Text

Initial Exam 2010-301 Final Administrative JPMs
	ML102780331
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: ML102780331 (524)
	v • d • e

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 ___________

Initial 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 1 of 35

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% and stable for last 7 days

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 2 of 35

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:

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 3 of 35

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.

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 4 of 35

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 5 of 35

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]

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

COMMENTS:

G2.1.37 SR10301 6 of 35

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 7 of 35

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 8 of 35

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 9 of 35

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)

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 10 of 35

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 11 of 35

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 12 of 35

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 COMMENTS:

G2.1.37 SR10301 13 of 35

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 14 of 35

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]

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 15 of 35

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 16 of 35

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 17 of 35

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% and stable for last 14 days

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 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% and stable for last 14 days

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.

PROCEDURE NO:

1-DRP-003 REVISION NO:

SURRY POWER STATION 92 PROCEDURE TYPE: UNIT NO:

DESIGN REFERENCE PROCEDURE 1 PROCEDURE TITLE:

CURVE BOOK REACT MGT REVISION

SUMMARY

Revised in accordance with EN FB 10-0045:

Revised to update Attachments 30 and 32 through 37 to reflect the change in burnup range of the core. These attachments are applicable through 13,500 MWD/T and current projections for the month of May 2010 indicate that the Surry Unit 1 core will exceed this burnup range during the month.

(Pages 70, and 72 through 78)

UNIT ONE INFORMATION USE

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 2 of 195 TABLE OF CONTENTS Section Page 1.0 PURPOSE 7

2.0 REFERENCES

7 3.0 INITIAL CONDITIONS 8 4.0 PRECAUTIONS AND LIMITATIONS 8 5.0 INSTRUCTIONS 8

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 3 of 195 TABLE OF CONTENTS Section Page SECTION 1 - ATTACHMENTS - PHYSICS CURVES 1 Heatup And Cooldown Curve 9 2 Saturation Pressure Temperature Curve 12 3 Saturation Pressure Temperature Curve 13 4 Containment Allowable Air Partial Pressure Indication vs. Service Water Temperature 14 5 Allowable Air Partial Pressure Table 15 6 Intentionally left blank 28 7 Core Heatup Times For Surry 29 8 Boron Addition Rate - Coolant Hot 31 9 Boron Addition Rate - Coolant Cold 32 10 Boron Addition - Coolant Hot 33 11 Boron Addition - Coolant Cold 34 12 Dilution Rate - Coolant Hot 35 13 Dilution Rate - Coolant Cold 36 14 Dilution Nomograph - Coolant Hot 37 15 Dilution Nomograph - Coolant Cold 38 16 Dilution And Letdown Rate Nomograph - Coolant Hot 39 17 Blended Flow Nomograph 40 18 Blended Flow Nomograph 41 19 Blended Flow Table For 9.5 gpm From BAST 42 20 Blended Flow Table For 7.0 gpm From BAST 43 21 Blended Flow Table For 5.0 gpm From BAST 44 22 VCT Batch Mix Table 45 23 Gallons Of Boric Acid Needed To Increase RCS By 1 ppm 46 24 RCS Dilution Table 48 25 Control Rod Insertion Limits vs Power Level (For 3 Loop Normal Operation) 50

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 4 of 195 TABLE OF CONTENTS Section Page 26 Surry Unit 1 - Cycle 23 Critical Boron Concentration vs. Burnup Hot Full Power, All Rods Out 51 27 Surry Unit 1 - Cycle 23 Boron Coefficient vs Burnup 53 28 Surry Unit 1 - Cycle 23 HZP Integral Rod Worth Table For Control Banks C And D in Overlap 54 29 Surry Unit 1 - Cycle 23 At Power Integral Rod Worth Table For Control Banks C And D In Overlap 62 30 Surry Unit 1 - Cycle 23 Isothermal Temperature Defect vs. Average Moderator Temperature 70 31 Surry Unit 1 - Cycle 23 Power Defect 71 32 Surry Unit 1 - Cycle 23 Xenon Reactivity Worth At HZP vs. Previous Equilibrium Power Level 72 33 Surry Unit 1 - Cycle 23 Xenon Reactivity Worth Following Startup 73 34 Surry Unit 1 - Cycle 23 Xenon Reactivity Worth Following Reactor Trip (100 Hours) 74 35 Surry Unit 1 - Cycle 23 Xenon Reactivity Worth Following Reactor Trip (25 Hours) 75 36 Surry Unit 1 - Cycle 23 Xenon Reactivity Worth Following Orderly Shutdown 76 37 Surry Unit 1 - Cycle 23 Net Isotopic Decay Reactivity After Shutdown From HFP 77 38 Surry Unit 1 - Cycle 23 Total Rod Worth vs. Burnup 79 39 Surry Unit 1 - Cycle 23 Shutdown Banks Worth vs. Burnup 80 40 Surry Unit 1 - Cycle 23 Stuck Rod Worth vs. Burnup 81 41 Surry Unit 1 - Cycle 23 Worth Of A Single Rod Bank Out Of Sequence Up To 18 Steps 82 42 Surry Unit 1 - Cycle 23 Reactivity Redistribution Factor vs. Burnup 83 43 Surry Unit 1 - Cycle 23 Hot To Cold Temperature Defect vs. Average Moderator Temperature 84

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 5 of 195 TABLE OF CONTENTS Section Page 44 Surry Unit 1 - Cycle 23 1.1 X Cb(N-1) vs. Temperature at Various Burnups 86 45 Surry Unit 1 - Cycle 23 1.5 X Cb(N-1) vs. Temperature at Various Burnups 87 46 SURRY UNIT 1 - CYCLE 23 Isothermal Temperature Coefficient At Various Power Levels Vs. Burnup With All Rods Out 88 47 SURRY UNIT 1 - CYCLE 23 Minimum Boron Concentration Required To Meet 1770 PCM Shutdown 89 48 Surry Unit 1 - Cycle 23 Boron Coefficient Vs. Burnup For Zero Percent Power 90 49 SURRY UNIT 1 - CYCLE 23 Conservative Zero Power Minimum Insertion Limit Shutdown Margin Data 91 50 Load Change Charts 92 51 Startup And Loading Times 95 52 Capability Curves 97 53 Primary Drains Tank 99 54 Boron Recovery Tank 100 55 Primary Grade Water Tank 101 56 300,000 Gallon Condensate Storage Tank 102 57 110,000 Gallon Condensate Storage Tank 103 58 RWST 104 59 Chemical Addition Tank 107 60 Boric Acid Storage Tanks 109 61 Pressurizer Relief Tank 110 62 Pressurizer Relief Tank Mass Versus Indicated Level 111 63 Pressurizer Relief Tank Volume Versus Indicated Level 117 64 Safety Injection Accumulator Level 126 65 Primary Drain Transfer Tank 127 66 Primary Drain Transfer Tank Volume Versus Indicated Level 128 67 Liquid Waste Tank 137

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 6 of 195 TABLE OF CONTENTS Section Page 68 Containment Sump Volume 138 69 Containment Sump Volume - Narrow Range Level 141 70 Containment Water Volume vs. Water Level Elevation 142 71 Component Cooling Surge Tank 144 72 Enthalpy Steam Table (100% Quality) 147 73 Enthalpy Saturated Liquid Table 148 74 Enthalpy Compressed Liquid Table (800 psia) 149 75 Density Compressed Liquid Table (800 psia) 155 76 Enthalpy Thermodynamic Properties of Compressed Liquid Table (2250 psia) 161 77 Density Thermodynamic Properties of Compressed Liquid Table (400 psia) 162 78 Enthalpy Thermodynamic Properties of Compressed Liquid Table (2500 psia) 166 79 Density Thermodynamic Properties Of Compressed Liquid Table (2500 psia) 168 80 Enthalpy Seal Water Injection Table (2500 psia) 172 81 Diesel Driven Fire Pump Fuel Oil Tank Level 173 82 EDG No. 1 and EDG No. 3 Auxiliary Fuel Oil Tank Level 174 83 EDG No. 1 and EDG No. 3 Base Fuel Oil Tank Level 181 84 Main Condenser 184 85 RCS Inventory vs Plant Elevation 187

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 7 of 195 1.0 PURPOSE 1.1 To provide instructions for the maintenance of the Curve Book, which contains the Physics Curves for Surry Unit 1.

1.2 To provide guidelines for the receipt and generation of curves.

2.0 REFERENCES

2.1 Technical Specifications Surry Power Station Units 1 and 2 2.2 VPAP-0303, Scaling/Setpoint Change and Curve Program 2.3 VPAP-0301, Design Change Process 2.4 CM-AA-CLC-301, Engineering Calculations 2.5 NF-AA-NCD-101, Nuclear Core Design Procedures and Methods: Purpose, Organization and Use 2.6 Calculation Note PM-419, Revision 0, Addendum B 2.7 NE Technical Report No. 908, Revision 0 2.8 CTS 2753, Core Uprate 2.9 CTS 3423, Calorimetric Task Team 2.10 DR S-97-2736, Blender POT Setting Changes 2.11 DR S-98-0496, Containment Sump Wide Range Transmitter Curve 2.12 NAF-980034, Rev. 0, 1/2-DRP-3 Wide Range Sump Level Curve 2.13 DR S-98-1412, 1/2-CN-TK-1 TS Volume

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 8 of 195 2.14 ET NAF 98-0126, Rev. 0, Loss of Decay Heat Removal Capacity 2.15 PI S-2001-0630, PRT Curves Updated to Address DR 3.0 INITIAL CONDITIONS None 4.0 PRECAUTIONS AND LIMITATIONS None 5.0 INSTRUCTIONS 5.1 New curves or revisions to existing curves generated by Nuclear Analysis and Fuel shall be received under transmittal accompanied by the following documentation as a minimum:

Calculation number

Justification for new curve or revision to existing curve 5.2 Those curves that require the generation of a DCP will be processed in accordance with VPAP-0301, Design Change Process.

5.3 Upon receipt of new or revised curves, from Nuclear Analysis and Fuel or by generation of a DCP, a revision to this procedure will be initiated.

SECTION 1 - ATTACHMENTS - PHYSICS CURVES

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 9 of 195 (Page 1 of 3)

Attachment 1 HEATUP AND COOLDOWN CURVE PSV Lift 2500 Setpoint 100 psi Steam Line/Header dP PORV Lift Setpoint Leak Test Limit Nom. Operating Pressure SI Block 2000 PZR Surge Indicated Wide Range RCS Pressure (psig)

Line Delta-T Limit PZR/PZR Spray Delta-T Limit Composite Heatup/Cooldown 1500 Curve (RV Beltline)

LTOPS Enabled or PZR Bubble Required Administrative RCP NPSH Limit (Below 1000 psig, Indicated Narrow Range Pressure) 1000 RHR Permissive LTOPS Setpoint Administrative 500 Saturation Limit RCP 200 psid 80 F Vessel (#1 Seal)

Head Bolt NDT Limit 0

0 100 200 300 400 500 600 700 Indicated Cold Leg Temperature (Deg. F)

Graphics No: PC300 The PZR Surge Line Delta-T Limit and PZR/PZR Spray Delta-T Limit curves

HEATUP are not applicable AND during water COOLDOWN solid operations. CURVE

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Attachment 1 HEATUP AND COOLDOWN CURVE (Blowup of 0-1000 PSIG by 0-450 °F) 1000 Pressurizer Surge Line Delta-T Limit LTOPS Enabled or PZR Bubble Required 800 PZR/PZR Spray Delta-T Limit Composite Heatup/Cooldown Curve (RV Beltline)

Indicated Narrow Range RCS Pressure (psig) 600 Administrative RCP NPSH Limit RHR Permissive 400 LTOPS Setpoint RCP 200 psid

(#1 Seal) 200 Administrative Saturation 80 F Vessel Limit Head Bolt NDT Limit 0

0 100 200 300 400 Graphics No: PC301 Indicated Cold Leg Temperature (Deg. F)

The PZR Surge Line Delta-T Limit and PZR/PZR Spray Delta-T Limit curves are notHEATUP AND applicable during COOLDOWN water solid operations. CURVE

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Attachment 1 HEATUP AND COOLDOWN CURVE 2500 100 psi Steam Line/Header dP 2000 Indicated Wide Range RCS Pressure (psig)

PZR Surge Line Delta-T Limit 1500 PZR/PZR Spray Delta-T Limit

Administrative RCP NPSH Limit Composite Heatup/Cooldown (Below 1000 psig, Indicated Narrow Range Pressure)

Curve (RV Beltline) 1000 Administrative 500 Saturation Limit 0

0 100 200 300 400 500 600 700 Indicated Cold Leg Temperature (Deg. F) Graphics No: PC302 The PZR Surge Line Delta-T Limit and PZR/PZR Spray Delta-T Limit curves

are not applicable during HEATUP ANDwater solid operations.CURVE COOLDOWN

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Attachment 2 SATURATION PRESSURE TEMPERATURE CURVE 2700 2600 2500 2400 2300 2200 2100 2000 1900 1800 SATURATION PRESSURE PSIG 1700 1600 1500 1400 1300 Safe Area 1200 1100 TSAT TSAT -50 F 1000 900 Unsafe Area (50 F Subcooled) 800 700 600 500 400 300 200 100 0

200 300 400 500 600 700 SATURATION TEMPERATURE F Graphics No: KM1131 SATURATION PRESSURE TEMPERATURE CURVE

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Attachment 3 SATURATION PRESSURE TEMPERATURE CURVE 2700 2600 2500 2400 2300 2200 2100 2000 1900 SATURATION PRESSURE PSIG 1800 1700 1600 1500 1400 1300 Safe Area 1200 PSAT PSAT for TSAT -50 F 1100 (50 F Subcooled) 1000 Unsafe Area 900 800 700 600 500 400 300 200 100 0

700 600 500 400 300 200 SATURATION TEMPERATURE F Graphics No: KM1132 SATURATION PRESSURE TEMPERATURE CURVE

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Attachment 4 CONTAINMENT ALLOWABLE AIR PARTIAL PRESSURE INDICATION VS. SERVICE WATER TEMPERATURE 11.6 11.4 (70,11.3) 11.2 Acceptable Operation Air Partial Pressure, psia Inside the Lines 11.0 10.8 Containment Temperature Between 75 F and 125 F 10.6 10.4 (100,10.3) 10.2 (25,10.3) (70,10.1)

(100,10.1) 10.0 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 Service Water Temperature, deg-F Graphics No. SB1766 Note: Operation On or Outside the Line Requires Entry into TS 3.8.D.1.a

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 25.0 11.3 10.3000 28.1 11.3 10.2862 25.1 11.3 10.2996 28.2 11.3 10.2858 25.2 11.3 10.2991 28.3 11.3 10.2853 25.3 11.3 10.2987 28.4 11.3 10.2849 25.4 11.3 10.2982 28.5 11.3 10.2844 25.5 11.3 10.2978 28.6 11.3 10.2840 25.6 11.3 10.2973 28.7 11.3 10.2836 25.7 11.3 10.2969 28.8 11.3 10.2831 25.8 11.3 10.2964 28.9 11.3 10.2827 25.9 11.3 10.2960 29.0 11.3 10.2822 26.0 11.3 10.2956 29.1 11.3 10.2818 26.1 11.3 10.2951 29.2 11.3 10.2813 26.2 11.3 10.2947 29.3 11.3 10.2809 26.3 11.3 10.2942 29.4 11.3 10.2804 26.4 11.3 10.2938 29.5 11.3 10.2800 26.5 11.3 10.2933 29.6 11.3 10.2796 26.6 11.3 10.2929 29.7 11.3 10.2791 26.7 11.3 10.2924 29.8 11.3 10.2787 26.8 11.3 10.2920 29.9 11.3 10.2782 26.9 11.3 10.2916 30.0 11.3 10.2778 27.0 11.3 10.2911 30.1 11.3 10.2773 27.1 11.3 10.2907 30.2 11.3 10.2769 27.2 11.3 10.2902 30.3 11.3 10.2764 27.3 11.3 10.2898 30.4 11.3 10.2760 27.4 11.3 10.2893 30.5 11.3 10.2756 27.5 11.3 10.2889 30.6 11.3 10.2751 27.6 11.3 10.2884 30.7 11.3 10.2747 27.7 11.3 10.2880 30.8 11.3 10.2742 27.8 11.3 10.2876 30.9 11.3 10.2738 27.9 11.3 10.2871 31.0 11.3 10.2733 28.0 11.3 10.2867 31.1 11.3 10.2729

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 31.2 11.3 10.2724 34.2 11.3 10.2591 31.3 11.3 10.2720 34.3 11.3 10.2587 31.4 11.3 10.2716 34.4 11.3 10.2582 31.5 11.3 10.2711 34.5 11.3 10.2578 31.6 11.3 10.2707 34.6 11.3 10.2573 31.7 11.3 10.2702 34.7 11.3 10.2569 31.8 11.3 10.2698 34.8 11.3 10.2564 31.9 11.3 10.2693 34.9 11.3 10.2560 32.0 11.3 10.2689 35.0 11.3 10.2556 32.1 11.3 10.2684 35.1 11.3 10.2551 32.2 11.3 10.2680 35.2 11.3 10.2547 32.3 11.3 10.2676 35.3 11.3 10.2542 32.4 11.3 10.2671 35.4 11.3 10.2538 32.5 11.3 10.2667 35.5 11.3 10.2533 32.6 11.3 10.2662 35.6 11.3 10.2529 32.7 11.3 10.2658 35.7 11.3 10.2524 32.8 11.3 10.2653 35.8 11.3 10.2520 32.9 11.3 10.2649 35.9 11.3 10.2516 33.0 11.3 10.2644 36.0 11.3 10.2511 33.1 11.3 10.2640 36.1 11.3 10.2507 33.2 11.3 10.2636 36.2 11.3 10.2502 33.3 11.3 10.2631 36.3 11.3 10.2498 33.4 11.3 10.2627 36.4 11.3 10.2493 33.5 11.3 10.2622 36.5 11.3 10.2489 33.6 11.3 10.2618 36.6 11.3 10.2484 33.7 11.3 10.2613 36.7 11.3 10.2480 33.8 11.3 10.2609 36.8 11.3 10.2476 33.9 11.3 10.2604 36.9 11.3 10.2471 34.0 11.3 10.2600 37.0 11.3 10.2467 34.1 11.3 10.2596 37.1 11.3 10.2462

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 37.2 11.3 10.2458 40.2 11.3 10.2324 37.3 11.3 10.2453 40.3 11.3 10.2320 37.4 11.3 10.2449 40.4 11.3 10.2316 37.5 11.3 10.2444 40.5 11.3 10.2311 37.6 11.3 10.2440 40.6 11.3 10.2307 37.7 11.3 10.2436 40.7 11.3 10.2302 37.8 11.3 10.2431 40.8 11.3 10.2298 37.9 11.3 10.2427 40.9 11.3 10.2293 38.0 11.3 10.2422 41.0 11.3 10.2289 38.1 11.3 10.2418 41.1 11.3 10.2284 38.2 11.3 10.2413 41.2 11.3 10.2280 38.3 11.3 10.2409 41.3 11.3 10.2276 38.4 11.3 10.2404 41.4 11.3 10.2271 38.5 11.3 10.2400 41.5 11.3 10.2267 38.6 11.3 10.2396 41.6 11.3 10.2262 38.7 11.3 10.2391 41.7 11.3 10.2258 38.8 11.3 10.2387 41.8 11.3 10.2253 38.9 11.3 10.2382 41.9 11.3 10.2249 39.0 11.3 10.2378 42.0 11.3 10.2244 39.1 11.3 10.2373 42.1 11.3 10.2240 39.2 11.3 10.2369 42.2 11.3 10.2236 39.3 11.3 10.2364 42.3 11.3 10.2231 39.4 11.3 10.2360 42.4 11.3 10.2227 39.5 11.3 10.2356 42.5 11.3 10.2222 39.6 11.3 10.2351 42.6 11.3 10.2218 39.7 11.3 10.2347 42.7 11.3 10.2213 39.8 11.3 10.2342 42.8 11.3 10.2209 39.9 11.3 10.2338 42.9 11.3 10.2204 40.0 11.3 10.2333 43.0 11.3 10.2200 40.1 11.3 10.2329 43.1 11.3 10.2196

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 43.2 11.3 10.2191 46.1 11.3 10.2062 43.3 11.3 10.2187 46.2 11.3 10.2058 43.4 11.3 10.2182 46.3 11.3 10.2053 43.5 11.3 10.2178 46.4 11.3 10.2049 43.6 11.3 10.2173 46.5 11.3 10.2044 43.7 11.3 10.2169 46.6 11.3 10.2040 43.8 11.3 10.2164 46.7 11.3 10.2036 43.9 11.3 10.2160 46.8 11.3 10.2031 44.0 11.3 10.2156 46.9 11.3 10.2027 44.1 11.3 10.2151 47.0 11.3 10.2022 44.2 11.3 10.2147 47.1 11.3 10.2018 44.3 11.3 10.2142 47.2 11.3 10.2013 44.4 11.3 10.2138 47.3 11.3 10.2009 44.5 11.3 10.2133 47.4 11.3 10.2004 44.6 11.3 10.2129 47.5 11.3 10.2000 44.7 11.3 10.2124 47.6 11.3 10.1996 44.8 11.3 10.2120 47.7 11.3 10.1991 44.9 11.3 10.2116 47.8 11.3 10.1987 45.0 11.3 10.2111 47.9 11.3 10.1982 45.1 11.3 10.2107 48.0 11.3 10.1978 45.2 11.3 10.2102 48.1 11.3 10.1973 45.3 11.3 10.2098 48.2 11.3 10.1969 45.4 11.3 10.2093 48.3 11.3 10.1964 45.5 11.3 10.2089 48.4 11.3 10.1960 45.6 11.3 10.2084 48.5 11.3 10.1956 45.7 11.3 10.2080 48.6 11.3 10.1951 45.8 11.3 10.2076 48.7 11.3 10.1947 45.9 11.3 10.2071 48.8 11.3 10.1942 46.0 11.3 10.2067 48.9 11.3 10.1938

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 49.0 11.3 10.1933 52.1 11.3 10.1796 49.1 11.3 10.1929 52.2 11.3 10.1791 49.2 11.3 10.1924 52.3 11.3 10.1787 49.3 11.3 10.1920 52.4 11.3 10.1782 49.4 11.3 10.1916 52.5 11.3 10.1778 49.5 11.3 10.1911 52.6 11.3 10.1773 49.6 11.3 10.1907 52.7 11.3 10.1769 49.7 11.3 10.1902 52.8 11.3 10.1764 49.8 11.3 10.1898 52.9 11.3 10.1760 49.9 11.3 10.1893 53.0 11.3 10.1756 50.0 11.3 10.1889 53.1 11.3 10.1751 50.1 11.3 10.1884 53.2 11.3 10.1747 50.2 11.3 10.1880 53.3 11.3 10.1742 50.3 11.3 10.1876 53.4 11.3 10.1738 50.4 11.3 10.1871 53.5 11.3 10.1733 50.5 11.3 10.1867 53.6 11.3 10.1729 50.6 11.3 10.1862 53.7 11.3 10.1724 50.7 11.3 10.1858 53.8 11.3 10.1720 50.8 11.3 10.1853 53.9 11.3 10.1716 50.9 11.3 10.1849 54.0 11.3 10.1711 51.0 11.3 10.1844 54.1 11.3 10.1707 51.1 11.3 10.1840 54.2 11.3 10.1702 51.2 11.3 10.1836 54.3 11.3 10.1698 51.3 11.3 10.1831 54.4 11.3 10.1693 51.4 11.3 10.1827 54.5 11.3 10.1689 51.5 11.3 10.1822 54.6 11.3 10.1684 51.6 11.3 10.1818 54.7 11.3 10.1680 51.7 11.3 10.1813 54.8 11.3 10.1676 51.8 11.3 10.1809 54.9 11.3 10.1671 51.9 11.3 10.1804 55.0 11.3 10.1667 52.0 11.3 10.1800 55.1 11.3 10.1662

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 55.2 11.3 10.1658 58.3 11.3 10.1520 55.3 11.3 10.1653 58.4 11.3 10.1516 55.4 11.3 10.1649 58.5 11.3 10.1511 55.5 11.3 10.1644 58.6 11.3 10.1507 55.6 11.3 10.1640 58.7 11.3 10.1502 55.7 11.3 10.1636 58.8 11.3 10.1498 55.8 11.3 10.1631 58.9 11.3 10.1493 55.9 11.3 10.1627 59.0 11.3 10.1489 56.0 11.3 10.1622 59.1 11.3 10.1484 56.1 11.3 10.1618 59.2 11.3 10.1480 56.2 11.3 10.1613 59.3 11.3 10.1476 56.3 11.3 10.1609 59.4 11.3 10.1471 56.4 11.3 10.1604 59.5 11.3 10.1467 56.5 11.3 10.1600 59.6 11.3 10.1462 56.6 11.3 10.1596 59.7 11.3 10.1458 56.7 11.3 10.1591 59.8 11.3 10.1453 56.8 11.3 10.1587 59.9 11.3 10.1449 56.9 11.3 10.1582 60.0 11.3 10.1444 57.0 11.3 10.1578 60.1 11.3 10.1440 57.1 11.3 10.1573 60.2 11.3 10.1436 57.2 11.3 10.1569 60.3 11.3 10.1431 57.3 11.3 10.1564 60.4 11.3 10.1427 57.4 11.3 10.1560 60.5 11.3 10.1422 57.5 11.3 10.1556 60.6 11.3 10.1418 57.6 11.3 10.1551 60.7 11.3 10.1413 57.7 11.3 10.1547 60.8 11.3 10.1409 57.8 11.3 10.1542 60.9 11.3 10.1404 57.9 11.3 10.1538 61.0 11.3 10.1400 58.0 11.3 10.1533 61.1 11.3 10.1396 58.1 11.3 10.1529 61.2 11.3 10.1391 58.2 11.3 10.1524 61.3 11.3 10.1387

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 61.4 11.3 10.1382 64.5 11.3 10.1244 61.5 11.3 10.1378 64.6 11.3 10.1240 61.6 11.3 10.1373 64.7 11.3 10.1236 61.7 11.3 10.1369 64.8 11.3 10.1231 61.8 11.3 10.1364 64.9 11.3 10.1227 61.9 11.3 10.1360 65.0 11.3 10.1222 62.0 11.3 10.1356 65.1 11.3 10.1218 62.1 11.3 10.1351 65.2 11.3 10.1213 62.2 11.3 10.1347 65.3 11.3 10.1209 62.3 11.3 10.1342 65.4 11.3 10.1204 62.4 11.3 10.1338 65.5 11.3 10.1200 62.5 11.3 10.1333 65.6 11.3 10.1196 62.6 11.3 10.1329 65.7 11.3 10.1191 62.7 11.3 10.1324 65.8 11.3 10.1187 62.8 11.3 10.1320 65.9 11.3 10.1182 62.9 11.3 10.1316 66.0 11.3 10.1178 63.0 11.3 10.1311 66.1 11.3 10.1173 63.1 11.3 10.1307 66.2 11.3 10.1169 63.2 11.3 10.1302 66.3 11.3 10.1164 63.3 11.3 10.1298 66.4 11.3 10.1160 63.4 11.3 10.1293 66.5 11.3 10.1156 63.5 11.3 10.1289 66.6 11.3 10.1151 63.6 11.3 10.1284 66.7 11.3 10.1147 63.7 11.3 10.1280 66.8 11.3 10.1142 63.8 11.3 10.1276 66.9 11.3 10.1138 63.9 11.3 10.1271 67.0 11.3 10.1133 64.0 11.3 10.1267 67.1 11.3 10.1129 64.1 11.3 10.1262 67.2 11.3 10.1124 64.2 11.3 10.1258 67.3 11.3 10.1120 64.3 11.3 10.1253 67.4 11.3 10.1116 64.4 11.3 10.1249 67.5 11.3 10.1111

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 67.6 11.3 10.1107 70.5 11.283 10.1 67.7 11.3 10.1102 70.6 11.280 10.1 67.8 11.3 10.1098 70.7 11.277 10.1 67.9 11.3 10.1093 70.8 11.273 10.1 68.0 11.3 10.1089 70.9 11.270 10.1 68.1 11.3 10.1084 71.0 11.267 10.1 68.2 11.3 10.1080 71.1 11.263 10.1 68.3 11.3 10.1076 71.2 11.260 10.1 68.4 11.3 10.1071 71.3 11.257 10.1 68.5 11.3 10.1067 71.4 11.253 10.1 68.6 11.3 10.1062 71.5 11.250 10.1 68.7 11.3 10.1058 71.6 11.247 10.1 68.8 11.3 10.1053 71.7 11.243 10.1 68.9 11.3 10.1049 71.8 11.240 10.1 69.0 11.3 10.1044 71.9 11.237 10.1 69.1 11.3 10.1040 72.0 11.233 10.1 69.2 11.3 10.1036 72.1 11.230 10.1 69.3 11.3 10.1031 72.2 11.227 10.1 69.4 11.3 10.1027 72.3 11.223 10.1 69.5 11.3 10.1022 72.4 11.220 10.1 69.6 11.3 10.1018 72.5 11.217 10.1 69.7 11.3 10.1013 72.6 11.213 10.1 69.8 11.3 10.1009 72.7 11.210 10.1 69.9 11.3 10.1004 72.8 11.207 10.1 70.0 11.3 10.1 72.9 11.203 10.1 70.1 11.297 10.1 73.0 11.200 10.1 70.2 11.293 10.1 73.1 11.197 10.1 70.3 11.290 10.1 73.2 11.193 10.1 70.4 11.287 10.1 73.3 11.190 10.1

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 73.4 11.187 10.1 76.5 11.083 10.1 73.5 11.183 10.1 76.6 11.080 10.1 73.6 11.180 10.1 76.7 11.077 10.1 73.7 11.177 10.1 76.8 11.073 10.1 73.8 11.173 10.1 76.9 11.070 10.1 73.9 11.170 10.1 77.0 11.067 10.1 74.0 11.167 10.1 77.1 11.063 10.1 74.1 11.163 10.1 77.2 11.060 10.1 74.2 11.160 10.1 77.3 11.057 10.1 74.3 11.157 10.1 77.4 11.053 10.1 74.4 11.153 10.1 77.5 11.050 10.1 74.5 11.150 10.1 77.6 11.047 10.1 74.6 11.147 10.1 77.7 11.043 10.1 74.7 11.143 10.1 77.8 11.040 10.1 74.8 11.140 10.1 77.9 11.037 10.1 74.9 11.137 10.1 78.0 11.033 10.1 75.0 11.133 10.1 78.1 11.030 10.1 75.1 11.130 10.1 78.2 11.027 10.1 75.2 11.127 10.1 78.3 11.023 10.1 75.3 11.123 10.1 78.4 11.020 10.1 75.4 11.120 10.1 78.5 11.017 10.1 75.5 11.117 10.1 78.6 11.013 10.1 75.6 11.113 10.1 78.7 11.010 10.1 75.7 11.110 10.1 78.8 11.007 10.1 75.8 11.107 10.1 78.9 11.003 10.1 75.9 11.103 10.1 79.0 11.000 10.1 76.0 11.100 10.1 79.1 10.997 10.1 76.1 11.097 10.1 79.2 10.993 10.1 76.2 11.093 10.1 79.3 10.990 10.1 76.3 11.090 10.1 79.4 10.987 10.1 76.4 11.087 10.1 79.5 10.983 10.1

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 79.6 10.980 10.1 82.6 10.880 10.1 79.7 10.977 10.1 82.7 10.877 10.1 79.8 10.973 10.1 82.8 10.873 10.1 79.9 10.970 10.1 82.9 10.870 10.1 80.0 10.967 10.1 83.0 10.867 10.1 80.1 10.963 10.1 83.1 10.863 10.1 80.2 10.960 10.1 83.2 10.860 10.1 80.3 10.957 10.1 83.3 10.857 10.1 80.4 10.953 10.1 83.4 10.853 10.1 80.5 10.950 10.1 83.5 10.850 10.1 80.6 10.947 10.1 83.6 10.847 10.1 80.7 10.943 10.1 83.7 10.843 10.1 80.8 10.940 10.1 83.8 10.840 10.1 80.9 10.937 10.1 83.9 10.837 10.1 81.0 10.933 10.1 84.0 10.833 10.1 81.1 10.930 10.1 84.1 10.830 10.1 81.2 10.927 10.1 84.2 10.827 10.1 81.3 10.923 10.1 84.3 10.823 10.1 81.4 10.920 10.1 84.4 10.820 10.1 81.5 10.917 10.1 84.5 10.817 10.1 81.6 10.913 10.1 84.6 10.813 10.1 81.7 10.910 10.1 84.7 10.810 10.1 81.8 10.907 10.1 84.8 10.807 10.1 81.9 10.903 10.1 84.9 10.803 10.1 82.0 10.900 10.1 85.0 10.800 10.1 82.1 10.897 10.1 85.1 10.797 10.1 82.2 10.893 10.1 85.2 10.793 10.1 82.3 10.890 10.1 85.3 10.790 10.1 82.4 10.887 10.1 85.4 10.787 10.1 82.5 10.883 10.1 85.5 10.783 10.1

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 85.6 10.780 10.1 88.6 10.680 10.1 85.7 10.777 10.1 88.7 10.677 10.1 85.8 10.773 10.1 88.8 10.673 10.1 85.9 10.770 10.1 88.9 10.670 10.1 86.0 10.767 10.1 89.0 10.667 10.1 86.1 10.763 10.1 89.1 10.663 10.1 86.2 10.760 10.1 89.2 10.660 10.1 86.3 10.757 10.1 89.3 10.657 10.1 86.4 10.753 10.1 89.4 10.653 10.1 86.5 10.750 10.1 89.5 10.650 10.1 86.6 10.747 10.1 89.6 10.647 10.1 86.7 10.743 10.1 89.7 10.643 10.1 86.8 10.740 10.1 89.8 10.640 10.1 86.9 10.737 10.1 89.9 10.637 10.1 87.0 10.733 10.1 90.0 10.633 10.1 87.1 10.730 10.1 90.1 10.630 10.1 87.2 10.727 10.1 90.2 10.627 10.1 87.3 10.723 10.1 90.3 10.623 10.1 87.4 10.720 10.1 90.4 10.620 10.1 87.5 10.717 10.1 90.5 10.617 10.1 87.6 10.713 10.1 90.6 10.613 10.1 87.7 10.710 10.1 90.7 10.610 10.1 87.8 10.707 10.1 90.8 10.607 10.1 87.9 10.703 10.1 90.9 10.603 10.1 88.0 10.700 10.1 91.0 10.600 10.1 88.1 10.697 10.1 91.1 10.597 10.1 88.2 10.693 10.1 91.2 10.593 10.1 88.3 10.690 10.1 91.3 10.590 10.1 88.4 10.687 10.1 91.4 10.587 10.1 88.5 10.683 10.1 91.5 10.583 10.1

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 91.6 10.580 10.1 94.6 10.480 10.1 91.7 10.577 10.1 94.7 10.477 10.1 91.8 10.573 10.1 94.8 10.473 10.1 91.9 10.570 10.1 94.9 10.470 10.1 92.0 10.567 10.1 95.0 10.467 10.1 92.1 10.563 10.1 95.1 10.463 10.1 92.2 10.560 10.1 95.2 10.460 10.1 92.3 10.557 10.1 95.3 10.457 10.1 92.4 10.553 10.1 95.4 10.453 10.1 92.5 10.550 10.1 95.5 10.450 10.1 92.6 10.547 10.1 95.6 10.447 10.1 92.7 10.543 10.1 95.7 10.443 10.1 92.8 10.540 10.1 95.8 10.440 10.1 92.9 10.537 10.1 95.9 10.437 10.1 93.0 10.533 10.1 96.0 10.433 10.1 93.1 10.530 10.1 96.1 10.430 10.1 93.2 10.527 10.1 96.2 10.427 10.1 93.3 10.523 10.1 96.3 10.423 10.1 93.4 10.520 10.1 96.4 10.420 10.1 93.5 10.517 10.1 96.5 10.417 10.1 93.6 10.513 10.1 96.6 10.413 10.1 93.7 10.510 10.1 96.7 10.410 10.1 93.8 10.507 10.1 96.8 10.407 10.1 93.9 10.503 10.1 96.9 10.403 10.1 94.0 10.500 10.1 97.0 10.400 10.1 94.1 10.497 10.1 97.1 10.397 10.1 94.2 10.493 10.1 97.2 10.393 10.1 94.3 10.490 10.1 97.3 10.390 10.1 94.4 10.487 10.1 97.4 10.387 10.1 94.5 10.483 10.1 97.5 10.383 10.1

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Attachment 5 ALLOWABLE AIR PARTIAL PRESSURE TABLE Maximum Maximum Allowable Air Minimum Allowable Allowable Air Minimum Allowable Service Water Partial Pressure Air Partial Pressure Service Water Partial Pressure Air Partial Pressure Temperature (°F) (psia) (psia) Temperature (°F) (psia) (psia) 97.6 10.380 10.1 97.7 10.377 10.1 97.8 10.373 10.1 97.9 10.370 10.1 98.0 10.367 10.1 98.1 10.363 10.1 98.2 10.360 10.1 98.3 10.357 10.1 98.4 10.353 10.1 98.5 10.350 10.1 98.6 10.347 10.1 98.7 10.343 10.1 98.8 10.340 10.1 98.9 10.337 10.1 99.0 10.333 10.1 99.1 10.330 10.1 99.2 10.327 10.1 99.3 10.323 10.1 99.4 10.320 10.1 99.5 10.317 10.1 99.6 10.313 10.1 99.7 10.310 10.1 99.8 10.307 10.1 99.9 10.303 10.1 100.0 10.300 10.1

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Attachment 6 INTENTIONALLY LEFT BLANK

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Attachment 7 CORE HEATUP TIMES FOR SURRY Time to Uncovery 120 Decreased Inventory Time to Uncovery Reduced Inventory 100 Time After Loss Of RHR (Minutes) 80 60 40 20 Time To Core Boiling 0

0 50 100 150 200 250 300 350 400 450 Time After Shutdown (Hours)

Graphics No: MT1525A CORE HEATUP TIMES

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Attachment 7 CORE HEATUP TIMES FOR SURRY 200 Time to Uncovery Decreased Inventory 180 Time to Uncovery Reduced Inventory 160 140 Time After Loss Of RHR (Minutes) 120 100 80 60 40 Time To 20 Core Boiling 0

0 250 500 750 1000 1250 Time After Shutdown (Hours)

Graphics No: MT1526A CORE HEATUP TIMES

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Attachment 8 BORON ADDITION RATE - COOLANT HOT 10 300 20 8.0 100 250 15 6.0 200 500 150 10 4.0 9 3.6 8 3.2 1000 100 7 2.8 90 80 6 2.4 70 5 2.0 1500 60 50 4 1.6 45 40 3 1.2 Based on 12,200 ppm (7 wt %) 35 2000 Boron in Makeup and 9200 ft 3 Coolant Volume 30 25 2 0.8 2500 20 15 3000 1 0.4 ppm Boron Boron Addition Boric Acid Approx Pot Setting in Coolant Rate, ppm/hr Flow, gpm 1-CH-FC-1113A Graphics No: KM1104J BORON ADDITION RATE - COOLANT HOT (~ 580 F)

FIGURE S-3.1-1 (UNIT 1)

NOTE: DO NOT set pot setting above 8.0 (20 GPM) on 1-CH-FC-1113A.

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Attachment 9 BORON ADDITION RATE - COOLANT COLD 10 20 8.0 100 15 6.0 150 500 10 4.0 100 90 9 3.6 80 8 3.2 1000 70 7 2.8 60 6 2.4 50 5 2.0 1500 40 4 1.6 30 3 1.2 2000 Based on 12,200 ppm (7 wt %) 20 Boron in Makeup and 9200 ft 3 Coolant Volume 2 0.8 2500 10 3000 1 0.4 ppm Boron Boron Addition Boric Acid Approx Pot Setting in Coolant Rate, ppm/hr Flow, gpm 1-CH-FC-1113A Graphics No: KM1104M BORON ADDITION RATE - COOLANT COLD (~ 100 F)

FIGURE S-3.1-2 (UNIT 1)

NOTE: DO NOT set pot setting above 8.0 (20 GPM) on 1-CH-FC-1113A.

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Attachment 10 BORON ADDITION - COOLANT HOT 3000 700 600 2500 500 2000 400 2500 1500 300 1200 1000 200 2000 700 150 500 100 1500 90 80 300 70 60 50 1000 200 40 Based on 12,200 ppm (7 wt %)

Boron in Makeup and 9200 ft 3 Coolant Volume 30 100 500 20 15 100 50 10 ppm Boron 0 Boric Acid 10 ppm Boron in Coolant Volume, Gallons Addition BORON ADDITION RATE - COOLANT HOT (~ 580 F) Graphics No: KM1104B FIGURE S-3.1-3

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Attachment 11 BORON ADDITION - COOLANT COLD 3000 700 600 500 3000 400 2500 2500 300 2000 1500 200 1200 2000 1000 150 700 100 90 1500 500 80 70 60 300 50 40 1000 200 30 20 500 100 15 100 10 10 0 Boric Acid ppm Boron ppm Boron Volume, gal Addition in Coolant Graphics No: CB1420 BORON ADDITION - COOLANT COLD (~ 100 F)

FIGURE S-3.1-4

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Attachment 12 DILUTION RATE - COOLANT HOT 3000 700 200 500 2000 400 300 10.0 150 1500 200 1000 150 100 6.67 100 70 6.00 90 500 50 5.37 80 40 30 4.67 70 20 4.00 60 15 3.33 50 200 10 7

2.67 40 5

100 4 80 3 2.00 30 60 2 50 1.5 40 1 1.33 20 30 Coolant Dilution Rate Based on 3

9200 ft Coolant Volume, ppm/hr 20 1.00 15 15 10 0.67 10 ppm Boron in Coolant Approx. Pot Setting Diluation Water 1-CH-FC-1114A Flow, gpm 1-CH-HFC-1114 Graphics No: KM1105D DILUTION RATE - COOLANT HOT (~ 580 F)

FIGURE S-3.1-5 (UNIT 1)

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Attachment 13 DILUTION RATE - COOLANT COLD 3000 500 200 400 2000 300 10.0 150 200 1500 150 100 100 70 6.67 100 700 6.00 90 50 5.37 80 500 30 4.67 70 20 15 4.00 60 10 50 200 3.33 7

150 5 40 2.67 4

100 3 80 2.00 30 2

60 1.5 50 1 40 Coolant Dilution 1.33 20 Rate Based on 30 9200 FT3 Coolant Volume, ppm/hr 1.00 15 20 15 10 0.67 10 ppm Boron Approx. Pot Setting Dilution Water in Coolant 1-CH-FC-1114A Flow, gpm 1-CH-HFC-1114 Graphics No: CB1421A DILUTION RATE - COOLANT COLD (~ 100 F)

FIGURE S-3.1-6

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Attachment 14 DILUTION NOMOGRAPH - COOLANT HOT 10 15 10 20 30 30 40 50 50 60 80 100 100 1 300 1.5 200 2 500 3

5 1000 10 500 15 20 30 50 3000 100 5000 1000 150 200 300 10,000 500 2000 1000 30,000 3000 ppm Boron Dilution Based on 50,000 9200 ft 3 Coolant Volume ppm Boron Dilution Graphics No: KM1106 in Coolant Water gal DILUTION VOLUME NOMOGRAPH - COOLANT HOT (~ 580 F)

FIGURE S-3.1-7

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Attachment 15 DILUTION NOMOGRAPH - COOLANT COLD 10 15 30 20 50 30 40 50 100 60 80 100 300 1 500 200 1.5 2

3 1000 5

10 15 500 20 3000 30 50 5000 1000 100 150 10,000 200 300 2000 500 30,000 1000 3000 ppm Boron Dilution Based on 50,000 ppm Boron 9200 Ft 3 Coolant Volume Dilution in Coolant Water, gal Graphics No: CB1422 DILUTION VOLUME NOMOGRAPH - COOLANT COLD ( 100 F)

FIGURE S-3.1-8

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Attachment 16 DILUTION AND LETDOWN RATE NOMOGRAPH - COOLANT HOT 5

1 2 3 4 1500 10 150 500 1 2 4 140 1000 2 3 5 15 1,000 130 0.2 20 120 2,000 0.5 25 110 1 30 5,000 100 1.5 40 10,000 90 2

4 50 80 20,000 30,000 6 8 60 10 70 50,000 70 100 20 80 60 Volume makeup 90 water 100 50 gal.

50 40 30 200 Letdown Rate, gpm 20 300 10 400 ppm Boron ppm Boron in Coolant Dilution Graphics No: KM1107 DILUTION AND LETDOWN RATE NOMOGRAPH - COOLANT HOT (~ 580 F)

FIGURE S-3.1-9

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Attachment 17 BLENDED FLOW NOMOGRAPH y z For more exact results use 2000 600 Z= x *x12200

+y 500 x

400 40 30 1000 300 20 8.0 200 10 4.0 500 150 10.0 5 2.0 400 4 1.6 3 1.2 100 6.67 300 90 6.00 2 0.8 80 5.33 70 4.67 1 0.4 200 60 4.00 50 3.33 150 0.5 0.20 40 2.67 0.4 0.16 0.3 0.12 100 30 2.00 0.08 0.2 20 1.33 0.1 0.04 Boric Acid Flow Based Approx Pot Setting 50 on 12200 ppm Boron in 1-CH-FC-1113A 40 Makeup, gpm 10 0.67 30 Dilution Water Approx Pot Settings ppm Boron in Flow, gpm 1-CH-FC-1114A Blend Flow, gpm 1-CH-HFC-1114 Graphics No: CB1424F BLENDED FLOW NOMOGRAPH FIGURE S-3.1-10 (UNIT 1)

NOTE: DO NOT set pot setting above 8.0 (20 GPM) on 1-CH-FC-1113A.

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Attachment 18 BLENDED FLOW NOMOGRAPH 2100 2000 Note: For exact results use the following equations: 1900 1800 C BL = f BA * (C BAST

1748) 1700 f BA + f PG 1600 Where C BL = ppm in blended flow f PG = f BA * (CBAST

1748) - f 1500 BA C BAST = concentration of BAST in %

C BL 1400 f BA = flow of Boric Acid in gpm f BA = f PG f PG = flow of PG in gpm 1300 (C BAST

1748)

-1 C BL 1200 1100 8.0 20 7.2 18 1000 10.0 150 6.4 16 900 5.6 14 9.33 140 4.8 12 4.4 11 800 8.67 130 4.0 10 3.6 9 3.2 8 700 8.00 120 ppm Boron in 2.8 7 Blend Flow (CBL) 7.33 110 2.4 6 Approx Pot Setting Boric Acid Flow Based 1-CH-FC-1113A on 12200 ppm Boron in 6.67 100 BAST, gpm (fBA) 6.00 90 5.33 80 Approx Pot Setting Dilution 1-CH-FC-1114A Water 1-CH-HFC-1114 Flow (f PG) Graphics No: KM1108H BLENDED FLOW NOMOGRAPH FIGURE S-3.1-10 (UNIT 1)

NOTE: DO NOT set pot setting above 8.0 (20 GPM) on 1-CH-FC-1113A.

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Attachment 19 BLENDED FLOW TABLE FOR 9.5 GPM FROM BAST BAST BAST BAST BAST BAST BAST BAST BLEND 7.0 7.3 7.5 7.8 8.0 8.2 8.5 1000 106.7 111.7 115.0 120.0 123.3 126.7 131.7 1100 96.2 100.7 103.7 108.3 111.3 114.3 118.8 1200 87.4 91.5 94.3 98.4 101.2 104.0 108.1 1300 79.9 83.7 86.3 90.1 92.7 95.2 99.1 1400 73.5 77.1 79.5 83.0 85.4 87.8 91.3 1500 68.0 71.3 73.5 76.9 79.1 81.3 84.6 1600 63.2 66.3 68.3 71.5 73.5 75.6 78.7 1700 58.9 61.8 63.8 66.7 68.6 70.6 73.5 1800 55.1 57.8 59.7 62.5 64.3 66.1 68.9 1900 51.7 54.3 56.1 58.7 60.4 62.2 64.8 2000 48.6 51.1 52.8 55.3 56.9 58.6 61.1 2100 45.9 48.2 49.8 52.2 53.8 55.3 57.7 2200 43.3 45.6 47.1 49.4 50.9 52.4 54.7 2300 41.0 43.2 44.7 46.8 48.3 49.7 51.9 2400 38.9 41.0 42.4 44.5 45.9 47.2 49.3 2500 37.0 39.0 40.3 42.3 43.6 45.0 47.0

Select the column corresponding to the BAST concentration.

This table shows the PG flowrate needed to obtain the blended flow shown in the far left column.

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Attachment 20 BLENDED FLOW TABLE FOR 7.0 GPM FROM BAST BAST BAST BAST BAST BAST BAST BAST BLEND 7.0 7.3 7.5 7.8 8.0 8.2 8.5 1000 78.7 82.3 84.4 88.4 90.9 93.3 97.0 1100 70.9 74.2 76.4 79.8 82.0 84.2 87.6 1200 64.4 67.4 69.5 72.5 74.6 76.6 79.7 1300 58.9 61.7 63.6 66.4 68.3 70.2 73.0 1400 54.2 56.8 58.6 61.2 62.9 64.7 67.3 1500 50.1 52.5 54.2 56.6 58.3 59.9 62.3 1600 46.5 48.8 50.4 52.7 54.2 55.7 58.0 1700 43.4 45.5 47.0 49.1 50.6 52.0 54.2 1800 40.6 42.6 44.0 46.0 47.4 48.7 50.8 1900 38.1 40.0 41.3 43.2 44.5 45.8 47.7 2000 35.8 37.7 38.9 40.7 41.9 43.2 45.0 2100 33.8 35.5 36.7 38.4 39.6 40.8 42.5 2200 31.9 33.6 34.7 36.4 37.5 38.6 40.3 2300 30.2 31.8 32.9 34.5 35.6 36.6 38.2 2400 28.7 30.2 31.2 32.8 33.8 34.8 36.3 2500 27.3 28.7 29.7 31.2 32.2 33.1 34.6

Select the column corresponding to the BAST concentration.

This table shows the PG flowrate needed to obtain the blended flow shown in the far left column.

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Attachment 21 BLENDED FLOW TABLE FOR 5.0 GPM FROM BAST BAST BAST BAST BAST BAST BAST BAST BLEND 7.0 7.3 7.5 7.8 8.0 8.2 8.5 1000 56.2 58.8 60.6 63.2 64.9 66.7 69.3 1100 50.6 53.0 54.6 57.0 58.6 60.2 62.5 1200 46.0 48.2 49.6 51.8 53.3 54.7 56.9 1300 42.1 44.1 45.4 47.4 48.8 50.1 52.1 1400 38.7 40.6 41.8 43.7 44.9 46.2 48.1 1500 35.8 37.5 38.7 40.4 41.6 42.8 44.5 1600 33.2 34.9 36.0 37.6 38.7 39.8 41.4 1700 31.0 32.5 33.6 35.1 36.1 37.2 38.7 1800 29.0 30.4 31.4 32.9 33.8 34.8 36.3 1900 27.2 28.6 29.5 30.9 31.8 32.7 34.1 2000 25.6 26.9 27.8 29.1 30.0 30.8 32.1 2100 24.1 25.4 26.2 27.5 28.3 29.1 30.4 2200 22.8 24.0 24.8 26.0 26.8 27.6 28.8 2300 21.6 22.7 23.5 24.6 25.4 26.2 27.3 2400 20.5 21.6 22.3 23.4 24.1 24.9 26.0 2500 19.5 20.5 21.2 22.3 23.0 23.7 24.7

Select the column corresponding to the BAST concentration.

This table shows the PG flowrate needed to obtain the blended flow shown in the far left column.

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Attachment 22 VCT BATCH MIX TABLE

(* Gallons of acid to add to 100 gallons of PG)

VCT BAST BAST BAST BAST BAST BAST BAST PPM 7.0 7.3 7.5 7.8 8.0 8.2 8.5 100 0.8 0.8 0.8 0.7 0.7 0.7 0.7 200 1.7 1.6 1.5 1.5 1.5 1.4 1.4 300 2.5 2.4 2.3 2.2 2.2 2.1 2.1 400 3.4 3.2 3.1 3.0 2.9 2.9 2.8 500 4.3 4.1 4.0 3.8 3.7 3.6 3.5 600 5.2 4.9 4.8 4.6 4.5 4.4 4.2 700 6.1 5.8 5.6 5.4 5.3 5.1 4.9 800 7.0 6.7 6.5 6.2 6.1 5.9 5.7 900 7.9 7.6 7.4 7.1 6.9 6.7 6.4 1000 8.9 8.5 8.3 7.9 7.7 7.5 7.2 1100 9.9 9.4 9.2 8.8 8.5 8.3 8.0 1200 10.9 10.4 10.1 9.7 9.4 9.1 8.8 1300 11.9 11.3 11.0 10.5 10.2 10.0 9.6 1400 12.9 12.3 12.0 11.4 11.1 10.8 10.4 1500 14.0 13.3 12.9 12.4 12.0 11.7 11.2 1600 15.0 14.3 13.9 13.3 12.9 12.6 12.1 1700 16.1 15.4 14.9 14.2 13.8 13.5 12.9 1800 17.2 16.4 15.9 15.2 14.8 14.4 13.8 1900 18.4 17.5 16.9 16.2 15.7 15.3 14.7 2000 19.5 18.6 18.0 17.2 16.7 16.2 15.6 2100 20.7 19.7 19.1 18.2 17.7 17.2 16.5 2200 21.9 20.8 20.2 19.2 18.7 18.1 17.4 2300 23.1 22.0 21.3 20.3 19.7 19.1 18.3 2400 24.4 23.2 22.4 21.4 20.7 20.1 19.3 2500 25.7 24.4 23.6 22.5 21.8 21.1 20.2

1. Select the column corresponding to the BAST concentration.

This table shows the number of gallons from the BAST needed to make a VCT Batch of the concentration shown in the far left column, assuming 100 gallons of PG water are in the VCT.

2. For other batch sizes, ratio the gallons of acid.

3. This table may also be used for flow rates. For example, a 1400 ppm mix can be made by combining 100 gpm of PG water with 12.0 gpm from the BAST (at 7.5 w/o).

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Attachment 23 GALLONS OF BORIC ACID NEEDED TO INCREASE RCS BY 1 PPM (2235 PSIG, 550 °F, RCS VOLUME=9200 CUBIC FEET)

CURRENT RCS BAST BAST BAST BAST BAST BAST BAST PPM 7.0 7.3 7.5 7.8 8.0 8.2 8.5 0 4.3 4.1 4.0 3.9 3.8 3.7 3.5 250 4.4 4.2 4.1 3.9 3.8 3.7 3.6 500 4.5 4.3 4.2 4.0 3.9 3.8 3.7 750 4.6 4.4 4.3 4.1 4.0 3.9 3.7 1000 4.7 4.5 4.3 4.2 4.1 3.9 3.8 1250 4.8 4.6 4.4 4.2 4.1 4.0 3.9 1500 4.9 4.7 4.5 4.3 4.2 4.1 3.9 1750 5.0 4.8 4.6 4.4 4.3 4.2 4.0 2000 5.1 4.9 4.7 4.5 4.4 4.3 4.1 2250 5.3 5.0 4.8 4.6 4.5 4.4 4.2 (450 PSIG, 350 °F, RCS VOLUME=9200 CUBIC FEET)

CURRENT RCS BAST BAST BAST BAST BAST BAST BAST PPM 7.0 7.3 7.5 7.8 8.0 8.2 8.5 0 5.1 4.9 4.8 4.6 4.5 4.4 4.2 250 5.2 5.0 4.9 4.7 4.6 4.4 4.3 500 5.3 5.1 5.0 4.8 4.6 4.5 4.4 750 5.4 5.2 5.1 4.9 4.7 4.6 4.4 1000 5.6 5.3 5.2 4.9 4.8 4.7 4.5 1250 5.7 5.4 5.3 5.0 4.9 4.8 4.6 1500 5.8 5.6 5.4 5.2 5.0 4.9 4.7 1750 6.0 5.7 5.5 5.3 5.1 5.0 4.8 2000 6.1 5.8 5.6 5.4 5.2 5.1 4.9 2250 6.3 5.9 5.8 5.5 5.3 5.2 5.0

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Attachment 23 GALLONS OF BORIC ACID NEEDED TO INCREASE RCS BY 1 PPM (0 PSIG, 100 °F, RCS VOLUME=9200 CUBIC FEET)

CURRENT RCS BAST BAST BAST BAST BAST BAST BAST PPM 7.0 7.3 7.5 7.8 8.0 8.2 8.5 0 5.7 5.5 5.3 5.1 5.0 4.9 4.7 250 5.8 5.6 5.4 5.2 5.1 4.9 4.8 500 5.9 5.7 5.5 5.3 5.2 5.0 4.8 750 6.1 5.8 5.6 5.4 5.3 5.1 4.9 1000 6.2 5.9 5.7 5.5 5.4 5.2 5.0 1250 6.3 6.0 5.9 5.6 5.5 5.3 5.1 1500 6.5 6.2 6.0 5.7 5.6 5.4 5.2 1750 6.6 6.3 6.1 5.9 5.7 5.5 5.3 2000 6.8 6.5 6.3 6.0 5.8 5.6 5.4 2250 7.0 6.6 6.4 6.1 5.9 5.8 5.5

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 48 of 195 (Page 1 of 2)

Attachment 24 RCS DILUTION TABLE RCS PPM 0 PSIG/70 °F 450 PSIG/350 °F 2235 PSIG/547 °F 50 1766 1581 1336 100 779 698 590 200 368 330 279 300 241 216 182 400 179 160 136 500 142 128 108 600 118 106 90 700 101 91 77 800 88 79 67 900 78 70 59 1000 70 63 53 1100 64 57 48 1200 59 53 44 1300 54 48 41 1400 50 45 38 1500 47 42 35 1600 44 39 33 1700 41 37 31 1800 39 35 29 1900 37 33 28 2000 35 31 27 2100 33 30 25 2200 32 29 24 2300 30 27 23 2400 29 26 22 2500 28 25 21

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 49 of 195 (Page 2 of 2)

Attachment 24 RCS DILUTION TABLE NOTES:

1. The table shows gallons of primary grade water needed to dilute the RCS 1 ppm.

2. For temperatures significantly different than those shown, interpolate.

3. Examples:

(a) If the RCS is at 2235 psig/547°F with a boron concentration of 1100 ppm, how much primary grade water is needed to dilute to 1050 ppm?

(1100 - 1050) x 48 = 2400 gallons (b) In example (a) if the RCS is to be diluted a large amount, for example to 500 ppm, select the table value midway between the two boron concentrations. In this example (b) the dilution value at 800 ppm would be chosen.

(1100 - 500) x 67 = 40, 200 gallons The results will always be slightly conservative (will not result in overdilution).

4. For more precise dilution volumes, use the following formulas:

W= -69751 x ln 1 + --------------------

B2 - B1 At 0 psig/70°F B1 - 10 W= -62462 x ln 1 + --------------------

B2 - B1 At 350 psig/450°F B1 - 10 W= -52784 x ln 1 + --------------------

B2 - B1 At 2235 psig/547°F B1 - 10 Where W= gallons of PG water to add B1 = initial boron concentration B2 = final boron concentration and ln is the natural log.

DO NOT use the base 10 log, which will yield conservative but very inaccurate results.

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 50 of 195 (Page 1 of 1)

Attachment 25 CONTROL ROD INSERTION LIMITS VS POWER LEVEL (FOR 3 LOOP NORMAL OPERATION)

NOTE: ARO EQUALS 228 STEPS OVERLAP EQUALS 100 STEPS 220 (48.13, 228) 200 180 (100, 183) 160 Rod Bank Position (5 steps withdrawn/div)

C-Bank (0, 151) 140 120 D-Bank 100 80 60 40 20 (0, 23) 0 0 10 20 30 40 50 60 70 80 90 100 Power Level (2 percent/div) S1C23RodInsertionLimit.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 51 of 195 (Page 1 of 2)

Attachment 26 SURRY UNIT 1 - CYCLE 23 CRITICAL BORON CONCENTRATION VS. BURNUP HOT FULL POWER, ALL RODS OUT 1500 1400 1300 1200 1100 Critical Boron Concentration (20 ppm/div) 1000 900 800 700 600 500 400 300 200 100 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (200 MWD/MTU/div)

S1C23HFPCriticalBoron.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 52 of 195 (Page 2 of 2)

Attachment 26 SURRY UNIT 1 - CYCLE 23 CRITICAL BORON CONCENTRATION VS. BURNUP HOT FULL POWER, ALL RODS OUT 1500 1400 1300 1200 1100 Boron (no Depl)

Boron (w/Depl) 1000 Critical Boron Concentration (20 ppm/div) 900 800 700 600 500 400 300 200 100 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (200 MWD/MTU/div) S1C23HFPCriticalBoronB10.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 53 of 195 (Page 1 of 1)

Attachment 27 SURRY UNIT 1 - CYCLE 23 BORON COEFFICIENT VS BURNUP

-9.80 0% Power

-9.60 25% Power 50% Power

-9.40 75% Power 100% Power

-9.20

-9.00 Boron Coefficient (-0.05 pcm/ppm/div)

-8.80

-8.60

-8.40

-8.20

-8.00

-7.80

-7.60

-7.40

-7.20 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU/div)

S1C23BoronCoeff.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 54 of 195 (Page 1 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 228 228 0.0 0.0 0.0 0.0 0.0 0.0 225 228 0.0 0.0 0.0 0.0 0.0 0.0 223 228 2.1 2.8 3.4 4.1 4.9 5.2 221 228 7.4 9.6 11.9 14.2 16.6 18.0 219 228 14.2 18.2 22.5 27.1 31.5 33.8 217 228 22.9 29.4 36.4 43.2 49.9 53.4 215 228 33.2 42.3 52.0 61.1 70.0 74.5 213 228 44.5 56.8 69.0 80.6 91.9 97.5 211 228 56.8 72.3 87.3 101.7 115.4 122.1 209 228 70.5 89.3 107.4 124.5 140.5 148.4 207 228 84.8 107.0 128.1 147.7 166.0 174.8 205 228 100.0 125.7 150.0 172.3 192.9 202.7 203 228 117.3 146.9 174.8 200.0 223.1 234.0 201 228 133.0 166.0 196.6 224.2 249.0 260.7 199 228 149.6 186.1 219.7 249.6 276.2 288.7 197 228 166.3 206.3 242.8 275.0 303.4 316.7 195 228 184.9 228.6 268.4 302.9 333.3 347.3 193 228 201.7 248.5 290.8 327.2 358.9 373.5 191 228 218.8 268.9 313.7 352.0 385.1 400.3 189 228 236.1 289.3 336.7 377.0 411.5 427.2 187 228 253.5 309.9 359.8 401.7 437.5 453.7 185 228 269.8 328.8 380.9 424.3 461.0 477.7 183 228 286.4 348.2 402.5 447.5 485.3 502.4 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 55 of 195 (Page 2 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 181 228 303.6 368.4 425.0 471.6 510.5 528.1 179 228 318.8 385.8 444.2 491.9 531.7 549.5 177 228 334.1 403.5 463.7 512.7 553.2 571.4 175 228 349.5 421.3 483.4 533.6 575.0 593.5 173 228 364.8 438.6 502.7 554.1 596.3 615.1 171 228 378.9 454.9 520.3 572.7 615.5 634.5 169 228 393.3 471.4 538.3 591.7 635.2 654.5 167 228 408.9 489.1 557.8 612.4 656.6 676.3 165 228 421.5 503.2 573.3 628.6 673.3 693.1 163 228 434.5 517.7 589.1 645.3 690.4 710.4 161 228 447.3 532.1 604.8 661.8 707.5 727.7 159 228 461.4 547.8 621.9 679.7 725.9 746.3 157 228 473.5 561.3 636.2 694.8 741.3 761.8 155 228 485.9 575.0 650.8 710.1 757.0 777.5 153 228 498.2 588.7 665.5 725.3 772.6 793.3 151 228 510.6 602.2 680.0 740.2 787.7 808.5 149 228 521.9 614.5 693.0 753.6 801.2 822.0 147 228 533.5 627.2 706.4 767.4 815.1 836.0 145 228 545.7 640.3 720.3 781.6 829.5 850.3 143 228 556.1 651.4 731.9 793.3 841.1 861.9 141 228 566.9 662.8 743.8 805.3 852.9 873.6 139 228 577.7 674.3 755.7 817.3 864.8 885.4 137 228 588.5 685.6 767.3 828.9 876.2 896.7 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 56 of 195 (Page 3 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 135 228 598.6 696.0 777.8 839.2 886.2 906.5 133 228 608.9 706.7 788.6 849.9 896.4 916.6 131 228 620.2 718.3 800.3 861.3 907.5 927.4 129 228 629.6 727.8 809.6 870.1 915.8 935.4 127 228 639.4 737.5 819.2 879.2 924.2 943.6 125 228 649.1 747.3 828.6 888.1 932.6 951.7 123 228 659.8 757.8 838.8 897.6 941.3 960.1 121 228 668.9 766.6 847.0 905.0 947.9 966.4 119 228 678.4 775.7 855.4 912.6 954.8 972.9 117 228 688.0 784.9 863.9 920.1 961.5 979.3 115 228 697.9 794.2 872.2 927.4 967.8 985.3 113 228 707.1 802.6 879.6 933.7 973.2 990.3 111 228 716.6 811.4 887.2 940.1 978.7 995.4 109 228 726.7 820.5 895.1 946.6 984.3 1000.0 107 228 735.5 828.2 901.4 951.6 988.3 1004.0 105 228 744.6 836.1 907.8 956.7 992.4 1008.0 103 228 753.9 844.1 914.2 961.7 996.5 1011.1 101 228 763.2 852.0 920.3 966.4 999.6 1014.9 99 227 772.0 859.1 925.6 970.3 1003.0 1017.7 97 225 781.0 866.5 931.1 974.3 1006.2 1020.0 96 224 785.6 870.1 933.5 976.0 1007.6 1021.6 95 223 791.9 875.9 939.0 981.5 1013.5 1027.9 94 222 797.2 881.0 944.2 987.1 1019.8 1034.6 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 57 of 195 (Page 4 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 93 221 802.6 886.5 950.0 993.7 1027.4 1042.7 92 220 808.5 892.4 956.4 1000.9 1035.4 1051.3 91 219 814.4 898.6 963.4 1008.9 1044.6 1061.0 90 218 820.7 905.3 970.8 1017.3 1054.1 1071.1 89 217 827.0 912.3 979.2 1027.2 1065.4 1083.2 88 216 835.5 921.1 988.8 1037.8 1077.1 1095.4 87 215 841.5 928.1 997.2 1047.8 1088.5 1107.5 86 214 848.0 935.4 1005.9 1058.0 1100.0 1119.6 85 213 855.2 943.6 1015.7 1069.3 1112.9 1133.1 84 212 862.2 951.5 1025.1 1080.4 1125.4 1146.3 83 211 869.9 960.2 1035.5 1092.5 1139.0 1160.6 82 210 877.6 969.3 1046.5 1105.4 1153.7 1176.1 81 209 885.4 978.0 1056.7 1117.3 1166.8 1189.8 80 208 893.8 987.5 1067.9 1130.2 1181.2 1204.8 79 207 901.4 996.2 1078.3 1142.2 1194.6 1218.8 78 206 909.3 1005.3 1089.4 1155.2 1209.2 1234.1 77 205 917.4 1014.5 1100.4 1168.0 1223.5 1249.0 76 204 925.4 1023.7 1111.4 1180.9 1237.9 1264.1 75 203 934.8 1034.7 1124.8 1196.7 1255.6 1283.0 74 202 942.9 1043.9 1135.8 1209.3 1269.7 1297.5 73 201 952.2 1054.1 1147.4 1222.5 1284.0 1312.1 72 200 960.7 1063.6 1158.8 1235.6 1298.6 1327.2 71 199 969.3 1073.3 1170.0 1248.5 1312.7 1341.9 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 58 of 195 (Page 5 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 70 198 978.1 1083.2 1181.8 1262.1 1327.9 1357.7 69 197 986.9 1092.8 1192.8 1274.7 1341.7 1372.0 68 196 997.4 1105.0 1207.5 1291.9 1361.0 1392.6 67 195 1005.8 1113.9 1217.6 1303.2 1373.2 1405.0 66 194 1015.4 1124.1 1228.9 1315.7 1386.7 1418.7 65 193 1024.4 1133.9 1240.0 1328.3 1400.4 1432.8 64 192 1033.5 1143.7 1251.0 1340.5 1413.8 1446.6 63 191 1042.8 1153.8 1262.4 1353.5 1428.0 1461.3 62 190 1052.4 1164.0 1273.8 1366.2 1441.8 1475.6 61 189 1061.9 1174.3 1285.4 1379.2 1455.9 1490.2 60 188 1071.8 1185.0 1297.3 1392.6 1470.6 1505.4 59 187 1082.7 1196.3 1309.3 1405.4 1484.2 1519.2 58 186 1092.0 1205.9 1319.7 1416.7 1496.2 1531.6 57 185 1101.4 1215.9 1330.6 1428.7 1509.1 1544.8 56 184 1111.2 1226.1 1341.5 1440.5 1521.6 1557.7 55 183 1121.1 1236.6 1352.9 1452.9 1535.0 1571.5 54 182 1131.3 1247.1 1364.0 1464.8 1547.6 1584.4 53 181 1141.6 1258.1 1376.0 1478.0 1561.9 1599.2 52 180 1153.8 1270.3 1388.3 1490.5 1574.6 1611.9 51 179 1162.8 1279.7 1398.3 1501.2 1585.9 1623.5 50 178 1172.4 1289.6 1408.6 1512.0 1597.3 1635.0 49 177 1182.9 1300.4 1419.9 1523.9 1609.7 1647.7 48 176 1192.8 1310.7 1430.7 1535.2 1621.5 1659.7 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 59 of 195 (Page 6 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 47 175 1203.7 1322.0 1442.3 1547.2 1634.0 1672.5 46 174 1214.7 1333.3 1454.1 1559.7 1647.1 1685.8 45 173 1225.2 1344.0 1464.9 1570.7 1658.2 1697.0 44 172 1236.4 1355.4 1476.4 1582.2 1669.9 1708.8 43 171 1246.7 1365.9 1487.0 1592.9 1680.7 1719.6 42 170 1257.0 1376.5 1497.9 1604.1 1692.1 1731.2 41 169 1267.7 1387.5 1508.9 1615.2 1703.5 1742.6 40 168 1278.2 1398.2 1519.9 1626.4 1714.8 1754.1 39 167 1290.3 1410.8 1532.8 1639.6 1728.3 1767.7 38 166 1300.4 1421.2 1543.2 1650.0 1738.7 1778.1 37 165 1312.0 1432.8 1554.6 1661.0 1749.4 1788.7 36 164 1322.1 1443.2 1565.0 1671.4 1759.7 1799.0 35 163 1332.4 1453.8 1575.6 1681.7 1770.0 1809.2 34 162 1342.9 1464.6 1586.4 1692.6 1780.9 1820.1 33 161 1353.3 1475.2 1597.0 1703.0 1791.0 1830.2 32 160 1365.6 1488.1 1610.3 1716.5 1804.8 1844.1 31 159 1375.4 1498.1 1620.0 1725.9 1813.8 1853.0 30 158 1386.4 1509.2 1630.9 1736.2 1823.7 1862.7 29 157 1396.5 1519.7 1641.2 1746.4 1833.6 1872.5 28 156 1406.7 1530.1 1651.5 1756.3 1843.3 1882.1 27 155 1416.9 1540.7 1662.1 1766.7 1853.5 1892.2 26 154 1427.3 1551.4 1672.8 1777.1 1863.6 1902.2 25 153 1437.7 1562.1 1683.5 1787.6 1873.8 1912.3 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 60 of 195 (Page 7 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 24 152 1448.4 1573.2 1694.5 1798.4 1884.3 1922.7 23 151 1459.5 1584.5 1705.5 1808.8 1894.1 1932.3 22 150 1468.9 1594.0 1714.8 1817.7 1902.6 1940.5 21 149 1478.2 1603.7 1724.5 1827.0 1911.6 1949.4 20 148 1487.7 1613.4 1734.1 1836.2 1920.4 1958.1 19 147 1497.3 1623.4 1744.0 1845.9 1929.8 1967.3 18 146 1506.8 1633.2 1753.6 1855.1 1938.6 1975.9 17 145 1516.8 1643.6 1764.1 1865.3 1948.6 1985.8 16 144 1527.1 1654.0 1774.1 1874.6 1957.0 1993.9 15 143 1535.3 1662.4 1782.4 1882.5 1964.6 2001.3 14 142 1543.4 1670.7 1790.5 1890.3 1972.0 2008.6 13 141 1552.1 1679.7 1799.4 1898.9 1980.2 2016.5 12 140 1560.3 1688.1 1807.8 1906.9 1987.8 2024.0 11 139 1569.0 1697.1 1816.6 1915.4 1995.8 2031.8 10 138 1577.9 1706.3 1825.7 1924.2 2004.2 2040.0 9 137 1585.7 1714.2 1833.5 1931.4 2010.9 2046.5 8 136 1593.9 1722.6 1841.5 1939.0 2017.9 2053.2 7 135 1601.0 1729.7 1848.6 1945.6 2024.1 2059.2 6 134 1608.4 1737.3 1856.0 1952.8 2030.9 2065.8 5 133 1615.5 1744.6 1863.3 1959.6 2037.3 2072.0 4 132 1622.6 1751.9 1870.5 1966.5 2043.8 2078.3 3 131 1631.1 1760.5 1879.0 1974.7 2051.5 2085.8 2 130 1637.6 1767.2 1885.5 1980.7 2057.0 2091.1 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 61 of 195 (Page 8 of 8)

Attachment 28 SURRY UNIT 1 - CYCLE 23 HZP INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 1 129 1644.3 1773.9 1891.9 1986.6 2062.4 2096.2 0 128 1650.6 1780.2 1898.1 1992.4 2067.8 2101.4 0 126 1661.4 1791.2 1909.2 2003.3 2078.1 2111.5 0 124 1673.8 1803.8 1921.8 2015.6 2089.9 2122.9 0 122 1682.6 1812.6 1930.6 2023.8 2097.3 2129.9 0 120 1692.7 1822.7 1940.4 2033.0 2105.6 2137.9 0 118 1703.3 1833.1 1950.6 2042.5 2114.2 2146.0 0 116 1714.4 1844.1 1961.1 2052.1 2122.8 2154.1 0 114 1724.5 1853.8 1970.2 2060.1 2129.6 2160.4 0 112 1735.0 1863.8 1979.5 2068.2 2136.4 2166.7 0 110 1745.7 1874.0 1988.8 2076.2 2143.2 2173.0 0 108 1756.8 1884.5 1998.2 2084.0 2149.6 2178.2 0 106 1767.1 1893.9 2006.4 2090.6 2154.8 2183.3 0 104 1777.9 1903.8 2014.8 2097.3 2160.1 2187.6 0 102 1789.4 1914.2 2023.7 2104.2 2164.5 2191.9 0 100 1799.8 1923.4 2031.0 2109.6 2169.1 2196.1 0 98 1810.5 1932.7 2038.4 2114.9 2173.3 2199.3 S1C23RodWorthHZPMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 62 of 195 (Page 1 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 228 228 0.0 0.0 0.0 0.0 0.0 0.0 225 228 0.0 0.0 0.0 0.0 0.0 0.0 223 228 2.1 2.4 2.9 3.4 4.0 4.3 221 228 6.9 8.2 9.7 11.3 13.3 14.4 219 228 12.6 15.0 17.7 20.7 24.1 25.6 217 228 19.6 23.2 27.3 31.8 36.4 39.3 215 228 27.1 31.9 37.2 43.0 48.9 52.4 213 228 35.3 41.3 47.9 55.1 62.3 66.6 211 228 43.3 50.7 58.7 67.2 76.5 81.5 209 228 52.9 61.6 70.9 80.8 91.6 97.3 207 228 62.7 72.7 83.4 94.6 106.6 112.9 205 228 73.1 84.5 96.6 109.1 122.1 129.3 203 228 84.9 97.9 111.4 125.4 139.8 147.5 201 228 95.7 109.9 124.7 139.7 155.5 163.6 199 228 107.3 122.7 138.7 154.9 171.7 180.4 197 228 118.8 135.5 152.7 170.1 187.9 197.1 195 228 131.9 150.0 168.5 187.0 205.7 215.7 193 228 143.8 163.0 182.5 202.2 221.8 231.9 191 228 156.1 176.4 197.0 217.4 238.1 248.6 189 228 168.5 190.0 211.5 232.9 254.5 265.4 187 228 181.5 204.0 226.5 248.8 271.1 282.5 185 228 193.6 217.0 240.4 263.7 286.5 298.2 183 228 206.2 230.5 254.8 278.8 302.4 314.4 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 63 of 195 (Page 2 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 181 228 219.4 244.7 269.9 294.7 319.0 331.4 179 228 231.4 257.4 284.0 308.8 333.6 346.3 177 228 243.6 270.4 297.7 323.1 348.6 361.6 175 228 256.0 283.6 311.6 338.1 363.8 377.1 173 228 268.6 296.9 325.6 352.8 379.1 392.7 171 228 280.6 310.2 338.7 366.4 393.3 407.2 169 228 292.9 323.1 352.2 380.6 408.0 422.2 167 228 306.2 336.5 367.0 396.0 424.1 438.6 165 228 318.2 348.9 379.2 408.8 437.6 452.0 163 228 329.9 361.1 392.0 422.0 451.4 466.0 161 228 341.6 373.3 404.7 435.2 465.1 480.3 159 228 354.0 387.0 418.9 450.0 480.5 495.9 157 228 366.3 399.0 431.4 463.0 493.9 509.6 155 228 378.3 411.5 444.3 476.4 507.8 523.8 153 228 390.4 424.0 457.3 489.9 521.8 538.0 151 228 402.9 436.9 470.7 503.8 536.2 552.7 149 228 414.5 448.8 483.0 516.6 549.5 566.2 147 228 426.6 461.2 495.8 529.8 563.2 580.1 145 228 439.2 474.2 509.2 543.7 577.6 594.8 143 228 450.6 485.9 521.2 556.1 590.4 607.9 141 228 462.2 497.8 533.5 568.8 603.6 621.3 139 228 474.0 509.9 545.9 581.7 616.9 634.8 137 228 486.0 522.1 558.5 594.7 630.3 648.5 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 64 of 195 (Page 3 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 135 228 497.4 533.7 570.4 606.9 642.9 661.3 133 228 509.1 545.6 582.6 619.5 655.9 674.5 131 228 521.8 558.5 595.9 633.2 670.1 688.9 129 228 532.8 569.7 607.3 644.9 682.2 701.2 127 228 544.1 581.2 619.0 657.0 694.6 713.8 125 228 555.4 592.6 630.7 668.9 707.0 726.3 123 228 567.8 605.1 643.5 682.2 720.6 740.2 121 228 578.6 616.0 654.6 693.5 732.3 752.0 119 228 589.8 627.3 666.0 705.2 744.3 764.2 117 228 600.9 638.4 677.4 716.9 756.3 776.4 115 228 612.7 650.3 689.4 729.2 768.9 789.2 113 228 623.8 661.4 700.6 740.6 780.6 801.0 111 228 635.1 672.7 712.1 752.3 792.6 813.2 109 228 647.0 684.6 724.1 764.5 805.1 825.8 107 228 657.7 695.3 734.9 775.5 816.3 837.1 105 228 668.7 706.1 745.8 786.6 827.6 848.5 103 228 679.7 717.1 756.8 797.7 838.9 860.0 101 228 690.9 728.2 767.9 809.0 850.4 871.6 99 227 701.4 738.6 778.4 819.6 861.1 882.4 97 225 712.3 749.3 789.1 830.4 872.1 893.4 96 224 717.8 754.8 794.6 835.9 877.7 899.1 95 223 725.7 763.0 803.2 845.1 887.5 909.3 94 222 732.7 770.3 810.9 853.3 896.4 918.5 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 65 of 195 (Page 4 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 93 221 739.8 777.8 818.9 862.0 905.8 928.3 92 220 747.4 785.8 827.4 871.2 915.7 938.7 91 219 755.1 793.9 836.2 880.7 926.1 949.5 90 218 763.2 802.5 845.4 890.5 936.7 960.5 89 217 771.4 811.3 854.9 900.9 948.1 972.4 88 216 781.7 822.1 866.2 913.0 960.8 985.5 87 215 789.5 830.4 875.2 922.5 971.1 996.2 86 214 797.7 839.1 884.5 932.6 981.8 1007.3 85 213 806.9 848.8 894.9 943.7 993.7 1019.6 84 212 815.5 858.1 904.8 954.3 1005.0 1031.2 83 211 825.1 868.2 915.6 965.9 1017.4 1044.0 82 210 834.7 878.5 926.7 977.8 1030.1 1057.1 81 209 844.1 888.5 937.2 988.9 1041.9 1069.2 80 208 854.4 899.3 948.7 1001.1 1054.7 1082.4 79 207 863.9 909.3 959.4 1012.3 1066.6 1094.6 78 206 873.5 919.6 970.3 1024.0 1078.9 1107.2 77 205 883.4 930.1 981.4 1035.8 1091.3 1119.9 76 204 893.2 940.4 992.4 1047.4 1103.6 1132.5 75 203 904.7 952.8 1005.6 1061.3 1118.3 1147.6 74 202 914.5 963.0 1016.4 1072.8 1130.2 1159.8 73 201 925.6 974.6 1028.5 1085.4 1143.4 1173.3 72 200 936.0 985.6 1040.1 1097.5 1156.1 1186.2 71 199 946.5 996.6 1051.6 1109.6 1168.7 1199.0 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 66 of 195 (Page 5 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 70 198 957.2 1007.9 1063.6 1122.1 1181.7 1212.3 69 197 967.7 1018.9 1075.0 1134.0 1194.1 1224.9 68 196 980.7 1032.7 1089.6 1149.4 1210.2 1241.3 67 195 990.4 1042.8 1100.1 1160.3 1221.4 1252.8 66 194 1001.7 1054.4 1112.2 1172.7 1234.2 1265.8 65 193 1012.6 1065.8 1124.0 1185.0 1246.9 1278.6 64 192 1023.4 1077.0 1135.7 1197.1 1259.3 1291.2 63 191 1034.5 1088.6 1147.7 1209.5 1272.2 1304.3 62 190 1045.8 1100.3 1159.8 1222.1 1285.1 1317.4 61 189 1057.1 1112.1 1172.0 1234.6 1298.1 1330.5 60 188 1068.8 1124.3 1184.7 1247.7 1311.6 1344.2 59 187 1081.2 1137.0 1197.7 1261.1 1325.2 1358.0 58 186 1092.0 1148.1 1209.1 1272.7 1337.1 1370.0 57 185 1103.2 1159.6 1220.9 1284.9 1349.5 1382.6 56 184 1114.4 1171.2 1232.8 1297.0 1361.9 1395.1 55 183 1126.0 1183.1 1245.1 1309.7 1374.8 1408.2 54 182 1137.5 1194.9 1257.1 1321.9 1387.4 1420.8 53 181 1149.7 1207.5 1270.1 1335.3 1401.0 1434.6 52 180 1162.8 1220.8 1283.6 1348.9 1414.8 1448.5 51 179 1173.4 1231.7 1294.7 1360.2 1426.3 1460.1 50 178 1184.3 1242.8 1306.0 1371.7 1438.0 1471.9 49 177 1196.2 1255.0 1318.5 1384.4 1450.9 1484.9 48 176 1207.5 1266.5 1330.2 1396.3 1463.0 1497.1 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 67 of 195 (Page 6 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 47 175 1219.7 1278.9 1342.8 1409.1 1476.0 1510.2 46 174 1232.0 1291.5 1355.7 1422.2 1489.3 1523.6 45 173 1243.6 1303.3 1367.6 1434.2 1501.4 1535.8 44 172 1256.0 1315.8 1380.2 1447.0 1514.3 1548.8 43 171 1267.4 1327.4 1392.0 1458.8 1526.3 1560.8 42 170 1279.1 1339.3 1404.0 1471.0 1538.6 1573.1 41 169 1290.9 1351.3 1416.2 1483.3 1551.0 1585.6 40 168 1302.6 1363.1 1428.2 1495.4 1563.2 1597.9 39 167 1316.2 1377.0 1442.2 1509.7 1577.5 1612.3 38 166 1328.1 1389.0 1454.3 1521.9 1589.2 1624.1 37 165 1340.5 1401.6 1467.0 1534.5 1601.9 1636.8 36 164 1351.4 1413.2 1478.7 1546.3 1613.9 1648.8 35 163 1363.6 1424.9 1490.5 1558.3 1625.8 1660.8 34 162 1375.5 1437.0 1502.8 1570.6 1638.2 1673.2 33 161 1387.0 1448.7 1514.5 1582.4 1650.1 1685.1 32 160 1400.7 1462.6 1528.5 1596.6 1665.3 1700.4 31 159 1412.2 1474.3 1539.6 1607.7 1676.4 1711.6 30 158 1424.6 1486.7 1552.1 1620.2 1689.0 1724.1 29 157 1436.5 1498.8 1564.2 1632.4 1701.2 1736.5 28 156 1448.2 1510.7 1576.3 1644.6 1713.4 1748.7 27 155 1460.3 1523.0 1588.6 1657.0 1726.0 1761.3 26 154 1472.5 1535.4 1601.1 1669.6 1738.6 1773.8 25 153 1484.7 1547.8 1613.7 1682.2 1751.4 1786.6 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 68 of 195 (Page 7 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 24 152 1497.5 1560.7 1626.7 1695.4 1764.5 1799.9 23 151 1510.7 1573.3 1640.3 1708.9 1778.1 1813.6 22 150 1521.9 1585.5 1651.8 1720.6 1790.0 1825.5 21 149 1533.5 1597.3 1663.7 1732.7 1802.1 1837.5 20 148 1545.1 1609.1 1675.7 1744.7 1814.1 1849.7 19 147 1556.4 1621.3 1688.0 1757.2 1826.7 1862.4 18 146 1568.7 1633.2 1700.1 1769.4 1839.0 1874.8 17 145 1580.6 1645.2 1713.1 1782.6 1852.4 1888.2 16 144 1594.3 1658.4 1726.5 1796.0 1866.0 1901.9 15 143 1604.1 1669.2 1738.1 1807.8 1877.3 1913.2 14 142 1614.4 1680.3 1748.8 1818.7 1888.3 1924.3 13 141 1625.7 1691.2 1760.6 1830.7 1900.4 1936.3 12 140 1636.2 1702.7 1771.6 1841.9 1911.8 1948.0 11 139 1647.4 1714.2 1783.3 1853.9 1924.0 1960.0 10 138 1658.9 1725.2 1794.5 1866.1 1936.4 1972.6 9 137 1669.2 1736.4 1806.0 1877.0 1947.6 1983.8 8 136 1680.0 1746.8 1817.3 1888.4 1959.2 1995.8 7 135 1689.3 1756.4 1826.3 1897.6 1970.0 2006.6 6 134 1698.9 1766.2 1836.4 1907.9 1979.8 2016.5 5 133 1708.3 1775.9 1846.3 1918.0 1990.8 2027.7 4 132 1717.6 1785.3 1856.0 1928.0 2000.3 2037.3 3 131 1728.4 1796.4 1867.4 1939.6 2012.3 2049.4 2 130 1737.1 1805.3 1876.4 1948.9 2021.8 2059.0 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 69 of 195 (Page 8 of 8)

Attachment 29 SURRY UNIT 1 - CYCLE 23 AT POWER INTEGRAL ROD WORTH TABLE FOR CONTROL BANKS C AND D IN OVERLAP Note: Worth At Nominal HFP Conditions CYCLE BURNUP RANGE (MWD/MTU)

D-BANK C-BANK 8000.1 10000.1 12000.1 14000.1 16000.1 17500.1 POS POS TO TO TO TO TO TO STEPS STEPS 10000.0 12000.0 14000.0 16000.0 17500.0 18500.0 1 129 1746.0 1814.4 1885.7 1958.4 2032.2 2069.5 0 128 1754.0 1822.6 1894.2 1967.1 2040.4 2077.8 0 126 1767.3 1836.0 1907.8 1981.0 2054.7 2092.3 0 124 1781.9 1850.8 1922.9 1996.6 2070.7 2108.6 0 122 1793.1 1862.1 1934.3 2008.2 2082.5 2120.5 0 120 1805.3 1874.4 1946.9 2021.0 2095.7 2133.8 0 118 1818.2 1887.3 1959.9 2034.4 2109.3 2147.7 0 116 1831.6 1900.8 1973.6 2048.3 2123.6 2162.2 0 114 1844.1 1913.3 1986.2 2061.1 2136.7 2175.3 0 112 1856.8 1926.0 1999.0 2074.1 2149.9 2188.7 0 110 1869.6 1938.7 2011.9 2087.2 2163.2 2202.1 0 108 1883.0 1952.0 2025.2 2100.7 2177.0 2216.0 0 106 1895.2 1964.2 2037.4 2113.0 2189.5 2228.6 0 104 1907.9 1976.7 2050.0 2125.7 2202.3 2241.6 0 102 1921.1 1989.9 2063.1 2139.0 2215.8 2255.2 0 100 1933.3 2001.9 2075.1 2150.9 2227.9 2267.3 0 98 1945.5 2013.9 2087.0 2162.9 2240.0 2279.4 S1C23RodWorthAtPowerMOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 70 of 195 (Page 1 of 1)

Attachment 30 SURRY UNIT 1 - CYCLE 23 ISOTHERMAL TEMPERATURE DEFECT VS. AVERAGE MODERATOR TEMPERATURE NOTE: For EOL Burnup Exceeding 13500 MWD/MTU FOR ALL RODS OUT, ZERO POWER 1000 900 0 ppm 800 500 ppm 700 1000 ppm Temperature Defect (20pcm/div) 600 500 400 300 200 100 0

-100 500 510 520 530 540 550 o

Average Moderator Temperature (2 F/div)

S1C23IsothermalTempDefectEOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 71 of 195 (Page 1 of 1)

Attachment 31 SURRY UNIT 1 - CYCLE 23 POWER DEFECT NOTE: For Use Through Nominal Full Power End Of Reactivity

-3000 100%

-2500 POWER

-2000 75%

POWER Power Defect (-50 pcm/div)

-1500 50%

POWER

-1000 25%

POWER

-500 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU/div) S1C23PowerDefectThroughEOR.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 72 of 195 (Page 1 of 1)

Attachment 32 SURRY UNIT 1 - CYCLE 23 XENON REACTIVITY WORTH AT HZP VS. PREVIOUS EQUILIBRIUM POWER LEVEL Note: For EOL Burnup Exceeding 13500 MWD/MTU

-3000

-2800

-2600

-2400

-2200 Xenon Reactivity Worth (-50 pcm/div)

-2000

-1800

-1600

-1400

-1200

-1000

-800

-600

-400

-200 0

0 10 20 30 40 50 60 70 80 90 100 Previous Equilibrium Power Level (2 percent / div)

S1C23XenonHZPvsPrevEOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 73 of 195 (Page 1 of 1)

Attachment 33 SURRY UNIT 1 - CYCLE 23 XENON REACTIVITY WORTH FOLLOWING STARTUP Note: For EOL Burnup Exceeding 13500 MWD/MTU

-3000 100%

-2800 power

-2600 75%

-2400 power

-2200 50%

power Xenon Reactivity Worth (-50 pcm/div)

-2000

-1800 25%

power

-1600

-1400

-1200

-1000

-800

-600

-400

-200 0

0 10 20 30 40 50 60 70 80 90 100 Time (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months / div)

S1C23XenonStartupEOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 74 of 195 (Page 1 of 1)

Attachment 34 SURRY UNIT 1 - CYCLE 23 XENON REACTIVITY WORTH FOLLOWING REACTOR TRIP (100 HOURS)

Note: For EOL Burnup Exceeding 13500 MWD/MTU

-5000

-4500

-4000 100%

power

-3500 Xenon Reactivity Worth (-100 pcm/div) 75%

-3000 power

-2500 50%

power

-2000 25%

power

-1500

-1000

-500 0

0 10 20 30 40 50 60 70 80 90 100 Time (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months / div)

S1C23XenonTripEOL100.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 75 of 195 (Page 1 of 1)

Attachment 35 SURRY UNIT 1 - CYCLE 23 XENON REACTIVITY WORTH FOLLOWING REACTOR TRIP (25 HOURS)

Note: For EOL Burnup Exceeding 13500 MWD/MTU

-5000

-4500

-4000

-3500 Xenon Reactivity Worth (-100 pcm/div)

-3000

-2500 100%

power

-2000 75%

power

-1500 50%

power

-1000 25%

power

-500 0

0 5 10 15 20 25 Time (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months / div)

S1C23XenonTripEOL25.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 76 of 195 (Page 1 of 1)

Attachment 36 SURRY UNIT 1 - CYCLE 23 XENON REACTIVITY WORTH FOLLOWING ORDERLY SHUTDOWN Note: For EOL Burnup Exceeding 13500 MWD/MTU

-5000

-4500

-4000 100%

power

-3500 Xenon Reactivity Worth (-100 pcm/div) 75%

-3000 power

-2500 50%

power

-2000 25%

power

-1500

-1000

-500 0

0 10 20 30 40 50 60 70 80 90 100 Time After Shutdown (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months / div)

S1C23XenonShutEOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 77 of 195 (Page 1 of 2)

Attachment 37 SURRY UNIT 1 - CYCLE 23 NET ISOTOPIC DECAY REACTIVITY AFTER SHUTDOWN FROM HFP Note: For EOL Burnup Range Exceeding 13500 MWD/MTU Excluding Xenon

-250

-200 0 ppm Net Isotopic Decay Reactivity (10 pcm/division)

-150 500 ppm

-100 1000 ppm

-50 1500 ppm 2000 ppm 0

2500 ppm 50 0 200 400 600 800 Time After Shutdown (40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months s/division)

S1C23NetIsotopicDecayEOL.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 78 of 195 (Page 2 of 2)

Attachment 37 SURRY UNIT 1 - CYCLE 23 NET ISOTOPIC DECAY REACTIVITY AFTER SHUTDOWN FROM HFP Note: For EOL Burnup Range Exceeding 13500 MWD/MTU Excluding Xenon

-100 0 ppm

-90

-80 500 ppm

-70 Net Isotopic Decay Reactivity (5 pcm/division)

-60

-50 1000 ppm

-40

-30 1500 ppm

-20

-10 2000 ppm 0

10 20 2500 ppm 30 0 4 8 12 16 20 24 28 32 36 40 Time After Shutdown (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s/division)

S1C23NetIsotopicDecayEOL40hours.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 79 of 195 (Page 1 of 1)

Attachment 38 SURRY UNIT 1 - CYCLE 23 TOTAL ROD WORTH VS. BURNUP Note: For Use In Shutdown Margin Calculations Only 7900 7800 7700 7600 7500 Total Rod Worth (25 pcm/div) 7400 7300 7200 7100 7000 6900 6800 6700 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU / div)

S1C23TotalRodWorth.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 80 of 195 (Page 1 of 1)

Attachment 39 SURRY UNIT 1 - CYCLE 23 SHUTDOWN BANKS WORTH VS. BURNUP Note: For Use In Shutdown Margin Calculations Only 3600 3500 3400 Shutdown Banks Worth (10 pcm/div) 3300 3200 3100 3000 2900 2800 2700 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU / div)

S1C23ShutdownBanksWorth.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 81 of 195 (Page 1 of 1)

Attachment 40 SURRY UNIT 1 - CYCLE 23 STUCK ROD WORTH VS. BURNUP Note: For Use In Shutdown Margin Calculations Only 2400 2300 2200 2100 2000 1900 1800 Stuck Rod Worth (25 pcm/div) 1700 1600 1500 1400 1300 1200 1100 1000 900 800 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU / div)

S1C23StuckRodWorth.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 82 of 195 (Page 1 of 1)

Attachment 41 SURRY UNIT 1 - CYCLE 23 WORTH OF A SINGLE ROD BANK OUT OF SEQUENCE UP TO 18 STEPS Note: For Use In Shutdown Margin Calculations Only 275 250 225 200 Worth (5 pcm/div) 175 150 125 100 75 50 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU / div)

S1C23BankWorthOutOfSequence.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 83 of 195 (Page 1 of 1)

Attachment 42 SURRY UNIT 1 - CYCLE 23 REACTIVITY REDISTRIBUTION FACTOR VS. BURNUP Note: For Use In Shutdown Margin Calculations Only 250 200 Reactivity Redistribution Factor (10 pcm/div) 150 100 50 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU / div)

S1C23ReactRedistFactor.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 84 of 195 (Page 1 of 2)

Attachment 43 SURRY UNIT 1 - CYCLE 23 HOT TO COLD TEMPERATURE DEFECT VS. AVERAGE MODERATOR TEMPERATURE NOTE: For Boron Concentrations Greater Than 1800 PPM, The 1800 PPM Curve Should Be Used 6500 0 ppm 6000 5500 5000 400 ppm Temperature Defect (100 pcm/div) 4500 4000 3500 800 ppm 3000 2500 2000 1200 ppm 1500 1000 1500 ppm 500 1800 ppm 0

550 500 450 400 350 300 250 200 150 100 50 0 Moderator Temperature (10 deg-F/div) S1C23HotToColdDefect.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 85 of 195 (Page 2 of 2)

Attachment 43 SURRY UNIT 1 - CYCLE 23 HOT TO COLD TEMPERATURE DEFECT VS. AVERAGE MODERATOR TEMPERATURE NOTE: For Boron Concentrations Greater Than 1800 PPM, The 1800 PPM Curve Should Be Used 1200 0 ppm 1000 Temperature Defect (25 pcm/div) 400 ppm 800 800 ppm 600 1200 ppm 400 1500 ppm 200 1800 ppm 0

550 540 530 520 510 500 Moderator Temperature (1 deg-F/div) S1C23HotToColdDefect500.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 86 of 195 (Page 1 of 1)

Attachment 44 SURRY UNIT 1 - CYCLE 23 1.1 X Cb(N-1) VS. TEMPERATURE AT VARIOUS BURNUPS The 0-5000 MWD/MTU curve is bounding for all burnups through 5000 MWD/MTU. Interpolation is acceptable greater than 5000 MWD/MTU.

1600 1400 1200 0 - 5000 MWD/MTU 1000 Boron Concentration (25 ppm/div) 800 10000 MWD/MTU 600 15000 400 MWD/MTU 200 19900 MWD/MTU 0

200 250 300 350 400 450 500 550 0

Moderator Temperature (10 F/div)

S1C23CBn-1-11.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 87 of 195 (Page 1 of 1)

Attachment 45 SURRY UNIT 1 - CYCLE 23 1.5 X Cb(N-1) VS. TEMPERATURE AT VARIOUS BURNUPS The 0-5000 MWD/MTU curve is bounding for all burnups through 5000 MWD/MTU. Interpolation is acceptable greater than 5000 MWD/MTU.

2200 2000 1800 1600 0 - 5000 MWD/MTU 1400 Boron Concentration (25 ppm/div) 1200 10000 1000 MWD/MTU 800 600 15000 MWD/MTU 400 200 19900 MWD/MTU 0

200 250 300 350 400 450 500 550 0

Moderator Temperature (10 F/div)

S1C23CBn-1-15.pdf

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Attachment 46 SURRY UNIT 1 - CYCLE 23 ISOTHERMAL TEMPERATURE COEFFICIENT AT VARIOUS POWER LEVELS VS. BURNUP WITH ALL RODS OUT

-40 100% Power

-35 75% Power

-30 50% Power Isothermal Temperature Coefficient (1 pcm/oF/div)

-25 25% Power

-20 0% Power

-15

-10

-5 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU/div)

S1C23IsothermalTempCoeffs.pdf

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Attachment 47 SURRY UNIT 1 - CYCLE 23 MINIMUM BORON CONCENTRATION REQUIRED TO MEET 1770 PCM SHUTDOWN The 0-5000 MWD/MTU curve is bounding for all burnups through 5000 MWD/MTU. Interpolation is acceptable greater than 5000 MWD/MTU.

1800 1600 0 MWD/MTU 1400 to 5000 MWD/MTU BORON CONCENTRATION (25 ppm/div) 1200 9000 MWD/MTU 1000 800 14000 MWD/MTU 600 400 200 19900 MWD/MTU 0

0 50 100 150 200 250 300 350 400 450 500 550 o

CORE AVERAGE TEMPERATURE (10 F/div)

S1C23MinShutdownBoron.pdf

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Attachment 48 SURRY UNIT 1 - CYCLE 23 BORON COEFFICIENT VS. BURNUP FOR ZERO PERCENT POWER ECP Calculations Only

-10.00

-9.80

-9.60

-9.40

-9.20 Boron Coefficient (-0.05 pcm/ppm/div)

-9.00

-8.80

-8.60

-8.40

-8.20

-8.00

-7.80

-7.60

-7.40 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Cycle Burnup (500 MWD/MTU/div)

S1C23BoronCoeffECPOnly.pdf

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Attachment 49 SURRY UNIT 1 - CYCLE 23 CONSERVATIVE ZERO POWER MINIMUM INSERTION LIMIT SHUTDOWN MARGIN DATA 1700 1600 1500 1400 1300 1200 Critical Boron Concentration (20 ppm/div) 1100 1000 900 800 700 600 500 400 300 0 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 9,000 10,000 11,000 12,000 13,000 14,000 15,000 16,000 17,000 18,000 19,000 20,000 Burnup (200 MWD/MTU/div)

S1C23Dat23SDM.pdf

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 92 of 195 (Page 1 of 3)

Attachment 50 LOAD CHANGE CHARTS 400 300 TEMPERATURE DEGREES F 200 130 100 0

0 20 40 60 80 100 PERCENT RATED LOAD Graphics No: KM1114 FIRST - STAGE TEMPERATURE CHANGE ABOVE ZERO LOAD FIGURE 1

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Attachment 50 LOAD CHANGE CHARTS 400 0

1 00 TEMPERATURE CHANGE DEGREES F a city 200 0

p e Ca gu e 300 Fa ti Lin es g cl atin Cy er 3000 Op ded en m

om 5000 R ec um im ax 0 200 M 1000 ne tin g Li pera 50000 orm al O n d e d N mme 100 Reco 130 0

0 0.5 1 1.5 2 2.5 3 TIME TO CHANGE LOAD HOURS Graphics No: KM1115 LOAD CHANGE FIGURE 2

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Attachment 50 LOAD CHANGE CHARTS USE OF CHARTS All load changes are assumed to take place from initially steady-state rotor temperatures at the first stage zone, and to be accomplished at a uniform rate.

(a) Load-Change Charts, Figures 1 and 2:

EXAMPLE: Find the recommended time to change load from 25% to 100% of rated load.

PROCEDURE From Figure 1, find the change in first-stage temperature between 25% and 100%

load. Enter Figure 2 with this valuerature change and read the recommended time of 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months determined by the intersection with the 10,000 cycle guide line.

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Attachment 51 STARTUP AND LOADING TIMES 210 180 To t 150 al CUMULATIVE TIME MINUTES Ti m e

Fr om St 120 ar Increase tt o 97 Load Fu ll L oa d 90 60 Hold 33 5 Load 30 Above 300 F Apply 10 Accelerate Initial Load 35 To Sync Speed 0

0 100 200 300 400 INITIAL H.P. TURBINE FIRST-STAGE METAL TEMPERATURE DEGREES F Graphics No: KM1116 RECOMMENDED START-UP AND LOADING TIMES NUCLEAR STEAM SYSTEM UNITS FIGURE 3

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Attachment 51 STARTUP AND LOADING TIMES Figure 3 is designed to limit the maximum rotor stress during the entire program of acceleration, synchronizing, holding at minimum load, followed by increasing load to full capability. The recommended time per each phase of the program are determined by the measured first-stage temperature at the time of starting. The curves on the chart give the cumulative times for the sequence of events. The dotted lines illustrate the following example:

If the measured first stage metal temperature is 125 °F at starting:

1) Accelerate uniformly to synchronous speed in 35 minutes, as determined from the bottom curve.

2) Synchronize, apply 5% load and hold for 33 minutes, as determined from the difference between the bottom and middle curves. The total elapsed time from starting is 68 minutes, given by the middle curve.

3) Apply load at a uniform rate, reaching full load in 97 minutes, as determined by the difference between the middle and top curves. The total elapsed time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 45 minutes is given by the top curve.

4) After reaching full load, perform subsequent load changes in accordance with Figures 1 and 2.

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Attachment 52 CAPABILITY CURVES OVEREXCITED 800.00 75 PSIG PF 7 00 700.00 0. 0 PF 60 PSIG .80 F 600.00 0 5 0P 45 PSIG 0.8 00 PF 0.9 PF 500.00 15 0.9 400.00 300.00 PF 0.980 200.00 REACTIVE MVA 100.00 Megawatts 0.00 100.00 200.0 400.0 600.0 800.0 1000.0 1200.0 200.00 0.980 PF 300.00 0.95 UNDEREXCITED 400.00 0 PF 500.00 0.90 0 PF 0.8 50 600.00 0. PF

0. 80 Steady State Stability Limit Curve 70 0 1055MVA, 22KV, 0.9PF, 75PSIG 0 PF 700.00 PF 1055.0 MVA 0.900 PF 22.0 kV 27686 AMPERES 3 PHASE 60 HERTZ 1800 RPM 0.54 SCR COLD GAS 46 C Graphics No. CS4665

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Attachment 52 CAPABILITY CURVES 800.00 75 PSIG PF 0 In the Overexcited Region, the limiting 70 F 700.00 0. 0P factor is the Field Windings on the OVEREXCITED 60 PSIG 0 0.8 PF Generator Rotor due to the required 600.00 50 high current flow and subsequent I2R VARS 45 PSIG 0.8 00 PF Out 0.9 PF heating.

500.00 15 0.9 400.00 300.00 PF The (3) D-Shaped Curves represent 0.980 200.00 Hydrogen Pressure. Since the Generator cooling medium is REACTIVE MVA 100.00 Hydrogen, the higher the pressure the more load you can carry.

Megawatts 0.00 100.00 200.0 400.0 600.0 800.0 1000.0 1200.0 200.00 0.980 PF UNDEREXCITED 300.00 400.00 0.95 VARS 0 PF In 0.90 In the Underexcited Region, the 500.00 0 PF limiting factor is the heating of the 0.8 laminated iron at the ends of the 50 600.00 0. PF stator core.

0. 80 Steady State Stability Limit Curve 70 0 1055MVA, 22KV, 0.9PF, 75PSIG 0 PF 700.00 PF Graphics No. CS3324A The Generator Manufacturer, Westinghouse, provides the Main Generator Capability Curve. A few things to consider when using the Curves are as follows:

At unity Power Factor, O MVAR, you would directly read the Horizontal Axis for the MW value and plot the Operating point.

When you Boost or Buck the Grid, the Generator is carrying Inductive Load and this is indicated on the MVAR Meter as VARS OUT or VARS IN.

When the Generator Terminal Voltage is increased above the Grid Voltage, we are Boosting the Grid Voltage, we are Overexcited, producing VARS, have a lagging Power Factor, and indicate VARS OUT. To plot the Operating Point, you would again plot the MW value on the horizontal axis and also the MVAR value on the vertical axis. Since we were VARS OUT, Overexcited, we plot above the origin. This now defines the Operating Point.

When the Generator Terminal Voltage is decreased below the Grid Voltage, we are Bucking the Grid Voltage, we are Underexcited, absorbing VARS, have a leading Power Factor, and indicate VARS IN. To plot the Operating Point, you would again plot the MW value on the horizontal axis and also the MVAR value on the vertical axis. Since we were VARS IN, Underexcited, we plot below the origin. This now defines the Operating Point.

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Attachment 53 PRIMARY DRAINS TANK 4

HI-HI Level 3

HI Level THOUSAND GALLONS 0-90 Inches 2

5

-11

- BR LT 0-84 Inches 00 R-1

-B LT 1

50 gal / div LO Level 0

0 20 40 60 80 100 2% / div INDICATOR PERCENT Graphics No: KM1120 PRIMARY DRAINS TANK

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Attachment 54 BORON RECOVERY TANK 125 HI Level 100 THOUSAND GALLONS 75 50 25 2500 gal / div Low Level 0

0 20 40 60 80 100 2% / div INDICATOR PERCENT Graphics No: KM1121 BORON RECOVERY TANK

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Attachment 55 PRIMARY GRADE WATER TANK 200 HI Level THOUSAND GALLONS 100 Low Level 2500 gal / div 0

0 20 40 60 80 100 2% / div INDICATOR PERCENT Graphics No: KM1125 PRIMARY GRADE WATER TANK

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Attachment 56 300,000 GALLON CONDENSATE STORAGE TANK 300 HI Level THOUSAND GALLONS 200 Low Level 100 5000 gal / div 0

0 20 40 60 80 100 2% / div INDICATOR PERCENT Graphics No: KM1126

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Attachment 57 110,000 GALLON CONDENSATE STORAGE TANK 110,000 Gallon Condensate Storage Tank LI-CN-100 0-100%

Range 0-294 In. H2O Tank diameter 28 feet 120000 110000 100000 90000 80000 GALLONS 60000 40000 20000 2000 gal/div LO-LO Alarm at 20% LO Alarm at 92.7%

0 0 20 40 60 80 100 2% / div INDICATED LEVEL PERCENT Graphics No: KM1127

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Attachment 58 RWST UNIT 1 VOLUME VS WIDE RANGE LEVEL NOTE: Linear Region 3895 Gal/% to 92.1%

Volume at 0% = 13,800 gallons 400 350 300 VOLUME THOUSAND GALLONS 250 200 150 100 50 13,800 0

0 10 20 30 40 50 60 70 80 90 100 INDICATED LEVEL PERCENT Graphics No: KM1781 UNIT 1 VOLUME VS WIDE RANGE LEVEL

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Attachment 58 RWST UNIT 1 VOLUME VS NARROW RANGE LEVEL NARROW TOTAL NARROW RANGE VOLUME RANGE TOTAL VOLUME LEVEL % (GALLONS) LEVEL% (GALLONS) 90.0 364366 92.6 374493 90.1 364756 92.7 374882 90.2 365145 92.8 375271 90.3 365535 92.9 375659 90.4 365924 93.0 376047 90.5 366314 93.1 376435 90.6 366703 93.2 376822 90.7 367093 93.3 377209 90.8 367482 93.4 377595 90.9 367872 93.5 377981 91.0 368262 93.6 378366 91.1 368651 93.7 378750 91.2 369041 93.8 379134 91.3 369430 93.9 379516 91.4 369820 94.0 379898 91.5 370209 94.1 380280 91.6 370599 94.2 380660 91.7 370988 94.3 381039 91.8 371378 94.4 381418 91.9 371767 94.5 381795 92.0 372157 94.6 382171 END OF LINEAR 92.1 372546 94.7 382546 REGION 92.2 372936 94.8 382920 92.3 373325 94.9 383293 92.4 373715 95.0 383665 92.5 374104

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Attachment 58 RWST UNIT 1 VOLUME VS NARROW RANGE LEVEL NARROW TOTAL NARROW RANGE VOLUME RANGE TOTAL VOLUME LEVEL% (GALLONS) LEVEL% (GALLONS) 95.1 384035 97.6 392644 95.2 384404 97.7 392950 95.3 384771 97.8 393253 95.4 385137 97.9 393553 95.5 385501 98.0 393849 95.6 385864 98.1 394142 95.7 386225 98.2 394432 95.8 386585 98.3 394718 95.9 386943 98.4 395001 96.0 387299 98.5 395280 96.1 387653 98.6 395556 96.2 388005 98.7 395828 96.3 388356 98.8 396097 96.4 388704 98.9 396363 96.5 389050 99.0 396625 96.6 389394 99.1 396884 96.7 389734 99.2 397139 96.8 390071 99.3 397391 96.9 390404 99.4 397639 97.0 390734 99.5 397884 97.1 391061 99.6 398126 97.2 391384 99.7 398364 97.3 391704 99.8 398599 97.4 392021 99.9 398830 97.5 392334 100.0 399057

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Attachment 59 CHEMICAL ADDITION TANK 4500 Maximum = 4311 Gallons 4000 VOLUME GALLONS 3000 2000 1000 0

0 20 40 60 80 100 INDICATED LEVEL PERCENT Graphics No: KM1129C REFUELING WATER CHEMICAL ADDITION TANK - UNIT 1 NOTE: 100% indicates a fluid level of 430 inches above the level transmitter tap for 18% NaOH solution at 68°F.

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Attachment 59 CHEMICAL ADDITION TANK 92.0 91.5 4 0 F re =

pe ratu Tem 91.0 CAT Tank Level Indication ( )

F

= 68 ture p era 90.5 Tem F

90 re =

p e ratu 90.0 Tem 89.5 17.0 17.1 17.2 17.3 17.4 17.5 17.6 17.7 17.8 17.9 18.0 NaOH Concentration Graphics No. CS1243A MINIMUM T.S. LEVEL (3930 GALLONS) VS NaOH CONCENTRATION AT VARIOUS SOLUTION TEMPERATURES

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Attachment 60 BORIC ACID STORAGE TANKS 9000 For Boric Acid Concentration = 7.0 - 8.5%

4 Overflow HI 8000 100% Level 7299 Gallons 7000 3 LO Level 83%

Admin Level 1 TS Limit 79%

6000 6000 Gallons 2 LO-LO Admin 81%

Tank Volume Gallons 5000 Operational Limit

4000 3000 2000 1253 200 gal / div 1000 0

0 10 20 30 40 50 60 70 80 90 100 1% / div Indicated Level Percent Graphics No: KM1130 1 TS Limit (6000 gallons) 79%

2 LO-LO Admin Operational Limit 81%

3 LO Level Admin Limit 83%

Overflow High Level

81% ~ TS Limit with Gauge 4 100% Inaccuracy Minimum Operational Limit

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Attachment 61 PRESSURIZER RELIEF TANK 10000 9000 8000 EQUIVALENT 100 F LIQUID VOLUME GALLONS 7000 6000 5000 4000 3000 2000 1000 0

0 10 20 30 40 50 60 70 80 90 100 INDICATED LEVEL PERCENT Graphics No: KM1135 PRESSURIZER RELIEF TANK

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 59.0 48801.12 61.1 50730.20 59.1 48893.33 61.2 50821.65 59.2 48985.51 61.3 50913.07 59.3 49077.65 61.4 51004.44 59.4 49169.76 61.5 51095.77 59.5 49261.83 61.6 51187.06 59.6 49353.87 61.7 51278.31 59.7 49445.88 61.8 51369.51 59.8 49537.86 61.9 51460.68 59.9 49629.79 62.0 51551.80 60.0 49721.70 62.1 51642.88 60.1 49813.56 62.2 51733.91 60.2 49905.40 62.3 51824.91 60.3 49997.19 62.4 51915.85 60.4 50088.95 62.5 52006.76 60.5 50180.67 62.6 52097.62 60.6 50272.36 62.7 52188.43 60.7 50364.00 62.8 52279.20 60.8 50455.61 62.9 52369.92 60.9 50547.18 63.0 52460.60 61.0 50638.71 63.1 52551.23

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 63.2 52641.81 65.3 54532.53 63.3 52732.34 65.4 54621.98 63.4 52822.83 65.5 54711.38 63.5 52913.27 65.6 54800.72 63.6 53003.66 65.7 54890.01 63.7 53094.00 65.8 54979.24 63.8 53184.30 65.9 55068.41 63.9 53274.54 66.0 55157.53 64.0 53364.73 66.1 55246.58 64.1 53454.88 66.2 55335.58 64.2 53544.97 66.3 55424.52 64.3 53635.01 66.4 55513.40 64.4 53725.00 66.5 55602.22 64.5 53814.94 66.6 55690.99 64.6 53904.82 66.7 55779.69 64.7 53994.66 66.8 55868.33 64.8 54084.44 66.9 55956.91 64.9 54174.16 67.0 56045.43 65.0 54263.84 67.1 56133.88 65.1 54353.45 67.2 56222.28 65.2 54443.02 67.3 56310.61

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 67.4 56398.88 69.5 58237.31 67.5 56487.09 69.6 58324.09 67.6 56575.23 69.7 58410.81 67.7 56663.31 69.8 58497.45 67.8 56751.32 69.9 58584.02 67.9 56839.27 70.0 58670.51 68.0 56927.15 70.1 58756.94 68.1 57014.97 70.2 58843.28 68.2 57102.72 70.3 58929.56 68.3 57190.41 70.4 59015.76 68.4 57278.03 70.5 59101.88 68.5 57368.58 70.6 59187.93 68.6 57453.06 70.7 59273.90 68.7 57540.48 70.8 59359.80 68.8 57627.82 70.9 59445.62 68.9 57715.10 71.0 59531.36 69.0 57802.31 71.1 59617.02 69.1 57889.45 71.2 59702.61 69.2 57976.52 71.3 59788.11 69.3 58063.52 71.4 59873.54 69.4 58150.45 71.5 59958.89

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 71.6 60044.16 73.7 61815.69 71.7 60129.35 73.8 61899.10 71.8 60214.46 73.9 61982.42 71.9 60299.49 74.0 62065.66 72.0 60384.44 74.1 62148.80 72.1 60469.30 74.2 62231.85 72.2 60554.09 74.3 62314.81 72.3 60638.79 74.4 62397.68 72.4 60723.40 74.5 62480.46 72.5 60807.94 74.6 62563.14 72.6 60892.39 74.7 62645.74 72.7 60976.76 74.8 62728.23 72.8 61061.04 74.9 62810.64 72.9 61145.23 75.0 62892.95 73.0 61229.34 75.1 62975.17 73.1 61313.37 75.2 63057.29 73.2 61397.31 75.3 63139.32 73.3 61481.16 75.4 63221.25 73.4 61564.92 75.5 63303.08 73.5 61648.60 75.6 63384.82 73.6 +1732.19 75.7 63466.46

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 75.8 63548.00 77.9 65237.05 75.9 63629.44 78.0 65316.33 76.0 63710.79 78.1 65395.50 76.1 63792.04 78.2 65474.56 76.2 63873.19 78.3 65553.52 76.3 63954.23 78.4 65632.36 76.4 64035.18 78.5 65711.10 76.5 64116.03 78.6 65789.72 76.6 64196.77 78.7 65868.23 76.7 64277.42 78.8 65946.64 76.8 64357.96 78.9 66024.93 76.9 64438.40 79.0 66103.10 77.0 64518.73 79.1 66181.17 77.1 64598.97 79.2 66259.12 77.2 64679.09 79.3 66336.96 77.3 64759.12 79.4 66414.68 77.4 64839.04 79.5 66492.29 77.5 64918.85 79.6 66569.78 77.6 64998.56 79.7 66647.16 77.7 65078.16 79.8 66724.42 77.8 65157.66 79.9 66801.56

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Attachment 62 PRESSURIZER RELIEF TANK MASS VERSUS INDICATED LEVEL Indicated Level PRT Water Mass Indicated Level PRT Water Mass (Percent) (lbm) (Percent) (lbm) 80.0 66878.59 82.1 68468.17 80.1 66955.50 82.2 68542.49 80.2 67032.29 82.3 68616.68 80.3 67108.96 82.4 68690.73 80.4 67185.51 82.5 68764.66 80.5 67261.95 82.6 68838.46 80.6 67338.26 82.7 68912.13 80.7 67414.45 82.8 68985.67 80.8 67490.52 82.9 69059.07 80.9 67566.47 83.0 69132.34 81.0 67642.30 81.1 67718.00 81.2 67793.58 81.3 67869.04 81.4 67944.37 81.5 68019.58 81.6 68094.66 81.7 68169.61 81.8 68244.44 81.9 68319.15 82.0 68393.72

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 0.0 223.19 0.5 247.91 1.0 273.50 1.5 299.93 2.0 327.17 2.5 355.20 3.0 383.98 3.5 413.51 4.0 443.76 4.5 474.71 5.0 506.34 5.5 538.64 6.0 571.58 6.5 605.16 7.0 639.36 7.5 674.17 8.0 709.56 8.5 745.53 9.0 782.06 9.5 819.15

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 10.0 856.78 10.5 894.93 11.0 933.60 11.5 972.78 12.0 1012.45 12.5 1052.61 13.0 1093.25 13.5 1134.35 14.0 1175.91 14.5 1217.91 15.0 1260.35 15.5 1303.22 16.0 1346.52 16.5 1390.22 17.0 1434.32 17.5 1478.82 18.0 1523.71 18.5 1568.98 19.0 1614.62 19.5 1660.62 20.0 1706.97 20.5 1753.68

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 21.0 1800.0 21.5 1848.11 22.0 1895.81 22.5 1943.84 23.0 1992.18 23.5 2040.83 24.0 2089.77 24.5 2139. 01 25.0 2188.53 25.5 2238.33 26.0 2288.41 26.5 2338.75 27.0 2389.35 27.5 2440.20 28.0 2491.30 28.5 2542.65 29.0 2594.22 29.5 2646.03 30.0 2698.06 30.5 2750.30 31.0 2802.76 31.5 2855.42

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 32.0 2908.28 32.5 2961.34 33.0 3014.58 33.5 3068.00 34.0 3121.60 34.5 3175.37 35.0 3229.31 35.5 3283.40 36.0 3337.65 36.5 3392.05 370 3446.58 37.5 3501.26 38.0 3556.06 38.5 3611.00 39.0 3666.05 39.5 3721.22 40.0 3776.49 40.5 3831.87 41.0 3887.35 41.5 3942.93 42.0 3998.59 42.5 4054.34

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 43.0 4110.16 43.5 4166.05 44.0 4222.01 44.5 4278.04 45.0 4334.12 45.5 4390.25 46.0 4446.42 46.5 4502.64 47.0 4558.89 47.5 4615.18 48.0 4671.49 48.5 4727.81 49.0 4784.16 49.5 4840.51 50.0 4896.86 50.5 4953.22 51.0 5009.57 51.5 5065.90 52.0 5122.22 52.5 5178.52 53.0 5234.79 53.5 5291.03

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 54.0 5347.23 54.5 5403.39 55.0 5459.50 55.5 5515.55 56.0 5571.55 56.5 5627.49 57.0 5683.35 57.5 5739.14 58.0 5794.85 58.5 5850.48 59.0 5906.01 59.5 5961.45 60.0 6016.79 60.5 6072.02 61.0 6127.14 61.5 6182.14 62.0 6237.02 62.5 6291.77 63.0 6346.38 63.5 6400.86 64.0 6455.19 64.5 6509.38

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 65.0 6563.40 65.5 6617.27 66.0 6670.97 66.5 6724.49 67.0 6777.84 67.5 6831.00 68.0 6883.97 68.5 6936.75 69.0 6989.33 69.5 7041.69 70.0 7093.85 70.5 7145.78 71.0 7197.49 71.5 7248.97 72.0 7300.21 72.5 7351.21 73.0 7401.95 73.5 7452.44 74.0 7502.67 74.5 7552.63 75.0 7602.31 75.5 7651.71 76.0 7700.83 76.5 7749.64 77.0 7798.16

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 77.5 7846. 37 78.0 7894.26 78.5 7941.83 79.0 7989.07 79.5 8035.97 80.0 8082.53 80.5 8128.73 81.0 8220.06 82.0 8265.16 82.5 8309.89 83.0 8354.22 83.5 8398.16 84.0 8441.68 84.5 8484.80 85.0 8527.49 85.5 8569.74 86.0 8611.56 86.5 8652.92 87.0 8693.82 87.5 8734.26 88.0 8774.21 88.5 8813.67 89.0 8852.64 89.5 8891.09 90.0 8929.02

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Attachment 63 PRESSURIZER RELIEF TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRAN REF LEG CAL TEMP 70.0 DEGREES F DENSITY 62.305 LBM/FT3 ACTUAL TANK WATER TEMP 85.0 DEGREES F DENSITY 62.172 LBM/FT3 INDICATED LEVEL EQUIVALENT 110 °F (PERCENT) VOLUME (GALLONS) 90.5 8966.42 91.0 9003.27 91.5 9039.56 92.0 9075.29 92.5 9110.43 93.0 9144.98 93.5 9178.92 94.0 9212.23 94.5 9244.90 95.0 9276.91 95.5 9308.25 96.0 9338.91 96.5 9368.85 97.0 9398.06 97.5 9426.53 98.0 9454.22 98.5 9481.12 99.0 9507.19 99.5 9532.42 NOTE: The transmitter will no longer increase with increase level after 99.5%

indication.

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Attachment 64 SAFETY INJECTION ACCUMULATOR LEVEL NOTE: For Operating Limits refer to 1-PT-36.

1100 SAFETY INJECTION ACCUMULATOR VOLUME CUBIC FEET 1050 1000 950 900 5 cubic feet / div 850 800 0 10 20 30 40 50 60 70 80 90 100 2% / div INDICATED LEVEL PERCENT Graphics No: KM1136B SAFETY INJECTION ACCUMULATOR LEVEL

Reference:

1) Surry Power Station SCR No. 88-02, Safety Injection Accumulator Levels Surry 1 & 2

2) Calculation EE-0376 dated 5/9/91

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Attachment 65 PRIMARY DRAIN TRANSFER TANK 700 600 EQUIVALENT 110 F LIQUID VOLUME GALLONS 500 400 300 200 100 0

0 10 20 30 40 50 60 70 80 90 100 INDICATED LEVEL PERCENT Graphics No: KM1138 PRIMARY DRAIN TRANSFER TANK

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 0.094 0.0 3.63 3.64 0.113 0.5 4.82 4.83 0.133 1.0 6.13 6.14 0.152 1.5 7.54 7.55 0.171 2.0 9.04 9.06 0.191 2.5 10.64 10.67 0.210 3.0 12.33 12.36 0.229 3.5 14.10 14.13 0.249 4.0 15.95 15.98 0.268 4.5 17.87 17.91 0.287 5.0 19.87 19.91 0.307 5.5 21.94 21.98 0.326 6.0 24.07 24.13 0.345 7.0 28.54 28.60 0.384 7.5 30.87 30.94 0.403 8.0 33.26 33.33 0.423 8.5 35.71 35.78 0.461 9.5 40.77 40.86 0.480 10.0 43.38 43.48 0.500 10.5 46.05 46.15 0.519 11.0 48.77 48.87 0.538 11.5 51.53 51.65 0.558 12.0 54.35 54.47

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 0.577 12.5 57.21 57.34 0.596 13.0 60.12 60.25 0.616 13.5 63.08 63.21 0.635 14.0 66.08 66.22 0.654 14.5 69.12 69.27 0.674 15.0 72.20 72.36 0.712 16.0 78.50 78.67 0.732 16.5 81.70 81.88 0.751 17.0 84.95 85.13 0.770 17.5 88.23 88.42 0.790 18.0 91.55 91.75 0.809 18.5 94.91 95.11 0.828 19.0 98.30 98.51 0.848 19.5 101.72 101.94 0.867 20.0 105.18 105.41 0.886 20.5 108.67 108.91 0.906 21.0 112.20 112.44 0.925 21.5 115.75 116.00 0.944 22.0 119.34 119.60 0.964 22.5 122.96 123.22 0.983 23.0 126.60 126.88 1.002 23.5 130.28 130.56 1.022 24.0 133.98 134.27

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 1.041 24.5 137.70 138.00 1.060 25.0 141.46 141.76 1.080 25.5 145.24 145.55 1.099 26.0 149.04 149.36 1.118 26.5 152.87 153.20 1.138 27.0 156.72 157.06 1.157 27.5 160.60 160.94 1.176 28.0 164.49 164.85 1.195 28.5 168.41 168.77 1.215 29.0 172.35 172.72 1.234 29.5 176.31 176.69 1.253 30.0 180.29 180.68 1.273 30.5 184.28 184.68 1.292 31.0 188.30 188.71 1.311 31.5 192.34 192.75 1.331 32.0 196.39 196.81 1.350 32.5 200.47 200.90 1.369 33.0 204.56 205.01 1.389 33.5 208.68 209.13 1.408 34.0 212.81 213.27 1.427 34.5 216.96 217.43 1.447 35.0 221.13 221.61 1.466 35.5 225.31 225.80

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 1.485 36.0 229.50 230.00 1.505 36.5 233.71 234.22 1.524 37.0 237.94 238.45 1.543 37.5 242.17 242.70 1.563 38.0 246.42 246.95 1.582 38.5 250.68 251.22 1.601 39.0 254.95 255.50 1.621 39.5 259.23 259.79 1.640 40.0 263.52 264.09 1.659 40.5 267.82 268.40 1.679 41.0 272.13 272.72 1.698 41.5 276.45 277.05 1.717 42.0 280.77 281.38 1.737 42.5 285.11 285.72 1.756 43.0 289.45 290.07 1.775 43.5 293.79 294.43 1.795 44.0 298.14 298.79 1.814 44.5 302.50 303.16 1.833 45.0 306.86 307.53 1.853 45.5 311.23 311.90 1.872 46.0 315.60 316.28 1.891 46.5 319.97 320.66 1.910 47.0 324.35 325.05

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 1.930 47.5 328.73 329.44 1.949 48.0 333.11 333.83 1.968 48.5 337.49 338.22 1.988 49.0 341.87 342.61 2.007 49.5 346.25 347.00 2.026 50.0 350.63 351.39 2.046 50.5 355.02 355.78 2.065 51.0 359.40 360.17 2.084 51.5 363.77 364.56 2.104 52.0 368.15 368.95 2.123 52.5 372.53 373.33 2.142 53.0 376.90 377.71 2.162 53.5 381.26 382.09 2.181 54.0 385.63 386.46 2.200 54.5 389.98 390.83 2.220 55.0 394.34 395.19 2.239 55.5 398.69 399.55 2.258 56.0 403.03 403.90 2.278 56.5 407.36 408.24 2.297 57.0 411.69 412.58 2.316 57.5 416.01 416.91 2.336 58.0 420.32 421.23 2.355 58.5 424.62 425.54

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 2.374 59.0 428.92 429.84 2.394 59.5 433.20 434.14 2.413 60.0 437.47 438.42 2.432 60.5 441.74 442.69 2.452 61.0 445.99 446.95 2.471 61.5 450.23 451.20 2.490 62.0 454.45 455.44 2.510 62.5 458.67 459.66 2.529 63.0 462.86 463.87 2.548 63.5 467.05 468.06 2.568 64.0 471.22 472.24 2.587 64.5 475.37 476.40 2.606 65.0 479.51 480.55 2.625 65.5 483.63 484.68 2.645 66.0 487.73 488.79 2.664 66.5 491.82 492.88 2.683 67.0 495.87 496.95 2.703 67.5 499.91 500.99 2.722 68.0 503.93 505.02 2.741 68.5 507.94 509.04 2.761 69.0 511.92 513.03 2.780 69.5 515.88 517.00 2.799 70.0 519.83 520.95

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 2.819 71.0 527.65 528.80 2.857 71.5 531.53 532.68 2.877 72.0 535.39 536.55 2.896 72.5 539.23 540.39 2.915 73.0 543.04 544.21 2.935 73.5 546.82 548.01 2.954 74.0 550.58 551.78 2.973 74.5 554.32 555.52 2.993 75.0 558.03 559.23 3.012 75.5 561.71 562.92 3.031 76.0 565.36 566.58 3.051 76.5 568.98 570.22 3.070 77.0 572.58 573.82 3.089 77.5 576.14 577.39 3.109 78.0 579.68 580.93 3.128 78.5 583.18 584.44 3.147 79.0 585.64 587.91 3.167 79.5 590.08 591.36 3.186 80.0 593.48 594.76 3.205 80.5 596.84 598.14 3.225 81.0 600.17 601.47 3.244 81.5 603.47 604.77

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 3.263 82.0 606.72 608.03 3.283 82.5 609.94 611.26 3.302 83.0 613.11 614.44 3.321 83.5 616.25 617.58 3.341 84.0 619.35 620.69 3.360 84.5 622.40 623.75 3.379 85.0 625.41 626.77 3.398 85.5 628.38 629.74 3.418 86.0 631.30 632.67 3.437 86.5 634.17 635.55 3.456 87.0 637.00 638.38 3.476 87.5 639.78 641.17 3.495 88.0 642.51 643.90 3.514 88.5 645.19 646.59 3.534 89.0 647.82 649.22 3.553 89.5 650.39 651.80 3.572 90.0 652.91 654.33 3.592 90.5 655.37 656.79 3.611 91.0 657.78 659.20 3.630 91.5 660.12 661.55 3.650 92.0 662.41 663.84 3.669 92.5 664.63 666.07 3.688 93.0 666.78 668.22

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Attachment 66 PRIMARY DRAIN TRANSFER TANK VOLUME VERSUS INDICATED LEVEL LEVEL TRANSMITTER REFERENCE LEG TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/^TANK LEVEL COLUMN TEMP 100.0 DEGREES F, DENSITY 61.996 LBM/FT3 WATER ACTUAL TANK EQUIVALENT HEIGHT INDICATED LEVEL VOLUME 100°F VOLUME (FEET) (PERCENT) (GALLONS) (GALLONS) 3.708 93.5 668.87 670.32 3.727 94.0 670.88 672.34 3.746 94.5 672.83 674.29 3.766 95.0 674.70 676.16 3.785 95.5 676.49 677.95 3.804 96.0 678.20 679.66 3.824 96.5 679.82 681.29 3.843 97.0 681.35 682.82 3.862 97.5 682.79 684.26 3.882 98.0 684.12 685.60 3.901 98.5 685.34 686.83 3.920 99.0 686.45 687.93 3.940 99.5 687.42 688.91 3.959 100.0 688.24 689.73

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Attachment 67 LIQUID WASTE TANK 260 HI-HI Level Alarm 12' 5 1/4" 240 HI Level Alarm 12' 3" 220 200 180 TANK VOLUME CUBIC FEET 160 140 120 23.15 Cubic Feet / Foot of Tank Level 100 80 60 5 cubic feet / div 40 Low Level Alarm 3' 20 0

0 1 2 3 4 5 6 7 8 9 10 11 12 13 0.2 feet / div TANK LEVEL FEET Graphics No: KM1140 1-LW-TK-14, 1-LW-TK-15

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Attachment 68 CONTAINMENT SUMP VOLUME 60 55 50 45 40 SUMP VOLUME GALLONS 35 30 25 20 15 10 5

0 100 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 LI-DA-100 INDICATION PERCENT Graphics No: KM1142A CONTAINMENT SUMP VOLUME UNIT 1

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Attachment 68 CONTAINMENT SUMP VOLUME Level (%) Gallons Level (%) Gallons Level (%) Gallons Level (%) Gallons 0 19.63 17.5 25.22125 35 30.8125 52.5 36.40375 0.5 19.78975 18 25.381 35.5 30.97225 53 36.5635 1 19.9495 18.5 25.54075 36 31.132 53.5 36.72325 1.5 20.10925 19 25.7005 36.5 31.29175 54 36.883 2 20.269 19.5 25.86025 37 31.4515 54.5 37.04275 2.5 20.42875 20 26.02 37.5 31.61125 55 37.2025 3 20.5885 20.5 26.17975 38 31.771 55.5 37.36225 3.5 20.74825 21 26.3395 38.5 31.93075 56 37.522 4 20.908 21.5 26.49925 39 32.0905 56.5 37.68175 4.5 21.06775 22 26.659 39.5 32.25025 57 37.8415 5 21.2275 22.5 26.81875 40 32.41 57.5 38.00125 5.5 21.38725 23 26.9785 40.5 32.56975 58 38.161 6 21.547 23.5 27.13825 41 32.7295 58.5 38.32075 6.5 21.70675 24 27.298 41.5 32.88925 59 38.4805 7 21.8665 24.5 27.45775 42 33.049 59.5 38.64025 7.5 22.02625 25 27.6175 42.5 33.20875 60 38.8 8 22.186 25.5 27.77725 43 33.3685 60.5 38.95975 8.5 22.34575 26 27.937 43.5 33.52825 61 39.1195 9 22.5055 26.5 28.09675 44 33.688 61.5 39.27925 9.5 22.66525 27 28.2565 44.5 33.84775 62 39.439 10 22.825 27.5 28.41625 45 34.0075 62.5 39.59875 10.5 22.98475 28 28.576 45.5 34.16725 63 39.7585 11 23.1445 28.5 28.73575 46 34.327 63.5 39.91825 11.5 23.30425 29 28.8955 46.5 34.48675 64 40.078 12 23.464 29.5 29.05525 47 34.6465 64.5 40.23775 12.5 23.62375 30 29.215 47.5 34.80625 65 40.3975 13 23.7835 30.5 29.37475 48 34.966 65.5 40.55725 13.5 23.94325 31 29.5345 48.5 35.12575 66 40.717 14 24.103 31.5 29.69425 49 35.2855 66.5 40.87675 14.5 24.26275 32 29.854 49.5 35.44525 67 41.0365 15 24.4225 32.5 30.01375 50 35.605 67.5 41.19625 15.5 24.58225 33 30.1735 50.5 35.76475 68 41.356 16 24.742 33.5 30.33325 51 35.9245 68.5 41.51575 16.5 24.90175 34 30.493 51.5 36.08425 69 41.6755 17 25.0615 34.5 30.65275 52 36.244 69.5 41.83525

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Attachment 68 CONTAINMENT SUMP VOLUME Level (%) Gallons Level (%) Gallons Level (%) Gallons Level (%) Gallons 70 41.995 79 44.8705 88 47.746 97 50.6215 70.5 42.15475 79.5 45.03025 88.5 47.90575 97.5 50.78125 71 42.3145 80 45.19 89 48.0655 98 50.941 71.5 42.47425 80.5 45.34975 89.5 48.22525 98.5 51.10075 72 42.634 81 45.5095 90 48.385 99 51.2605 72.5 42.79375 81.5 45.66925 90.5 48.54475 99.5 51.42025 73 42.9535 82 45.829 91 48.7045 100 51.58 73.5 43.11325 82.5 45.98875 91.5 48.86425 74 43.273 83 46.1485 92 49.024 74.5 43.43275 83.5 46.30825 92.5 49.18375 75 43.5925 84 46.468 93 49.3435 75.5 43.75225 84.5 46.62775 93.5 49.50325 76 43.912 85 46.7875 94 49.663 76.5 44.07175 85.5 46.94725 94.5 49.82275 77 44.2315 86 47.107 95 49.9825 77.5 44.39125 86.5 47.26675 95.5 50.14225 78 44.551 87 47.4265 96 50.302 78.5 44.71075 87.5 47.58625 96.5 50.46175

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Attachment 69 CONTAINMENT SUMP VOLUME - NARROW RANGE LEVEL 50000 44000 38000 32000 26000 20000 SUMP VOLUME GALLONS 14000 8000 2000 2000 1800 1600 1400 1200 1000 800 600 400 200 0

0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 NARROW RANGE LEVEL (LI-DA-110A & B) INCHES Graphics No: KM1143A CONTAINMENT SUMP VOLUME VS NARROW RANGE LEVEL (LI-DA-110A & B)

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Attachment 70 CONTAINMENT WATER VOLUME VS. WATER LEVEL ELEVATION 700 600 Containment Water Volume, Thousand Gallons 500 400 300 200 100 0

0 2 4 6 8 10 Containment Water Elevation Level, Feet Graphics No. CS5426 CONTAINMENT WATER VOLUME VS WATER LEVEL ELEVATION

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Attachment 70 CONTAINMENT WATER VOLUME VS. WATER LEVEL ELEVATION Water Volume Level (Feet) (Gallons) x 1000 0 0 0.114 0.51 0.18 0.93 0.27 1.36 0.353 1.78 0.52 2.69 0.937 4.91 1.353 7.21 1.69 9.65 1.937 18.09 2.468 62.42 2.937 101.35 3.937 184.35 4.937 267.36 5.385 311.43 5.937 350.63 6.937 435.63 7.645 495.81 9.437 642.88

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 144 of 195 (Page 1 of 3)

Attachment 71 COMPONENT COOLING SURGE TANK FLUID TOTAL FLUID TOTAL HEIGHT VOLUME HEIGHT VOLUME PERCENT GALLONS PERCENT GALLONS 1 4 33 791 2 12 34 826 3 21 35 860 4 33 36 895 5 47 37 930 6 62 38 966 7 78 39 1001 8 96 40 1037 9 114 41 1073 10 134 42 1109 11 155 43 1145 12 177 44 1182 13 200 45 1219 14 223 46 1255 15 248 47 1291 16 273 48 1329 17 299 49 1365 18 325 50 1403 19 352 51 1439 20 380 52 1476 21 409 53 1513 22 438 54 1549 23 468 55 1586 24 498 56 1623 25 529 57 1659 26 560 58 1695 27 592 59 1731 28 624 60 1767 29 657 61 1803 30 690 62 1839 31 723 63 1874 32 757 64 1910

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 145 of 195 (Page 2 of 3)

Attachment 71 COMPONENT COOLING SURGE TANK FLUID TOTAL FLUID TOTAL HEIGHT VOLUME HEIGHT VOLUME PERCENT GALLONS PERCENT GALLONS 65 1945 83 2506 66 1979 84 2531 67 2014 85 2557 68 2047 86 2581 69 2082 87 2605 70 2115 88 2628 71 2148 89 2650 72 2180 90 2670 73 2212 91 2690 74 2244 92 2709 75 2275 93 2726 76 2306 94 2743 77 2336 95 2757 78 2366 96 2771 79 2395 97 2783 80 2424 98 2792 81 2452 99 2800 82 2479 100 2804

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 146 of 195 (Page 3 of 3)

Attachment 71 COMPONENT COOLING SURGE TANK 3

2.8 2.6 2.4 2.2 2

GALLONS (THOUSANDS) 1.8 1.6 1.4 1.2 1

0.8 0.6 0.4 0.2 0

0 20 40 60 80 100 CC WATER LEVEL (% LEVEL)

Graphics No: KM1733 1-CC-TK-1 VOLUME VS. WATER LEVEL

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 147 of 195 (Page 1 of 1)

Attachment 72 ENTHALPY STEAM TABLE (100% QUALITY)

ABSOL PRSR (PSIA) 0 1 2 3 4 5 6 7 8 9 750 1200.69 1200.66 1200.64 1200.61 1200.59 1200.56 1200.54 1200.51 1200.49 1200.46 760 1200.44 1200.41 1200.39 1200.36 1200.34 1200.31 1200.29 1200.26 1200.23 1200.21 770 1200.18 1200.16 1200.13 1200.11 1200.08 1200.05 1200.03 1200.00 1199.98 1199.95 780 1199.92 1199.90 1199.87 1199.84 1199.82 1199.79 1199.76 1199.74 1199.71 1199.68 790 1199.66 1199.63 1199.60 1199.58 1199.55 1199.52 1199.50 1199.47 1199.44 1199.41 800 1199.39 1199.36 1199.33 1199.30 1199.28 1199.25 1199.22 1199.19 1199.17 1199.14 810 1199.11 1199.08 1199.05 1199.03 1199.00 1198.97 1198.94 1198.91 1198.89 1198.86 820 1198.83 1198.80 1198.77 1198.74 1198.71 1198.69 1198.66 1198.63 1198.60 1198.57 830 1198.54 1198.51 1198.48 1198.45 1198.43 1198.40 1198.37 1198.34 1198.31 1198.28 840 1198.25 1198.22 1198.19 1198.16 1198.13 1198.10 1198.07 1198.04 1198.01 1197.98 850 1197.95 1197.92 1197.89 1197.86 1197.83 1197.80 1197.77 1197.74 1197.71 1197.68 860 1197.65 1197.62 1197.59 1197.56 1197.53 1197.50 1197.47 1197.44 1197.41 1197.37 870 1197.34 1197.31 1197.28 1197.25 1197.22 1197.19 1197.16 1197.13 1197.10 1197.06 880 1197.03 1197.00 1196.97 1196.94 1196.91 1196.87 1196.84 1196.81 1196.78 1196.75 890 1196.72 1196.68 1196.65 1196.62 1196.59 1196.56 1196.52 1196.49 1196.46 1196.43 900 1196.39 1196.36 1196.33 1196.30 1196.26 1196.23 1196.20 1196.17 1196.13 1196.10 910 1196.07 1196.04 1196.00 1195.97 1195.94 1195.90 1195.87 1195.84 1195.80 1195.77 920 1195.74 1195.71 1195.67 1195.64 1195.61 1195.57 1195.54 1195.50 1195.47 1195.44 930 1195.40 1195.37 1195.34 1195.30 1195.27 1195.23 1195.20 1195.17 1195.13 1195.10 940 1195.06 1195.03 1195.00 1194.96 1194.93 1194.89 1194.86 1194.82 1194.79 1194.75 950 1194.72 1194.69 1194.65 1194.62 1194.58 1194.55 1194.51 1194.48 1194.44 1194.41 960 1194.37 1194.34 1194.30 1194.27 1194.23 1194.20 1194.16 1194.13 1194.09 1194.05 970 1194.02 1193.98 1193.95 1193.91 1193.88 1193.84 1193.81 1193.77 1193.73 1193.70 980 1193.66 1193.63 1193.59 1193.55 1193.52 1193.48 1193.45 1193.41 1193.37 1193.34 990 1193.30 1193.27 1193.23 1193.19 1193.16 1193.12 1193.08 1193.05 1193.01 1192.97 1000 1192.94 1192.90 1192.86 1192.83 1192.79 1192.75 1192.71 1192.68 1192.64 1192.60

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 148 of 195 (Page 1 of 1)

Attachment 73 ENTHALPY SATURATED LIQUID TABLE ABSOL PRSR (PSIA) 0 1 2 3 4 5 6 7 8 9 750 500.89 501.07 501.26 501.44 501.62 501.80 501.98 502.16 502.34 502.52 760 502.70 502.88 503.06 503.24 503.42 503.60 503.78 503.96 504.14 504.32 770 504.50 504.68 504.86 505.04 505.22 505.40 505.57 505.75 505.93 506.11 780 506.29 506.46 506.64 506.82 506.99 507.17 507.35 507.53 507.70 507.88 790 508.05 508.23 508.41 508.58 508.76 508.93 509.11 509.29 509.46 509.64 800 509.81 509.99 510.16 510.34 510.51 510.68 510.86 511.03 511.21 511.38 810 511.55 511.73 511.90 512.08 512.25 512.42 512.59 512.77 512.94 513.11 820 513.29 513.46 513.63 513.80 513.97 514.15 514.32 514.49 514.66 514.83 830 515.00 515.17 515.35 515.52 515.69 515.86 516.03 516.20 516.37 516.54 840 516.71 516.88 517.05 517.22 517.39 517.56 517.73 517.90 518.07 518.23 850 518.40 518.57 518.74 518.91 519.08 519.25 519.41 519.58 519.75 519.92 860 520.09 520.25 520.42 520.59 520.76 520.92 521.09 521.26 521.42 521.59 870 521.76 521.92 522.09 522.26 522.42 522.59 522.75 522.92 523.09 523.25 880 523.42 523.58 523.75 523.91 524.08 524.24 524.41 524.57 524.74 524.90 890 525.07 525.23 525.39 525.56 525.72 525.89 526.05 526.21 526.38 526.54 900 526.70 526.87 527.03 527.19 527.36 527.52 527.68 527.84 528.01 528.17 910 528.33 528.49 528.66 528.82 528.98 529.14 529.30 529.47 529.63 529.79 920 529.95 530.11 530.27 530.43 530.59 530.76 530.92 531.08 531.24 531.40 930 531.56 531.72 531.88 532.04 532.20 532.36 532.52 532.68 532.84 533.00 940 533.16 533.32 533.47 533.63 533.79 533.95 534.11 534.27 534.43 534.59 950 534.74 534.90 535.06 535.22 535.38 535.54 535.69 535.85 536.01 536.17 960 536.32 536.48 536.64 536.80 536.95 537.11 537.27 537.42 537.58 537.74 970 537.89 538.05 538.21 538.36 538.52 538.68 538.83 538.99 539.14 539.30 980 539.45 539.61 539.77 539.92 540.08 540.23 540.39 540.54 540.70 540.85 990 541.01 541.16 541.32 541.47 541.63 541.78 541.93 542.09 542.24 542.40 1000 542.55 542.70 542.86 543.01 543.17 543.32 543.47 543.63 543.78 543.93

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 149 of 195 (Page 1 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 300 271.07 271.17 271.28 271.38 271.48 271.58 271.69 271.79 271.89 271.99 301 272.10 272.20 272.30 272.40 272.51 272.61 272.71 272.81 272.92 273.02 302 273.12 273.22 273.33 273.43 273.53 273.64 273.74 273.84 273.94 274.05 303 274.15 274.25 274.35 274.46 274.56 274.66 274.76 274.87 274.97 275.07 304 275.17 275.28 275.38 275.48 275.58 275.69 275.79 275.89 276.00 276.10 305 276.20 276.30 276.41 276.51 276.61 276.71 276.82 276.92 277.02 277.12 306 277.23 277.33 277.43 277.54 277.64 277.74 277.84 277.95 278.05 278.15 307 278.25 278.36 278.46 278.56 278.67 278.77 278.87 278.97 279.08 279.18 308 279.28 279.39 279.49 279.59 279.69 279.80 279.90 280.00 280.10 280.21 309 280.31 280.41 280.52 280.62 280.72 280.82 280.93 281.03 281.13 281.24 310 281.34 281.44 281.54 281.65 281.75 281.85 281.96 282.06 282.16 282.26 311 282.37 282.47 282.57 282.68 282.78 282.88 282.98 283.09 283.19 283.29 312 283.40 283.50 283.60 283.70 283.81 283.91 284.01 284.12 284.22 284.32 313 284.43 284.53 284.63 284.73 284.84 284.94 285.04 285.15 285.25 285.35 314 285.46 285.56 285.66 285.76 285.87 285.97 286.07 286.18 286.28 286.38 315 286.49 286.59 286.69 286.79 286.90 287.00 287.10 287.21 287.31 287.41 316 287.52 287.62 287.72 287.83 287.93 288.03 288.13 288.24 288.34 288.44 317 288.55 288.65 288.75 288.86 288.96 289.06 289.17 289.27 289.37 289.47 318 289.58 289.68 289.78 289.89 289.99 290.09 290.20 290.30 290.40 290.51 319 290.61 290.71 290.82 290.92 291.02 291.13 291.23 291.33 291.44 291.54 320 291.64 291.74 291.85 291.95 292.05 292.16 292.26 292.36 292.47 292.57 321 292.67 292.78 292.88 292.98 293.09 293.19 293.29 293.40 293.50 293.60 322 293.71 293.81 293.91 294.02 294.12 294.22 294.33 294.43 294.53 294.64 323 294.74 294.84 294.95 295.05 295.15 295.26 295.36 295.46 295.57 295.67 324 295.77 295.88 295.98 296.08 296.19 296.29 296.39 296.50 296.60 296.70 325 296.81 296.91 297.01 297.12 297.22 297.32 297.43 297.53 297.63 297.74

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 150 of 195 (Page 2 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 326 297.84 297.95 298.05 298.15 298.26 298.36 298.46 298.57 298.67 298.77 327 298.88 298.98 299.08 299.19 299.29 299.39 299.50 299.60 299.70 299.81 328 299.91 300.02 300.12 300.22 300.33 300.43 300.53 300.64 300.74 300.84 329 300.95 301.05 301.15 301.26 301.36 301.47 301.57 301.67 301.78 301.88 330 301.98 302.09 302.19 302.29 302.40 302.50 302.60 302.71 302.81 302.92 331 303.02 303.12 303.23 303.33 303.43 303.54 303.64 303.75 303.85 303.95 332 304.06 304.16 304.26 304.37 304.47 304.57 304.68 304.78 304.89 304.99 333 305.09 305.20 305.30 305.40 305.51 305.61 305.72 305.82 305.92 306.03 334 306.13 306.24 306.34 306.44 306.55 306.65 306.75 306.86 306.96 307.07 335 307.17 307.27 307.38 307.48 307.58 307.69 307.79 307.90 308.00 308.10 336 308.21 308.31 308.42 308.52 308.62 308.73 308.83 308.94 309.04 309.14 337 309.25 309.35 309.45 309.56 309.66 309.77 309.87 309.97 310.08 310.18 338 310.29 310.39 310.49 310.60 310.70 310.81 310.91 311.01 311.12 311.22 339 311.33 311.43 311.53 311.64 311.74 311.85 311.95 312.05 312.16 312.26 340 312.37 312.47 312.57 312.68 312.78 312.89 312.99 313.09 313.20 313.30 341 313.41 313.51 313.62 313.72 313.82 313.93 314.03 314.14 314.24 314.34 342 314.45 314.55 314.66 314.76 314.86 314.97 315.07 315.18 315.28 315.39 343 315.49 315.59 315.70 315.80 315.91 316.01 316.12 316.22 316.32 316.43 344 316.53 316.64 316.74 316.84 316.95 317.05 317.16 317.26 317.37 317.47 345 317.57 317.68 317.78 317.89 317.99 318.10 318.20 318.30 318.41 318.51 346 318.62 318.72 318.83 318.93 319.03 319.14 319.24 319.35 319.45 319.56 347 319.66 319.77 319.87 319.97 320.08 320.18 320.29 320.39 320.50 320.60 348 320.70 320.81 320.91 321.02 321.12 321.23 321.33 321.44 321.54 321.64 349 321.75 321.85 321.96 322.06 322.17 322.27 322.38 322.48 322.59 322.69

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 151 of 195 (Page 3 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 350 322.79 322.90 323.00 323.11 323.21 323.32 323.42 323.53 323.63 323.73 351 323.84 323.94 324.05 324.15 324.26 324.36 324.47 324.57 324.68 324.78 352 324.89 324.99 325.09 325.20 325.30 325.41 325.51 325.62 325.72 325.83 353 325.93 326.04 326.14 326.25 326.35 326.45 326.56 326.66 326.77 326.87 354 326.98 327.08 327.19 327.29 327.40 327.50 327.61 327.71 327.82 327.92 355 328.03 328.13 328.24 328.34 328.44 328.55 328.65 328.76 328.86 328.97 356 329.07 329.18 329.28 329.39 329.49 329.60 329.70 329.81 329.91 330.02 357 330.12 330.23 330.33 330.44 330.54 330.65 330.75 330.86 330.96 331.07 358 331.17 331.28 331.38 331.49 331.59 331.70 331.80 331.90 332.01 332.11 359 332.22 332.32 332.43 332.53 332.64 332.74 332.85 332.95 333.06 333.16 360 333.27 333.37 333.48 333.58 333.69 333.79 333.90 334.00 334.11 334.21 361 334.32 334.43 334.53 334.64 334.74 334.85 334.95 335.06 335.16 335.27 362 335.37 335.48 335.58 335.69 335.79 335.90 336.00 336.11 336.21 336.32 363 336.42 336.53 336.63 336.74 336.84 336.95 337.05 337.16 337.26 337.37 364 337.47 337.58 337.68 337.79 337.89 338.00 338.11 338.21 338.32 338.42 365 338.53 338.63 338.74 338.84 338.95 339.05 339.16 339.26 339.37 339.47 366 339.58 339.68 339.79 339.90 340.00 340.11 340.21 340.32 340.42 340.53 367 340.63 340.74 340.84 340.95 341.05 341.16 341.27 341.37 341.48 341.58 368 341.69 341.79 341.90 342.00 342.11 342.21 342.32 342.43 342.53 342.64 369 342.74 342.85 342.95 343.06 343.16 343.27 343.37 343.48 343.59 343.69 370 343.80 343.90 344.01 344.11 344.22 344.32 344.43 344.54 344.64 344.75 371 344.85 344.96 345.06 345.17 345.27 345.38 345.49 345.59 345.70 345.80 372 345.91 346.01 346.12 346.23 346.33 346.44 346.54 346.65 346.75 346.86 373 346.97 347.07 347.18 347.28 347.39 347.49 347.60 347.71 347.81 347.92 374 348.02 348.13 348.23 348.34 348.45 348.55 348.66 348.76 348.87 348.97

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 152 of 195 (Page 4 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 375 349.08 349.19 349.29 349.40 349.50 349.61 349.72 349.82 349.93 350.03 376 350.14 350.24 350.35 350.46 350.56 350.67 350.77 350.88 350.99 351.09 377 351.20 351.30 351.41 351.52 351.62 351.73 351.83 351.94 352.05 352.15 378 352.26 352.36 352.47 352.58 352.68 352.79 352.89 353.00 353.11 353.21 379 353.32 353.42 353.53 353.64 353.74 353.85 353.95 354.06 354.17 354.27 380 354.38 354.49 354.59 354.70 354.80 354.91 355.02 355.12 355.23 355.33 381 355.44 355.55 355.65 355.76 355.87 355.97 356.08 356.18 356.29 356.40 382 356.50 356.61 356.71 356.82 356.93 357.03 357.14 357.25 357.35 357.46 383 357.57 357.67 357.78 357.88 357.99 358.10 358.20 358.31 358.42 358.52 384 358.63 358.73 358.84 358.95 359.05 359.16 359.27 359.37 359.48 359.59 385 359.69 359.80 359.91 360.01 360.12 360.22 360.33 360.44 360.54 360.65 386 360.76 360.86 360.97 361.08 361.18 361.29 361.40 361.50 361.61 361.72 387 361.82 361.93 362.03 362.14 362.25 362.35 362.46 362.57 362.67 362.78 388 362.89 362.99 363.10 363.21 363.31 363.42 363.53 363.63 363.74 363.85 389 363.95 364.06 364.17 364.27 364.38 364.49 364.59 364.70 364.81 364.91 390 365.02 365.13 365.23 365.34 365.45 365.55 365.66 365.77 365.87 365.98 391 366.09 366.20 366.30 366.41 366.52 366.62 366.73 366.84 366.94 367.05 392 367.16 367.26 367.37 367.48 367.58 367.69 367.80 367.91 368.01 368.12 393 368.23 368.33 368.44 368.55 368.65 368.76 368.87 368.97 369.08 369.19 394 369.30 369.40 369.51 369.62 369.72 369.83 369.94 370.04 370.15 370.26 395 370.37 370.47 370.58 370.69 370.79 370.90 371.01 371.12 371.22 371.33 396 371.44 371.54 371.65 371.76 371.87 371.97 372.08 372.19 372.29 372.40 397 372.51 372.62 372.72 372.83 372.94 373.04 373.15 373.26 373.37 373.47 398 373.58 373.69 373.80 373.90 374.01 374.12 374.22 374.33 374.44 374.55 399 374.65 374.76 374.87 374.98 375.08 375.19 375.30 375.40 375.51 375.62

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 153 of 195 (Page 5 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 400 375.73 375.83 375.94 376.05 376.16 376.26 376.37 376.48 376.59 376.69 401 376.80 376.91 377.02 377.12 377.23 377.34 377.45 377.55 377.66 377.77 402 377.88 377.98 378.09 378.20 378.31 378.41 378.52 378.63 378.74 378.84 403 378.95 379.06 379.17 379.28 379.38 379.49 379.60 379.71 379.81 379.92 404 380.03 380.14 380.24 380.35 380.46 380.57 380.68 380.78 380.89 381.00 405 381.11 381.21 381.32 381.43 381.54 381.64 381.75 381.86 381.97 382.08 406 382.18 382.29 382.40 382.51 382.62 382.72 382.83 382.94 383.05 383.15 407 383.26 383.37 383.48 383.59 383.69 383.80 383.91 384.02 384.13 384.23 408 384.34 384.45 384.56 384.67 384.77 384.88 384.99 385.10 385.21 385.31 409 385.42 385.53 385.64 385.75 385.85 385.96 386.07 386.18 386.29 386.39 410 386.50 386.61 386.72 386.83 386.94 387.04 387.15 387.26 387.37 387.48 411 387.58 387.69 387.80 387.91 388.02 388.13 388.23 388.34 388.45 388.56 412 388.67 388.78 388.88 388.99 389.10 389.21 389.32 389.43 389.53 389.64 413 389.75 389.86 389.97 390.08 390.18 390.29 390.40 390.51 390.62 390.73 414 390.83 390.94 391.05 391.16 391.27 391.38 391.48 391.59 391.70 391.81 415 391.92 392.03 392.14 392.24 392.35 392.46 392.57 392.68 392.79 392.90 416 393.00 393.11 393.22 393.33 393.44 393.55 393.66 393.76 393.87 393.98 417 394.09 394.20 394.31 394.42 394.53 394.63 394.74 394.85 394.96 395.07 418 395.18 395.29 395.40 395.50 395.61 395.72 395.83 395.94 396.05 396.16 419 396.27 396.37 396.48 396.59 396.70 396.81 396.92 397.03 397.14 397.25 420 397.35 397.46 397.57 397.68 397.79 397.90 398.01 398.12 398.23 398.34 421 398.44 398.55 398.66 398.77 398.88 398.99 399.10 399.21 399.32 399.43 422 399.53 399.64 399.75 399.86 399.97 400.08 400.19 400.30 400.41 400.52 423 400.63 400.73 400.84 400.95 401.06 401.17 401.28 401.39 401.50 401.61 424 401.72 401.83 401.94 402.05 402.15 402.26 402.37 402.48 402.59 402.70

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 154 of 195 (Page 6 of 6)

Attachment 74 ENTHALPY COMPRESSED LIQUID TABLE (800 PSIA)

FW TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 425 402.81 402.92 403.03 403.14 403.25 403.36 403.47 403.58 403.69 403.79 426 403.90 404.01 404.12 404.23 404.34 404.45 404.56 404.67 404.78 404.89 427 405.00 405.11 405.22 405.33 405.44 405.55 405.66 405.77 405.88 405.98 428 406.09 406.20 406.31 406.42 406.53 406.64 406.75 406.86 406.97 407.08 429 407.19 407.30 407.41 407.52 407.63 407.74 407.85 407.96 408.07 408.18 430 408.29 408.40 408.51 408.62 408.73 408.84 408.95 409.06 409.17 409.28 431 409.39 409.50 409.61 409.72 409.83 409.94 410.05 410.16 410.27 410.38 432 410.49 410.59 410.70 410.81 410.92 411.03 411.14 411.25 411.36 411.47 433 411.58 411.69 411.81 411.92 412.03 412.14 412.25 412.36 412.47 412.58 434 412.69 412.80 412.91 413.02 413.13 413.24 413.35 413.46 413.57 413.68 435 413.79 413.90 414.01 414.12 414.23 414.34 414.45 414.56 414.67 414.78 436 414.89 415.00 415.11 415.22 415.33 415.44 415.55 415.66 415.77 415.88 437 415.99 416.10 416.21 416.33 416.44 416.55 416.66 416.77 416.88 416.99 438 417.10 417.21 417.32 417.43 417.54 417.65 417.76 417.87 417.98 418.09 439 418.20 418.31 418.43 418.54 418.65 418.76 418.87 418.98 419.09 419.20 440 419.31 419.42 419.53 419.64 419.75 419.86 419.97 420.09 420.20 420.31 441 420.42 420.53 420.64 420.75 420.86 420.97 421.08 421.19 421.30 421.42 442 421.53 421.64 421.75 421.86 421.97 422.08 422.19 422.30 422.41 422.53 443 422.64 422.75 422.86 422.97 423.08 423.19 423.30 423.41 423.52 423.64 444 423.75 423.86 423.97 424.08 424.19 424.30 424.41 424.52 424.64 424.75 445 424.86 424.97 425.08 425.19 425.30 425.41 425.53 425.64 425.75 425.86 446 425.97 426.08 426.19 426.30 426.42 426.53 426.64 426.75 426.86 426.97 447 427.08 427.20 427.31 427.42 427.53 427.64 427.75 427.86 427.98 428.09 448 428.20 428.31 428.42 428.53 428.64 428.76 428.87 428.98 429.09 429.20 449 429.31 429.43 429.54 429.65 429.76 429.87 429.98 430.10 430.21 430.32 450 430.43 430.54 430.65 430.77 430.88 430.99 431.10 431.21 431.33 431.44

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 155 of 195 (Page 1 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 300 0.017397785 57.47858 7.5815 301 0.017407461 57.44663 7.5794 302 0.017417172 57.41460 7.5772 303 0.017426920 57.38249 7.5751 304 0.017436703 57.35029 7.5730 305 0.017446522 57.31801 7.5709 306 0.017456378 57.28565 7.5687 307 0.017466270 57.25321 7.5666 308 0.017476198 57.22068 7.5644 309 0.017486163 57.18807 7.5623 310 0.017496165 57.15538 7.5601 311 0.017506204 57.12261 7.5579 312 0.017516280 57.08975 7.5558 313 0.017526393 57.05681 7.5536 314 0.017536543 57.02378 7.5514 315 0.017546732 56.99067 7.5492 316 0.017556957 56.95748 7.5470 317 0.017567221 56.92420 7.5448 318 0.017577523 56.89084 7.5426 319 0.017587863 56.85739 7.5404 320 0.017598242 56.82386 7.5382 321 0.017608659 56.79024 7.5359 322 0.017619115 56.75654 7.5337 323 0.017629610 56.72275 7.5315 324 0.017640144 56.68888 7.5292 325 0.017650718 56.65492 7.5269

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 156 of 195 (Page 2 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 326 0.017661331 56.62088 7.5247 327 0.017671983 56.58675 7.5224 328 0.017682675 56.55253 7.5201 329 0.017693408 56.51822 7.5179 330 0.017704180 56.48383 7.5156 331 0.017714994 56.44936 7.5133 332 0.017725847 56.41479 7.5110 333 0.017736742 56.38014 7.5087 334 0.017747677 56.34540 7.5064 335 0.017758654 56.31057 7.5040 336 0.017769672 56.27566 7.5017 337 0.017780732 56.24065 7.4994 338 0.017791834 56.20556 7.4970 339 0.017802978 56.17038 7.4947 340 0.017814164 56.13511 7.4923 341 0.017825392 56.09975 7.4900 342 0.017836663 56.06430 7.4876 343 0.017847977 56.02876 7.4852 344 0.017859334 55.99313 7.4829 345 0.017870735 55.95741 7.4805 346 0.017882179 55.92160 7.4781 347 0.017893667 55.88569 7.4757 348 0.017905199 55.84970 7.4733 349 0.017916775 55.81361 7.4709

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 157 of 195 (Page 3 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 350 0.017928396 55.77744 7.4684 351 0.017940062 55.74117 7.4660 352 0.017951772 55.70481 7.4636 353 0.017963528 55.66835 7.4611 354 0.017975330 55.63180 7.4587 355 0.017987177 55.59516 7.4562 356 0.01799907 55.55843 7.4538 357 0.018011009 55.52160 7.4513 358 0.018022995 55.48467 7.4488 359 0.018035028 55.44766 7.4463 360 0.018047107 55.41054 7.4438 361 0.018059234 55.37333 7.4413 362 0.018071409 55.33603 7.4388 363 0.018083632 55.29863 7.4363 364 0.018095902 55.26113 7.4338 365 0.018108221 55.22354 7.4313 366 0.018120589 55.18584 7.4287 367 0.018133006 55.14805 7.4262 368 0.018145472 55.11017 7.4236 369 0.018157988 55.07218 7.4211 370 0.01870553 55.03410 7.4185 371 0.018183169 54.99592 7.4159 372 0.018195835 54.95763 7.4133 373 0.018208552 54.91925 7.4108 374 0.01822132 54.88077 7.4082 375 0.018234139 54.84218 7.4056

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 158 of 195 (Page 4 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 376 0.018247010 54.80350 7.4029 377 0.018259934 54.76471 7.4003 378 0.018272909 54.72582 7.3977 379 0.018285938 54.68683 7.3951 380 0.018299019 54.64774 7.3924 381 0.018312154 54.60854 7.3898 382 0.018325342 54.56924 7.3871 383 0.018338585 54.52984 7.3844 384 0.018351881 54.49033 7.3818 385 0.018365233 54.45071 7.3791 386 0.018378640 54.41099 7.3764 387 0.018392102 54.37116 7.3737 388 0.018405620 54.33123 7.3710 389 0.018419195 54.29119 7.3683 390 0.018432826 54.25104 7.3655 391 0.018446513 54.21079 7.3628 392 0.018460259 54.17042 7.3601 393 0.018474062 54.12995 7.3573 394 0.018487923 54.08937 7.3545 395 0.018501842 54.04867 7.3518 396 0.018515821 54.00787 7.3490 397 0.018529859 53.96695 7.3462 398 0.018543956 53.92593 7.3434 399 0.018558114 53.88479 7.3406 400 0.018572332 53.84353 7.3378 401 0.018586612 53.80217 7.3350

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 159 of 195 (Page 5 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 402 0.018600953 53.76069 7.3322 403 0.018615355 53.71909 7.3293 404 0.018629820 53.67738 7.3265 405 0.018644348 53.63556 7.3236 406 0.018658939 53.59362 7.3208 407 0.018673594 53.55156 7.3179 408 0.018688312 53.50938 7.3150 409 0.018703096 53.46708 7.3121 410 0.018717944 53.42467 7.3092 411 0.018732859 53.38214 7.3063 412 0.018747839 53.33948 7.3034 413 0.018762885 53.29671 7.3005 414 0.018777999 53.25381 7.2975 415 0.018793181 53.21079 7.2946 416 0.018808430 53.16765 7.2916 417 0.018823748 53.12438 7.2886 418 0.018839135 53.08099 7.2857 419 0.018854592 53.03748 7.2827 420 0.018870119 52.99384 7.2797 421 0.018885717 52.95007 7.2767 422 0.018901386 52.90617 7.2737 423 0.018917127 52.86215 7.2706 424 0.018932941 52.81800 7.2676 425 0.018948827 52.77371 7.2646 426 0.018964787 52.72930 7.2615 427 0.018980822 52.68476 7.2584

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 160 of 195 (Page 6 of 6)

Attachment 75 DENSITY COMPRESSED LIQUID TABLE (800 PSIA)

TEMP

(°F) Specific Volume Density SQRT Density 428 0.018996931 52.64008 7.2553 429 0.019013116 52.59527 7.2523 430 0.019029376 52.55033 7.2492 431 0.019045713 52.50525 7.2461 432 0.019062128 52.46004 7.2429 433 0.019078621 52.41469 7.2398 434 0.019095192 52.36920 7.2367 435 0.019111842 52.32358 7.2335 436 0.019128572 52.27782 7.2303 437 0.019145383 52.23191 7.2272 438 0.019162275 52.18587 7.2240 439 0.019179250 52.13968 7.2208 440 0.019196307 52.09335 7.2176 441 0.019213447 52.04688 7.2144 442 0.019230672 52.00026 7.2111 443 0.019247981 51.95350 7.2079 444 0.019265376 51.90659 7.2046 445 0.019282858 51.85953 7.2014 446 0.019300426 51.81233 7.1981 447 0.019318083 51.76497 7.1948 448 0.019335829 51.71746 7.1915 449 0.019353664 51.66980 7.1882 450 0.019371589 51.62199 7.1848

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 161 of 195 (Page 1 of 1)

Attachment 76 ENTHALPY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2250 PSIA)

ENTHALPHY (BTU/LBM)

TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 500 487.51 488.66 489.81 490.97 492.13 493.28 494.44 495.60 496.77 497.93 510 499.10 500.26 501.43 502.60 503.77 504.95 506.12 507.30 508.48 509.65 520 510.84 512.02 513.20 514.39 515.58 516.77 517.96 519.15 520.35 521.55 530 522.75 523.95 525.15 526.35 527.56 528.77 529.98 531.19 532.41 533.63 540 534.84 536.07 537.29 538.51 539.74 540.97 542.20 543.44 544.68 545.92 550 547.16 548.40 549.65 550.90 552.15 553.40 554.66 555.92 557.18 558.44 560 559.71 560.98 562.26 563.53 564.81 566.09 567.38 568.66 569.95 571.25 570 572.55 573.85 575.15 576.46 577.77 579.08 580.40 581.72 583.04 584.37 580 585.70 587.04 588.38 589.72 591.07 592.42 593.77 595.13 596.50 597.87 590 599.24 600.62 602.00 603.38 604.78 606.17 607.57 608.98 610.39 611.81 600 613.23 614.66 616.09 617.53 618.97 620.42 621.88 623.34 624.81 626.29

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 162 of 195 (Page 1 of 4)

Attachment 77 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (400 PSIA)

Letdown Temp Density

(°F) Specific Volume (lbm/cubic feet) 60 0.016012822 62.45 61 0.016014275 62.44 62 0.016015785 62.44 63 0.016017354 62.43 64 0.016018979 62.43 65 0.016020660 62.42 66 0.016022397 62.41 67 0.016024188 62.41 68 0.016026033 62.40 69 0.016027932 62.39 70 0.016029883 62.38 71 0.016031886 62.38 72 0.016033941 62.37 73 0.016036046 62.36 74 0.016038202 62.35 75 0.016040408 62.34 76 0.016042663 62.33 77 0.016044966 62.32 78 0.016047318 62.32 79 0.016049717 62.31 80 0.016052164 62.30 81 0.016054657 62.29 82 0.016057196 62.28 83 0.016059782 62.27 84 0.016062413 62.26 85 0.016065088 62.25

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 163 of 195 (Page 2 of 4)

Attachment 77 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (400 PSIA)

Letdown Temp Density

(°F) Specific Volume (lbm/cubic feet) 86 0.016067809 62.24 87 0.016070574 62.23 88 0.016073382 62.21 89 0.016076234 62.20 90 0.016079129 62.19 91 0.016082067 62.18 92 0.016085047 62.17 93 0.016088070 62.16 94 0.016091134 62.15 95 0.016094240 62.13 96 0.016097387 62.12 97 0.016100574 62.11 98 0.016103802 62.10 99 0.016107071 62.08 100 0.016110380 62.07 101 0.016113728 62.06 102 0.016117116 62.05 103 0.016120543 62.03 104 0.016124009 62.02 105 0.016127514 62.01 106 0.016131057 61.99 107 0.016134639 61.98 108 0.016138259 61.96 109 0.016141916 61.95 110 0.016145612 61.94

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 164 of 195 (Page 3 of 4)

Attachment 77 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (400 PSIA)

Letdown Temp Density

(°F) Specific Volume (lbm/cubic feet) 111 0.016149345 61.92 112 0.016153115 61.91 113 0.016156922 61.89 114 0.016160766 61.88 115 0.016164646 61.86 116 0.016168563 61.85 117 0.016172517 61.83 118 0.016176506 61.82 119 0.016180532 61.80 120 0.016184593 61.79 121 0.016188690 61.77 122 0.016192822 61.76 123 0.016196990 61.74 124 0.016201193 61.72 125 0.016205431 61.71 126 0.016209703 61.69 127 0.016214011 61.68 128 0.016218353 61.66 129 0.016222729 61.64 130 0.016227139 61.63 131 0.016231584 61.61 132 0.016236063 61.59 133 0.016240575 61.57 134 0.016245122 61.56 135 0.016249702 61.54

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 165 of 195 (Page 4 of 4)

Attachment 77 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (400 PSIA)

Letdown Temp Density

(°F) Specific Volume (lbm/cubic feet) 136 0.016254315 61.52 137 0.016258962 61.50 138 0.016263642 61.49 139 0.016268355 61.47 140 0.016273101 61.45 141 0.016277880 61.43 142 0.016282692 61.41 143 0.016287536 61.40 144 0.016292413 61.38 145 0.016297322 61.36 146 0.016302264 61.34 147 0.016307238 61.32 148 0.016312244 61.30 149 0.016317283 61.28 150 0.016322353 61.27 151 0.016327455 61.25 152 0.016332588 61.23 153 0.016337754 61.21 154 0.016342951 61.19 155 0.016348179 61.17 156 0.016353439 61.15 157 0.016358730 61.13 158 0.016364053 61.11 159 0.016369407 61.09 160 0.016374791 61.07

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 166 of 195 (Page 1 of 2)

Attachment 78 ENTHALPY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 300 274.27 275.29 276.30 277.32 278.34 279.36 280.38 281.40 282.41 283.43 310 284.45 285.47 286.49 287.52 288.54 289.56 290.58 291.60 292.62 293.65 320 294.67 295.69 296.72 297.74 298.76 299.79 300.81 301.84 302.87 303.89 330 304.92 305.95 306.97 308.00 309.03 310.06 311.09 312.11 313.14 314.17 340 315.20 316.23 317.27 318.30 319.33 320.36 321.39 322.43 323.46 324.49 350 325.53 326.56 327.60 328.63 329.67 330.70 331.74 332.78 333.82 334.85 360 335.89 336.93 337.97 339.01 340.05 341.09 342.13 343.17 344.22 345.26 370 346.30 347.34 348.39 349.43 350.48 351.52 352.57 353.61 354.66 355.71 380 356.76 357.80 358.85 359.90 360.95 362.00 363.05 364.11 365.16 366.21 390 367.26 368.32 369.37 370.42 371.48 372.54 373.59 374.65 375.71 376.76 400 377.82 378.88 379.94 381.00 382.06 383.12 384.19 385.25 386.31 387.38 410 388.44 389.50 390.57 391.64 392.70 393.77 394.84 395.91 396.98 398.05 420 399.12 400.19 401.26 402.34 403.41 404.48 405.56 406.64 407.71 408.79 430 409.87 410.95 412.02 413.10 414.19 415.27 416.35 417.43 418.52 419.60 440 420.69 421.77 422.86 423.95 425.03 426.12 427.21 428.31 429.40 430.49 450 431.58 432.68 433.77 434.87 435.97 437.06 438.16 439.26 440.36 441.46 460 442.56 443.67 444.77 445.88 446.98 448.09 449.20 450.31 451.42 452.53 470 453.64 454.75 455.87 456.98 458.10 459.21 460.33 461.45 462.57 463.69 480 464.81 465.94 467.06 468.19 469.31 470.44 471.57 472.70 473.83 474.96 490 476.10 477.23 478.37 479.50 480.64 481.78 482.92 484.06 485.21 486.35 500 487.50 488.65 489.79 490.94 492.10 493.25 494.40 495.56 496.71 497.87 510 499.03 500.19 501.36 502.52 503.69 504.85 506.02 507.19 508.36 509.54 520 510.71 511.89 513.07 514.25 515.43 516.61 517.80 518.98 520.17 521.36 530 522.55 523.75 524.94 526.14 527.34 528.54 529.74 530.95 532.15 533.36 540 534.57 535.78 537.00 538.22 539.43 540.66 541.88 543.10 544.33 545.56 550 546.79 548.03 549.26 550.50 551.74 552.99 554.23 555.48 556.73 557.99

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 167 of 195 (Page 2 of 2)

Attachment 78 ENTHALPY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 560 559.24 560.50 561.76 563.03 564.29 565.56 566.83 568.11 569.39 570.67 570 571.95 573.24 574.53 575.82 577.11 578.41 579.72 581.02 582.33 583.64 580 584.96 586.28 587.60 588.93 590.26 591.59 592.93 594.27 595.61 596.96 590 598.31 599.67 601.03 602.40 603.77 605.14 606.52 607.90 609.29 610.69 600 612.08 613.49 614.89 616.31 617.72 619.15 620.57 622.01 623.45 624.89

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 168 of 195 (Page 1 of 4)

Attachment 79 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

Seal Water Injection and Charging Temp Density

(°F) Specific Volume (lbm/cubic feet) 60 0.015908506 62.86 61 0.015910173 62.85 62 0.015911891 62.85 63 0.015913660 62.84 64 0.01591548 62.83 65 0.015917349 62.82 66 0.015919267 62.82 67 0.015921234 62.81 68 0.015923248 62.80 69 0.015925309 62.79 70 0.015927417 62.78 71 0.015929571 62.78 72 0.015931770 62.77 73 0.015934015 62.76 74 0.015936304 62.75 75 0.015938637 62.74 76 0.015941014 62.73 77 0.015943435 62.72 78 0.015945898 62.71 79 0.015948403 62.70 80 0.015950951 62.69 81 0.015953540 62.68 82 0.01595617 62.67 83 0.015958842 62.66 84 0.015961553 62.65 85 0.015964305 62.64 86 0.015967097 62.63 87 0.015969928 62.62

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 169 of 195 (Page 2 of 4)

Attachment 79 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

Seal Water Injection and Density Charging Temp (°F) Specific Volume (lbm/cubic feet) 88 0.015972799 62.61 89 0.015975708 62.60 90 0.015978657 62.58 91 0.015981643 62.57 92 0.015984667 62.56 93 0.015987730 62.55 94 0.015990829 62.54 95 0.015993966 62.52 96 0.015997140 62.51 97 0.016000351 62.50 98 0.016003598 62.49 99 0.016006882 62.47 100 0.016010202 62.46 101 0.016013557 62.45 102 0.016016949 62.43 103 0.016020375 62.42 104 0.016023837 62.41 105 0.016027334 62.39 106 0.016030866 62.38 107 0.016034433 62.37 108 0.016038034 62.35 109 0.016041670 62.34 110 0.016045339 62.32 111 0.016049043 62.31 112 0.016052781 62.29 113 0.016056552 62.28 114 0.016060357 62.27

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 170 of 195 (Page 3 of 4)

Attachment 79 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

Seal Water Injection and Density Charging Temp (°F) Specific Volume (lbm/cubic feet) 115 0.016064195 62.25 116 0.016068067 62.24 117 0.016071971 62.22 118 0.016075909 62.20 119 0.016079879 62.19 120 0.016083882 62.17 121 0.016087918 62.16 122 0.016091986 62.14 123 0.016096086 62.13 124 0.016100218 62.11 125 0.016104383 62.09 126 0.016108579 62.08 127 0.016112807 62.06 128 0.016117067 62.05 129 0.016121359 62.03 130 0.016125681 62.01 131 0.016130036 62.00 132 0.016134421 61.98 133 0.016138837 61.96 134 0.016143285 61.95 135 0.016147763 61.93 136 0.016152273 61.91 137 0.016156813 61.89 138 0.016161383 61.88 139 0.016165984 61.86 140 0.016170615 61.84 141 0.016175277 61.82

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 171 of 195 (Page 4 of 4)

Attachment 79 DENSITY THERMODYNAMIC PROPERTIES OF COMPRESSED LIQUID TABLE (2500 PSIA)

Seal Water Injection and Density Charging Temp (°F) Specific Volume (lbm/cubic feet) 142 0.016179969 61.80 143 0.016184691 61.79 144 0.016189443 61.77 145 0.016194225 61.75 146 0.016199037 61.73 147 0.016203878 61.71 148 0.016208749 61.70 149 0.016213650 61.68 150 0.016218581 61.66 151 0.016223540 61.64 152 0.016228529 61.62 153 0.016233548 61.60 154 0.016238595 61.58 155 0.016243672 61.56 156 0.016248778 61.54 157 0.016253912 61.52 158 0.016259076 61.50 159 0.016264268 61.48 160 0.016269489 61.46

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 172 of 195 (Page 1 of 1)

Attachment 80 ENTHALPY SEAL WATER INJECTION TABLE (2500 PSIA)

TEMP

(°F) 0 1 2 3 4 5 6 7 8 9 60 35.08 36.07 37.06 38.04 39.03 40.02 41.00 41.99 42.97 43.96 70 44.95 45.93 46.92 47.91 48.89 49.88 50.87 51.85 52.84 53.83 80 54.82 55.80 56.79 57.78 58.76 59.75 60.74 61.73 62.71 63.70 90 64.69 65.68 66.66 67.65 68.64 69.63 70.62 71.60 72.59 73.58 100 74.57 75.56 76.54 77.53 78.52 79.51 80.50 81.49 82.48 83.46 110 84.45 85.44 86.43 87.42 88.41 89.40 90.39 91.38 92.36 93.35 120 94.34 95.33 96.32 97.31 98.30 99.29 100.28 101.27 102.26 103.25 130 104.24 105.23 106.22 107.21 108.20 109.19 110.18 111.17 112.16 113.15 140 114.14 115.13 116.13 117.12 118.11 119.10 120.09 121.08 122.07 123.06 150 124.05 125.05 126.04 127.03 128.02 129.01 130.00 131.00 131.99 132.98 160 133.97 134.97 135.96 136.95 137.94 138.94 139.93 140.92 141.91 142.91

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 173 of 195 (Page 1 of 1)

Attachment 81 DIESEL DRIVEN FIRE PUMP FUEL OIL TANK LEVEL INCHES GALLONS INCHES GALLONS 51.0 347 39.5 272 50.5 345 39.0 268 50.0 342 38.5 265 49.5 340 38.0 261 49.0 337 37.5 257 48.5 334 37.0 253 48.0 331 36.5 250 47.5 328 36.0 246 MAX FILL 47.0 325 35.5 242 46.5 322 35.0 239 46.0 319 34.5 235 45.5 315 34.0 231 45.0 312 33.5 227 44.5 309 33.0 224 44.0 305 32.5 220 43.5 301 32.0 216 43.0 298 31.5 213 42.5 294 31.0 209 42.0 291 30.5 205 41.5 287 30.0 201 41.0 283 29.5 198 40.5 279 29.0 194 40.0 276 28.5 190

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 174 of 195 (Page 1 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 0.00 0.0 0.0 0.25 0.4 0.0 0.50 1.1 0.0 0.75 2.1 0.0 1.00 3.2 0.0 1.25 4.5 0.0 1.50 5.9 0.0 1.75 7.4 1.5 2.00 9.0 3.1 2.25 10.7 4.9 2.50 12.5 6.7 2.75 14.4 8.6 3.00 16.5 10.6 3.25 18.6 12.7 3.50 20.7 14.8 3.75 23.0 17.1 4.00 25.3 19.4 4.25 27.6 21.8 4.50 30.0 24.2 4.75 32.6 26.7 5.00 35.2 29.3 5.25 37.8 32.0 5.50 40.5 34.7 5.75 43.3 37.4 6.00 46.1 40.2 6.25 48.9 43.1

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 175 of 195 (Page 2 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 6.50 51.9 46.0 6.75 54.9 49.0 7.00 57.9 52.1 7.25 61.0 55.1 7.50 64.0 58.1 7.75 67.1 61.2 8.00 70.3 64.5 8.25 73.6 67.7 8.50 74.9 69.0 8.75 80.3 74.4 9.00 83.7 77.8 9.25 87.1 81.3 9.50 90.6 84.7 9.75 93.9 88.0 10.00 97.4 91.5 10.25 100.9 95.0 10.50 105.1 99.2 10.75 108.7 102.8 11.00 112.4 106.5 11.25 116.1 110.3 11.50 119.9 114.0 11.75 123.6 117.8 12.00 127.4 121.5 12.25 131.3 125.4 12.50 135.1 129.2

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 176 of 195 (Page 3 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 12.75 138.9 133.1 13.00 142.7 136.9 13.25 146.6 140.7 13.50 150.5 144.6 13.75 154.3 148.5 14.00 158.2 152.4 14.25 162.2 156.3 14.50 166.2 160.3 14.75 170.3 164.4 15.00 174.2 168.4 15.25 178.2 172.4 15.50 182.3 176.4 15.75 186.3 180.4 16.00 190.5 184.7 16.25 194.7 188.8 16.50 198.8 193.0 16.75 202.9 197.0 17.00 207.0 201.1 17.25 211.1 205.3 17.50 215.3 209.5 17.75 219.5 213.6 18.00 223.7 217.9 18.25 227.9 222.1 18.50 232.1 226.3 18.75 236.3 230.4

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 177 of 195 (Page 4 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 19.00 240.5 234.6 19.25 244.7 238.8 19.50 248.8 243.0 19.75 251.9 246.0 20.00 257.3 251.5 20.25 261.6 255.7 20.50 265.9 260.0 20.75 270.8 264.9 21.00 275.1 269.2 21.25 279.4 273.5 21.50 283.6 277.8 21.75 287.9 282.0 22.00 292.1 286.2 22.25 296.3 290.4 22.50 300.5 294.6 22.75 304.7 298.8 23.00 308.8 303.0 23.25 313.0 307.2 23.50 317.2 311.3 23.75 321.4 315.6 24.00 325.6 319.8 24.25 329.8 323.9 24.50 334.0 328.1 24.75 338.1 332.2 25.00 342.2 336.3

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 178 of 195 (Page 5 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 25.25 346.3 340.4 25.50 350.4 344.5 25.75 354.6 348.7 26.00 358.7 352.8 26.25 362.8 356.9 26.50 366.9 361.0 26.75 370.7 364.9 27.00 374.7 368.8 27.25 378.7 372.8 27.50 382.8 376.9 27.75 386.7 380.9 28.00 390.6 384.7 28.25 394.4 388.5 28.50 398.3 392.4 28.75 402.1 396.2 29.00 405.9 400.1 29.25 409.7 403.9 29.50 413.5 407.7 29.75 417.3 411.4 30.00 421.2 415.3 30.25 425.0 419.1 30.50 428.6 422.7 30.75 432.3 426.5 31.00 436.0 430.1 31.25 440.1 434.2

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 179 of 195 (Page 6 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 31.50 443.7 437.8 31.75 447.2 441.3 32.00 450.6 444.7 32.25 454.0 448.1 32.50 457.3 451.5 32.75 460.7 454.8 33.00 464.1 458.3 33.25 467.4 461.6 33.50 470.7 464.9 33.75 474.0 468.1 34.00 480.1 474.3 34.25 483.1 477.3 34.50 486.1 480.2 34.75 489.0 483.1 35.00 491.0 485.1 35.25 494.9 489.0 35.50 497.8 491.9 35.75 500.5 494.7 36.00 503.3 497.4 36.25 505.9 500.0 36.50 508.5 502.6 36.75 508.6 502.7 37.00 511.1 505.3 37.25 513.6 507.7 37.50 516.0 510.1

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 180 of 195 (Page 7 of 7)

Attachment 82 EDG NO. 1 AND EDG NO. 3 AUXILIARY FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 37.75 518.3 512.4 38.00 520.5 514.7 38.25 522.7 516.8 38.50 524.8 518.9 38.75 526.8 520.9 39.00 528.7 522.9 39.25 530.6 524.7 39.50 532.3 526.4 39.75 533.9 528.1 40.00 535.5 529.6 40.25 536.9 531.0 40.50 538.2 532.3 40.75 539.2 533.4 41.00 540.3 534.5 41.25 541.0 535.1 41.50 541.6 535.7

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 181 of 195 (Page 1 of 3)

Attachment 83 EDG NO. 1 AND EDG NO. 3 BASE FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 0.000 0.000 0.000 0.250 7.212 0.000 0.500 14.424 0.000 0.750 21.636 0.000 1.000 28.848 0.000 1.250 36.061 0.000 1.500 43.273 0.000 1.750 50.485 7.212 2.000 57.697 14.424 2.250 64.909 21.636 2.500 72.121 28.848 2.750 79.333 36.060 3.000 86.545 43.272 3.250 93.758 50.485 3.500 100.970 57.697 3.750 108.182 64.909 4.000 115.394 71.121 4.250 122.606 79.333 4.500 129.818 86.545 4.750 137.030 93.757 5.000 144.242 100.969 5.250 151.455 108.182 5.500 158.667 115.394 5.750 165.879 122.606 6.000 173.091 129.818 6.250 180.303 137.030 6.500 187.515 144.242 6.750 194.727 151.454 7.000 201.939 158.666

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 182 of 195 (Page 2 of 3)

Attachment 83 EDG NO. 1 AND EDG NO. 3 BASE FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 7.250 209.152 165.879 7.500 216.364 173.091 7.750 223.576 180.303 8.000 230.788 187.515 8.250 238.000 194.727 8.500 245.212 201.939 8.750 252.424 209.151 9.000 259.636 216.363 9.250 266.848 223.575 9.500 274.061 230.788 9.750 281.273 238.000 10.000 288.485 245.212 10.250 295.697 252.424 10.500 302.909 259.636 10.750 310.121 266.848 11.000 317.333 274.060 11.250 324.545 281.272 11.500 331.758 288.485 11.750 338.970 295.697 12.000 346.182 302.909 12.250 353.394 310.121 12.500 360.606 317.333 12.750 367.818 324.545 13.000 375.030 331.757 13.250 382.242 338.969 13.500 389.455 346.182 13.750 396.667 353.394 14.000 403.879 360.606

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 183 of 195 (Page 3 of 3)

Attachment 83 EDG NO. 1 AND EDG NO. 3 BASE FUEL OIL TANK LEVEL HEIGHT OF FUEL TOTAL GALLONS USABLE GALLONS IN INCHES OF FUEL OF FUEL 14.250 411.091 367.818 14.500 418.303 375.030 14.750 425.515 382.242 15.000 432.727 389.454 15.250 439.939 396.666 15.500 447.152 403.879 15.750 454.364 411.091 16.000 461.576 418.303 16.250 468.788 425.515 16.500 476.000 432.727 16.750 483.212 439.939 17.000 490.424 447.151 17.250 497.636 454.363 17.500 504.848 461.575 17.750 512.061 468.788 18.000 519.273 476.000 18.250 526.485 483.212 18.500 533.697 490.424 18.750 540.909 497.636 19.000 548.121 504.848 19.063 549.924 506.651

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 184 of 195 (Page 1 of 3)

Attachment 84 MAIN CONDENSER Circ Flowrate Vs. Valve Opening 100 90 80 70 60 Flow %

50 40 30 20 10 0

0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 Degrees Graphics No: LD2502

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 185 of 195 (Page 2 of 3)

Attachment 84 MAIN CONDENSER Expected Cond Press Vs. Circ Inlet Temp 7

6 100%

90%

5 Circ Flow 80%

4 70%

HG abs 3 60%

50%

2 40%

1 30%

0 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Degree F Graphics No: LD2503 MAIN CONDENSER

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 186 of 195 (Page 3 of 3)

Attachment 84 MAIN CONDENSER NOTE:

1. From the local positions indicators for the four (4) Main Condenser Circulating Water Outlet Valves, determine the average degrees open.

2. From Page 1 of 3 of this attachment, determine the percent circulating water flow based on the average degrees open.

3. From Page 2 of 3 of this attachment, determine the expected Main Condenser pressure in inches of HG absolute based on circulating water inlet temperature (river water temperature) and the percent circulating water flow.

4. Convert Main Condenser absolute pressure to gauge pressure to compare with control board indications as follows:

Pressure (inches HG vacuum) = 29.92 inches HG - inches HG absolute

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 187 of 195 (Page 1 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS INVENTORY PERCENT PLANT 3 LOOPS PRESSURIZER ELEVATION ISOLATED LEVEL (FEET) (GALLONS) 100 58.2 40788 95 56.6 40346 90 55.1 39905 85 53.6 39463 80 52.0 39022 75 50.5 38580 70 49.0 38139 65 47.4 37697 60 45.9 37256 55 44.4 36815 50 42.8 36373 45 41.3 35932 40 39.8 35490 35 38.2 35049 30 36.7 34607 25 35.2 34166 20 33.6 33724 15 32.1 33283 10 30.6 32841 5 29.0 32400 0 27.5 31959

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 188 of 195 (Page 2 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 27.4 31930 27.3 31901 27.2 31873 27.1 31845 27.0 31818 26.9 31791 26.8 31765 26.7 31739 26.6 31714 26.5 31689 26.4 31666 26.3 31643 26.2 31620 26.1 31599 26.0 31578 25.9 31559 25.8 31540 25.7 31523 25.6 31506 25.5 31491 25.4 31477 25.3 31464 25.2 31452 25.1 31442

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 189 of 195 (Page 3 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS INVENTORY DESCRIPTION OF PLANT 3 LOOPS SIGNIFICANT RCS ELEVATION ISOLATED LEVELS (FEET) (GALLONS) 25.0 31433 24.9 31425 24.8 31419 24.7 31414 24.6 31411 TOP RX VESSEL 24.5 31410 PRZR SURGE LINE 24.4 31408 24.3 31405 24.2 31400 24.1 31393 24.0 31385 23.9 31379 23.8 31371 23.7 31360 23.6 31346 23.5 31330 23.4 31310 23.3 31289 23.2 31264 23.1 31238 23.0 31209 22.9 31177 22.8 31143

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 190 of 195 (Page 4 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 22.7 31107 22.6 31068 22.5 31028 22.4 30985 22.3 30940 22.2 30893 22.1 30844 22.0 30793 21.9 30740 21.8 30685 21.7 30628 21.6 30570 21.5 30510 21.4 30448 21.3 30385 21.2 30320 21.1 30253 21.0 30184 20.9 30115 20.8 30044 20.7 29972 20.6 29898 20.5 29823

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 191 of 195 (Page 5 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 20.4 29818 20.3 29814 20.2 29743 20.1 29670 20.0 29597 19.9 29523 19.8 29448 19.7 29373 19.6 29297 19.5 29220 19.4 29142 19.3 29064 19.2 28986 19.1 28907 19.0 28828 18.9 28748 18.8 28668 18.7 28588 18.6 28498 18.5 28408 18.4 28318 18.3 28229 18.2 28139

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 192 of 195 (Page 6 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 18.1 28049 18.0 27959 17.9 27870 17.8 27780 17.7 27690 17.6 27600 17.5 27510 17.4 27421 17.3 27331 17.2 27241 17.1 27151 17.0 27062 16.9 26972 16.8 26882 16.7 26791 16.6 26701 16.5 26611 16.4 26521 16.3 26431 16.2 26341 16.1 26250 16.0 26160 15.9 26070

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 193 of 195 (Page 7 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 15.8 25980 Reduced 15.7 25890 Inventory 15.6 25800 15.5 25709 15.4 25619 15.3 25529 15.2 25439 15.1 25349 15.0 25259 14.9 25168 14.8 25078 14.7 24988 14.6 24898 14.5 24808 14.4 24717 14.3 24627 14.2 24537 14.1 24447 14.0 24357 13.9 24267 13.8 24176 13.7 24086 13.6 23996

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 194 of 195 (Page 8 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS)

TOP CL 13.5 23906 NOZZLE 13.4 23816 13.3 23726 13.2 23635 13.1 23545 TOP HOT LEG 13.0 23455 TOP COLD LEG 12.9 23329 12.8 23157 12.7 22946 ADMIN. LIMIT 12.6 22716 12.5 22470 12.4 22211 12.3 21930 12.2 21630 12.1 21319 12.0 21001 11.9 20677 11.8 20352 11.7 20020 11.6 19699 11.5 19385 BOT SURGE 11.4 19086 LINE 11.3 18804

DOMINION 1-DRP-003 Surry Power Station Revision 92 Page 195 of 195 (Page 9 of 9)

Attachment 85 RCS INVENTORY VS PLANT ELEVATION RCS DESCRIPTION INVENTORY OF PLANT 3 LOOPS SIGNIFICANT ELEVATION ISOLATED RCS LEVELS (FEET) (GALLONS) 11.2 18530 11.1 18265 11.0 18012 10.9 17774 10.8 17555 BOT COLD LEG 10.7 17361 BOT HOT LEG 10.6 17214

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 RO 30 Minutes ___________

Initial 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

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 procedure for review by the Unit Supervisor.

G2.1.23 SR10301 1 of 55

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 in its 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 (CTMT SUMP LEVEL).

Final containment sump level was 62% as indicated on 1-DA-LI-100 (CTMT SUMP LEVEL).

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.

Terminating Cues

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 2 of 55

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 3 of 55

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 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 4 of 55

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.

STANDARD:

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

EVALUATORS NOTE:

None.

COMMENTS:

G2.1.23 SR10301 5 of 55

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 6 of 55

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 7 of 55

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 8 of 55

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:

Answer: 35 gallons [range 34 - 36 gallons]

COMMENTS:

G2.1.23 SR10301 9 of 55

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:

Answer: 39 gallons [range 38 - 40 gallons]

COMMENTS:

G2.1.23 SR10301 10 of 55

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]

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 11 of 55

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 12 of 55

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]

COMMENTS:

G2.1.23 SR10301 13 of 55

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 14 of 55

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:

None COMMENTS:

G2.1.23 SR10301 15 of 55

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 COMMENTS:

G2.1.23 SR10301 16 of 55

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 17 of 55

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 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 18 of 55

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 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:

G2.1.23 SR10301 19 of 55

Surry 2010-301 Perform 1-OPT-RC-10.0 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 20 of 55

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

G2.1.23 SR10301 21 of 55

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 This is a critical step.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

G2.1.23 SR10301 22 of 55

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.

(c) STA has initiated a CR and the number is CR123456 EVALUATORS NOTE:

System Engineer: Karlie F. Irwine COMMENTS:

G2.1.23 SR10301 23 of 55

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:

G2.1.23 SR10301 24 of 55

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 in its 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 (CTMT SUMP LEVEL).

Final containment sump level was 62% as indicated on 1-DA-LI-100 (CTMT SUMP LEVEL).

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 in its 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 (CTMT SUMP LEVEL).

Final containment sump level was 62% as indicated on 1-DA-LI-100 (CTMT SUMP LEVEL).

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

SI SI

SI SI SI SI

SI SI SI N/ASI

SI SI SI N/ASI SI N/ASI

N/ASI SI SI 125 SI 0

SI 0

SI N/ASI

SI X

SI

SI Skip Irwin

0 0 0

65 minutes ago 125 minutes ago 60 60

Surry 2010-301 Determine Tagout Boundaries U.S. Nuclear Regulatory Commission Surry Power Station SR10301 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 30 Minutes ___________

Initial Conditions

Task is to be PERFORMED in the CLASSROOM.

Standards

Correctly determine the tagging boundary to allow for maintenance on 1-RT-P-1B.

Initiating Cues

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). This blank flange will be installed in place of the normal suction valve, such that the normal suction valve (1-RT-27) will be removed.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

G2.2.13 SR10301 1 of 12

Surry 2010-301 Determine Tagout Boundaries Initial Conditions

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). This blank flange will be installed in place of the normal suction valve, such that the normal suction valve (1-RT-27) will be removed.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

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-124A SH 2

11448-FE-1K Tools and Equipment Safety Considerations

Computer only connected to Webtop

None Notes G2.2.13 SR10301 2 of 12

Surry 2010-301 Determine Tagout Boundaries 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 Reviews the initial conditions of the JPM and uses Webtop to identify the drawings associated with the Recirc and Transfer System that will be used to generate a safe working boundary. _______ UNSAT STANDARD:

(a) Utilizes Webtop and identifies that the following drawings are applicable:

11448-FM-124A SH 2 and 11448-FE-1K.

EVALUATORS NOTE:

If asked, provide candidate with system to drawing number summary sheet.

COMMENTS:

G2.2.13 SR10301 3 of 12

Surry 2010-301 Determine Tagout Boundaries STEP 2:

_______ SAT Reviews mechanical drawing 11448-FM-124A SH2 and identifies the mechanical boundaries (suction, discharge, vent, and drain) _______ UNSAT NOTE TO EVALUATOR:

There are two possible safe working boundaries for this component. They are listed below as Boundary A and Boundary B. All components for one choice are required for a safe working boundary.

STANDARD:

Boundary A Boundary B RT Suction Isol - CLOSED RT Suction Isol - CLOSED RT Pump ALT suction - CLOSED RT-37(38) - Suction Isol - CLOSED RT Chem injection Isol - CLOSED RT Chem injection Isol - CLOSED RT Discharge isol - CLOSED RT Discharge isol - CLOSED RT Discharge isol - CLOSED RT Pump Suction - OPEN (Not CS) RT Pump Suction - OPEN (Not CS)

Vents/Drains - Numerous Vents/drains exists - at least one of the following drains and at least one of the following vents shall be open.

Boundary A Boundary B RT Suction drain - OPEN RT Suction drain - OPEN RT Suction drain - OPEN RT Suction drain - OPEN RT Discharge drain - OPEN RT Discharge drain - OPEN RT Suction Vent - OPEN RT Suction Vent - OPEN RT Disch Vent - OPEN with PI removed RT Disch Vent - OPEN with PI Removed RT Loop Drain - OPEN RT Suction Vent - OPEN - if 1-RT-38 used instead of 1-RT-37.

This is a critical step.

EVALUATOR NOTES:

Component and component position are both critical.

If asked RT-S-1B will not be removed from the system.

COMMENTS:

G2.2.13 SR10301 4 of 12

Surry 2010-301 Determine Tagout Boundaries STEP 3:

_______ SAT Reviews electrical drawing 11448-FE-1K and identifies the electrical boundary (480V supply breaker) _______ UNSAT STANDARD:

(a) Notes that 1-EP-BKR-1A2-1-4B will need to be opened This is a critical step.

EVALUATOR NOTES:

Candidate may also no tag the control switch in OFF.

Component and component position are both critical.

COMMENTS:

G2.2.13 SR10301 5 of 12

Surry 2010-301 Determine Tagout Boundaries STEP 4 (Boundary A):

_______ SAT Completes the attached table and reports that the task is complete.

_______ UNSAT STANDARD:

Table is completed as follows:

Boundary A Component ID Number / Name Position Danger Tag Required 1 1-RT-P-1B Control Switch OFF No 2 1-EP-BKR-1A2-1-4B (B RT Pump OFF Yes Supply Breaker) 3 1-RT Pump Suction Isolation CLOSED YES 4 1-RT Pump ALT Suction CLOSED YES 5 1-RT Chem Injection Isol CLOSED YES 6 1-RT Pump Discharge Isol CLOSED YES 7 1-RT Pump Discharge Isol CLOSED YES 8 1-RT Pump Suction OPEN NO At least one of the following Drains 9 1-RT Suction Drain OPEN Either is acceptable 9 1-RT Suction Drain OPEN Either is acceptable 9 1-RT Discharge Drain OPEN Either is acceptable At least one of the following Vents 10 1-RT Suction Vent OPEN Either is acceptable 10 1-RT Discharge Vent OPEN w/PI Either is acceptable Removed EVALUATORS NOTE:

Minimum of 1 vent and 1 drain required. Additional vents/drains may be utilized and tags not required to be placed on additional vents/drains.

COMMENTS:

G2.2.13 SR10301 6 of 12

Surry 2010-301 Determine Tagout Boundaries STEP 4 (Boundary B):

_______ SAT Completes the attached table and reports that the task is complete.

_______ UNSAT STANDARD:

Table is completed as follows:

Boundary B Component ID Number / Name Position Danger Tag Required 1 1-RT-P-1B Control Switch OFF No 2 1-EP-BKR-1A2-1-4B (B RT Pump OFF Yes Supply Breaker) 3 1-RT Pump Suction Isolation CLOSED Yes 4 1-RT-37/38 - Pump Suction Isol CLOSED Yes 5 1-RT Chem Injection Isol CLOSED Yes 6 1-RT Pump Discharge Isol CLOSED Yes 7 1-RT Pump Suction OPEN No At least one of the following Drains 8 1-RT Suction Drain OPEN Either is acceptable 8 1-RT Suction Drain OPEN Either is acceptable 8 1-RT Discharge Drain OPEN Either is acceptable 8 1-RT Loop Drain OPEN Either is acceptable At least one of the following Vents 9 1-RT Suction Vent OPEN Either is acceptable 9 1-RT Discharge Vent OPEN w/PI Either is acceptable Removed 9 1-RT Suction Vent OPEN Either is acceptable EVALUATORs NOTE - ONLY IF 1-RT-38 used vs. 1-RT-37 EVALUATORS NOTE: Minimum of 1 vent and 1 drain required. Additional vents/drains may be utilized and tags not required to be placed on additional vents/drains.

COMMENTS:

STOP TIME:

G2.2.13 SR10301 7 of 12

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 1 of 12

Surry 2010-301 Determine Tagout Boundaries G2.2.13 SR10301 2 of 12

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

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). This blank flange will be installed in place of the normal suction valve, such that the normal suction valve (1-RT-27) will be removed.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

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

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B).

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B). This blank flange will be installed in place of the normal suction valve, such that the normal suction valve (1-RT-27) will be removed.

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

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

Unit One is shutdown and chemical cleaning of the B Steam Generator is scheduled for tomorrow. To facilitate this work, a temporary suction blank needs to be installed on the B RT pump (1-RT-P-1B).

I am the Nuclear Shift Manager. I need you to determine the electrical and mechanical tagging boundaries that will allow maintenance to safely install the temporary blank flange on 1-RT-P-1B.

(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 19 20 21 22 23

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 ___________

Initial 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 20

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 20

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 20

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 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 Today/Now COMMENTS:

G2.1.20 SR10301 4 of 20

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 89 °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 Today/Now 89 °F COMMENTS:

G2.1.20 SR10301 5 of 20

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 STANDARD:

a) Utilizing the highest (in accordance with note prior to step 1) of either 1-CV-PI-101A/B 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 Today/Now 89 °F 11.21 (11.17-11.25 range)

Answer:

CV-PI-101A/B- highest reading should be 11.21 psia [range 11.17 - 11.25]

If asked, PCS points are as they appear on printout.

COMMENTS:

G2.1.20 SR10301 6 of 20

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 0.67682 [0.67 - 0.68]

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 Today/Now 89 °F 11.21 (11.17- 0.67682 (0.67-11.25 range) 0.68 range)

Answer: 0.67682 [Acceptable Range 0.67 - 0.68]

COMMENTS:

G2.1.20 SR10301 7 of 20

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 Today/Now 89 °F 11.21 (11.17- 0.67682 (0.67- 10.53 (10.49 -

11.25 range) 0.68 range) 10.58 range)

Answer:

Candidate should calculate Pair to be 10.53 [range 10.49 - 10.58]

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 20

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 96F.

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 20

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 20

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.

- Screen Shots - Screen Shots - Screen Shots Attachment 1 - Screen Shots 98.2 DEGF 111.8 DEGF 108.4 DEGF 103.4 DEGF 98.0 DEGF 97.6 DEGF 92.3 DEGF 91.4 DEGF 95.6 DEGF 89.6 DEGF 89.7 DEGF 89.0 DEGF 96.5 DEGF 92.7 DEGF 92.5 DEGF 108.2 DEGF 102.3 DEGF 89.3 DEGF 93.0 DEGF 98.0 DEGF

Attachment 1 - Screen Shots OUTLET TEMP OUTLET TEMP OUTLET TEMP OUTLET TEMP 101.0 DEGF 101.0 DEGF 100.0 DEGF 101.0 DEGF INLET TEMP INLET TEMP INLET TEMP INLET TEMP 96.0 DEG 96.0 DEG 96.0 DEG 96.0 DEG

Surry 2010-301 PT Review (1-OPT-CH-002)

U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure GEN2.2.37 (3.6/4.6)

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 Initial Conditions

Task is to be PERFORMED in the classroom.

Standards

Reviews completed 1-OPT-CH-002 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B, for accuracy and determines operability.

Initiating Cues

I am the Shift Manager and you are the Unit Supervisor. Here is a copy of 1-OPT-CH-002 (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.

This was a quarterly test.

Review 1-OPT-CH-002 (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.

G2.2.37 SR10301 1 of 14

Surry 2010-301 PT Review (1-OPT-CH-002)

Terminating Cues

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

Tools and Equipment

Calculator

Copy of completed 1-OPT-CH-002 (REV 47), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B.

Safety Considerations

None Notes G2.2.37 SR10301 2 of 14

Surry 2010-301 PT Review (1-OPT-CH-002)

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:

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

_______ UNSAT STANDARD:

Reviews purpose of procedure steps 1.1 - 1.9.

EVALUATORS NOTE: N/A COMMENTS:

STEP 2:

_______ SAT STEP 2 - Review the References section (Section 2.0)

_______ UNSAT STANDARD:

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

EVALUATORS NOTE: N/A COMMENTS:

G2.2.37 SR10301 3 of 14

Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 3:

_______ SAT STEP 3 - Reviews the Initial Conditions section (Section 3.0)

_______ UNSAT STANDARD:

Reviews Initial Conditions steps 3.1 - 3.4.

EVALUATORS NOTE: N/A COMMENTS:

STEP 4:

_______ SAT STEP 4 - Reviews the Precautions and Limitations section (Section 4.0)

_______ UNSAT STANDARD:

Reviews precautions and limitations steps 4.1 - 4.15.

EVALUATORS NOTE: N/A COMMENTS:

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Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 5:

_______ SAT STEP 5 - Reviews the Special Tools and Equipment section (Section 5.0)

_______ UNSAT STANDARD:

Reviews Special Tools and Equipment section steps 5.1 - 5.8.

EVALUATORS NOTE: N/A COMMENTS:

STEP 6:

_______ SAT STEP 6.1 - Reviews Work Preparation section (Section 6.1).

_______ UNSAT STANDARD:

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

Verifies step 6.1.1 is N/Ad.

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. CANDIDATE IDENTIFIES THAT ONE STOPWATCH USED IS NOT IN CAL - THIS IS A CRITICAL STEP

Verifies step 6.1.4 is initialed.

th Verifies step 6.1.5 is initialed and blocks are correctly checked off. The 6 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.

EVALUATORS NOTE: N/A COMMENTS:

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Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 7:

_______ SAT STEPS 6.2-6.4 - Reviews Steps 6.2 - 6.4 of 1-OPT-CH-002

_______ UNSAT STANDARD:

Verifies all steps in 6.2 - 6.4 are N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

STEP 8:

_______ SAT 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 _______ UNSAT 6.5.1 - 6.5.20).

STANDARD:

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/Ad.

Verifies step 6.5.6.a is N/Ad.

Verifies step 6.5.7 is N/Ad.

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/Ad.

Verifies step 6.5.12 is N/Ad.

Verifies lube oil pressure recorded in step 6.5.16 is between 8-35 psig.

Verifies step 6.5.17 N/Ad.

Verifies pump and damper checks were sat IAW step 6.5.20 on non-running charging pumps.

EVALUATORS NOTE: N/A COMMENTS:

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Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 9:

_______ SAT STEP 6.6- Reviews 1-CH-P-1B Performance Test section of procedure (Section 6.6.1 - 6.6.26). _______ UNSAT 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/Ad.

Verifies data is recorded in step 6.6.5 - 6.6.7.

Verifies step 6.6.10.b is N/Ad.

Verifies data recorded on Attachments 1 and 2 IAW steps 6.6.12 - 6.6.16.

Verifies step 6.6.17 and step 6.6.18 are N/Ad.

Verifies data is recorded in step 6.6.22.

Verifies step 6.6.26 N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

STEP 10:

_______ SAT STEPS 6.7-6.8 - Reviews Steps 6.7 - 6.8 of 1-OPT-CH-002

_______ UNSAT STANDARD:

Verifies all steps in 6.7 - 6.8 are N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

STEP 11:

_______ SAT STEP 6.9- Reviews Obtaining Oil Samples section of procedure Section 6.9.1-6.9.2). _______ UNSAT 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/Ad.

EVALUATORS NOTE: N/A COMMENTS:

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Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 12:

_______ SAT STEP 6.10 - Reviews Step 6.10 of 1-OPT-CH-002.

_______ UNSAT STANDARD:

Verifies all steps of 6.10 are N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

STEP 12:

_______ SAT STEP 7.0- Reviews Follow-On section of procedure (Section 7.1 - 7.4).

_______ UNSAT 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.

EVALUATORS NOTE: N/A COMMENTS:

STEP 13:

_______ SAT - Reviews Attachment 1 Data.

_______ UNSAT STANDARD:

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

Step 6.1.3 - CANDIDATE IDENTIFIES THAT ONE STOPWATCH USED IS NOT IN CAL - THIS IS A CRITICAL STEP EVALUATORS NOTE: N/A COMMENTS:

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Surry 2010-301 PT Review (1-OPT-CH-002)

STEP 14:

_______ SAT - Reviews Attachment 2 Data.

_______ UNSAT 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.

EVALUATORS NOTE: N/A COMMENTS:

STEP 15:

_______ SAT - Reviews Attachment 4 Data.

_______ UNSAT 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.

EVALUATORS NOTE: N/A COMMENTS:

STEP 16:

_______ SAT - Reviews Attachment 9.

_______ UNSAT STANDARD:

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

Verifies all steps in attachment 9 are properly initialed or N/Ad as applicable.

EVALUATORS NOTE: N/A COMMENTS:

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STOP TIME:

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ANSWER KEY 1-OPT-CH-002 REVIEW

1. Attachment 1, Step 6.1.3 - Listed stopwatch is out of CAL. (CRITICAL TASK)

2. Attachment 2, outboard horizontal vibration (pt 22) on the pump exceeds the inoperable range limit given. (CRITICAL TASK)

3. Attachment 4, 1-CH-MOV-1287B exceeds open stroke time limits. (CRITICAL TASK)

4. 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.

5. 7.1.2, PT is marked as SAT versus UNSAT. (CRITICAL TASK)

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

7. No comments made in the Operator Comments section.

8. 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)

9. 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)

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

Task

Task is to be performed in the classroom.

Review 1-OPT-CH-002 (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-002 (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-002 (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.

This was a quarterly test.

Review 1-OPT-CH-002 (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.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 is at 100% power.

1-OPT-CH-002 (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-002 (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.

This was a quarterly test.

Review 1-OPT-CH-002 (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.

ANSWER SHEET 1-OPT-CH-002 REVIEW

Date Total(gpm) Identified(gpm) Unidentified(gpm) Sump(gpm) 'A' (gpd) 05/15/09 0.320 0.290 0.030 0.180 0.200 05/16/09 0.360 0.300 0.060 0.190 0.300 05/17/09 0.310 0.270 0.040 0.180 0.300 05/18/09 0.290 0.260 0.030 0.170 0.300 05/19/09 0.310 0.220 0.090 0.160 0.300 05/20/09 0.290 0.200 0.080 0.150 0.300 05/21/09 0.260 0.230 0.030 0.140 0.300 05/22/09 0.270 0.200 0.070 0.150 0.300 05/23/09 0.250 0.170 0.080 0.140 0.300 05/24/09 0.230 0.230 0.000 0.150 0.300 05/25/09 0.230 0.220 0.010 0.130 0.300 05/26/09 0.230 0.180 0.050 0.120 0.300 05/27/09 0.220 0.220 0.000 0.130 0.300 05/28/09 0.230 0.190 0.040 0.140 0.300 05/29/09 0.850 0.810 0.040 0.130 0.300 05/30/09 0.380 0.360 0.020 0.120 0.300 05/31/09 0.310 0.310 0.000 0.140 0.300 06/01/09 0.280 0.250 0.030 0.140 0.200 06/02/09 0.260 0.260 0.000 0.140 0.200 06/03/09 0.250 0.240 0.010 0.150 0.300 06/04/09 0.280 0.270 0.010 0.140 0.300 06/05/09 0.260 0.210 0.050 0.140 0.300 06/06/09 0.240 0.240 0.000 0.140 0.300 06/07/09 0.230 0.170 0.060 0.130 0.300 06/08/09 0.230 0.210 0.020 0.130 0.300 06/09/09 0.260 0.210 0.050 0.120 0.300 06/10/09 0.230 0.220 0.010 0.150 0.300 06/11/09 0.260 0.200 0.060 0.130 0.300 06/12/09 0.230 0.230 0.000 0.190 0.300 06/13/09 0.220 0.190 0.030 0.140 0.300 06/14/09 0.310 0.230 0.100 0.150 0.300 06/15/09 0.270 0.200 0.080 0.140 0.300 06/16/09 0.280 0.180 0.100 0.150 0.300 06/17/09 0.260 0.190 0.060 0.150 0.300 06/18/09 0.260 0.200 0.030 0.150 0.300 06/19/09 0.270 0.190 0.080 0.130 0.300 06/20/09 0.260 0.200 0.060 0.130 0.300 06/21/09 0.280 0.170 0.110 0.000 0.300 06/22/09 0.270 0.210 0.060 0.140 0.200 06/23/09 0.270 0.210 0.060 0.150 0.300 06/24/09 0.280 0.270 0.090 0.300 0.300 06/25/09 0.690 0.690 0.000 0.170 0.300 06/26/09 0.440 0.410 0.030 0.180 0.300 06/27/09 0.380 0.350 0.030 0.190 0.300 06/28/09 0.350 0.300 0.050 0.170 0.300 06/29/09 0.320 0.260 0.050 0.170 0.300

06/30/09 0.320 0.240 0.080 0.170 0.300 07/01/09 0.320 0.240 0.090 0.170 0.300 07/02/09 0.350 0.290 0.080 0.180 0.300 07/03/09 0.310 0.260 0.050 0.170 0.300 07/04/09 0.300 0.240 0.060 0.170 0.300 07/05/09 0.300 0.260 0.040 0.160 0.300 07/06/09 0.280 0.230 0.050 0.170 0.300 07/07/09 0.280 0.250 0.030 0.150 0.300 07/08/09 0.290 0.210 0.080 0.160 0.300 07/09/09 0.270 0.270 0.010 0.160 0.300 07/10/09 0.270 0.220 0.050 0.150 0.300 07/11/09 0.270 0.220 0.050 0.160 0.300 07/12/09 0.260 0.200 0.060 0.160 0.300 07/13/09 0.270 0.220 0.050 0.150 0.300 07/14/09 0.260 0.170 0.090 0.170 0.300 07/15/09 0.270 0.230 0.040 0.190 0.300 07/16/09 0.280 0.180 0.100 0.200 0.300 07/17/09 0.250 0.240 0.010 0.170 0.300 07/18/09 0.240 0.190 0.050 0.190 0.300 07/19/09 0.270 0.190 0.070 0.170 0.300 07/20/09 0.240 0.210 0.030 0.170 0.300 07/21/09 0.280 0.220 0.050 0.190 0.300 07/22/09 0.260 0.210 0.050 0.180 0.300 07/23/09 0.270 0.160 0.110 0.180 0.300 07/24/09 0.280 0.180 0.100 0.180 0.300 07/25/09 0.280 0.160 0.120 0.160 0.300 07/26/09 0.280 0.200 0.090 0.170 0.300 07/27/09 0.260 0.180 0.090 0.170 0.300 07/28/09 0.270 0.220 0.050 0.170 0.300 07/29/09 0.270 0.160 0.110 0.190 0.300 07/30/09 0.240 0.190 0.050 0.150 0.300 07/31/09 0.260 0.190 0.070 0.150 0.300 08/01/09 0.240 0.170 0.070 0.170 0.300 08/02/09 0.260 0.190 0.070 0.170 0.300 08/03/09 0.230 0.190 0.050 0.170 0.300 08/04/09 0.260 0.160 0.090 0.165 0.300 08/05/09 0.260 0.180 0.090 0.161 0.300 08/06/09 0.260 0.220 0.040 0.157 0.300 08/07/09 0.250 0.160 0.090 0.150 0.300 08/08/09 0.250 0.160 0.090 0.160 0.300 08/09/09 0.250 0.170 0.090 0.140 0.300 08/10/09 0.250 0.160 0.090 0.160 0.300 08/11/09 0.280 0.170 0.110 0.160 0.300 08/12/09 0.270 0.190 0.080 0.150 0.300 08/13/09 0.260 0.260 0.010 0.150 0.300 08/14/09 0.250 0.190 0.060 0.150 0.300 08/15/09 0.240 0.190 0.050 0.150 0.300

08/16/09 0.260 0.200 0.060 0.150 0.300 08/17/09 0.250 0.190 0.060 0.290 0.300 08/18/09 0.260 0.190 0.070 0.160 0.300 08/19/09 0.260 0.200 0.070 0.170 0.300 08/20/09 0.250 0.180 0.070 0.160 0.300 08/21/09 0.250 0.190 0.060 0.150 0.300 08/22/09 0.230 0.210 0.020 0.160 0.300 08/23/09 0.250 0.180 0.060 0.150 0.300 08/24/09 0.240 0.200 0.030 0.170 0.300 08/25/09 0.260 0.190 0.070 0.160 0.300 08/26/09 0.260 0.210 0.060 0.160 0.300 08/27/09 0.300 0.240 0.060 0.160 0.300 08/28/09 0.230 0.170 0.060 0.160 0.300 08/29/09 0.230 0.230 0.010 0.150 0.300 08/30/09 0.270 0.240 0.030 0.150 0.300 08/31/09 0.250 0.170 0.090 0.150 0.300 09/01/09 0.290 0.200 0.090 0.160 0.300 09/02/09 0.260 0.190 0.070 0.150 0.300 09/03/09 0.230 0.190 0.040 0.160 0.300 09/04/09 0.280 0.180 0.100 0.150 0.300 09/05/09 0.250 0.180 0.070 0.150 0.300 09/06/09 0.340 0.290 0.080 0.140 0.300 09/07/09 0.240 0.150 0.090 0.140 0.300 09/08/09 0.310 0.250 0.050 0.140 0.300 09/09/09 0.300 0.280 0.020 0.150 0.300 09/10/09 0.340 0.290 0.050 0.110 0.300 09/11/09 0.270 0.210 0.060 0.120 0.300 09/12/09 0.310 0.240 0.080 0.150 0.300 09/13/09 0.240 0.210 0.030 0.180 0.300 09/14/09 0.290 0.200 0.090 0.110 0.300 09/15/09 0.280 0.170 0.100 0.110 0.300 09/16/09 0.230 0.160 0.070 0.130 0.300 09/17/09 0.230 0.160 0.070 0.130 0.300 09/18/09 0.220 0.130 0.090 0.110 0.300 09/19/09 0.280 0.220 0.060 0.130 0.300 09/20/09 0.220 0.150 0.070 0.110 0.300 09/21/09 0.220 0.160 0.060 0.140 0.300 09/22/09 0.200 0.170 0.030 0.100 0.300 09/23/09 0.280 0.210 0.070 0.170 0.300 09/24/09 0.160 0.130 0.030 0.210 0.300 09/25/09 0.280 0.240 0.040 0.230 0.300 09/26/09 0.220 0.170 0.040 0.160 0.300 09/27/09 0.280 0.180 0.090 0.140 0.300 09/28/09 0.210 0.110 0.100 0.180 0.300 09/29/09 0.260 0.170 0.090 0.150 0.300 09/30/09 0.320 0.250 0.060 0.140 0.300 10/01/09 0.320 0.240 0.080 0.200 0.300

10/02/09 0.280 0.250 0.030 0.140 0.300 10/03/09 0.270 0.200 0.070 0.170 0.300 10/04/09 0.300 0.240 0.060 0.130 0.300 10/05/09 0.270 0.220 0.060 0.190 0.300 10/06/09 0.280 0.290 0.000 0.190 0.300 10/07/09 0.210 0.210 0.000 0.190 0.300 10/08/09 0.180 0.150 0.020 0.130 0.300 10/09/09 0.330 0.260 0.070 0.120 0.300 10/10/09 0.320 0.290 0.030 0.110 0.300 10/11/09 0.330 0.290 0.040 0.180 0.300 10/12/09 0.250 0.180 0.070 0.140 0.300 10/13/09 0.350 0.290 0.060 0.120 0.300 10/14/09 0.380 0.330 0.050 0.130 0.300 10/15/09 0.340 0.270 0.070 0.140 0.300 10/16/09 0.180 0.150 0.030 0.110 0.300 10/17/09 0.200 0.200 0.010 0.110 0.300 10/18/09 0.160 0.150 0.010 0.110 0.300 10/19/09 0.370 0.350 0.010 0.120 0.300 10/20/09 0.500 0.460 0.040 0.120 0.300 10/21/09 0.370 0.350 0.020 0.110 0.300 10/22/09 0.410 0.410 0.000 0.170 0.300 10/23/09 0.480 0.480 0.000 0.150 0.300 10/24/09 0.420 0.360 0.060 0.150 0.300 10/25/09 0.530 0.420 0.110 0.150 0.300 10/26/09 0.310 0.250 0.060 0.150 0.300 10/27/09 0.300 0.200 0.100 0.140 0.300 10/28/09 0.360 0.350 0.000 0.140 0.300 10/29/09 0.290 0.290 0.000 0.160 0.300 10/30/09 0.390 0.310 0.080 0.160 0.300 10/31/09 0.500 0.380 0.120 0.140 0.300 11/01/09 0.490 0.450 0.040 0.130 0.300 11/02/09 0.340 0.260 0.070 0.140 0.300 11/03/09 0.370 0.260 0.110 0.140 0.300 11/04/09 0.450 0.450 0.000 0.140 0.300 11/05/09 0.410 0.380 0.030 0.130 0.300 11/06/09 0.470 0.390 0.080 0.120 0.300 11/07/09 0.400 0.270 0.130 0.140 0.300 11/08/09 0.230 0.160 0.070 0.150 0.300 11/09/09 0.520 0.460 0.060 0.130 0.300 11/10/09 0.470 0.390 0.080 0.130 0.300 11/11/09 0.350 0.290 0.060 0.147 0.300 11/12/09 0.470 0.380 0.090 0.150 0.300 11/13/09 0.520 0.430 0.090 0.140 0.300 11/14/09 0.450 0.360 0.090 0.130 0.300 11/15/09 0.330 0.270 0.060 0.130 0.300 11/16/09 0.420 0.330 0.090 0.130 0.300 11/17/09 0.550 0.500 0.040 0.140 0.300

11/18/09 0.560 0.540 0.020 0.140 0.300 11/19/09 0.390 0.300 0.090 0.140 0.300 11/20/09 0.420 0.390 0.040 0.140 0.300 11/21/09 0.500 0.430 0.070 0.140 0.300 11/22/09 0.530 0.500 0.020 0.140 0.300 11/23/09 0.540 0.480 0.060 0.140 0.300 11/24/09 0.390 0.320 0.070 0.140 0.300 11/25/09 0.600 0.520 0.080 0.140 0.300 11/26/09 0.700 0.660 0.040 0.130 0.300 11/27/09 0.530 0.480 0.050 0.130 0.300 11/28/09 0.550 0.530 0.020 0.130 0.300 11/29/09 0.540 0.500 0.040 0.130 0.300 11/30/09 0.640 0.560 0.070 0.130 0.300 12/01/09 0.600 0.500 0.110 0.130 0.300 12/02/09 0.470 0.370 0.100 0.140 0.300 12/03/09 0.430 0.410 0.020 0.180 0.300 12/04/09 0.550 0.430 0.120 0.140 0.300 12/05/09 0.560 0.440 0.120 0.135 0.300 12/06/09 0.650 0.550 0.100 0.125 0.300 12/07/09 0.330 0.290 0.050 0.130 0.300 12/08/09 0.510 0.490 0.020 0.140 0.300 12/09/09 0.540 0.430 0.100 0.140 0.300 12/10/09 0.520 0.440 0.080 0.130 0.300 12/11/09 0.360 0.270 0.090 0.130 0.300 12/12/09 0.500 0.470 0.030 0.130 0.300 12/13/09 0.610 0.530 0.080 0.130 0.300 12/14/09 0.620 0.520 0.100 0.130 0.300 12/15/09 0.730 0.670 0.060 0.140 0.300 12/16/09 0.290 0.230 0.070 0.110 0.300 12/17/09 0.330 0.250 0.080 0.100 0.300 12/18/09 0.510 0.400 0.110 0.090 0.300 12/19/09 0.390 0.340 0.050 0.140 0.300 12/20/09 0.540 0.430 0.110 0.120 0.300 12/21/09 0.250 0.150 0.100 0.130 0.300 12/22/09 0.470 0.370 0.100 0.130 0.300 12/23/09 0.500 0.410 0.090 0.100 0.300 12/24/09 0.370 0.270 0.110 0.110 0.300 12/25/09 0.280 0.250 0.040 0.120 0.400 12/26/09 0.400 0.330 0.070 0.120 0.300 12/27/09 0.520 0.400 0.120 0.130 0.300 12/28/09 0.570 0.470 0.100 0.130 0.200 12/29/09 0.570 0.540 0.030 0.130 0.300 12/30/09 0.540 0.390 0.150 0.100 0.300 12/31/09 0.420 0.310 0.100 0.100 0.300 01/01/10 0.450 0.410 0.050 0.110 24.300 01/02/10 0.350 0.230 0.120 0.125 24.400 01/03/10 0.510 0.460 0.060 0.120 24.100

01/04/10 0.480 0.350 0.130 0.130 24.500 01/05/10 0.240 0.220 0.020 0.120 24.400 01/06/10 0.410 0.350 0.060 0.110 24.300 01/07/10 0.560 0.510 0.040 0.130 24.400 01/08/10 0.640 0.610 0.030 0.110 24.200 01/09/10 0.420 0.320 0.100 0.120 24.400 01/10/10 0.730 0.570 0.170 0.165 24.300 01/11/10 0.570 0.470 0.110 0.120 24.200 01/12/10 0.660 0.540 0.120 0.160 24.400 01/13/10 0.560 0.470 0.090 0.120 24.200 01/14/10 0.560 0.470 0.090 0.140 24.300 01/15/10 0.690 0.610 0.080 0.030 24.500 01/16/10 0.460 0.380 0.070 0.120 24.200 01/17/10 0.680 0.600 0.080 0.120 24.400 01/18/10 0.530 0.410 0.120 0.110 24.400 01/19/10 0.570 0.490 0.080 0.120 24.300 01/20/10 0.510 0.410 0.110 0.110 24.500 01/21/10 0.720 0.650 0.080 0.120 24.200 01/22/10 0.630 0.530 0.100 0.130 24.400 01/23/10 0.520 0.500 0.020 0.120 24.400 01/24/10 0.660 0.500 0.160 0.190 24.500 01/25/10 0.550 0.480 0.080 0.100 24.400 01/26/10 0.760 0.760 0.000 0.130 24.300 01/27/10 0.450 0.370 0.090 0.100 24.400 01/28/10 0.800 0.760 0.030 0.120 24.200 01/29/10 0.590 0.520 0.070 0.133 24.400 01/30/10 0.630 0.580 0.050 0.116 24.300 01/31/10 0.550 0.500 0.050 0.099 24.200 02/01/10 0.740 0.710 0.030 0.113 24.400 02/02/10 0.730 0.610 0.130 0.140 24.200 02/03/10 0.580 0.490 0.090 0.096 24.300 02/04/10 0.510 0.420 0.090 0.120 24.500 02/05/10 0.820 0.790 0.030 0.140 24.200 02/06/10 0.570 0.570 0.000 0.130 24.400 02/07/10 0.590 0.480 0.110 0.120 24.400 02/08/10 0.660 0.560 0.110 0.120 24.300 02/09/10 0.720 0.660 0.060 0.123 24.400 02/10/10 0.520 0.410 0.100 0.136 24.100 02/11/10 0.470 0.430 0.040 0.090 24.500 02/12/10 0.640 0.560 0.080 0.090 24.400 02/13/10 0.540 0.440 0.090 0.110 24.300 02/14/10 0.560 0.500 0.060 0.160 24.400 02/15/10 0.500 0.340 0.160 0.120 24.200 02/16/10 0.470 0.360 0.120 0.109 24.400 02/17/10 0.630 0.470 0.150 0.128 24.300 02/18/10 0.470 0.290 0.170 0.141 24.200 02/19/10 0.250 0.230 0.020 0.120 24.400

02/20/10 0.370 0.290 0.080 0.130 24.200 02/21/10 0.600 0.470 0.130 0.150 24.300 02/22/10 0.600 0.590 0.010 0.200 24.500 02/23/10 0.730 0.630 0.090 0.130 24.200 02/24/10 0.510 0.390 0.120 0.110 24.400 02/25/10 0.560 0.480 0.090 0.120 24.400 02/26/10 0.800 0.730 0.070 0.120 24.300 02/27/10 0.600 0.540 0.060 0.140 24.500 02/28/10 0.580 0.530 0.050 0.100 24.200 03/01/10 0.610 0.530 0.090 0.130 24.400 03/02/10 0.680 0.680 0.000 0.170 24.400 03/03/10 0.480 0.440 0.040 0.120 24.300 03/04/10 0.310 0.310 0.000 0.100 24.400 03/05/10 0.420 0.340 0.080 0.123 24.100 03/06/10 0.430 0.390 0.040 0.151 24.500 03/07/10 0.510 0.500 0.010 0.120 24.400 03/08/10 0.400 0.330 0.080 0.110 24.300 03/09/10 0.520 0.470 0.050 0.150 24.400 03/10/10 0.500 0.420 0.080 0.170 24.200 03/11/10 0.780 0.710 0.070 0.120 24.400 03/12/10 0.690 0.640 0.050 0.120 24.300 03/13/10 0.600 0.540 0.060 0.140 24.200 03/14/10 0.480 0.430 0.040 0.160 24.400 03/15/10 0.570 0.570 0.000 0.120 24.200 03/16/10 0.640 0.640 0.000 0.110 24.300 03/17/10 0.360 0.300 0.060 0.130 24.500 03/18/10 0.410 0.380 0.030 0.100 24.200 03/19/10 0.270 0.250 0.020 0.100 24.400 03/20/10 0.330 0.280 0.060 0.140 24.400 03/21/10 0.390 0.360 0.030 0.150 24.400 03/22/10 0.230 0.230 0.000 0.140 24.300 03/23/10 0.530 0.530 0.000 0.126 24.400 03/24/10 0.340 0.290 0.050 0.142 24.100 03/25/10 0.570 0.530 0.040 0.120 24.500 03/26/10 0.810 0.730 0.070 0.120 24.400 03/27/10 0.380 0.300 0.080 0.130 24.300 03/28/10 0.330 0.270 0.060 0.130 24.400 03/29/10 0.340 0.300 0.040 0.110 24.200 03/30/10 0.500 0.500 0.000 0.110 24.400 03/31/10 0.560 0.560 0.000 0.130 24.300 04/01/10 0.440 0.440 0.000 0.120 24.200 04/02/10 0.280 0.240 0.040 0.130 24.400 04/03/10 0.340 0.270 0.060 0.110 24.200 04/04/10 0.380 0.380 0.000 0.110 24.300 04/05/10 0.180 0.180 0.000 0.100 24.500 04/06/10 0.490 0.480 0.020 0.130 24.200 04/07/10 0.400 0.400 0.000 0.100 24.400

04/08/10 0.320 0.300 0.030 0.170 24.400 04/09/10 0.430 0.430 0.000 0.142 24.200 04/10/10 0.170 0.150 0.020 0.139 24.300 04/11/10 0.500 0.500 0.000 0.135 24.500 04/12/10 0.470 0.430 0.040 0.115 24.200 04/13/10 0.400 0.400 0.000 0.140 24.400 04/14/10 0.670 0.670 0.000 0.140 24.400 04/15/10 0.330 0.330 0.000 0.130 24.300 04/16/10 0.350 0.300 0.050 0.130 24.400 04/17/10 0.730 0.660 0.070 0.160 24.100 04/18/10 0.400 0.400 0.000 0.190 24.500 04/19/10 0.180 0.150 0.030 0.160 24.400 04/20/10 0.300 0.300 0.000 0.160 24.300 04/21/10 0.440 0.440 0.000 0.120 24.400 04/22/10 0.280 0.270 0.100 0.140 24.200 04/24/10 0.560 0.500 0.060 0.130 24.400 04/25/10 0.230 0.190 0.040 0.150 24.300 04/26/10 0.570 0.570 0.000 0.122 24.200 04/27/10 0.143 0.340 0.000 0.150 24.400 04/28/10 0.138 0.430 0.010 0.110 24.200 04/29/10 0.300 0.290 0.010 0.150 24.300 04/30/10 0.340 0.340 0.000 0.140 24.500 05/01/10 0.510 0.490 0.020 0.140 24.200 05/02/10 0.380 0.350 0.030 0.120 24.400 05/03/10 0.400 0.400 0.000 0.110 24.400 05/04/10 0.150 0.150 0.000 0.120 24.100 05/05/10 0.190 0.140 0.050 0.130 24.300 05/06/10 0.210 0.140 0.060 0.180 24.400 05/07/10 0.220 0.160 0.060 0.140 24.100 05/08/10 0.200 0.130 0.080 0.140 24.500 05/09/10 0.210 0.120 0.050 0.120 24.400 05/10/10 0.230 0.150 0.070 0.140 24.300 05/11/10 0.210 0.140 0.070 0.130 24.400 05/12/10 0.240 0.170 0.060 0.160 24.200 05/13/10 0.220 0.150 0.070 0.150 24.400 05/14/10 0.250 0.180 0.060 0.140 24.300 05/15/10 0.240 0.150 0.090 0.140 24.200 05/16/10 0.220 0.120 0.110 0.130 24.400 05/17/10 0.250 0.150 0.100 0.130 24.200 05/18/10 0.230 0.130 0.090 0.130 24.300 05/19/10 0.230 0.140 0.100 0.130 24.500 05/20/10 0.250 0.160 0.090 0.130 24.200 05/21/10 0.250 0.160 0.090 0.130 24.400

'B' (gpd) 'C' (gpd) 1.100 0.300 1.100 0.200 1.100 0.200 1.000 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.000 0.300 1.100 0.300 1.100 0.300 1.000 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.300 1.100 0.300 1.100 0.300 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200

1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200

1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.000 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.000 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.000 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.400 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200

1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200

1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.000 0.200 1.100 0.200 1.100 0.300 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.000 0.200 1.000 0.200 1.000 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 1.100 0.200 15.100 25.600 15.200 25.100 15.300 25.300

14.900 25.700 14.800 25.400 14.600 25.600 14.800 25.300 14.600 25.700 14.200 25.400 15.000 25.400 15.200 25.300 15.300 25.700 14.800 25.400 14.900 25.400 15.200 25.600 15.300 25.100 15.200 25.300 15.200 25.700 15.100 25.400 15.200 25.600 15.300 25.300 14.900 25.700 14.800 25.400 14.600 25.400 14.800 25.600 14.600 25.100 14.200 25.300 15.000 25.700 15.200 25.400 15.300 25.100 14.800 25.300 14.900 25.600 15.200 25.300 15.300 25.700 15.200 25.400 15.200 25.400 15.200 25.600 15.300 25.100 14.800 25.300 14.900 25.700 15.200 25.400 15.300 25.600 15.200 25.300 15.200 25.700 15.300 25.400 14.900 25.400 14.900 25.600 14.800 25.100 14.600 25.300 14.800 25.700

14.600 25.400 14.700 25.600 15.000 25.200 14.900 25.300 15.100 25.600 15.200 25.300 15.300 25.700 14.900 25.400 14.800 25.400 14.600 25.600 14.700 25.100 15.000 25.300 15.100 25.700 15.200 25.400 15.300 25.600 14.900 25.300 14.800 25.700 14.600 25.400 14.800 25.400 14.600 25.600 14.200 25.100 15.000 25.300 15.200 25.700 15.300 25.400 14.800 25.600 14.900 25.300 15.200 25.600 15.300 25.300 15.200 25.700 15.200 25.400 15.300 25.400 14.900 25.600 14.900 25.100 14.800 25.300 14.600 25.700 14.800 25.400 14.600 25.600 14.700 25.300 15.000 25.700 14.900 25.400 15.100 25.400 15.200 25.600 15.300 25.100 14.900 25.300 14.800 25.700 14.600 25.400 14.800 25.600

14.600 25.300 14.200 25.600 15.000 25.300 15.200 25.700 15.300 25.400 14.800 25.400 14.900 25.600 15.200 25.100 15.300 25.300 15.200 25.700 15.200 25.400 15.300 25.600 14.900 25.300 14.900 25.700 14.800 25.400 14.600 25.400 14.800 25.600 14.600 25.100 14.200 25.300 15.000 25.700 15.200 25.400 15.300 25.600 14.800 25.300 14.900 25.600 15.200 25.300 15.300 25.700 15.200 25.400 15.200 25.400 15.300 25.600 14.900 25.100 14.800 25.300 14.600 25.700 14.800 25.400 14.600 25.600 14.200 25.300 15.000 25.700 15.200 25.400 15.300 25.400 14.800 25.600 14.900 25.100 15.200 25.300 15.300 25.700 15.200 25.400

Surry 2010-301 Calculate Stay Time U.S. Nuclear Regulatory Commission Surry Power Station SR10301 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.

G2.3.4 SR10301 1 of 85

Surry 2010-301 Calculate Stay Time 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 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

None

Computer with only access to Webtop Notes G2.3.4 SR10301 2 of 85

Surry 2010-301 Calculate Stay Time 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 Answer to first question by the Shift Manager:

_______ UNSAT 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.

EVALUATORS 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.

COMMENTS:

G2.3.4 SR10301 3 of 85

Surry 2010-301 Calculate Stay Time STEP 2:

_______ SAT Answer to second question by the Shift Manager:

_______ UNSAT 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.

EVALUATORS 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:

G2.3.4 SR10301 4 of 85

Surry 2010-301 Calculate Stay Time STEP 3:

_______ SAT Reports task is complete.

_______ UNSAT 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.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

STOP TIME:

G2.3.4 SR10301 5 of 85

Surry 2010-301 Perform 1-OPT-RC-10.0 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

Task may be PERFORMED in the simulator or classroom.

Correctly determines 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 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.

G2.1.23 SR10301 1 of 85

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

G2.1.23 SR10301 2 of 85

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

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)

G2.1.23 SR10301 3 of 85

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) 40 Minutes ___________

Initial 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

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 4 of 85

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 (CTMT SUMP LEVEL).

Final containment sump level was 62% as indicated on 1-DA-LI-100 (CTMT SUMP LEVEL).

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 in its 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 5 of 85

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 6 of 85

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 7 of 85