Text

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 U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.1.20 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title Determine Partial Pressure following a Loss of Containment Cooling K/A: G2.1.20 - Ability to interpret and execute procedure steps. (4.6/4.6)

Applicability 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.

G2.1.20 SR10301 1 of 319

Surry 2010-301 Calculate Partial Pressure 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

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

None

Steam Tables

Tech Specs

DRP-003 Notes PCS Screen Shots are provide to facilitate classroom performance.

G2.1.20 SR10301 2 of 319

Surry 2010-301 Calculate Partial Pressure Performance Checklist Notes to the Evaluator.

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

START TIME:

STEP 1:

_______ SAT Notes prior to Step 1 of Attachment 2:

_______ UNSAT

This calculation 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 EVALUATORS NOTE:

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

COMMENTS:

G2.1.20 SR10301 3 of 319

Surry 2010-301 Calculate Partial Pressure STEP 2:

_______ SAT Step 1 of Attachment 2:

_______ UNSAT

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 Attachment 2.

EVALUATOR NOTES:

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 10.41 SI COMMENTS:

STEP 3:

_______ SAT Step 2 of Attachment 2:

_______ UNSAT

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 follows:

Date/Time Tmin Ptot Psat Pair Initials Today/0000 N/A N/A N/A 10.41 SI Today/Now COMMENTS:

G2.1.20 SR10301 4 of 319

Surry 2010-301 Calculate Partial Pressure STEP 4:

_______ SAT Step 3 of Attachment 2:

_______ UNSAT

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 10.41 SI Today/Now 88 °F COMMENTS:

G2.1.20 SR10301 5 of 319

Surry 2010-301 Calculate Partial Pressure 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 10.41 SI Today/Now 88 °F 11.29 (PCS)

Answer:

If CV-PI-101A/B chosen - highest reading should be 11.27 psia [range 11.20 - 11.30]

If PCS points are utilized - highest reading should be 11.29 psia COMMENTS:

G2.1.20 SR10301 6 of 319

Surry 2010-301 Calculate Partial Pressure STEP 6:

_______ SAT Step 5 of Attachment 2

_______ UNSAT

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 10.41 SI Today/Now 88 °F 11.29 (PCS) 0.65551 Answer: 0.65551 [Acceptable Range 0.65 - 0.66]

COMMENTS:

G2.1.20 SR10301 7 of 319

Surry 2010-301 Calculate Partial Pressure STEP 7:

_______ SAT Step 6 of Attachment 2:

_______ UNSAT

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 10.41 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 10.54 - 10.65]

If PCS used - should calculate Pair to be 10.63449 [range 10.63 - 10.64]

COMMENTS:

STEP 8:

_______ SAT Note prior to step 7:

A more precise measurement of Pair may be obtained by performing the following _______ UNSAT 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:

G2.1.20 SR10301 8 of 319

Surry 2010-301 Calculate Partial Pressure STEP 9:

_______ SAT Step 7 of Attachment 2:

_______ UNSAT

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 12 and goes to step 12.

EVALUATOR NOTES:

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

STEP 10:

Step 13 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 NOTES:

Trainee to obtain CW temperature from PCS Screen Shots located at the end of this JPM - CW inlet temp will be 94F.

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:

G2.1.20 SR10301 9 of 319

Surry 2010-301 Calculate Partial Pressure STEP 11:

_______ SAT Reports task is complete.

_______ UNSAT 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.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

STOP TIME:

G2.1.20 SR10301 10 of 319

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 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.

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 P1LM001A CNTMT IR PRESSURE (BL) 11.29 PSIA P1LM002A CNTMT IR PRESSURE (RD) 11.27 PSIA P1LM003A CNTMT IR PRESSURE (WT) 11.23 PSIA P1LM004A CNTMT IR PRESSURE (YW) 11 25 PSIA G2.1.37 SR10301 2 of 319

Surry 2010-301 Perform 1-OP-RX-010 98.2 DEG 111.8 DEG 108.4 DEG 103.4 DEG 98.0 DEG F

97.6 DEG 92.3 DEG 91.4 DEG 95.6 DEG 89.6 DEG 88.7 DEG 88.0 DEG 96.5 DEG 92.7 DEG 92.5 DEG F

108.2 DEG 102.3 DEG 93.0 DEG 89.3 DEG 98.0 DEG G2.1.37 SR10301 3 of 319

Surry 2010-301 Perform 1-OP-RX-010 OUTLET TEMP OUTLET TEMP OUTLET TEMP OUTLET TEMP 101.0 DEGF 101.0 DEGF 101.0 DEGF 101.0 DEGF INLET TEMP INLET TEMP INLET TEMP INLET TEMP 94.0 DEG 94.0 DEG 94.0 DEG 94.0 DEG G2.1.37 SR10301 4 of 319

Surry 2010-301 Perform 1-OP-RX-010 U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.1.37 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title COMPLETE A REACTIVITY

SUMMARY

SHEET K/A: G2.1.37 - 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.

G2.1.37 SR10301 5 of 319

Surry 2010-301 Perform 1-OP-RX-010 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: 13090 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.

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 G2.1.37 SR10301 6 of 319

Surry 2010-301 Perform 1-OP-RX-010 Performance Checklist Notes to the Evaluator.

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

START TIME:

STEP 1:

_______ SAT 3.0 INITIAL CONDITIONS

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

STEP 2:

_______ SAT Note prior to Step 5.1.1:

G2.1.37 SR10301 7 of 319

Surry 2010-301 Perform 1-OP-RX-010

The items listed in Step 5.1.1 will be updated every 2 weeks by Reactor _______ UNSAT Engineering.

STANDARD:

(a) Acknowledges the Note.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 8 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 3:

_______ SAT Step 5.1.1

_______ UNSAT 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.

EVALUATORS NOTE:

None.

COMMENTS:

STEP 4:

_______ SAT Notes prior to Step 5.2.1:

The following guidelines should be used when performing calculations: _______ UNSAT 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.

G2.1.37 SR10301 9 of 319

Surry 2010-301 Perform 1-OP-RX-010

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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 10 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 5:

_______ SAT Step 5.2.1

_______ UNSAT 5.2.1 Perform Attachment 1 to calculate reactivity parameters.

STANDARD:

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

EVALUATORS NOTE:

None.

COMMENTS:

STEP 6:

_______ SAT Note prior to Step 1 of Attachment 1:

Unless a specific value is given, the most recent Core Burn-up value from the _______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 11 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 7

_______ SAT , Step 1:

_______ UNSAT

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: 13090 (MWD/MTU)

b. ITC: -26.48 (PCM/°F)

c. Differential Boron Worth (DBW): -8.30 (PCM/PPM)

d. Boron Concentration of in-service BAST (Cb BAST): 13952 ppm EVALUATORS 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: -8.30 pcm/ppm ACCEPTABLE RANGE: [-8.28 to -8.33]

G2.1.37 SR10301 12 of 319

Surry 2010-301 Perform 1-OP-RX-010

d. BAST Boron Concentration was provided as an initial condition.

COMMENTS:

G2.1.37 SR10301 13 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 8:

_______ SAT , Step 2:

_______ UNSAT

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.

EVALUATORS 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:

G2.1.37 SR10301 14 of 319

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 15 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 9:

_______ SAT Note prior to Step 3 of Attachment 1:

When RCS Boron Concentration is less than 12 ppm, the equation in Step 3 will _______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 16 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 10:

_______ SAT , Step 3:

_______ UNSAT

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.

EVALUATORS 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:

G2.1.37 SR10301 17 of 319

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 18 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 11:

_______ SAT , Step 4:

_______ UNSAT

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).

EVALUATORS NOTE:

None.

COMMENTS:

STEP 12:

_______ SAT , Step 5:

_______ UNSAT

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)

G2.1.37 SR10301 19 of 319

Surry 2010-301 Perform 1-OP-RX-010

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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 20 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 13:

_______ SAT , Step 6:

_______ UNSAT

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 + (-0.000236577) [may round to -0.00024]

d. -50813 x LN(0.999763423) [based on previous rounding 0.99976]

e. -50813 x -0.000236605 [based on previous rounding -0.00024]

f. 12.02 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.

EVALUATORS 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:

G2.1.37 SR10301 21 of 319

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 22 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 14:

_______ SAT Notes prior to Step 7 of Attachment 1:

When RCS Boron Concentration is less than 16 ppm, the equation in Step 7 will _______ UNSAT yield invalid results.

When RCS Boron Concentration is less than 16 ppm, the amount of dilution to make a 1 °F Tave change will be greater than 50,000 gallons.

STANDARD:

(a) Acknowledges the Notes.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 23 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 15:

_______ SAT , Step 7:

_______ UNSAT

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 - (0.006965066)) [may round to 0.00697]

d. -50813 x LN(0.993034934 [based on previous rounding 0.99303]

e. -50813 x -0.006986435 [based on previous rounding -0.00699]

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

g. Answer: 355 gallons [acceptable range 353 - 357]

This is a critical step.

EVALUATORS 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 G2.1.37 SR10301 24 of 319

Surry 2010-301 Perform 1-OP-RX-010 COMMENTS:

G2.1.37 SR10301 25 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 16:

_______ SAT 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 _______ UNSAT height with the highest rod worth. Interpolation to an unlisted rod height is not necessary.

STANDARD:

(a) Acknowledges the Notes.

EVALUATORS NOTE:

None COMMENTS:

G2.1.37 SR10301 26 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 17

_______ SAT , Step 8:

_______ UNSAT

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 EVALUATORS 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 29 (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]

G2.1.37 SR10301 27 of 319

Surry 2010-301 Perform 1-OP-RX-010 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:

G2.1.37 SR10301 28 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 18

_______ SAT Step 5.2.2 Transfer appropriate values to Attachment 2, Reactivity Summary Sheet.

_______ UNSAT 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 353 - 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 EVALUATORS 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:

G2.1.37 SR10301 29 of 319

Surry 2010-301 Perform 1-OP-RX-010 G2.1.37 SR10301 30 of 319

Surry 2010-301 Perform 1-OP-RX-010 STEP 5:

_______ SAT Reports completion of 1-OP-RX-010 and that the calculations are ready to be independently

_______ UNSAT verified.

STANDARD:

(a) Verbal or written status report that a 1-OP-RX-010 is ready to be independently verified.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

STOP TIME:

G2.1.37 SR10301 31 of 319

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: 13090 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: 13090 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.

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Surry 2010-301 Perform 1-OPT-RC-10.0 U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.1.23 Applicant________________________________ Start Time___________________

Examiner_______________________________

Date ___________________________________ Stop Time___________________

Title COMPLETE 1-OPT-RC-10.0, REACTOR COOLANT LEAKAGE - COMPUTER CALCULATED K/A: G2.1.23 - 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 SRO(I) 30 Minutes ___________

Conditions

Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

Performance of 1-OPT-RC-10.0, Reactor Coolant Leakage - Computer Calculated, is required.

Standards G2.1.23 SR10301 25 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0

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.

G2.1.23 SR10301 26 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 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.

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.

G2.1.23 SR10301 27 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 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

None

RCS Leakrate Spreadsheet

Large Stapler Notes G2.1.23 SR10301 28 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 Performance Checklist Notes to the Evaluator.

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

START TIME:

STEP 1:

_______ SAT 3.0 INITIAL CONDITIONS

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

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 STEP 2:

_______ SAT 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The RCS leak rate program on the PCS plant computer will halt if VCT level _______ UNSAT 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 G2.1.23 SR10301 31 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.23 SR10301 32 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 3:

_______ SAT Reviews completed procedure Section 6.1 and procedure Section 6.12 up to Step 6.2.12.

_______ UNSAT STANDARD:

(a) Acknowledges procedure status up to Step 6.2.12.

EVALUATORS NOTE:

None COMMENTS:

STEP 4:

_______ SAT Step 6.2.12:

_______ UNSAT 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 a. REPEAT steps 6.2.7 through 6.2.12 leakrate greater than -0.08 to obtain valid unidentified RCS Leak gpm 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 a. Enter zero for unidentified RCS leak leakrate less than or equal to rate.

-0.08 gpm b. Adjust total leak rate fto equal to the identified leak rate.

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

G2.1.23 SR10301 33 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STANDARD:

(a) Marks the Initial Column Lines as N/A.

EVALUATORS NOTE:

None.

COMMENTS:

G2.1.23 SR10301 34 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 5:

_______ SAT Step 6.2.13

_______ UNSAT 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.

EVALUATORS NOTE:

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from Current values:

the LAST (most recent previously calculated leak rate data) performance of 1-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate 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:

G2.1.23 SR10301 35 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 6:

_______ SAT Step 6.2.14

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

STEP 7:

_______ SAT Step 6.2.15

_______ UNSAT 6.2.15 Verify one PDTT pump is in AUTO.

STANDARD:

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

EVALUATORS NOTE:

None COMMENTS:

G2.1.23 SR10301 36 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 8:

_______ SAT Step 6.2.16

_______ UNSAT 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.

EVALUATORS NOTE:

Candidate will proceed to Section 6.3.

COMMENTS:

STEP 9:

_______ SAT Reviews procedure Section 6.3 up to Step 6.3.2. _______ UNSAT STANDARD:

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

EVALUATORS NOTE:

None COMMENTS:

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 STEP 10:

_______ SAT Step 6.3.3

_______ UNSAT 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.

EVALUATORS NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being Column 2 Column 3 analyzed Final Value of Parameter Initial Value of ** Change in at END of Time Parameter at Parameter (+ or -

START of Time ) (final value -

initial value)

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

CTMT Sump Level Circle instrument used Circle instrument N/A instrument used: 1-DA-LI-100, used 1-DA-LI-100, 1-DA-LI- 1-DA-LI-110A, or 1-DA-LI-100, 110A, or 1-DA-LI- 1-DA-LI-110B 1-DA-LI-110A, or 110B 1-DA-LI-110B CTMT Sump Level (% or IN) 47 (% or IN) N/A CTMT Sump Volume (gallons) (gallons) (gallons) from curve in 1-DRP- 34.6465 003 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:

G2.1.23 SR10301 39 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 Answer: 35 gallons [range 34 - 36 gallons]

COMMENTS:

G2.1.23 SR10301 40 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 11:

_______ SAT Step 6.3.4

_______ UNSAT 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.

EVALUATORS NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being Column 2 Column 3 analyzed Final Value of Parameter Initial Value of ** Change in at END of Time Parameter at Parameter (+ or -

START of Time ) (final value -

initial value)

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

CTMT Sump Level Circle instrument used Circle instrument N/A instrument used: 1-DA-LI-100, used 1-DA-LI-100, 1-DA-LI- 1-DA-LI-110A, or 1-DA-LI-100, 110A, or 1-DA-LI- 1-DA-LI-110B 1-DA-LI-110A, or 110B 1-DA-LI-110B CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume (gallons) (gallons) (gallons) from curve in 1-DRP- 39.439 34.6465 003 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:

G2.1.23 SR10301 41 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 Answer: 39 gallons [range 38 - 40 gallons]

COMMENTS:

G2.1.23 SR10301 42 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 12:

_______ SAT Step 6.3.5

_______ UNSAT 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.

EVALUATORS NOTE:

Table 1 - Containment Sump In Leakage Rate Parameter being Column 2 Column 3 analyzed Final Value of Parameter Initial Value of ** Change in at END of Time Parameter at Parameter (+ or -

START of Time ) (final value -

initial value)

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

CTMT Sump Level Circle instrument used Circle instrument N/A instrument used: 1-DA-LI-100, used 1-DA-LI-100, 1-DA-LI- 1-DA-LI-110A, or 1-DA-LI-100, 110A, or 1-DA-LI- 1-DA-LI-110B 1-DA-LI-110A, or 110B 1-DA-LI-110B CTMT Sump Level 62 (% or IN) 47 (% or IN) N/A CTMT Sump Volume (gallons) (gallons) (gallons) from curve in 1-DRP- 39.439 34.6465 4.7925 003 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]

G2.1.23 SR10301 43 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 Table 2 - Containment Sump In Leakage rate Change in Parameter (+/-) Divided by Elapsed Time Sump In Leakage rate (final value - initial value)

CTMT Sump Volume (minutes) (gpm)

Change 4.7925 60 (gallons)

Elapsed time will be filled in as an initial condition.

COMMENTS:

G2.1.23 SR10301 44 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 13:

_______ SAT Step 6.3.6

_______ UNSAT 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.

EVALUATORS NOTE:

Table 2 - Containment Sump In Leakage rate Change in Parameter (+/-) Divided by Elapsed Time Sump In Leakage rate (final value - initial value)

CTMT Sump Volume (minutes) (gpm)

Change 4.7925 60 0.08 (gallons)

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]

COMMENTS:

G2.1.23 SR10301 45 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 14:

_______ SAT Step 6.3.7

_______ UNSAT 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.

EVALUATORS NOTE:

Summary of Reactor Coolant Leak Rate Test Results RCS Leak Rate Data Identified leakage from Current values:

the LAST (most recent previously calculated leak rate data) performance of 1-OPT-RC-10.0 or 1-OPT-RC-10.1, as appropriate 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]

G2.1.23 SR10301 46 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 COMMENTS:

G2.1.23 SR10301 47 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 15:

_______ SAT Step 6.3.8

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

STEP 16:

_______ SAT Step 6.4

_______ UNSAT Note prior to Step 6.4.1:

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

STANDARD:

(a) Acknowledges the note.

EVALUATORS NOTE:

None COMMENTS:

G2.1.23 SR10301 48 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 17:

_______ SAT Step 6.4.1

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

STEP 18:

_______ SAT Note prior to Step 6.4.2:

Primary to secondary leakage determination through each SG is required every _______ UNSAT 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.

EVALUATORS NOTE:

G2.1.23 SR10301 49 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0

None COMMENTS:

G2.1.23 SR10301 50 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 19:

_______ SAT Step 6.4.2

_______ UNSAT 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 EVALUATORS NOTE:

None COMMENTS:

STEP 20:

_______ SAT Step 6.4.3

_______ UNSAT 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.

EVALUATORS NOTE:

None G2.1.23 SR10301 51 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 COMMENTS:

G2.1.23 SR10301 52 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 21:

_______ SAT Step 6.5

_______ UNSAT 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.

EVALUATORS NOTE:

None COMMENTS:

G2.1.23 SR10301 53 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 22:

_______ SAT Step 6.5.1

_______ UNSAT 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.

EVALUATORS NOTE:

Pre-data Entry Total Identified Unidentified Sump 'A' 'B' Date (gpm) (gpm) (gpm) (gpm) (gpd) (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 2 of 3 consecutive 9 last Unidentified Unident.

7 Day Consecutive 2 Leak Rates > Leak Rate Average Unidentified Consecutive baseline > baseline Unident. Unidentified Leak Rates > Unidentified mean + 2 mean + 3 Unident.

Leakage Leak Rate > baseline Leak Rates standard standard Leak Rate Date (gpm) .1 gpm mean >.15 gpm deviations deviations >.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 G2.1.23 SR10301 54 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 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:

G2.1.23 SR10301 55 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 23:

_______ SAT Step 6.5.2

_______ UNSAT 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.

EVALUATORS NOTE:

Post-data Entry Total Identified Unidentified Sump 'A' 'B' Date (gpm) (gpm) (gpm) (gpm) (gpd) (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 2 of 3 consecutive 9 last Unidentified Unident.

7 Day Consecutive 2 Leak Rates > Leak Rate Average Unidentified Consecutive baseline > baseline Unident. Unidentified Leak Rates > Unidentified mean + 2 mean + 3 Unident.

Leakage Leak Rate > baseline Leak Rates standard standard Leak Rate Date (gpm) .1 gpm mean >.15 gpm deviations deviations >.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 G2.1.23 SR10301 56 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 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:

_______ SAT Notes prior to Step 6.5.3:

The following information is determined by 1-OPT-RC-10.0 spreadsheet in Daily _______ UNSAT 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 Notes.

EVALUATORS NOTE:

None COMMENTS:

G2.1.23 SR10301 57 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 25:

_______ SAT Step 6.5.3

_______ UNSAT 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.

EVALUATORS NOTE:

If asked, acknowledge the need to perform 1-OP-RC-014. State another operator G2.1.23 SR10301 58 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 will perform this procedure and to continue on with 1-OPT-RC-10.0 COMMENTS:

G2.1.23 SR10301 59 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 26:

_______ SAT 7.1 Acceptance Criteria.

_______ UNSAT 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 G2.1.23 SR10301 60 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 This is a critical step.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

G2.1.23 SR10301 61 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STEP 27:

_______ SAT 7.2 Follow on Tasks.

_______ UNSAT 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.

EVALUATORS NOTE:

System Engineer: Karlie F. Irwine.

COMMENTS:

G2.1.23 SR10301 62 of 319

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 STEP 28:

_______ SAT 7.3 Notification, Documentation and Procedure Closeout.

_______ UNSAT 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.

EVALUATORS NOTE:

None.

COMMENTS:

STOP TIME (Part 1):

G2.1.23 SR10301 64 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 PART 2 of JPM:

Start Time:

STEP 28: PART 2 of JPM

_______ SAT Directions to Candidate:

Now that you have completed 1-OPT-RC-10.0, Reactor Coolant Leakage - Computer _______ UNSAT 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).

EVALUATORS NOTE:

None.

COMMENTS:

G2.1.23 SR10301 65 of 319

Surry 2010-301 Perform 1-OPT-RC-10.0 STOP TIME (Part 2):

G2.1.23 SR10301 66 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: 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 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 + 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