20 gallons per day through SG B IAW either of the following. Enter N/A for this subsection if RCS temperature is less than 200 °F.

If Reactor power is greater than 25%, all N

-16 Radiation Monitors are operable.

If Reactor power is less than or equal to 25%, OR any N

-16 Radiation Monitor is inoperable, Chemistry has verified leakage IAW 0-CPT-SG-003, Steam Generator Primary to Secondary Leakage, if stable RCS conditions exist.

STANDARD: (a) Acknowledges that reactor power is greater than 25% and that SG B is greater than 20 gallons per day.

EVALUATOR'S NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

STEP 1 8:

Note prior to Step 6.4.2:

Primary to secondary leakage determination through each SG is required every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . If an SG N

-16 Radiation Monitor is inoperable, sampling will be used to determine this leak rate

.

STANDARD: (a) Acknowledges the note

. EVALUATOR'S NOTE:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 50 of 319 None COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 51 of 319 STEP 19: Step 6.4.2 6.4.2 Record primary to secondary leakage from each SG below. Enter N/A for SG(s) if N

-16 monitor inoperable.

SG A gpd SG B gpd SG C gpd STANDARD: (a) Records the values from the initial conditions as indicated below SG A 24.4 gpd SG B 22.1 gpd SG C 25.6 gpd EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 20: Step 6.4.3 6.4.3 If any N-16 inoperable, AND RCS is in a stable condition to perform leakrate, THEN notify Chemistry AND record person notified and date/time below. Otherwise, enter N/A.

STANDARD: (a) Records N/A for this step.

EVALUATOR'S NOTE:

None _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 52 of 319 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 53 of 319 STEP 21: Step 6.5 Notes prior to Step 6.5.1:

The Leakrate spreadsheet is located at S:

\SURRY PWR STA\3\Data1\OPS\Leakrate\1-OPT-RC-10.0. Backup leakrates are to be entered in "Backup Statistics" tab of spreadsheet, if applicable.

STANDARD: (a) Acknowledges the notes

. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 54 of 319 STEP 22: Step 6.5.1 6.5.1 Update 1-OPT-RC-10.0 Data Entry tab in 1

-OPT-RC-10.0 spreadsheet with Daily primary leak rate, primary to secondary leak rate, and sump in

-leakage information.

STANDARD: (a) Opens the leakrate spreadsheet and enters the required data.

EVALUATOR'S NOTE:

Pre-data Entry Date Total (gpm) Identified(gpm) Unidentified(gpm) Sump (gpm) 'A' (gpd) 'B' (gpd) 'C' (gpd) 05/15/10 0.240 0.150 0.090 0.140 24.200 15.200 25.400 05/16/10 0.220 0.120 0.110 0.130 24.400 15.300 25.400 05/17/10 0.250 0.150 0.100 0.130 24.200 14.800 25.600 05/18/10 0.230 0.130 0.090 0.130 24.300 14.900 25.100 05/19/10 0.230 0.140 0.100 0.130 24.500 15.200 25.300 05/20/10 0.250 0.160 0.090 0.130 24.200 15.300 25.700 05/21/10 0.250 0.160 0.090 0.130 24.400 15.200 25.400 Action Level 1 Action Level 2 Action Level 3 Date Uniden t. Leakage (gpm) 7 Day Average Unidentified Leak Rate > .1 gpm 9 last Consecutive Unidentified Leak Rates > baseline mean 2 Consecutive Unidentified Leak Rates >.15 gpm 2 of 3 consecutive Unidentified Leak Rates > baseline mean + 2 standard deviations Uniden t. Leak Rate

> baseline mean + 3 standard deviations Unident. Leak Rate >.3 gpm 05/21/10 0.090 0 0 0 0 0 0 05/20/10 0.090 0 0 0 0 0 0 05/19/10 0.100 0 0 0 0 0 0 _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 55 of 319 05/18/10 0.090 0 0 0 0 0 0 05/17/10 0.100 0 0 0 0 0 0 05/16/10 0.110 0 0 0 0 0 0 05/15/10 0.090 0 0 0 0 0 0 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 56 of 319 STEP 2 3: Step 6.5.2 6.5.2 Review leakage trends in 1

-OPT-RC-10.0 spreadsheet.

STANDARD: (a) Reviews the trends for 5/22/10 and notes that B SG primary to secondary leakage is elevated and that the plant is in action level 1 for RCS leakage.

EVALUATOR'S NOTE:

Post-data Entry Date Total (gpm) Identified(gpm) Unidentified(gpm) Sump (gpm) 'A' (gpd) 'B' (gpd) 'C' (gpd) 05/15/10 0.240 0.150 0.090 0.140 24.200 15.200 25.400 05/16/10 0.220 0.120 0.110 0.130 24.400 15.300 25.400 05/17/10 0.250 0.150 0.100 0.130 24.200 14.800 25.600 05/18/10 0.230 0.130 0.090 0.130 24.300 14.900 25.100 05/19/10 0.230 0.140 0.100 0.130 24.500 15.200 25.300 05/20/10 0.250 0.160 0.090 0.130 24.200 15.300 25.700 05/21/10 0.250 0.160 0.090 0.130 24.400 15.200 25.400 05/22/10 0.280 0.150 0.130 0.080 24.400 22.100 25.600 Action Level 1 Action Level 2 Action Level 3 Date Uniden t. Leakage (gpm) 7 Day Average Unidentified Leak Rate > .1 gpm 9 last Consecutive Unidentified Leak Rates > baseline mean 2 Consecutive Unidentified Leak Rates >.15 gpm 2 of 3 consecutive Unidentified Leak Rates > baseline mean + 2 standard deviations Uniden t. Leak Rate

> baseline mean + 3 standard deviations Unident. Leak Rate >.3 gpm 5/22/10 0.13 1 0 0 0 0 0 05/21/10 0.090 0 0 0 0 0 0 05/20/10 0.090 0 0 0 0 0 0 _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 57 of 319 05/19/10 0.100 0 0 0 0 0 0 05/18/10 0.090 0 0 0 0 0 0 05/17/10 0.100 0 0 0 0 0 0 05/16/10 0.110 0 0 0 0 0 0 05/15/10 0.090 0 0 0 0 0 0 COMMENTS: STEP 24: Note s prior to Step 6.5.3: The following information is determined by 1

-OPT-RC-10.0 spreadsheet in "Daily Statistics" tab with Yellow representing Action Level 1, Orange representing Action Level 2, and Red representing Action Level 3

. If all Action levels are Green, then all criteria is satisfied.

The OPT-RC-10.0 spreadsheet Action Level criteria are not subject to change and do not need to have the revision number verified. Changes will be made to the baseline mean unidentified leak rate and baseline standard deviation of unidentified leak rate by Engineering following Refueling Outages and as required. STANDARD: (a) Acknowledges the Note s. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 58 of 319 STEP 25: Step 6.5.3 6.5.3 IF any of the following criteria apply to the unidentified leakage, THEN initiate 1

-OP-RC-014. Otherwise, enter N/A.

Action Level 1 One seven day rolling average of Unified RCS Leak Rate greater than 0.1 gpm.

Nine consecutive daily Unidentified RCS Leakrates greater than baseline mean.

Action Level 2 Two consecutive daily Unidentified RCS leakrates greater than 0.15 gpm. Two of Three consecutive daily Unidentified RCS Leakrates greater than mean +2 standard deviations

. Action Level 3 One Unidentified RCS leakrates greater than 0.3 gpm.

One Unidentified RCS Leakrate greater than mean +3 standard deviations.

STANDARD: (a) Marks the step as follows:

.

Action Level 1:

X One seven day rolling average of Unified RCS Leak Rate greater than 0.1 gpm.

Nine consecutive daily Unidentified RCS Leakrates greater than baseline mean.

This is a critical step.

EVALUATOR'S NOTE:

If asked, acknowledge the need to perform 1

-OP-RC-014. State another operator

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 59 of 319 will perform this procedure and to continue on with 1

-OPT-RC-10.0 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 60 of 319 STEP 26: 7.1 Acceptance Criteria

. 7.1.1 Evaluate the test results by reviewing the following acceptance criteria.

The Unidentified Leakage Rate is less than or equal to 1.0 gpm.

The Total Identified Leakage Rate is less than or equal to 10.0 gpm.

Primary to secondary leakage through each Steam Generator is being monitored IAW 0

-CPT-SG-003, OR is less than or equal to 100 gallons per day through SG A and SG C AND less than or equal to 20 gallons per day through SG B as determined by N

-16 Radiation Monitors 7.1.2 Document the test results.

Satisfactory Unsatisfactory

STANDARD: (a) Completes this section as follows:

7.1.1 Evaluate the test results by reviewing the following acceptance criteria.

X The Unidentified Leakage Rate is less than or equal to 1.0 gpm.

X The Total Identified Leakage Rate is less than or equal to 10.0 gpm. Primary to secondary leakage through each Steam Generator is being monitored IAW 0

-CPT-SG-003, OR is less than or equal to 100 gallons per day through SG A and SG C AND less than or equal to 20 gallons per day through SG B as determined by N

-16 Radiation Monitors

7.1.2 Document the test results.

Satisfactory X Unsatisfactory

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 61 of 319 This is a critical step.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 62 of 319 STEP 27: 7.2 Follow on Tasks.

7.2.1 If the test was unsatisfactory, THEN perform the following actions. Otherwise, enter N/A.

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

b. Notify System Engineering of unsatisfactory conditions and record the name of the person notified.

c. The system engineer will initiate an evaluation for license renewal of potential aging effects such as material or cracking.

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

e. Initiate the use of 1

-AP-16.00, Excessive RCS Leakage.

7.2.2 IF a partial operability test was performed, THEN document the reason for the partial test in Operator Comments. Otherwise, enter N/A.

STANDARD: (a) The candidate will document that the test was performed unsat in the Operator Comments due to the primary to secondary leakage. May also note that the plant is in action level 1 and 1

-OP-RC-014 is required. Words to the effect follow: "This PT was completed unsat due to primary to secondary leakage greater than 20 gpd on B SG."

(b) Will inform the evaluator that system engineering needs to be notified, a CR will be required and that AP

-16 will need to be evaluated.

EVALUATOR'S NOTE:

System Engineer: Karlie F. Irwin e. COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 63 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 64 of 319 STEP 28: 7.3 Notification, Documentation and Procedure Closeout.

7.3.1 Notify Shift Supervision that the test is complete

. 7.3.2 Document Leak Rate results in Unit 1 Narrative Logs

. STANDARD: (a) Will inform the evaluator that the test is complete.

(b) Will inform the evaluator that the leak rate needs to be documented

. EVALUATOR'S NOTE:

None. COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME (Part 1):

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 65 of 319 PART 2 of JPM:

Start Time: STEP 28: PART 2 of JPM

Directions to Candidate:

Now that you have completed 1

-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, I need you to determine if the results are within the bounds of the Technical Specifications, and if not, what actions are necessary.

STANDARD: (a) Will inform the evaluator that the results are not within the bound of Technical Specifications.

(b) Will inform the evaluator that the actions from Technical Specification 3.1.C.3 need to be adhered to (i.e., 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months clock to hotshutdown).

EVALUATOR'S NOTE:

None. COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 66 of 319 STOP TIME (Part 2):

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

Task Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Given simulated plant conditions, perform the remainder of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and submitted the procedure for review by the Unit Supervisor.

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 It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review.

The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic.

One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed.

Containment Sump Data:

Initial containment sump level was 47% as indicated on 1

-DA-LI-100. Final containment sump level was 62% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 15

- 25 gpd range per steam generator for the past week. Today the N

-16 monitors are slightly elevated and indicate the following:

SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:

\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Initiating Cues:

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need y ou to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review.

The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic.

One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed. Containment Sump Data:

Initial containment sump level was 47% as indicated on 1

-DA-LI-100. Final containment sump level was 62% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 15

- 25 gpd range per steam generator for the past week. Today the N

-16 monitors are slightly elevated and indicate the following: SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:

\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Initiating Cues:

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need you to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM.

REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: 125 Minutes ago DURATION REQUESTED: 125 ESTIMATED STOP TIME: Now OPERATOR ENTERED PARAMETERS:

YLR0001K, OP ENTERED MINUTES TO RUN = 125 MIN YLR0002K, OP ENTERED IDENT LEAKAGE = 0 GPM U9130, ROLLING PRT LEAKRATE = 0.00 GPM

REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: 12 5 Minutes ago DURATION REQUESTED: 125 ESTIMATED STOP TIME: Now OPERATOR ENTERED PARAMETERS:

YLR0001K, OP ENTERED MINUTES TO RUN = 125 MIN YLR0002K, OP ENTERED IDENT LEAKAGE = 0 GPM U9130, ROLLING PRT LEAKRATE = 0.00 GPM

CALCULATION OF LEAK RATES

1) RAW DATA OF PDTT LEVEL

- START: 40.70 END: 42.91

2) SAMPLE DATA:

RCS TEMPERATURE AVERAGE

((T0400A + T0420A + T0440A)/3:

573.36 573.38 573.37 573.39 573.32 573.38 573.31 573.28 573.40 573.32 573.43 573.32 573.40 573.34 573.35 573.30 573.32 573.34 573.33 573.30 573.33 573.38 573.32 573.35 573.30 573.32 573.37 573.33 573.32 573.32 573.34 573.36 573.34 573.34 573.32 573.32 573.30 573.34 573.31 573.31 573.30 PRESSURIZER LEVEL AVERAGE

((L0480A + L0481A + L0482A)/3):

56.67 56.79 56.77 56.82 56.77 56.77 56.76 56.71 56.77 56.76 56.77 56.75 56.72 56.69 56.70 56.70 56.69 56.70 56.70 56.71 56.72 56.77 56.75 56.76 56.74 56.76 56.77 56.72 56.65 56.72 56.73 56.76 56.74 56.76 56.72 56.72 56.73 56.70 56.73 56.70 56.73 VCT LEVEL (L0112A): 42.90 42.81 42.63 42.60 42.50 42.44 42.35 42.38 42.35 42.32 42.26 42.20 42.14 42.14 42.14 42.05 41.93 41.83 41.74 41.65 41.56 41.44 41.41 41.31 41.19 41.25 41.13 41.07 41.01 40.95 40.95 40.77 40.80 40.67 40.61 40.58 40.52 40.49 40.40 40.40 40.34 RCS PRESSURE AVERAGE

((P0480A + P0481A + P0482A)/3):

2243.38 2243.62 2243.38 2243.87 2243.30 2243.54 2243.22 2243.13 2243.22 2243.54 2243.79 2243.87 2242.89 2242.81 2243.22 2242.73 2243.05 2243.54 2243.54 2242.73 2243.70 2243.95 2244.11 2243.79 2243.54 2244.44 2243.22 2243.46 2243.30 2242.97 2243.70 2244.44 2244.03 2243.54 2244.03 2243.54 2243.30 2242.65 2243.46 2243.22 2243.70

3) LINEAR REGRESSION STATISTICS:

PARAMETER SLOPE START VALUE END VALUE ------------------------------

TEMPERATURE

-0.00037 573.36 573.31 PRESSURIZER LEVEL

-0.00026 56.75 56.71 VCT LEVEL -0.020 70 42.86 40.27 4) MASS CHANGE DATA (A NEGATIVE RATE IMPLIES MASS TRANSFER OUT OF THE VOLUME):

RCS: -0.00037 DEGF/MIN *

-0.07 LBM/CU FT(DEGF)

82.08.8 CU FT

= 0.22 LBM/MIN PRZR: -0.00026 PCT/MIN

74.0 GAL/PCT

0.13368 CU FT/GAL

37.12 LBM/CU FT

= -0.10 LBM/MIN VCT: -0.02070 PCT/MIN

14.1 GAL/PCT

0.13368CU FT/GAL

61.87 LBM/CU FT

= -2.41 LBM/MIN

5) CONVERSIONS FOR PDTT, PRT AND IDENTIFIED LEAKAGE TO LBM:

PDTT CHANGE:

42.91 PCT

- 40.70 PCV = 2.21 P CT PDTT: 2.21 PCT

71.16 LBM/PCT /

125 MIN = 1.26 LBM/MIN PRT: 0.00 GAL/MIN

0.13368 CU FT/GAL

61.856 LBM/CU FT

= 0.00 LBM.MIN IDENTIFIED LEAKAGE:

0.00 GAL/MIN

0.13368 CU FT/GAL

62.310 LBM/CU FT

= 0.00 LBM.MIN

6) TOTAL LEAKAGES IN LBM/MIN

RCS: (-1.0)

0.22 LBM/MIN

+ -0.10 LBM/MIN

+ -2.41 LBM/MIN

= 2.29 LBM/MIN IDENTIFIED:

1.26 LBM/MIN

+ 0.00 LBM/MIN

= 1.26 LBM/MIN UNIDENTIFIED:

2.29 LBM/MIN

- 1.26 LBM/MIN

= 1.03 LBM/MIN

7) TOTAL LEAKAGES IN GALLONS/MINUTE:

RCS: 2.29 LBM/MIN

7.48052 GAL/CU FT /

61.856 LBM/CU FT

= 0.28 GAL/MIN IDENTIFIED:

1.26 LBM/MIN

7.48052 GAL/CU FT /

61.856 LBM/CU FT

= 0.15 GAL/MIN UNIDENTIFIED:

0.28 GAL/MIN - 0.15 GAL/MIN

= 0.13 GAL/MIN NOTE: VALUES WITH A QUALITY OF "B" ARE UNRELIABLE REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: Now

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 1 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 2 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 3 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 4 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 5 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 6 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 7 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 8 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 9 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 10 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 11 of 319 SI SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 12 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 13 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 14 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 15 of 319 SI SI SI SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 16 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 17 of 319 N/A SI SI SI SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 18 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 19 of 319 SI SI SI N/A SI N/A SI SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 20 of 319 N/A SI SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 21 of 319 0 SI SI N/A SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 22 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 23 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 24 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 25 of 319 SI SI X Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 26 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 27 of 31 9 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 28 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 29 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 30 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 31 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 32 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 33 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 34 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 35 of 319 Skip Irwin SI Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 36 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 37 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 38 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 39 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 40 of 319 0 0 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 41 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 42 of 319 0 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 43 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 44 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 45 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 46 of 319 125 minutes ago 65 minutes ago 60 60 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 47 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 48 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.1.23 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title COMPLETE 1-OPT-R C-10.0, REACTOR COOLANT LEAKAGE

- COMPUTER CALCULATED K/A: G 2.1.23 - Ability to perform specific system and integrated plant procedure during all modes of plant operation. (4.3/4.4) Applicability Est Completion Time Actual Time RO 4 0 Minutes ___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM

. Performance of 1

-OP T-RC-10.0 , Reactor Coolant Leakage

- Computer Calculated, is required

. Standards Completes the remaining portions of 1

-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and determines that the procedure was unsatisfactory.

Initiating Cues Given simulated plant conditions, perform the remainder of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and submitted the Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 49 of 319 procedure for review by the Unit Supervisor.

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 50 of 319 Initia l Conditions It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated

. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review. The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic

. One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed.

Containment Sump Data: Initial containment sump level was 47% as indicated on 1

-DA-LI-100 Final containment sump level was 6 2% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 1 5 - 25 gpd range per steam generator for the past week. Today the N-16 monitors are slightly elevated and indicate the following:

SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:

\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need you to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM

. Terminating Cues 1-OPT-RC-10.0 has been completed and is ready to be reviewed.

Procedures

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 51 of 319 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated (Revision

33) Tools and Equipment Safety Considerations Calculator RCS Leakrate Spreadsheet Large Stapler None Notes Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 52 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: 3.0 INITIAL CONDITIONS

Notes prior to Step 3.1 Reactor Coolant System (RCS) temperature and pressure stability for the purposes of this procedure shall be determined by Shift Supervision.

An RCS water inventory balance must be performed once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance requirement specified time intervals may be adjusted plus or minus 25% to accommodate normal test schedules.

If required RCS pressure conditions cannot be met, 1

-OPT-RC-10.01, Reactor Coolant Leakage

- Manually Calculated, must be performed.

3.1 Verify that the Reactor Coolant System is being maintained at stable temperature and pressure.

3.2 Verify that Reactor Coolant System Pressure is greater than 2100 psig and less than 2500 psig.

STANDARD: (a) Acknowledges/Reviews the Initial Conditions.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 53 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 54 of 319 STEP 2: 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The RCS leak rate program on the PCS plant computer will halt if VCT level increases by 2.0%, if PDTT level decreases by 1.0%, or if PRZR level changes (increases or decreases) by 2.0% during the performance of the program.

4.2 Routine daily leak rate determinations should be performed over a minimum time period of two hours, when a computer calculation of the RCS leak rate is performed.

4.3 Reactor Coolant System sampling should not take place during the performance of this procedure.

4.4 RCS temperature and pressure should be maintained as stable as possible when a RCS leak rate calculation is being performed during a pause in a Reactor Coolant System (RCS) heat up or cool down.

4.5 A leak rate based on an RCS water inventory balance is required once

every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , but is not required to be completed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. (stable pressure, temperature, power level, Pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flow)

Refer to Tech Spec 4.13, SR 4.13.A.

4.6 The initials identification block in Subsection 7.3 must be completed before this procedure is closed out.

4.7 If any one data point from the leakrate printout or the final leakrate results are marked with POOR or BAD, or has any reason code, (for example, L, H, or S) the leakrate should be considered unreliable.

4.8 The RCS leak rate calculation should not be performed until 10 minutes have passed following pumping the PDTT.

4.9 The RCS must be maintained at steady state during the performance of the leak rate.

Steady state is defined as:

Power change less than one percent of rated Thermal Power RCS temperature change less than 2°F RCS pressure change less than 5 psig No change in letdown or makeup systems PRZR level change less than 2%

No RCP standpipe fills

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 55 of 319 4.10 Any evolution that changes level in the PDTT (for example, draining the PRT, making up to the RCP Vapor Seal Tank, or cycling of the Gas Stripper) may negate the validity of this OPT.

STANDARD: (a) Acknowledges/Reviews the Precautions and Limitations.

EVALUATOR'S NOTE:

None COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 56 of 319 STEP 3: Reviews completed procedure Section 6.1 and procedure Section 6.12 up to Step 6.2.12.

STANDARD: (a) Acknowledges procedure status up to Step 6.2.12.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 4: Step 6.2.12:

6.2.12 Evaluate unidentified RCS leak rate result and perform the actions indicated in the table below. Enter N/A for the condition that does not exist, or if the unidentified RCS leak rate is positive Evaluation of RCS Leakrate Unidentified RCS Leakrate:

Actions to be taken:

Initials With a negative Unidentified leakrate greater than

-0.08 gpm a. REPEAT steps 6.2.7 through 6.2.12 to obtain valid unidentified RCS Leak Rate Calculation.

b. IF a valid Unidentified RCS Leak Rate calculation cannot be obtained, THEN perform a manual leak rate IAW 1-OPT-RC-10.0 With a negative Unidentified leakrate less than or equal to

-0.08 gpm a. Enter zero for unidentified RCS leak rate. b. Adjust total leak rate fto equal to the identified leak rate.

c. Make a comment in the Operator Comments in Subsection 7.3.

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 57 of 319 STANDARD: (a) Marks the Initial Column Lines as "N/A"

. EVALUATOR'S NOTE

None. COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 58 of 319 STEP 5: Step 6.2.13 6.2.13 Record the Total, Unidentified, and Identified RCS leak rates (gpm) in Attachment 1. Use results from Step 6.2.12 if performed, otherwise use computer printout results.

STANDARD: (a) Proceeds to Attachment 1 to record data from RCS Leak Rate Printout.

EVALUATOR'S NOTE

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from the LAST (most recent previously calculated leak rate data) performance of 1

-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate Current values:

Total OTHER Identified Leakage:

0 (gpm) 0 (gpm) Total Unidentified RCS Leak Rate:

0.13 (gpm) Identified RCS Leak Rate: 0.15 (gpm) Total RCS Leak Rate:

0.28 (gpm) COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 59 of 319 STEP 6: Step 6.2.14

6.2.14 Print and attach the PCS computer printout leak rate program results to this procedure as a permanent record of the derivation of the RCS Leak rates recorded in Step 6.2.13.

STANDARD: (a) Acknowledges and signs this Step. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 7: Step 6.2.1 5 6.2.1 5 Verify one PDTT pump is in AUTO.

STANDARD: (a) Recalls from initial conditions that one PDTT pump is in Automatic

.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 60 of 319 STEP 8: Step 6.2.16

6.2.16 IF charging flow control was placed in Manual in Step 6.2.4, THEN do the following. Otherwise, enter N/A.

a. Verify or adjust CHG flow to maintain PRZR level at programmed setpoint. b. Place 1-CH-FCV-1122, CHG FLOW CNTRL, in Auto.

STANDARD: (a) Recalls from initial conditions that charging flow control is in Automatic and marks this step as N/A.

EVALUATOR'S NOTE:

Candidate will proceed to Section 6.3.

COMMENTS: _______ SAT

_______ UNSAT

STEP 9:

Reviews procedure Section 6.3 up to Step 6.3.2.

STANDARD: (a) Acknowledges procedure status up to Step 6.3.2 and that these steps have been signed off as completed.

EVALUATOR'S NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 61 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 62 of 319 STEP 10: Step 6.3.3 6.3.3 Record the required initial data for calculating the Containment Sump in-leakage rate (Attachment 4, Table 1

- Containment Sump In Leakage Rate, Column 3).

STANDARD: (a) Recalls from initial conditions that initial containment sump level was 47%.

(b) Records initial containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes) CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level

(% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1

-DRP-003 (gallons) (gallons) 34.6465 (gallons) Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 34.6465 [range 34.6465

- 35 gallons]

If candidate uses graph to determine containment volume:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 63 of 319 Answer: 35 gallons [range 34

- 36 gallons]

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 64 of 319 STEP 11: Step 6.3.4 6.3.4 Record the required final data for calculating the Containment Sump in-leakage rate (Attachment 4, Table 1

- Containment Sump In Leakage Rate, Column 2).

STANDARD: (a) Recalls from initial conditions that final containment sump level was 62%. (b) Records final containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes)

CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1

-DRP-003 (gallons) 39.439 (gallons) 34.6465 (gallons)

Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 39.439 [range 39

- 39.439 gallons]

If candidate uses graph to determine containment volume:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 65 of 319 Answer: 39 gallons [range 38

- 40 gallons]

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 66 of 319 STEP 12: Step 6.3.5 6.3.5 Calculate the change in parameter from the initial start conditions to the final end conditions and record the elapsed time in Table 2

- Containment Sump In

-leakage Rate. (Attachment 4).

STANDARD: (a) Calculated the difference in containment sump volume.

This is a critical step.

(b) Records difference in containment sump level in Attachment 4.

EVALUATOR'S NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being analyzed Column 2 Column 3 Final Value of Parameter at END of Time Initial Value of Parameter at START of Time

- Change in Parameter (+ or

-) (final value

- initial value)

Elapsed Time 65 minutes ago 125 minutes ago 60 (Minutes)

CTMT Sump Level instrument used:

1-DA-LI-100, 1-DA-LI-110A, or 1

-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B Circle instrument used 1-DA-LI-100, 1-DA-LI-110A, or 1-DA-LI-110B N/A CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume from curve in 1-DRP-003 (gallons) 39.439 (gallons) 34.6465 (gallons) 4.7925 Elapsed time will be filled in as an initial condition.

If candidate uses chart to determine containment volume:

Answer: 4.7925 [range 4

- 5 gallons] If candidate uses graph to determine containment volume:

Answer: 4 gallons [range 2 - 6 gallons] _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 67 of 319 Table 2 - Containment Sump In Leakage rate Change in Parameter (+/

-) (final value

- initial value)

Divided by Elapsed Time Sump In Leakage rate CTMT Sump Volume Change 4.7925 (gallons) (minutes) 60 (gpm) Elapsed time will be filled in as an initial condition.

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 68 of 319 STEP 13: Step 6.3.6 6.3.6 Calculate the total Containment Sump In Leakage Rate in gallons per minute. (Attachment 4, Table 2

- Containment Sump In Leakage Rate).

STANDARD: (a) Calculates the containment sump in leakage rate in gallons per minute.

This is a critical step.

(b) Records containment sump in leakage rate in Attachment 4.

EVALUATOR'S NOTE:

Table 2 - Containment Sump In Leakage rate Change in Parameter (+/

-) (final value

- initial value)

Divided by Elapsed Time Sump In Leakage rate CTMT Sump Volume Change 4.7925 (gallons) (minutes) 60 (gpm) 0.08 If candidate uses chart to determine containment volume:

Answer: 0.079875 4 gpm [range 0.0 6 - 0.0 83 gpm]

If candidate uses graph to determine containment volume:

Answer: 0.06667 gpm [range 0.0 3 - 0.1 gallons] COMMENTS: _______ SAT

_______ UNSA T

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 69 of 319 STEP 14: Step 6.3.7 6.3.7 Transfer the Containment Sump In Leakage Rate from Attachment 4, Table 2

- Containment Sump In Leakage Rate, to Attachment 1.

STANDARD: (a) Records containment sump in leakage rate on Attachment 1.

EVALUATOR'S NOTE:

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from the LAST (most recent previously calculated leak rate data) performance of 1

-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate Current values:

Total OTHER Identified Leakage:

0 (gpm) 0 (gpm) Total Unidentified RCS Leak Rate:

0.13 (gpm) Identified RCS Leak Rate: 0.15 (gpm) Total RCS Leak Rate:

0.28 (gpm) CTMT Sump In Leakage CTMT Sump In Leakage Rate:

0.08 (gpm) If candidate uses chart to determine containment volume:

Answer: 0.0798754 gpm [range 0.06

- 0.083 gpm]

If candidate uses graph to determine containment volume:

Answer: 0.06667 gpm [range 0.03

- 0.1 gallons]

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 70 of 319 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 71 of 319 STEP 15: Step 6.3.8 6.3.8 Verify or place one CTMT sump pump is in AUTO.

STANDARD: (a) Recalls from initial conditions that one CTMT sump pump is in Automatic

. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 16: Step 6.4 Note prior to Step 6.4.1:

This Subsection is not required if performing a backup leak rate.

STANDARD: (a) Acknowledges the note

.

EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 72 of 319 STEP 17: Step 6.4.1 6.4.1 Verify primary to secondary leakage through SG A and SG C is less than or equal to 100 gallons per day AND less than or equal to 20 gallons per day through SG B IAW either of the following. Enter N/A for this subsection if RCS temperature is less than 200 °F.

If Reactor power is greater than 25%, all N

-16 Radiation Monitors are operable.

If Reactor power is less than or equal to 25%, OR any N

-16 Radiation Monitor is inoperable, Chemistry has verified leakage IAW 0-CPT-SG-003, Steam Generator Primary to Secondary Leakage, if stable RCS conditions exist.

STANDARD: (a) Acknowledges that reactor power is greater than 25% and that SG B is greater than 20 gallons per day.

EVALUATOR'S NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

STEP 1 8:

Note prior to Step 6.4.2:

Primary to secondary leakage determination through each SG is required every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . If an SG N

-16 Radiation Monitor is inoperable, sampling will be used to determine this leak rate

.

STANDARD: (a) Acknowledges the note

. EVALUATOR'S NOTE:

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 73 of 319 None COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 74 of 319 STEP 19: Step 6.4.2 6.4.2 Record primary to secondary leakage from each SG below. Enter N/A for SG(s) if N

-16 monitor inoperable.

SG A gpd SG B gpd SG C gpd STANDARD: (a) Records the values from the initial conditions as indicated below SG A 24.4 gpd SG B 22.1 gpd SG C 25.6 gpd EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

STEP 20: Step 6.4.3 6.4.3 If any N-16 inoperable, AND RCS is in a stable condition to perform leakrate, THEN notify Chemistry AND record person notified and date/time below. Otherwise, enter N/A.

STANDARD: (a) Records N/A for this step.

EVALUATOR'S NOTE:

None _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 75 of 319 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 76 of 319 STEP 21: Step 6.5 Notes prior to Step 6.5.1:

The Leakrate spreadsheet is located at S:

\SURRY PWR STA\3\Data1\OPS\Leakrate\1-OPT-RC-10.0. Backup leakrates are to be entered in "Backup Statistics" tab of spreadsheet, if applicable.

STANDARD: (a) Acknowledges the notes

. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 77 of 319 STEP 22: Step 6.5.1 6.5.1 Update 1-OPT-RC-10.0 Data Entry tab in 1

-OPT-RC-10.0 spreadsheet with Daily primary leak rate, primary to secondary leak rate, and sump in

-leakage information.

STANDARD: (a) Opens the leakrate spreadsheet and enters the required data.

EVALUATOR'S NOTE:

Pre-data Entry Date Total (gpm) Identified(gpm) Unidentified(gpm) Sump (gpm) 'A' (gpd) 'B' (gpd) 'C' (gpd) 05/15/10 0.240 0.150 0.090 0.140 24.200 15.200 25.400 05/16/10 0.220 0.120 0.110 0.130 24.400 15.300 25.400 05/17/10 0.250 0.150 0.100 0.130 24.200 14.800 25.600 05/18/10 0.230 0.130 0.090 0.130 24.300 14.900 25.100 05/19/10 0.230 0.140 0.100 0.130 24.500 15.200 25.300 05/20/10 0.250 0.160 0.090 0.130 24.200 15.300 25.700 05/21/10 0.250 0.160 0.090 0.130 24.400 15.200 25.400 Action Level 1 Action Level 2 Action Level 3 Date Uniden t. Leakage (gpm) 7 Day Average Unidentified Leak Rate > .1 gpm 9 last Consecutive Unidentified Leak Rates > baseline mean 2 Consecutive Unidentified Leak Rates >.15 gpm 2 of 3 consecutive Unidentified Leak Rates > baseline mean + 2 standard deviations Uniden t. Leak Rate

> baseline mean + 3 standard deviations Unident. Leak Rate >.3 gpm 05/21/10 0.090 0 0 0 0 0 0 05/20/10 0.090 0 0 0 0 0 0 05/19/10 0.100 0 0 0 0 0 0 _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 78 of 319 05/18/10 0.090 0 0 0 0 0 0 05/17/10 0.100 0 0 0 0 0 0 05/16/10 0.110 0 0 0 0 0 0 05/15/10 0.090 0 0 0 0 0 0 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 79 of 319 STEP 2 3: Step 6.5.2 6.5.2 Review leakage trends in 1

-OPT-RC-10.0 spreadsheet.

STANDARD: (a) Reviews the trends for 5/22/10 and notes that B SG primary to secondary leakage is elevated and that the plant is in action level 1 for RCS leakage.

EVALUATOR'S NOTE:

Post-data Entry Date Total (gpm) Identified(gpm) Unidentified(gpm) Sump (gpm) 'A' (gpd) 'B' (gpd) 'C' (gpd) 05/15/10 0.240 0.150 0.090 0.140 24.200 15.200 25.400 05/16/10 0.220 0.120 0.110 0.130 24.400 15.300 25.400 05/17/10 0.250 0.150 0.100 0.130 24.200 14.800 25.600 05/18/10 0.230 0.130 0.090 0.130 24.300 14.900 25.100 05/19/10 0.230 0.140 0.100 0.130 24.500 15.200 25.300 05/20/10 0.250 0.160 0.090 0.130 24.200 15.300 25.700 05/21/10 0.250 0.160 0.090 0.130 24.400 15.200 25.400 05/22/10 0.280 0.150 0.130 0.080 24.400 22.100 25.600 Action Level 1 Action Level 2 Action Level 3 Date Uniden t. Leakage (gpm) 7 Day Average Unidentified Leak Rate > .1 gpm 9 last Consecutive Unidentified Leak Rates > baseline mean 2 Consecutive Unidentified Leak Rates >.15 gpm 2 of 3 consecutive Unidentified Leak Rates > baseline mean + 2 standard deviations Uniden t. Leak Rate

> baseline mean + 3 standard deviations Unident. Leak Rate >.3 gpm 5/22/10 0.13 1 0 0 0 0 0 05/21/10 0.090 0 0 0 0 0 0 05/20/10 0.090 0 0 0 0 0 0 _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 80 of 319 05/19/10 0.100 0 0 0 0 0 0 05/18/10 0.090 0 0 0 0 0 0 05/17/10 0.100 0 0 0 0 0 0 05/16/10 0.110 0 0 0 0 0 0 05/15/10 0.090 0 0 0 0 0 0 COMMENTS: STEP 24: Note s prior to Step 6.5.3: The following information is determined by 1

-OPT-RC-10.0 spreadsheet in "Daily Statistics" tab with Yellow representing Action Level 1, Orange representing Action Level 2, and Red representing Action Level 3

. If all Action levels are Green, then all criteria is satisfied.

The OPT-RC-10.0 spreadsheet Action Level criteria are not subject to change and do not need to have the revision number verified. Changes will be made to the baseline mean unidentified leak rate and baseline standard deviation of unidentified leak rate by Engineering following Refueling Outages and as required. STANDARD: (a) Acknowledges the Note s. EVALUATOR'S NOTE:

None COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 81 of 319 STEP 25: Step 6.5.3 6.5.3 IF any of the following criteria apply to the unidentified leakage, THEN initiate 1

-OP-RC-014. Otherwise, enter N/A.

Action Level 1 One seven day rolling average of Unified RCS Leak Rate greater than 0.1 gpm.

Nine consecutive daily Unidentified RCS Leakrates greater than baseline mean.

Action Level 2 Two consecutive daily Unidentified RCS leakrates greater than 0.15 gpm. Two of Three consecutive daily Unidentified RCS Leakrates greater than mean +2 standard deviations

. Action Level 3 One Unidentified RCS leakrates greater than 0.3 gpm.

One Unidentified RCS Leakrate greater than mean +3 standard deviations.

STANDARD: (a) Marks the step as follows:

.

Action Level 1:

X One seven day rolling average of Unified RCS Leak Rate greater than 0.1 gpm.

Nine consecutive daily Unidentified RCS Leakrates greater than baseline mean.

This is a critical step.

EVALUATOR'S NOTE:

If asked, acknowledge the need to perform 1

-OP-RC-014. State another operator

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 82 of 319 will perform this procedure and to continue on with 1

-OPT-RC-10.0 COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 83 of 319 STEP 26: 7.1 Acceptance Criteria

. 7.1.1 Evaluate the test results by reviewing the following acceptance criteria.

The Unidentified Leakage Rate is less than or equal to 1.0 gpm.

The Total Identified Leakage Rate is less than or equal to 10.0 gpm.

Primary to secondary leakage through each Steam Generator is being monitored IAW 0

-CPT-SG-003, OR is less than or equal to 100 gallons per day through SG A and SG C AND less than or equal to 20 gallons per day through SG B as determined by N

-16 Radiation Monitors 7.1.2 Document the test results.

Satisfactory Unsatisfactory

STANDARD: (a) Completes this section as follows:

7.1.1 Evaluate the test results by reviewing the following acceptance criteria.

X The Unidentified Leakage Rate is less than or equal to 1.0 gpm.

X The Total Identified Leakage Rate is less than or equal to 10.0 gpm. Primary to secondary leakage through each Steam Generator is being monitored IAW 0

-CPT-SG-003, OR is less than or equal to 100 gallons per day through SG A and SG C AND less than or equal to 20 gallons per day through SG B as determined by N

-16 Radiation Monitors

7.1.2 Document the test results.

Satisfactory X Unsatisfactory

_______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 84 of 319 This is a critical step.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 85 of 319 STEP 27: 7.2 Follow on Tasks.

7.2.1 If the test was unsatisfactory, THEN perform the following actions. Otherwise, enter N/A.

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

b. Notify System Engineering of unsatisfactory conditions and record the name of the person notified.

c. The system engineer will initiate an evaluation for license renewal of potential aging effects such as material or cracking.

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

e. Initiate the use of 1

-AP-16.00, Excessive RCS Leakage.

7.2.2 IF a partial operability test was performed, THEN document the reason for the partial test in Operator Comments. Otherwise, enter N/A.

STANDARD: (a) The candidate will document that the test was performed unsat in the Operator Comments due to the primary to secondary leakage. May also note that the plant is in action level 1 and 1

-OP-RC-014 is required. Words to the effect follow: "This PT was completed unsat due to primary to secondary leakage greater than 20 gpd on B SG."

(b) Will inform the evaluator that system engineering needs to be notified, a CR will be required and that AP

-16 will need to be evaluated.

EVALUATOR'S NOTE:

System Engineer: Karl ie F. Irwin e COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 86 of 319 Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 87 of 319 STEP 28: 7.3 Notification, Documentation and Procedure Closeout.

7.3.1 Notify Shift Supervision that the test is complete

. 7.3.2 Document Leak Rate results in Unit 1 Narrative Logs

. STANDARD: (a) Will inform the evaluator that the test is complete.

(b) Will inform the evaluator that the leak rate needs to be documented

. EVALUATOR'S NOTE:

None. COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME:

Surry 2010-301 Perform 1-OPT-RC-10.0 G2.1.23 SR10301 88 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Given simulated plant conditions, perform the remainder of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated, and submitted the procedure for review by the Unit Supervisor.

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 It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review.

The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic.

One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed.

Containment Sump Data:

Initial containment sump level was 47% as indicated on 1

-DA-LI-100. Final containment sump level was 62% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 15

- 25 gpd range per steam generator for the past week. Today the N

-16 monitors are slightly elevated and indicate the following:

SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Initiating Cues:

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need you to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions It is mid-shift on May 22, 2010. Unit 1 power is 100 percent.

I am the Nuclear Shift Manager. I have assigned you to complete the normal daily 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. The procedure is complete up through Step 6.2.11 and the computer generated leak rate data sheet has just been printed out, the leak rate ran for 125 minutes. You are to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review.

The following are the Unit conditions:

Reactor power: 100%

Charging flow control is in automatic.

One PDTT pump was placed in automatic after the PCS computer leak rate program results were printed.

Containment Sump Data:

Initial containment sump level was 47% as indicated on 1

-DA-LI-100. Final containment sump level was 62% as indicated on 1

-DA-LI-100. Containment Sump leak rate elapsed time

- 60 minutes.

After this data was recorded, one containment sump pump was placed back in automatic Primary to Secondary Leakage exists and is known and has been indicating in the 15

- 25 gpd range per steam generator for the past week. Today the N

-16 monitors are slightly elevated and indicate the following:

SG A: 24.4 gpd SG B: 22.1 gpd SG C: 25.6 gpd The Leakrate spreadsheet is located at folder S:

\SURRY PWR STA

\3\Ops\Leakrate on the desktop of your laptop computer.

Initiating Cues:

Here is a partially completed copy of 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated. I need you to complete 1-OPT-RC-10.0, Reactor Coolant Leakage

- Computer Calculated it is entirety and when done turn the procedure in for review

. When you are ready to have your work reviewed, please inform me, as this will end the JPM.

REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: 125 Minutes ago DURATION REQUESTED: 125 ESTIMATED STOP TIME: Now OPERATOR ENTERED PARAMETERS:

YLR0001K, OP ENTERED MINUTES TO RUN = 125 MIN YLR0002K, OP ENTERED IDENT LEAKAGE = 0 GPM U9130, ROLLING PRT LEAKRATE = 0.00 GPM

REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: 12 5 Minutes ago DURATION REQUESTED: 125 ESTIMATED STOP TIME: Now OPERATOR ENTERED PARAMETERS:

YLR0001K, OP ENTERED MINUTES TO RUN = 125 MIN YLR0002K, OP ENTERED IDENT LEAKAGE = 0 GPM U9130, ROLLING PRT LEAKRATE

= 0.00 GPM

CALCULATION OF LEAK RATES

1) RAW DATA OF PDTT LEVEL

- START: 40.70 END: 42.91

2) SAMPLE DATA:

RCS TEMPERATURE AVERAGE

((T0400A + T0420A + T0440A)/3:

573.36 573.38 573.37 573.39 573.32 573.38 573.31 573.28 573.40 573.32 573.43 573.32 573.40 573.34 573.35 573.30 573.32 573.34 573.33 573.30 573.33 573.38 573.32 573.35 573.30 573.32 573.37 573.33 573.32 573.32 573.34 573.36 573.34 573.34 573.32 573.32 573.30 573.34 573.31 573.31 573.30 PRESSURIZER LEVEL AVERAGE

((L0480A + L0481A + L0482A)/3):

56.67 56.79 56.77 56.82 56.77 56.77 56.76 56.71 56.77 56.76 56.77 56.75 56.72 56.69 56.70 56.70 56.69 56.70 56.70 56.71 56.72 56.77 56.75 56.76 56.74 56.76 56.77 56.72 56.65 56.72 56.73 56.76 56.74 56.76 56.72 56.72 56.73 56.70 56.73 56.70 56.73 VCT LEVEL (L0112A): 42.90 42.81 42.63 42.60 42.50 42.44 42.35 42.38 42.35 42.32 42.26 42.20 42.14 42.14 42.14 42.05 41.93 41.83 41.74 41.65 41.56 41.44 41.41 41.31 41.19 41.25 41.13 41.07 41.01 40.95 40.95 40.77 40.80 40.67 40.61 40.58 40.52 40.49 40.40 40.40 40.34 RCS PRESSURE AVERAGE

((P0480A + P0481A + P0482A)/3):

2243.38 2243.62 2243.38 2243.87 2243.30 2243.54 2243.22 2243.13 2243.22 2243.54 2243.79 2243.87 2242.89 2242.81 2243.22 2242.73 2243.05 2243.54 2243.54 2242.73 2243.70 2243.95 2244.11 2243.79 2243.54 2244.44 2243.22 2243.46 2243.30 2242.97 2243.70 2244.44 2244.03 2243.54 2244.03 2243.54 2243.30 2242.65 2243.46 2243.22 2243.70

3) LINEAR REGRESSION STATISTICS:

PARAMETER SLOPE START VALUE END VALUE ------------------------------

TEMPERATURE

-0.00037 573.36 573.31 PRESSURIZER LEVEL

-0.00026 56.75 56.71 VCT LEVEL -0.02070 42.86 40.27 4) MASS CHANGE DATA (A NEGATIVE RATE IMPLIES MASS TRANSFER OUT OF THE VOLUME):

RCS: -0.00037 DEGF/MIN *

-0.07 LBM/CU FT(DEGF)

82.08.8 CU FT

= 0.22 LBM/MIN PRZR: -0.00026 PCT/MIN

74.0 GAL/PCT

0.13368 CU FT/GAL

37.12 LBM/CU FT

= -0.10 LBM/MIN VCT: -0.02070 PCT/MIN

14.1 GAL/PCT

0.13368CU FT/GAL

61.87 LBM/CU FT

= -2.41 LBM/MIN

5) CONVERSIONS FOR PDTT, PRT AND IDENTIFIED LEAKAGE TO LBM:

PDTT CHANGE:

42.91 PCT

- 40.70 PCV = 2.21 PCT PDTT: 2.21 PCT

71.16 LBM/PCT

/ 125 MIN = 1.26 LBM/MIN PRT: 0.00 GAL/MIN

0.13368 CU FT/GAL

61.856 LBM/CU FT

= 0.00 LBM.MIN IDENTIFIED LEAKAGE:

0.00 GAL/MIN

0.13368 CU FT/GAL

62.310 LBM/CU FT

= 0.00 LBM.MIN

6) TOTAL LEAKAGES IN LBM/MIN

RCS: (-1.0)

0.22 LBM/MIN

+ -0.10 LBM/MIN

+ -2.41 LBM/MIN

= 2.29 LBM/MIN IDENTIFIED:

1.26 LBM/MIN

+ 0.00 LBM/MIN

= 1.26 LBM/MIN UNIDENTIFIED:

2.29 LBM/MIN

- 1.26 LBM/MIN

= 1.03 LBM/MIN

7) TOTAL LEAKAGES IN GALLONS/MINUTE:

RCS: 2.29 LBM/MIN

7.48052 GAL/CU FT /

61.856 LBM/CU FT

= 0.28 GAL/MIN IDENTIFIED:

1.26 LBM/MIN

7.48052 GAL/CU FT /

61.856 LBM/CU FT

= 0.15 GAL/MIN UNIDENTIFIED:

0.28 GAL/MIN

- 0.15 GAL/MIN

= 0.13 GAL/MIN NOTE: VALUES WITH A QUALITY OF "B" ARE UNRELIABLE REACTOR COOLANT SYSTEM LEAK RATE

DATE: 5/22/10 START TIME: Now

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Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Periodic Test Review 1

-OPT-CH-002 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B K/A: GEN2.2.37 Ability to determine operability and/or availability of safety related equipment.

Applicability Estimated Time Actual Time

SRO(I) 45 Minutes

Conditions Task is to be PERFORMED in the classroom.

Standards Reviews completed 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, for accuracy and determines operability

.

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 49 of 319 Initiating Cues I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, which has just been completed.

No maintenance has been performed on the Charging system.

Review 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B , 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 and any Technical Specification operability concerns if applicable

.

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

Tools and Equipment Calculator Copy of completed 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B. Safety Considerations None Notes Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 50 of 319 Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 51 of 319 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITICAL STEP.

START TIME:

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

STANDARD: Reviews purpose of procedure steps 1.1

- 1.9. EVALUATOR'S NOTE: N/A

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

STEP 2 - Review the References section (Section 2.0)

STANDARD: Reviews section 2.1, Source Documents, 2.2 Technical Specifications, 2.3 Technical References, and 2.4 Commitment Documents.

EVALUATOR'S NOTE: N/A

_______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 52 of 319 COMMENTS:

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 53 of 319 STEP 3: STEP 3 - Reviews the Initial Conditions section (Section 3.0)

STANDARD: Reviews Initial Conditions steps 3.1

- 3.4. EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT

STEP 4:

STEP 4 - Reviews the Precautions and Limitations section (Section 4.0) STANDARD: Reviews precautions and limitations steps 4.1

- 4.15.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 54 of 319 STEP 5: STEP 5 - Reviews the Special Tools and Equipment section (Section 5.0) STANDARD: Reviews Special Tools and Equipment section steps 5.1

- 5.8. EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

STEP 6: STEP 6.1 - Reviews Work Preparation section (Section 6.1).

STANDARD: Verifies proper placekeeping on all steps, notes, and cautions.

Verifies step 6.1.1 is N/A'd.

Verifies step 6.1.2 substeps a and b are initialed and Attachment 9 is properly filled out. Verifies step 6.1.3 is initialed and SQC numbers and Cal Due Dates are recorded on Attachment 1

. Verifies step 6.1.4 is initialed.

Verifies step 6.1.5 is initialed and blocks are correctly checked off. The 6 th block should be checked off which is "1

-CH-P-1B needs the Quarterly Test (1-CH-P-1B must be stopped), Perform Subsection 6.5 and Subsection 6.6

" Goes to subsection 6.5.

_______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 55 of 319 EVALUATOR'S NOTE: N/A COMMENTS:

STEP 7: STEPS 6.2-6.4 - Reviews Steps 6.2

- 6.4 of 1-OPT-CH-002 STANDARD: Verifies all steps in 6.2

- 6.4 are N/A'd. EVALUATOR'S NOTE: N/A COMMENTS: _______ SAT

_______ UNSAT STEP 8: STEP 6.5- Reviews Discharge Check Valve Close Test, MOV Timing, Lube Oil TCV Timing and Starting 1

-CH-P-1B section of procedure (Section 6.5.1 - 6.5.20). STANDARD: _______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 56 of 319 Verifies proper placekeeping on all steps, notes, and cautions.

Verifies step 6.5.1

- 6.5.20 are properly initialed.

Verifies open and close stroke times are recorded on Attachment 4 for 1

-CH- MOV-1286B, 1287B and 1275B.

Verifies discharge pressure recorded on Attachment 1 IAW step 6.5.1.e, 6.5.1.f, 6.5.1.g and that differential is < 7.5 psid IAW 6.5.1.g.

Verifies box checked in step 6.5.2 indicating that 1

-SW-TCV-108B was closed and goes to step 6.5.3.

Verifies step 6.5.

4 is N/A'd. Verifies step 6.5.6.

a is N/A'd. Verifies step 6.5.7 is N/A'd.

Verifies the open and closed stroke times, test position, and the as left position for 1-SW-TCV-108B are recorded on Attachment 4.

Verifies lube oil temperature recorded in step 6.5.6.d is between 60-120 °F. Verifies step 6.5.10.b is N/A'd. Verifies step 6.5.12 is N/A'd.

Verifies lube oil pressure rec orded in step 6.5.16 is between 8

-35 psig. Verifies step 6.5.17 N/A'd.

Verifies pump and damper checks were sat IAW step 6.5.20 on non

-running charging pumps.

EVALUATOR'S NOTE: N/A COMMENTS:

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 57 of 319 STEP 9: STEP 6.6- Reviews 1-CH-P-1B Performance Test section of procedure (Section 6.6.1 - 6.6.26). STANDARD: Verifies proper placekeeping on all steps, notes, and cautions.

Verifies step 6.6.1

- 6.6.26 are properly initialed.

Verifies step 6.6.3 is N/A'd.

Verifies data is recorded in step 6.6.5

- 6.6.7. Verifies step 6.6.10.b is N/A'd. Verifies data recorded on Attachme nts 1 and 2 IAW steps 6.6.12

- 6.6.16. Verifies step 6.6.17 and step 6.6.18 are N/A'd.

Verifies data is recorded in step 6.6.22.

Verifies step 6.6.26 N/A'd.

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

_______ UNSAT

STEP 10: STEPS 6.7-6.8 - Reviews Steps 6.7

- 6.8 of 1-OPT-CH-002 STANDARD: _______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 58 of 319 Verifies all steps in 6.7

- 6.8 are N/A'd.

EVALUATOR'S NOTE: N/A

COMMENTS:

STEP 1 1: STEP 6.9- Reviews Obtaining Oil Samples section of procedure Section 6.9.1

- 6.9.2). STANDARD: Verifies proper placekeeping on all steps, notes, and cautions.

Verifies steps in 6.9.1 are properly initialed and steps in 6.9.2 are N/A'd.

EVALUATOR'S NOTE: N/A

COMMENTS: _______ SAT

_______ UNSAT STEP 1 2: STEP 6.10 - Reviews Step 6.10 of 1

-OPT-CH-002. STANDARD: _______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 59 of 319 Verifies all steps of 6.10 are N/A'd.

EVALUATOR'S NOTE: N/A COMMENTS: STEP 1 2: STEP 7.0- Reviews Follow-On section of procedure (Section 7.1

- 7.4). STANDARD: Verifies proper placekeeping on all steps, notes, and cautions.

Evaluates the acceptance criteria in step 7.1.1 by reviewing attachment data referenced for each bulleted item.

EVALUATOR'S NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 13: Attachment 1

- Reviews Attachment 1 Data.

STANDARD: Review attachment 1 data and verifies all are within the acceptance criteria.

_______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 60 of 319 EVALUATOR'S NOTE: N/A COMMENTS: STEP 14:

- Reviews Attachment 2 Data.

STANDARD: Review attachment 2 data and verifies all are within the acceptance criteria.

Notes that the outboard horizontal vibration (pt 22) on the pump bearing is in the INOPERABLE RANGE and that OPT was checked as SAT.

This is a critical step.

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

_______ UNSAT STEP 15: Attachment 4- Reviews Attachment 4 Data.

STANDARD: Review attachment 4 data and verifies all are within the acceptance criteria.

Notes that 1

-CH-MOV-1287B OPEN stroke test time is not in the ACCEPTABLE range and that OPT was checked as SAT.

This is a critical step.

_______ SAT

_______ UNSAT

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 61 of 319 EVALUATOR'S NOTE: N/A COMMENTS:

STEP 16: Attachment 9- Reviews Attachment

9. STANDARD: Verifies proper placekeeping on all steps, notes, and cautions.

Verifies all steps in attachment 9 are properly initialed or N/A'd as applicable

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

_______ UNSAT STOP TIME:

____________________________________________________________________________________

Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 62 of 319 Surry 2010-301 PT Review (1

-OPT-CH-007) G2.2.37 SR10301 63 of 319 ANSWER KEY 1-OPT-CH-00 2 REVIEW 1. Attachment 2, outboard horizontal vibration (pt 22) on the pump exceeds the inoperable range limit given. (CRITICAL TASK)

2. Attachment 4, 1

-CH-MOV-1287B exceeds open stroke time limits. (CRITICAL TASK)

3. Step 7.1.1, Charging pump delta

-p and vibration status determinations are checked as NOT being inoperable. 1

-CH-MOV-1287B is checked as meeting the acceptance criteria.

4. 7.1.2, PT is marked as SAT versus UNSAT. (CRITICAL TASK)

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

6. No comments made in the Operator Comments section.

7. They are in violation of Tech Spec 3.2 because they do not have two boron injection subsystems due to 1-CH-P-1B being inoperable. They are in a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock to be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

. (CRITICAL TASK)

8. They are in violation of Tech Spec 3.

3 because they do not have two operable Safety Injection subsystems due to 1-CH-P-1B being inoperable. They are in a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock to be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

. (CRITICAL TASK)

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 1 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the classroom.

Review 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B , 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-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, has just been completed.

Initiating Cues I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, which has just been completed.

No maintenance has been performed on the Charging system.

Review 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, 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 and any Technical Specification operability concerns if applicable

.

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 2 of 319 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 is at 100% power.

1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B, has just been completed.

. Initiating Cues I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, which has just been completed.

No maintenance has been performed on the Charging system.

Review 1-OPT-CH-00 2 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1

-CH-P-1B, 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 and any Technical Specification operability concerns if applicable

.

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 3 of 319 ANSWER SHEET 1-OPT-CH-00 2 REVIEW _______________________________________________________________________________________

_______________________________________________________________________________________

_______________________________________________________________________________________ _______________________________________________________________________________________

_______________________________________________________________________________________

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 4 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.

2.13 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Determine Tagout Boundaries K/A: G2.2.13 - Knowledge of Tagging and Clearance Procedures. (4.1/4.3) Applicability Est Completion Time Actual Time RO 3 0 Minutes ___________

Conditions Task is to be PERFORMED in the CLASSROOM.

Standards Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 5 of 319 Correctly determine the tagging boundary to allow for maintenance on 1

-BC-P-1A. Initiating Cues It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely fix the pump seal on 1

-BC-P-1A.

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 6 of 319 Initial Conditions It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service. You are to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely replace the pump seal on 1

-BC-P-1A after the tags have been hung and associated piping drained.

Use the attached table to identify all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish identifying the tagging boundary, inform an examiner.

The computerized Tagging Systems are not operational and may not be used for this task.

Terminating Cues Applicant informs examiner that the task has been completed.

Tools, Equipment, and Procedures Applicants may request administrative procedures and plant drawings.

Procedures OP-AA-200, EQUIPMENT CLEARANCE 11448-FM-73A SH 1 11448-FE-1 B Tools and Equipment Safety Considerations Computer only connected to Webtop None Notes

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 7 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: Reviews the initial conditions of the JPM and uses Webtop to identify the drawings associated with the Bearing Cooling System that will be used to generate a safe working boundary.

STANDARD: (a) Utilizes Webtop and identifies that the following drawings are applicable:

11448-FM-73A SH 1 and 11448

-FE-1 B. EVALUATOR'S NOTE:

If asked , provide candidate with system to drawing number summary sheet

. COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 8 of 319 STEP 2: Reviews mechanical drawing 11448-FM-73A SH1 and identifies the mechanical boundaries (suction, discharge, vent, and drain)

STANDARD: (a) Notes that 1

-BC-70 (pump discharge valve) will need to be closed.

(b) Notes that 1

-BC-66 (pump suction valve) will need to be closed.

(c) Notes that 1

-BC-267 (pump discharge drain) will need to be opened.

(d) Notes that 1

-BC-171 (pump seal vent) will need to be opened.

(e) 1-BC-68 (1-BC-PI-101A isolation), 1

-BC-441 (1-BC-PI-115A isolation), and 1-BC-445 (1-BC-PI-116A isolation) are acceptable alternates to 1

-BC-171. This is a critical step.

EVALUATOR NOTES:

o Component and component position are both critical.

COMMENTS: _______ SAT

_______ UNSAT

STEP 3: Reviews electrical drawing 11448

-FE-1B and identifies the electrical boundary (4160V supply breaker) STANDARD: (a) Notes that 1-EP-BKR-15B8 will need to be opened This is a critical step.

EVALUATOR NOTES:

Candidate may also tag the control switch in pull to lock.

o Component and component position are both critical.

_______ SAT

_______ UNSAT

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 9 of 319 COMMENTS:

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 10 of 319 STEP 4: Completes the attached table and reports that the task is complete

. STANDARD: Table is completed as follows:

Component ID Number / Name Position Danger Tag Required 1 1-BC-P-1A Control Switch PTL No 2 1-EP-BKR-15B8 ('A' BC Pump Supply Breaker) Disconnect Yes 3 1-BC-70 ('A' BC Pump Discharge Valve) Closed Yes 4 1-BC-66 ('A' BC Pump Suction Valve) Closed Yes 5 1-BC-267 ('A' BC Pump Drain)

Open No 6 1-BC-171 ('A' BC Pump Seal Vent)

Open No 7 8 9 10 11 12 EVALUATOR'S NOTE:

1-BC-68 (1-BC-PI-101A isolation), 1

-BC-441 (1-BC-PI-115A isolation), and 1-BC-445 (1-BC-PI-116A isolation) are acceptable alternates to 1-BC-171. 1-BC-270 may also be used as an additional drain, the PI must be removed.

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 11 of 319 STOP TIME:

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 1 of 319 Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 2 of 319 Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 3 of 319 Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 1 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task may be PERFORMED in the classroom.

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 It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service.

You are to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely replace the pump seal o n 1-BC-P-1A after the tags have been hung and associated piping drained.

Use the attached table to identify all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish identifying the tagging boundary, inform an examiner.

The computerized Tagging Systems are not operational and may not be used for this task.

Initiating Cues It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely fix the pump seal on 1

-BC-P-1A.

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 2 of 319 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service.

You are to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely replace the pump seal on 1-BC-P-1A after the tags have been hung and associated piping drained.

Use the attached table to identify all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish identifying the tagging boundary, inform an examiner.

The computerized Tagging Systems are not operational and may not be used for this task.

Initiating Cues It has been reported that the outboard pump seal has failed on 1

-BC-P-1A and is leaking excessively. The shift secured 1

-BC-P-1A and placed 1

-BC-P-1B in service.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely fix the pump seal on 1

-BC-P-1A.

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 3 of 319 (TO BE GIVEN TO APPLICANT)

Component ID Number / Name Position Danger Tag Required? (Yes / No) 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 4 of 319 19 20 21 22 23 24 25

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 5 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.3.4 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Determine the Stay Time of an Operator in a Radiological Area without Exceeding Administrative Limits.

K/A: G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7) Applicability Est Completion Time Actual Time

RO/SRO(I) 20 Minutes ___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Standards Determines if an operator can spend in a radiological area without exceeding administrative dose limits and also determines how long an operator can remain in the radiological area assuming extensions are authorized.

Initiating Cues

Given simulated plant conditions, determine how long an operator can work in a radiological are without exceeding administrative dose limits. Also, assuming the maximum dose limit extension is authorized, how long can an operator perform work in a radiological area.

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 6 of 319 Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 7 of 319 Initia l Conditions I am the Nuclear Shift Manager. I need you to perform work in an area with a general dose rate of 400 mrem/hour. I anticipate that the work I need you to perform will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Based on the dose that you have received this year, you have already been upgraded to receive the Annual Administrative Dose Limit. I need you to tell me how long you can perform work in that area without requiring a further dose limit extension. It is currently the fourth quarter of the year and the dose you have received during the year is as follows:

o Quarter #1 (January

- March): 0.68 Rem o Quarter #2 (April

- June): 0.43 Rem o Quarter #3 (July

- September):

0.59 Rem o Quarter #4 (October

- Today): 0.10 Rem Finally, assuming that I am able to receive the maximum dose limit extension for you, inform me of how long you will be able to can perform work in that area and if you will be able to complete the job without assistance.

When you have completed this task please inform me of the results

. Terminating Cues Determination that work in the RCA cannot be performed without an extension and accurate stay time determination following maximum dose limit extension. Procedures VPAP-2101, Radiological Protection Program RP-AA-105, External Radiation Exposure Control Program C-HP-1031.024, Attachment 2 Tools and Equipment Safety Considerations Calculator Computer with only access to Webtop None Notes Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 8 of 319

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 9 of 319 Performance Checklist Notes to the Evaluator. Task critical elements are bolded and noted by the words "Critical Step" at the end of the step.

START TIME:

STEP 1: Answer to first question by the Shift Manager:

Based on the dose that you have received this year, I need you to tell me how long you can perform work in that area without requiring a dose limit extension and if you will be able to complete the job without assistance (assuming no dose extensions to the administrative limits). STANDARD: (a) Calculates dose received year to date as follows:

680 mrem + 430 mrem + 590 mrem + 100 mrem = 1800 mrem.

(b) Notes that the yearly dose limit without extension is 2000 mrem (c) Determines margin to yearly limit: 2000

- 1800 = 200 mrem (d) Calculates Stay Time: 200 mrem / 400 mrem/hour

= 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

This is a Critical Step

(e) Notes that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months task cannot be performed without assistance.

This is a Critical Step.

EVALUATOR'S NOTE:

Administrative limit is 2 Rem/year, with RCA lockout at 85% of administrative limit Can get extended to 3 Rem/Year with worker, manager and RP Manager approval. Can get extended to 5 Rem/year with worker, manager, RP Manager and Site VP approval. _______ SAT

_______ UNSAT

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 10 of 319 COMMENTS:

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 11 of 319 STEP 2: Answer to second question by the Shift Manager:

Finally, assuming that I am able to receive the maximum dose limit extension for you, inform me of how long you will be able to can perform work in that area and if you will be able to complete the job without assistance. STANDARD: (a) Calculates dose received year to date as follows:

680 mrem + 430 mrem + 590 mrem + 100 mrem = 1800 mrem.

(b) Notes that the maximum yearly dose limit with extension is 5000 mrem (c) Determines margin to yearly limit: 5000

- 1800 = 3200 mrem (d) Calculates Stay Time:

3200 mrem / 400 mrem/hour =

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This is a Critical Step (e) Notes that the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months task can be performed without assistance.

This is a Critical Step.

EVALUATOR'S NOTE:

Administrative limit is 2 Rem/year, with RCA lockout at 85% of administrative limit Can get extended to 3 Rem/Year with worker, manager and RP Manager approval. Can get extended to 5 Rem/year with worker, manager, RP Manager and Site VP approval. A candidate may state 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for part (d), as this is the projected time to complete the job. Follow

-up question concerning how the candidate arrived at 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months may be necessary to determine if the candidate is documenting actual stay time vice job completion time.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 12 of 319 Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 13 of 319 STEP 3: Reports task is complete

. STANDARD: (a) Verbal or written status report that the work cannot be done without assistance if a dose limit extension is not given and that with the extension the work can be performed without assistance.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS:

_______ SAT

_______ UNSAT

STOP TIME:

Surry 2010-301 Calculate Stay Time G2.3.4 SR10301 14 of 319 Surry 2010-301 Determine Classification G2.4.41 SR10301 1 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task may be PERFORMED in the simulator or classroom.

Correctly determine s the ability of an operator to perform a job in the RCA with or without an extension and the time the operator can perform that job without an extension

. 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:

I am the Nuclear Shift Manager. I need you to perform work in an area with a general dose rate of 400 mrem/hour. I anticipate that the work I need you to perform will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Based on the dose that you have received this year, you have already been upgraded to receive the Annual Administrative Dose Limit. I need you to tell me how long you can perform work in that area without requiring a further dose limit extension.

It is currently the fourth quarter of the year and the dose you have received during the year is as follows:

o Quarter #1 (January

- March): 0.68 Rem o Quarter #2 (April

- June): 0.43 Rem o Quarter #3 (July

- September):

0.59 Rem o Quarter #4 (October

- Today): 0.10 Rem Finally, assuming that I am able to receive the maximum dose limit extension for you, inform me of how long you will be able to can perform work in that area and if you will be able to complete the job without assistance.

Initiating Cues:

Surry 2010-301 Determine Classification G2.4.41 SR10301 2 of 319 Answer the two radiological control questions posed by the Nuclear Shift Manager and place your responses on the paper containing the questions

. When you have completed this task please inform me of the results

.

Surry 2010-301 Determine Classification G2.4.41 SR10301 3 of 319 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

I am the Nuclear Shift Manager. I need you to perform work in an area with a general dose rate of 400 mrem/hour. I anticipate that the work I need you to perform will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Based on the dose that you have received this year, you have already been upgraded to receive the Annual Administrative Dose Limit. I need you to tell me how long you can perform work in that area without requiring a further dose limit extension.

It is currently the fourth quarter of the year and the dose you have received during the year is as follows:

o Quarter #1 (January

- March): 0.68 Rem o Quarter #2 (April

- June): 0.43 Rem o Quarter #3 (July

- September):

0.59 Rem o Quarter #4 (October

- Today): 0.10 Rem Finally, assuming that I am able to receive the maximum dose limit extension for you, inform me of how long you will be able to can perform work in that area and if you will be able to complete the job without assistance.

Initiating Cues:

Answer the two radiological control questions posed by the Nuclear Shift Manager and place your responses on the paper containing the questions

. When you have completed this task please inform me of the results

.

Surry 2010-301 Determine Classification G2.4.41 SR10301 4 of 319 Shift Manager Questions and Operator Answers (TO BE GIVEN TO APPLICANT)

Question #1:

Based on the dose that you have received this year, I need you to tell me how long you can perform work in that area without requiring a dose limit extension and if you will be able to complete the job without assistance (assuming no dose extensions to the administrative limits).

Can be in the radiation area for: _______________________ minutes / hours (circle one)

Can complete the job without a dose extension in the allotted time: YES / NO (circle one)

Question #2:

Assuming that I am able to receive the maximum dose limit extension for you, inform me of how long you will be able to can perform work in that area and if you will be able to complete the job without assistance.

Surry 2010-301 Determine Classification G2.4.41 SR10301 5 of 319 Can be in the radiation area for: _______________________ minutes / hours (circle one)

After receiving the maximum extension can complete the job in the allotted time: YES / NO (circle one)

Surry 2010-301 Determine Classification G2.4.41 SR10301 6 of 319 U.S. Nuclear Regulatory Commission Surry Power Station SR 10 301 Administrative Job Performance Measure 2.4.41 TIME CRITICAL Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title CLASSIFY AN EVENT K/A: G2.4.41

- Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

Applicability Est Completion Time Actual Time SRO(I) 20 Minutes (Time Critical)

___________

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM

. A simulated SITE AREA EMERGENCY is in progress.

Standards Declares a Site Area Emergency using EAL Identifier SS1.2 in accordance with EPIP-1.01/EAL Table

. Initiating Cues Given simulated plant conditions, utilize EPIP

-1.10 and determine if classification is warranted.

Surry 2010-301 Determine Classification G2.4.41 SR10301 7 of 319 Initia l Conditions This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The AAC DG is tagged out for governor valve replacement. The Plan of the Day (POD) shows that the diesel will be returned to service next weekend. Both Units were initially at 100% power when a severe thunderstorm passed through the area.

Approximately 50 minutes ago, the station experienced a loss of the 'D' Transfer bus as the 'A' Reserve Station Service Transformer was struck and damaged by lightning (no fire).

At that time, #3 EDG tripped on overspeed during start

-up. Mechanics reset the overspeed, and when started, the #3 EDG experienced extremely high vibrations and the casing was penetrated by a connecting rod, and #3 EDG was subsequently tripped

. Approximately 35 minutes ago , Unit 1 reactor tripped due to a fault on the 'A' DC bus that damaged the 'A' Station Battery. Due to the significant amount of damage to the 'A' Station Battery, the electricians are estimating 2

- 3 days before the 'A' DC bus is restored.

Approximately 1 0 minutes ago , while performing 1

-AP-10.06, Loss of DC Power, the BOP reported that the 1B DC bus was 102 Volts and decreasing.

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.

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

Terminating Cues Report of classification determination

. Procedures EPIP-1.01, Emergency Manager Controlling Procedure (Revision 52)

Tools and Equipment Safety Considerations

None None Notes Surry 2010-301 Determine Classification G2.4.41 SR10301 8 of 319 Performance Checklist Notes to the Evaluator

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

START TIME:

STEP 1: Caution and Note prior to step 1.

CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.

NOTE: The PCS is potentially unreliable in the event of an earthquake. Therefore, PCS parameters should be evaluated for accuracy should an earthquake occur.

STANDARD: (a) Acknowledges CAUTION and NOTE EVALUATOR'S NOTE:

Candidate may choose to make EAL classification straight from EAL tables and NOT implement steps of EPIP

-1.01. Steps are given here as guidance. Critical task time ends when the classification is determined regardless of determination method.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2010-301 Determine Classification G2.4.41 SR10301 9 of 319 STEP 2: Step1 - EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using the applicable Emergency Action Level Matrix:

Hot Conditions (RCS > 200 °F)

Cold Conditions (RCS b) Review EAL associated with event category c) Use Control Room monitors, PCS, and outside reports to get indications of emergency conditions listed in the EAL Matrix d) Verify EAL

- CURRENTLY EXCEEDED e) Initiate a chronological log of events STANDARD: (a) Refers to the HOT chart (b) Determines event category to be Loss of Power.

(c) Refers to given conditions to determine EAL applicability (d) Determines EAL Identifier S S 1.2 conditions are met and declares a Site Area Emergency on this Identifier

. This is a Critical Step.

(e) Initiates (or verbalizes) a chronological log of events

.

EVALUATOR'S NOTE

If candidate makes EAL determination at this step, record stop time.

COMMENTS: STOP CRITICAL TASK TIME: ___________

TIME CRITI C AL- 15 minutes

_______ SAT

_______ UNSAT

Surry 2010-301 Determine Classification G2.4.41 SR10301 10 of 319 Surry 2010-301 Determine Classification G2.4.41 SR10301 11 of 319 STEP 3: Step 2 - RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME:

Emergency Classification EAL Identifier Time Declared SM /SEM Name Notification of Unusual Event Alert Site Area Emergency General Emergency STANDARD: (a) Completes the table as indicated below:

Emergency Classification EAL Identifier Time Declared SM /SEM Name Notification of Unusual Event Alert Site Area Emergency SS1.2 TBD TBD General Emergency EVALUATOR'S NOTE

Completion of this table is not required for successful completion of the JPM.

COMMENTS: _______ SAT

_______ UNSAT

Surry 2010-301 Determine Classification G2.4.41 SR10301 12 of 319 STEP 5: Reports declaration of the event in progress.

STANDARD: (a) Verbal or written status report that a Site Area Emergency should be declared on Tab SS1.2.

This is a Critical Step if not already performed.

EVALUATOR'S NOTE:

Acknowledge the completion of the task.

COMMENTS:

STOP CRITICAL TASK TIME:

___________

TIME CRITICAL

- 15 minutes

_______ SAT

_______ UNSAT

STOP TIME:

Surry 2010-301 Determine Classification G2.4.41 SR10301 13 of 319

- Screen Shots G2.4.41 SR10301 1 of 319 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task may be PERFORMED in the simulator or classroom.

Classify an event in accordance with EPIP

-1.01, Emergency Manager Controlling Procedure

. Directions

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

Initial Conditions:

This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The AAC DG is tagged out for governor valve replacement. The Plan of the Day (POD) shows that the diesel will be returned to service next weekend. Both Units were initially at 100% power when a severe thunderstorm passed through the area.

Approximately 50 minutes ago, the station experienced a loss of the 'D' Transfer bus as the 'A' Reserve Station Service Transformer was struck and damaged by lightning (no fire).

At that time, #3 EDG tripped on overspeed during start

-up. Mechanics reset the overspeed, and when started, the #3 EDG experienced extremely high vibrations and the casing was penetrated by a connecting rod, and #3 EDG was subsequently tripped.

Approximately 35 minutes ago, Unit 1 reactor tripped due to a fault on the 'A' DC bus that damaged the 'A' Station Battery. Due to the significant amount of damage to the 'A' Station Battery, the electricians are estimating 2

- 3 days before the 'A' DC bus is restored.

Approximately 10 minutes ago, while performing 1

-AP-10.06, Loss of DC Power, the BOP reported that the 1B DC bus was 102 Volts and decreasing.

Initiating Cues:

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.

- Screen Shots G2.4.41 SR10301 2 of 319 When you finish the actions necessary to accomplish this, please inform me of your classification, if necessary.

- Screen Shots G2.4.41 SR10301 3 of 319 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The AAC DG is tagged out for governor valve replacement. The Plan of the Day (POD) shows that the diesel will be returned to service next weekend. Both Units were initially at 100% power when a severe thunderstorm passed through the area.

Approximately 50 minutes ago, the station experienced a loss of the 'D' Transfer bus as the 'A' Reserve Station Service Transformer was struck and damaged by lightning (no fire).

At that time, #3 EDG tripped on overspeed during start

-up. Mechanics reset the overspeed, and when started, the #3 EDG experienced extremely high vibrations and the casing was penetrated by a connecting rod, and #3 EDG was subsequently tripped.

Approximately 35 minutes ago, Unit 1 reactor tripped due to a fault on the 'A' DC bus that damaged the 'A' Station Battery. Due to the significant amount of damage to the 'A' Station Battery, the electricians are estimating 2

- 3 days before the 'A' DC bus is restored.

Approximately 10 minutes ago, while performing 1

-AP-10.06, Loss of DC Power, the BOP reported that the 1B DC bus was 102 Volts and decreasing.

Initiating Cues:

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.

- Screen Shots G2.4.41 SR10301 4 of 319 When you finish the actions necessary to accomplish this, please inform me of your classification, if necessary.

Record classification and EAL identifier (if any): ______________________

_________________________

EMERGENCY CLASSIFICATION PROCEDURES NOT INCLUDED.

ML102780342

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