Text

301 Final Admin JPMs
	ML16007A505
Person / Time
Site:	Surry
Issue date:	01/07/2016
From:	; Division of Reactor Safety II
To:	; Virginia Electric & Power Co (VEPCO)
References
	Download: ML16007A505 (80)
	v • d • e

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 1 of 25 U.S. Nuclear Regulatory Commission Surry Power Station SR15301 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/SROI/SROU 45 Minutes Initial Conditions Task is to be PERFORMED in the CLASSROOM.

Performance of 2-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 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations.

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

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 2 of 25 Initial Conditions It is mid shift on Saturday. Unit 2 power is 100 percent.

2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations is scheduled to be completed on this shift.

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

Core burnup: 12147 MWD/MTU Isothermal temperature coefficient: -25.81 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: 529 ppm Control Bank D is at 225 steps C BAST is in-service on Unit 2 with a boron concentration of 13772 ppm.

A power reduction has not occurred and is not planned.

Here is a copy of 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations, through Step 5.2.4, and I will have another Operator complete the procedure.

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 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations (Revision 10).

2-DRP-003R, Curve Book, Revision 28, Table of contents and pages 52-72.

SRO-Only Question: Surry Technical Specifications.

Tools and Equipment Safety Considerations Calculator None Notes

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 3 of 25 Performance Checklist Notes to the Evaluator.

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

START TIME:

STEP 1:

3.0 INITIAL CONDITIONS 3.1 Unit 2 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:

_______ SAT

_______ UNSAT STEP 2:

Note prior to Step 5.1.1:

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

STANDARD:

(a) Acknowledges the Note.

EVALUATORS NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 4 of 25 STEP 3:

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

Core burn-up Isothermal Temperature Coefficient (ITC)

STANDARD:

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

EVALUATORS NOTE:

None.

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Notes prior to Step 5.2.1:

The following guidelines should be used when performing calculations:

o Do not 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 Reactivity2, Unit 2 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 2 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:

If asked: S:/ drive is not available (second bullet).

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 5 of 25 STEP 5:

Step 5.2.1 5.2.1 Perform Attachment 1 to calculate reactivity parameters.

STANDARD:

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

EVALUATORS NOTE:

None.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Note prior to Step 1 of Attachment 1:

Unless a specific value is given, the most recent Core Burn-up value from the Reactor Engineers should be used. This value is listed on the bench board. Do not interpolate for daily burn-up.

STANDARD:

(a) Acknowledges the Note.

EVALUATORS NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 6 of 25 STEP 7

, Step 1:

1.

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

a. Core Burn-up:

(MWD/MTU)

b. ITC:

(PCM/°F)

c. Differential Boron Worth (DBW):

(PCM/PPM)

d. Boron Concentration of in-service BAST (Cb BAST):

ppm STANDARD:

Completes Step 1 as indicated below:

1.

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

a. Core Burn-up: 12147 (MWD/MTU)

b. ITC:

-25.81 (PCM/°F)

c. Differential Boron Worth (DBW):

-8.15 (PCM/PPM)

d. Boron Concentration of in-service BAST (Cb BAST):

13772 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 Attachment 27 (page 54) of 2-DRP-003R.

Answer: -8.15 pcm/ppm ACCEPTABLE RANGE: [-8.13 to -8.17]

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

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 7 of 25 STEP 8:

, Step 2:

2.

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

-50813 x LN(1 + 1 / (Current Boron - Step 1d))

-50813 x LN(1 + 1 / ( - )) = gal (Reactivity Summary Line 7)

STANDARD:

Completes Step 2 as indicated below:

2.

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

a. -50813 x LN(1 + 1 / (529 - 13772))

b. -50813 x LN(1 + 1 / (-13243))

c. -50813 x LN(1 + (-0.000075511) [may round to -0.00007 / -0.00008]

d. -50813 x LN(0.999924488)

[based on rounding 0.99993 / 0.99992]

e. -50813 x -0.000075514

[based on rounding -0.00007 / -0.00008]

f.

3.837 gals

[based on rounding 3.56 gals / 4.06 gals]

g. Answer: 3.8 gallons [acceptable range: 3.6 - 4.1 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:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 8 of 25 STEP 9:

Note prior to Step 3 of Attachment 1:

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

STANDARD:

(a) Acknowledges the Note.

EVALUATORS NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 9 of 25 STEP 10:

, Step 3:

3.

IF RCS Boron concentration is greater than or equal to 12 ppm, THEN calculate the amount of dilution to make a -1 ppm change in accordance with the following. Otherwise, enter N/A

-50813 x LN(1 - 1 / (Current Boron - 10))

-50813 x LN(1 - 1 / ( - 10)) = gal (Reactivity Summary Line 8)

STANDARD:

Completes Step 3 as indicated below:

3.

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

a. -50813 x LN(1 - 1 / (529 - 10))

b. -50813 x LN(1 - 1 / (519))

c. -50813 x LN(1 - (0.001926782)) [may round to 0.00193]

d. -50813 x LN(0.998073217)

[based on rounding 0.00193 / 0.99807]

e. -50813 x -0.00192864

[based on rounding 0.99808 / -0.00193]

f.

98.00003 gals

[based on rounding 97.75 / 98.164 gals]

g. Answer: 98 gallons [acceptable range: 97.8 - 98.2 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).

Not Critical to round value, but does warrant a follow-up question based on first note in 5.2.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 10 of 25 STEP 11:

, Step 4:

4.

IF RCS Boron concentration is less than or equal to 12 ppm, THEN the amount of dilution to make a -1 ppm change is calculated by the following. Otherwise, enter N/A

-50813 x LN(1 - (1 / 2)) = 35221 gal (Reactivity Summary Line 8)

STANDARD:

4. Marks Step as Not Applicable (N/A).

EVALUATORS NOTE:

None.

COMMENTS:

_______ SAT

_______ UNSAT STEP 12:

, Step 5:

5.

Calculate the boron concentration change to cause a 1 °F temperature change.

/

=

ppm / °F (ITC, Step 1b)

(DBW, Step 1c)

STANDARD:

Completes Step 5 as indicated below:

5.

Calculate the boron concentration change to cause a 1 °F temperature change.

-25.81

/

-8.15

= 3.16687 ppm / °F (ITC, Step 1b)

(DBW, Step 1c)

a. ITC was provided as an initial condition.

b. DBW was read from a graph in 2-DRP-0003R, Curve Book.

c. Answer: 3.16687 ppm/°F ACCEPTABLE RANGE: [3.317466@ 8.13 DBW; 3.15912@ 8.17 DBW]

This is a critical step.

EVALUATORS NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 11 of 25 STEP 13:

, Step 6:

6.

Calculate the amount of boron to make a -1 °F Tave change.

-50813 x LN(1 + Step 5 / (Current Boron - Step 1d))

-50813 x LN(1 + / (

- )) = gal (Reactivity Summary Line 4)

STANDARD:

Completes Step 6 as indicated below:

6.

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

a. -50813 x LN(1 + 3.166871166 / (529 - 13772))

b. -50813 x LN(1 + 3.166871166 / (-13243))

c. -50813 x LN(1 + (-0.000239134803)

[may round to -0.00025/-.00024]

d. -50813 x LN(0.999760864)

[based on rounding 0.99975 / 0.99976]

e. -50813 x -0.0002391640774

[based on rounding -0.00025/-0.00024]

f.

12.2 gals

[based on rounding 12.7 to 12.1 gals]

g. Answer: 12.2 gallons [acceptable range: 12.7@ 8.13 DBW to 12.1@

8.17 DBW]

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:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 12 of 25 STEP 14:

Notes prior to Step 7 of Attachment 1:

When RCS Boron Concentration is less than 16 ppm, the equation in Step 7 will 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:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 13 of 25 STEP 15:

, Step 7:

7.

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

-50813 x LN(1 - Step 5 / (Current Boron - 10))

-50813 x LN(1 - / ( - 10)) = gal (Reactivity Summary Line 5)

STANDARD:

Completes Step 7 as indicated below:

7.

Calculate the amount of dilution to make a +1 oF change.

a. -50813 x LN(1 - 3.16687 / (529 - 10))

b. -50813 x LN(1 - 3.16687 / (519))

c. -50813 x LN(1 - (0.006101868)) [may round to 0.00610]

d. -50813 x LN(0.993898131)

[based on rounding 0.9939]

e. -50813 x -0.006120561

[based on rounding -0.00612]

f.

311.

[based on rounding 310.918 gals]

g. Answer: 311 gallons [acceptable range: 312 @ 8.13 DBW, 310 @ 8.17 DBW]

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:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 14 of 25 STEP 16:

Notes prior to Step 8 of Attachment 1:

If the value of ITC is between rod steps listed in the Curve Book, select the rod height with the highest rod worth. Interpolation to an unlisted rod height is not necessary.

STANDARD:

(a) Acknowledges the Notes.

EVALUATORS NOTE:

None COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 15 of 25 STEP 17

, Step 8:

NOTE: If the value of ITC is between rod steps listed in the Curve Book, select the rod height with the highest rod worth. Interpolation to an unlisted rod height is not necessary.

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:

225 Steps

b. Value of ITC:

(+) 25.81 pcm (record as + value)

c. Rod height associated with b:

217 Steps

d. Subtract a - c:

8 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 Attachment 29 (page 63) of DRP-0003.

Answer: 217 steps

d. 225 - 217 = 8 Steps [7 - 8 Steps].

Answer: 8 Steps [7 - 8 steps, 7 Steps based on misreading Note prior to Step 8 and interpolating based on ITC value.]

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:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 16 of 25 STEP 18 Step 5.2.2 Transfer appropriate values to Attachment 2, Reactivity Summary Sheet.

STANDARD:

Transfer appropriate values to Attachment 2, Reactivity Summary Sheet, as indicated below:

1.

Reactor Operators will discuss Items 4 - 8 with the Unit SRO following turnover.

2.

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

3.

Reactor Power 100

4.

Boron for 1 °F decrease 12.1 - 12.7 GAL BA

5.

Dilution for 1 °F increase 310 - 312 GAL PG

6.

Rod steps for 1 °F change 7 - 8 Steps

7.

Gallons of boric acid for 1 ppm change 3.6 - 4.1 GAL BA

8.

Gallons of PG for 1 ppm change 98 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.

Item 8 above: Not Critical to round value, but does warrant a follow-up question based on first note in 5.2.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 17 of 25 STEP 5:

Reports completion of 2-OP-RX-010 through Step 5.2.4.

STANDARD:

(a) Verbal or written status report that a 2-OP-RX-010 is ready to be independently verified.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 18 of 25 Examiner Key Initial 12147

- 25.81

- 8.15

[Range - 8.13 to - 8.17]

13772 Initial 529 13772 3.8 Initial 529 98 Range: 97.8 to 98.2 gals

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 19 of 25 Examiner Key N/A Initial Initial Initial

- 25.81

- 8.15 3.166871166 Range: 3.317466 to 3.15912 3.166871166 3.166871166 529 13772 12.2 Range: 12.7 to 12.1 529 311 Range: 310 to 312 gals

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 20 of 25 Examiner Key Initial 225 25.81 217 8

Range: 218 to 217 Range: 7 to 8

Surry 2015-301 Perform 2-OP-RX-010 G2.1.37 SR15301 21 of 25 Examiner Key 100 12.2 311 8

3.8 98 Range: 12.1 to 12.7 Range: 310 to 312 Range: 7 to 8 Range: 3.6 to 4.1 Range: 97.8 to 98.2 Signature Date

SRO Only Follow-up Question (2-OP-RX-010)

KEY Current Unit 2 RWST parameters are as follows:

Boron, by sample, is 2248 ppm.

RWST NR level 97.7% (392, 950 gallons).

REST Temperature 43 °F.

Please provide the answer to the following question in the space below.

Based on the current RWST parameters, is there a Technical Specification clock in effect for Unit 2? If so, what are the actions required to clear the clock?

Per TS 3.2.C.2a., TS 3.3.B.1.a., and TS 3.4.B.4.a.:

(Any One of the above specifications is acceptable).

Yes.

For conditions where the RWST is inoperable due to boron concentration or solution temperature not being within the limits specified, restore the parameters to within specified limits in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Boron concentration must be raised to at least 2300 ppm within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SRO Only Follow-up Questions Current Unit 2 RWST parameters are as follows:

Boron, by sample, is 2248 ppm.

RWST NR level 97.7% (392, 950 gallons).

RWST Temperature 43 °F.

Please provide the answer to the following question in the space below.

Based on the Chemistry report, is there a Technical Specification clock in effect for Unit 2? If so, what are the actions required to clear the clock?

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

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

Performance of 2-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 2 power is 100 percent.

2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations is scheduled to be completed on this shift.

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

Core burnup: 12147 MWD/MTU Isothermal temperature coefficient: -25.81 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: 529 ppm Control Bank D is at 225 steps C BAST is in-service on Unit 2 with a boron concentration of 13772 ppm.

A power reduction has not occurred and is not planned.

Initiating Cues:

Here is a copy of 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations, through Step 5.2.4, and I will have another Operator complete the procedure.

When you have completed Step 5.2.4, 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 2 power is 100 percent.

2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations is scheduled to be completed on this shift.

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

Core burnup: 12147 MWD/MTU Isothermal temperature coefficient: -25.81 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: 529 ppm Control Bank D is at 225 steps C BAST is in-service on Unit 2 with a boron concentration of 13772 ppm.

A power reduction has not occurred and is not planned.

Initiating Cues:

Here is a copy of 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations. I need you to perform 2-OP-RX-010, Documentation of Reactivity Parameters during Power Operations, through Step 5.2.4, and I will have another Operator complete the procedure.

When you have completed Step 5.2.4, please inform me, as this will end the JPM.

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 1 of 15 U.S Nuclear Regulatory Commission Surry Power Station SR15301 Administrative Job Performance Measure G2.1.23 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Determine Primary to Secondary Leakrate in accordance with 0-OSP-RC-002 and Determine Ramp Rate IAW 0-OSP-RC-002.

K/A: G.2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. RO: 4.3 / SRO: 4.7 Applicability Estimated Time Actual Time RO/SRO(D)/SRO(U) 15 Minutes Initial Conditions Task is to be PERFORMED in the CLASSROOM.

Performance of 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, Attachment 1, Hand Calculation of Primary-to-Secondary Leakage Using the Condenser Air Ejector Radiation Monitor is required.

Standards Calculate primary to secondary leakrate (RO/SRO) and Ramp Requirements (SRO Only).

Initiating Cues Given simulated plant conditions, calculate primary to secondary leakrate in accordance with 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, Attachment 1, Hand Calculation of Primary-to-Secondary Leakage Using the Condenser Air Ejector Radiation Monitor.

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 2 of 15 Initiating Cues Unit 1 was at 100% power when RM-G8, CNDSR AIR EJCTR Alert/Failure was received, with an indicated count rate as shown below.

The operating team implemented 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, but the PCS failed to respond when attempting to retrieve the associated data.

You are to perform 0-OSP-RC-002, Steam Generator Steam Generator Primary to Secondary Leakage,, Steps 1 through 7, to determine primary to secondary leakrate for Unit 1.

The following data is provided:

o Air Ejector Flowrate is A: 3.3 scfm; B: 4.4 scfm.

o Chemistry Data:

AR-41 Concentration:

7.45 E-03 Xe-135 Concentration:

1.19 E-04 All Other Nuclides Concentration:

Non Detectable When you have completed the calculation, inform your examiner.

Terminating Cues Primary to secondary leakrate successfully calculated (RO/SRO) and Ramp Requirements Determined (SRO Only).

Tools and Equipment Safety Considerations Calculator

- None O-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, Att. 1.

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 3 of 15 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded.

START TIME:

0-OSP-RC-002, Att. 1, Step 1 STEP 1: Acknowledges NOTE prior to Step 1: Multiple copies of this Attachment should be made as necessary.

STANDARD:

Candidate Reviews and acknowledges NOTE.

EVALUATOR NOTES:

None COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 1 STEP 2 Record the current time and date.

STANDARD:

a) Candidate records current time and date in appropriate blank.

b) Candidate initials Step 1.

EVALUATOR NOTES:

If asked: Provide Date and Time.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 4 of 15 0-OSP-RC-002, Att. 1, Step 2 STEP 3: Calculates Total Air Ejector flowrate.

STANDARD:

a) Candidate enters Air Ejector data from initial conditions for A and B in the appropriate blank.

b) Candidate totals flowrate and enters 7.7 in Total Flow blank.

c) Candidate initials Step 2.

EVALUATOR NOTES:

None.

COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 3 STEP 4: Records Air Ejector Radiation Monitor reading.

STANDARD:

a) Candidate records Air ejector Radiation Monitor reading in appropriate blank (1.45 E3).

b) Candidate initials Step 3.

EVALUATOR NOTES:

None COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 4 STEP 5: Enters Data for AR-41 and Xe-135 Concentrations on Step 4 Data Table STANDARD:

a) Candidate enters Data into table (AR-41, 7.45E-03; Xe-135, 1.19E-04).

b) Candidate Initials Step 4.

EVALUATOR NOTES:

None.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 5 of 15 0-OSP-RC-002, Att. 1, Step 5 STEP 6: Multiplies Data given for AR-41 and Xe-135 concentrations by Isotopic Efficiency in Step4 Table.

STANDARD:

a) Candidate multiplies AR-41 concentration by Efficiency Factor and writes this value in Table 4 Column 4 (4.45E+05).

b) Candidate multiplies Xe-135 concentration by Efficiency Factor and writes this value in Table 4 Column 4 (5.45E+05).

c) Candidate initials Step 5.

EVALUATOR NOTES:

None.

COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 6 STEP 7: Calculate RC (total AE RM response factor).

STANDARD:

a) Candidate Adds the products of Column 4, Table 4, and enters this value in the RC blank of Step 6 (9.90E+05).

b) Candidate initials Step 6.

EVALUATOR NOTES: N/A None COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 7 STEP 8: Calculate Unit 1 primary-to-secondary leak rate in gallons per day (QL)

STANDARD:

a) Acknowledges NOTE prior to Step 7 defining terms used in calculation.

b) Calculates Unit 1 QL and places results in Step 7 Blank (114.6).

EVALUATOR NOTES:

This is the Critical Step, acceptable Range 114.6 - 115, (114.6, no significant digits set; 115 based on 2 significant digits set).

COMMENTS:

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 6 of 15 STEP 9:

Reports task complete.

STANDARD:

Informs evaluator of task completion.

EVALUATOR NOTES:

--- END OF RO JPM ---

COMMENTS:

_______ SAT

_______ UNSAT 0-OSP-RC-002, Att. 1, Step 8 STEP 10:

SRO Only

Using Primary-to-Secondary Leakage calculated in Steps 1 - 7 of, Determine the Unit 1 Ramping Requirements in accordance with Attachments 2 through 8 of 0-OSP-RC-002.

STANDARD:

a) Candidate reviews Attachments 2 through 8, as appropriate.

b) Candidate Determines Unit 1 must be less than or equal to 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and be in Hot Shutdown within the next two hours (three hours total).

EVALUATOR NOTES: Provide Candidate with complete copy of 0-OSP-RC-002.

COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

SRO Only* Reports task complete.

STANDARD:

Informs evaluator of Unit Ramping requirements.

EVALUATOR NOTES:

None COMMENTS:

_______ SAT

_______ UNSAT STOP TIME: ________

Surry 2015-301 Primary to Secondary Leakage G2.1.25 SR15301 7 of 15 Comments

EVALUATORS REFERENCE COPY Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to 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 1 was at 100% power.

Initiating Cues RM-G8, CNDSR AIR EJCTR Alert/Failure received, with an indicated count with an indicated count rate as shown below.

The operating team implemented 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, but the PCS failed to respond when attempting to retrieve the associated data.

You are to perform O-OSP-RC-002, Steam Generator Steam Generator Primary to Secondary Leakage,, Steps 1 through 7, to determine primary to secondary leakrate for Unit 1.

The following data is provided:

o Air Ejector Flowrate is A: 3.3 scfm; B: 4.4 scfm.

o Chemistry Data:

AR-41 Concentration:

7.45 E-03 Xe-135 Concentration:

1.19 E-04 All Other Nuclides Concentration:

Non Detectable When you have completed the calculation, inform your examiner.

Initial Time Date Initial 3.3 4.4 7.7 1.45E3 Initial Initial 7.45 E-03 ND ND ND ND ND ND ND 1.19 E-04 ND ND 4.45 E5 5.45 E5 1

1

Initial Initial 9.9 E5 Initial 114.6 Range 114.6 to 115 gpd

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Task Task is to 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 1 was at 100% power.

Initiating Cues RM-G8, CNDSR AIR EJCTR Alert/Failure received, with an indicated count rate with an indicated count rate as shown below.

The operating team implemented 0-OSP-RC-002, Steam Generator Primary to Secondary Leakage Monitoring, but the PCS failed to respond when attempting to retrieve the associated data.

You are to perform O-OSP-RC-002, Steam Generator Steam Generator Primary to Secondary Leakage,, Steps 1 through 7, to determine primary to secondary leakrate for Unit 1.

The following data is provided:

o Air Ejector Flowrate is A: 3.3 scfm; B: 4.4 scfm.

o Chemistry Data:

AR-41 Concentration:

7.45 E-03 Xe-135 Concentration:

1.19 E-04 All Other Nuclides Concentration:

Non Detectable When you have completed the calculation, inform your examiner.

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

SRO Only Question Using Primary-to-Secondary Leakage calculated in Steps 1 - 7 of Attachment 1, determine the Unit 1 Ramping Requirements in accordance with Attachments 2 through 7 of 0-OSP-RC-002.

STANDARD:

a) Candidate reviews Attachments 2 through 8, as appropriate.

b) Candidate Determines Unit 1 must be less than or equal to 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and be in Hot Shutdown within the next two hours (three hours total).

EVALUATOR NOTES:

1) Provide Candidate with complete copy of 0-OSP-RC-002.

2) Ramp Rate must be determined using Attachment 2. CRITICAL STEP.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

SRO Only Question Using Primary-to-Secondary Leakage calculated in Steps 1 - 7 of Attachment 1, determine the Unit 1 Ramping Requirements in accordance with Attachments 2 through 7 of 0-OSP-RC-002.

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 1 of 14 U.S. Nuclear Regulatory Commission Surry Power Station SR15301 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 56), 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 56), 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 56),

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 56), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B, for completeness and accuracy.

List ALL discrepancies noted on the ANSWER SHEET provided.

When you are finished, inform your examiner of ALL problems noted in the procedure and any Technical Specification operability concerns if applicable.

Terminating Cues

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 2 of 14 Applicant has completed the procedure review and discussed problems with examiner.

Tools and Equipment Calculator Copy of completed 1-OPT-CH-002 (REV 56), CHARGING PUMP OPERABILITY AND PERFORMANCE TEST FOR 1-CH-P-1B.

Surry Technical Specifications.

Safety Considerations None Notes

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 3 of 14 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and noted at the end of the step as CRITICAL STEP.

START TIME:

STEP 1:

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

STANDARD:

Reviews purpose of procedure steps 1.1 - 1.9.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

STEP 2 - Review the References section (Section 2.0)

STANDARD:

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

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 4 of 14 STEP 3:

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

STANDARD:

Reviews Initial Conditions steps 3.1 - 3.4.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

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

STANDARD:

Reviews precautions and limitations steps 4.1 - 4.15.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 5 of 14 STEP 5:

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

STANDARD:

Reviews Special Tools and Equipment section steps 5.1 - 5.8.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

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

STANDARD:

Verifies proper place keeping on all steps, notes, and cautions.

Verifies step 6.1.1 substeps a and b are initialed and Attachment 9 is properly filled out.

Verifies step 6.1.2 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 6.1.3 is initialed.

Verifies step 6.1.4 is initialed and blocks are correctly checked off. The 6th 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:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 6 of 14 STEP 7:

STEPS 6.2-6.4 -

Reviews Steps 6.2 - 6.4 of 1-OPT-CH-002 STANDARD:

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

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

STEP 6.5-Reviews Discharge Check Valve Close Test, MOV Timing, Lube Oil TCV Timing and Starting 1-CH-P-1B section of procedure (Section 6.5.1 - 6.5.20).

STANDARD:

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.f, 6.5.1g, 6.5.1.h and that differential is < 7.5 psid IAW 6.5.1.g.

Verifies box checked in step 6.5.4 indicating that 1-SW-TCV-108B was closed and goes to step 6.5.5.

Verifies step 6.5.6 is N/Ad.

Verifies step 6.5.8.a is N/Ad.

Verifies step 6.5.9 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 6.5.8.d is between 60-120 °F.

Verifies step 6.5.15.b is N/Ad.

Verifies lube oil pressure recorded in step 6.5.19 is between 8-35 psig.

Verifies step 6.5.20 is N/Ad Verifies pump and damper checks were sat IAW step 6.5.22 on non-running charging pumps.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 7 of 14 STEP 9:

STEP 6.6-Reviews 1-CH-P-1B Performance Test section of procedure (Section 6.6.1 - 6.6.26).

STANDARD:

Verifies proper place keeping 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:

_______ SAT

_______ UNSAT STEP 10:

STEPS 6.7-6.8 -

Reviews Steps 6.7 - 6.8 of 1-OPT-CH-002 STANDARD:

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

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

STEP 6.9-Reviews Obtaining Oil Samples section of procedure Section 6.9.1-6.9.2).

STANDARD:

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

Verifies steps in 6.9.1 are properly initialed and steps in 6.9.2 are N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 8 of 14 STEP 12:

STEP 6.10 -

Reviews Step 6.10 of 1-OPT-CH-002.

STANDARD:

Verifies all steps of 6.10 are N/Ad.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 12:

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

STANDARD:

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

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

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 13:

Reviews Attachment 1 Data.

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:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 9 of 14 STEP 14:

Reviews Attachment 2 Data.

STANDARD:

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

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

This is a critical step.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 15:

Reviews Attachment 4 Data.

STANDARD:

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

Notes that 1-CH-MOV-1287B OPEN stroke test time is not in the ACCEPTABLE range and that OPT was checked as SAT.

This is a critical step.

EVALUATORS NOTE: N/A COMMENTS:

_______ SAT

_______ UNSAT STEP 16:

Reviews Attachment 9.

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:

_______ SAT

_______ UNSAT

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 10 of 14 STOP TIME:

Surry 2015-301 PT Review (1-OPT-CH-002)

G2.2.37 SR15301 11 of 14 ANSWER KEY 1-OPT-CH-002 REVIEW

1. Attachment 1, Step 6.1.2 - Listed stopwatch is out of CAL. (CRITICAL STEP)

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

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

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 STEP)

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 STEP)

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 STEP)

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 56), 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 56), 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 56),

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 56), 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 56), 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 56),

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 56), 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

Surry 2015-301 Determine Classification G2.4.41 SR15301 1 of 12 U.S. Nuclear Regulatory Commission Surry Power Station SR10301 Administrative Job Performance Measure 2.4.41 TIME CRITICAL Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title CLASSIFY AN EVENT K/A: G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

Applicability Est Completion Time Actual Time SRO 15 Minutes (Time Critical)

Conditions Task is to be PERFORMED in the SIMULATOR.

A simulated SITE AREA EMERGENCY is in progress.

Standards Declares a Site Area Emergency using EAL Identifier FS1.1 in accordance with EPIP-1.01/EAL Table.

Initiating Cues Given simulated plant conditions, utilize EPIP-1.01 and determine if classification is warranted.

Surry 2015-301 Determine Classification G2.4.41 SR15301 2 of 12 Initial Conditions This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The crew was performing actions in E-3, Steam Generator Tube Rupture, due to a SGTR in SG A.

Security reports steam leaving louvers of Unit 1 Safeguards.

BOP reports SG A steam pressure is lowering rapidly, and it appears that SG A is also faulted.

The crew has just entered E-2, Faulted Steam Generator Isolation.

Initiating Cues:

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. I need you to perform EPIP-1.01 and determine if this event should be classified.

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

Terminating Cues Report of classification determination.

Procedures EPIP-1.01, Emergency Manager Controlling Procedure (Revision 57).

Surry EAL Technical Basis (Revision 4).

Tools and Equipment Safety Considerations None None Notes This JPM is to be administered to the SRO immediately following the scenario (NRC Scenario 2). Ensure the SRO is sequestered following the scenario from the rest of the crew members prior to administering this JPM.

Provide same copy of EPIP-1.01 that is in SEM EP book. This copy will have CAP on every other page.

Surry 2015-301 Determine Classification G2.4.41 SR15301 3 of 12 Performance Checklist Notes to the Evaluator.

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

START TIME ________:

STEP 1:

Caution and Note prior to step 1.

CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.

NOTE:

The PCS is potentially unreliable in the event of an earthquake.

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

STANDARD:

(a) Acknowledges CAUTION and NOTE EVALUATORS NOTE:

Candidate may choose to make EAL classification straight from EAL tables and NOT implement steps of EPIP-1.01. Steps are given here as guidance.

Critical task time ends when the classification is determined regardless of determination method.

Provide copy of EPIP-1.01, Emergency Manager Controlling Procedure.

Candidate may use EAL Technical Basis book.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Determine Classification G2.4.41 SR15301 4 of 12 STEP 2:

Step1 - EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using the applicable Emergency Action Level Matrix:

Hot Conditions (RCS > 200 °F)

Cold Conditions (RCS 200 °F) b) Review EAL associated with event category c) Use Control Room monitors, PCS, and outside reports to get indications of emergency conditions listed in the EAL Matrix d) Verify EAL - CURRENTLY EXCEEDED e) Initiate a chronological log of events STANDARD:

(a) Refers to the HOT chart (b) Determines event category to be Loss of Power.

(c) Refers to given conditions to determine EAL applicability (d) Determines EAL Identifier FS1.1 conditions are met and declares a Site Area Emergency on this Identifier. This is a Critical Step.

(e) Initiates (or verbalizes) a chronological log of events.

EVALUATORS NOTE:

If candidate makes EAL determination at this step, record stop time.

COMMENTS:

STOP CRITICAL TASK TIME: ___________

TIME CRITICAL-15 minutes

_______ SAT

_______ UNSAT

Surry 2015-301 Determine Classification G2.4.41 SR15301 5 of 12 STEP 3:

Step 2 - RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME:

Emergency Classification EAL Identifier Time Declared SM /SEM Name Notification of Unusual Event Alert Site Area Emergency General Emergency STANDARD:

(a) Completes the table as indicated below:

Emergency Classification EAL Identifier Time Declared SM /SEM Name Notification of Unusual Event Alert Site Area Emergency FS1.1 TBD TBD General Emergency EVALUATORS NOTE:

Completion of this table is not required for successful completion of the JPM.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Determine Classification G2.4.41 SR15301 6 of 12 STEP 5:

Reports declaration of the event in progress.

STANDARD:

(a) Verbal or written status report that a Site Area Emergency should be declared on Tab FS1.1. This is a Critical Step (if not already performed).

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

STOP CRITICAL TASK TIME: ___________

TIME CRITICAL-15 minutes

_______ SAT

_______ UNSAT STOP TIME:

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

Task Task may be PERFORMED in the simulator or classroom.

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

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The crew was performing actions in E-3, Steam Generator Tube Rupture, due to a SGTR in SG A.

Security reports steam leaving louvers of Unit 1 Safeguards.

BOP reports SG A steam pressure is lowering rapidly, and it appears that SG A is also faulted.

The crew has just entered E-2, Faulted Steam Generator Isolation.

Initiating Cues:

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. I need you to perform EPIP-1.01 and determine if this event should be classified.

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

Operator Directions Handout (TO BE GIVEN TO APPLICANT - OPTIONAL)

Initial Conditions This JPM is TIME CRITICAL.

You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The crew was performing actions in E-3, Steam Generator Tube Rupture, due to a SGTR in SG A.

Security reports steam leaving louvers of Unit 1 Safeguards.

BOP reports SG A steam pressure is lowering rapidly, and it appears that SG A is also faulted.

The crew has just entered E-2, Faulted Steam Generator Isolation.

Initiating Cues:

Here is a copy of EPIP-1.01, Emergency Manager Controlling Procedure. I need you to perform EPIP-1.01 and determine if this event should be classified.

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

Record classification and EAL identifier (if any):

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 1 of 20 U.S. Nuclear Regulatory Commission Surry Power Station SR15301 Administrative Job Performance Measure G2.4.39 TIME CRITICAL Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Complete EPIP-2.01 K/A: G.2.4.39 - Knowledge of RO responsibilities in emergency plan implementation. (3.9/3.8)

Applicability Estimated Time Actual Time RO only.

15 Minutes

___ Minutes Conditions Task is to be PERFORMED in the simulator.

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

Initiating Cues EPIP-1.01, Emergency Manager Controlling Procedure EPIP-2.01, Report of Emergency to State and Local Governments.

Terminating Cues All State and Local Governments notified and EPIP-2.01 complete through step 9.

Procedures EPIP-2.01, Notification of State and Local Governments, Rev. 44.

Tools and Equipment Safety Considerations None None

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 2 of 20 Simulator Setup Call up 100% power IC and initialize (IC 269). Place simulator in RUN.

Initiate a Small Break LOCA.

Perform Immediate actions for E-0.

When RCS subcooling lowers to less than 30 degrees Fahrenheit, secure RCPs and place Simulator in FREEZE.

Initial Conditions This JPM is Time Critical.

I am the Station Emergency Manager (SEM) and you are the State and Local Communicator. A Small Break LOCA has occurred and the team is responding IAW the EOP network. I have declared an ALERT FA1.1 due to a Loss of Reactor Coolant System Barrier when RCS subcooling went less than 30 degrees Fahrenheit.

Initiating Cues I need you to initiate EPIP-2.01 and notify state and local governments of our emergency.

There are no releases in progress, and site access is available.

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

Notes Provide same copy of EPIP-2.01, and Attachment 2 that is contained in State & Local Communicator Book to candidate.

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 3 of 20 Notes to the Evaluator This JPM is Time Critical-15 minutes. Time starts from the JPM start time until transmittal is complete (step 1).

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

Critical step sequencing requirements: Steps 4 and 5 before Step 6.

Role play as the Station Emergency Manager. Approve Attachment 2 when given to you by student.

Time declared for the ALERT will be the JPM start time. Use TODAYS date.

START TIME: _________________:

STEP 1:

INITIATES PROCEDURE.

STANDARD:

Fills in name, date, time, and location in step 1 of EPIP-2.01.

EVALUATORS NOTE:

If asked: Use todays date. Time should be current time. Location is Surry Power Station Control Room (simulated).

A partial copy of EPIP-2.01 is included for the Evaluator at the end of this JPM. The candidate should use the same copy as provided in the State & Local Communicator binder in the MCR.

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

CHECKS FIRST REPORT OF EMERGENCY FOR EVENT REQUIRED STANDARD:

Answers yes to step 2 based on direction to perform EPIP-2.01.

EVALUATORS NOTE:

If asked: First report of emergency for event is required.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 4 of 20 STEP 3:

Reviews notes prior to step 3:

The initial notification of any emergency classification must be made (meaning contact initiated with the first agency) within 15 minutes of declaring the emergency class.

Attachment 1, Instructions for Completing Report of Emergency to State and Local Governments, may be referenced as needed.

Items 5 through 9 on the Report of Emergency to State and Local Governments are optional for a message reporting initial entry into the Emergency Plan or an emergency class change.

STANDARD:

Acknowledges notes.

EVALUATORS NOTE:

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

CHECKS EMERGENCY REMAINS IN EFFECT (Step 3)

STANDARD:

Determines emergency still in effect.

EVALUATORS NOTE:

If asked: The emergency does remain in effect.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 5 of 20 STEP 5:

RECORDS INFORMATION ON REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS (ATTACHMENT 2). (Step 4)

STANDARD:

a) Records message #1 on page 1 and 2 of attachment 2.

b) Checks box for Drill Message.

c) Item 1, Emergency Classification: ALERT checked, FA 1.1, Declared at time (given to trainee) and date (given to trainee). Writes name in space for Emergency Communicator. CRITICAL STEP.

d) Item 2, MET Data: Obtains MET Data from PCS or MCR Indications. CRITICAL STEP.

e) Item 3, Release of Radioactive Material. No radiological release: Will NOT transmit Report of Radiological conditions to Virginia EOC block is checked.

CRITICAL STEP.

f)

Item 4, Site Access: Available block is checked. CRITICAL STEP.

g) Item 5, Protective Action Recommendation: Is not required block is checked.

CRITICAL STEP.

h) Item 6, Update Schedule: 60 minutes recommended block is checked.

CRITICAL STEP.

i)

Items 7-11, Excluded from message block is checked.

EVALUATORS NOTE:

Item 1, If asked, what is declaration time? Provide time given at start of JPM.

Item 1 must be filled in completely after notification made.

Item 2, If asked is MET data available in MCR? Respond, Use MET data specified by EPIP-2.01. PCS EMCOMM should be accessed and data recorded from that screen.

Item 2, If asked to verify MET data, or is MET data verified? Respond, MET data has been verified. Normally all MET data is verified by second person (Training note).

Item 3, If asked, are there any releases? Respond No release in progress.

Item 4, If asked, Is Site access available? Respond, Site Access is available.

Item 5, If asked, are there any PARs? Respond, There are no PARs.

If asked for any other information: Respond, All the information you need has been provided.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 6 of 20 STEP 6:

HAVE SEM APPROVE REPORT. (Step 5)

STANDARD:

SEM reviews and approves report.

EVALUATORS NOTE:

Sign the report at top of the page as SEM.

Inform the candidate that they have permission to transmit report to State and Local governments.

A copy of Attachment 2 (before SEM approves) is included at end of JPM.

COMMENTS:

_______ SAT

_______ UNSAT STEP 7:

SEND REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS.

(Step 6)

STANDARD:

a) Acknowledges Note prior to step 6.

b) Check Instaphone clear of conflicting message or traffic.

c) Contacts State and Local governments.

d) Reads item 1.

e) Perform acknowledgement roll-call (check boxes) as EOC answers.

f)

Check Virginia EOC acknowledged message.

g) Check all local EOC(s) answered acknowledgement roll call.

h) Record date and time transmittal of item 1 completed. The TIME CRITICAL clock stops after transmittal of step 1 is completed. STOP TIME_________.

CRITICAL STEP.

i)

Read Items 2 through 5. CRITICAL STEP.

j)

Consult with Virginia EOC Watch officer to determine desired update schedule. CRITICAL STEP.

k) Completes item 6, Update Schedule. CRITICAL STEP.

l)

Read Items 7 through 11.

m) Repeat any items upon request.

n) Record time and date transmittal of items 2 - 11 completed.

o) Go to step 9.

EVALUATORS NOTE:

Booth instructor: will role-play the State and Local governments and will acknowledge all information.

Booth instructor: will request a 60 minute update.

Booth instructor: Virginia EOC duty officers name is John Smith.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 EP-RO Complete EPIP-2.01 Page 7 of 20 STEP 8:

NOTIFY SEM TRANSMITTAL WAS SENT (Step 9)

STANDARD:

Notifies SEM transmittal was sent.

EVALUATORS NOTE:

COMMENTS:

JPM COMPLETE

_______ SAT

_______ UNSAT STOP TIME: _____________

Comments:

Before SEM Approval Page 8 of 20

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

Initial Conditions This JPM is Time Critical.

I am the Station Emergency Manager (SEM) and you are the State and Local Communicator. A Small Break LOCA has occurred and the team is responding IAW the EOP network. I have declared an ALERT FA1.1 due to a Loss of Reactor Coolant System Barrier when RCS subcooling went less than 30 degrees Fahrenheit.

Initiating Cues I need you to initiate EPIP-2.01 and notify state and local governments of our emergency.

There are no releases in progress, and site access is available.

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

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions This JPM is Time Critical.

I am the Station Emergency Manager (SEM) and you are the State and Local Communicator. A Small Break LOCA has occurred and the team is responding IAW the EOP network. I have declared an ALERT FA1.1 due to a Loss of Reactor Coolant System Barrier when RCS subcooling went less than 30 degrees Fahrenheit.

Initiating Cues I need you to initiate EPIP-2.01 and notify state and local governments of our emergency.

There are no releases in progress, and site access is available.

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

Surry 2015-301 Determine Stay time Page 1 of 8 U.S. Nuclear Regulatory Commission Surry Power Station SR15301 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 the amount of time an operator can spend in a radiological area without exceeding administrative dose limits and also determines how long an operator can remain in the radiological area assuming extensions are authorized.

Initiating Cues Given simulated plant conditions, determine how long an operator can work in a radiological are without exceeding administrative dose limits. Also, assuming the maximum dose limit extension is authorized, how long can an operator perform work in a radiological area.

Surry 2015-301 Determine Stay time Page 2 of 8 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 will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 Based on the dose that you have received this year, you have already been authorized to receive 3,000 mrem for the current year.

Initiating Cues:

I need you to answer the following questions regarding the work:

1. Assuming the job will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months can you complete the job without requiring another dose extension, and how long you will be able to perform work in that area?

2. Assuming that I am able to receive the maximum dose limit extension for you, up to the federal limit, inform me how long you will be able to perform work in that area, and if you will be able to complete the job.

Record your answers on the attached page and inform me when you have completed.

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 Tools and Equipment Safety Considerations Calculator Computer with only access to Webtop None Notes

Surry 2015-301 Determine Stay time Page 3 of 8 Performance Checklist Notes to the Evaluator.

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

START TIME:

STEP 1:

Answer to first question by the Shift Manager:

Based on the dose that you have received this year, I need you to tell me how long you can perform work in that area without requiring a dose limit extension and if you will be able to complete the job without assistance (assuming no dose extensions to the administrative limits).

STANDARD:

(a) Calculates dose received year to date as follows:

680 mrem + 430 mrem + 590 mrem + 100 mrem = 1800 mrem.

(b) Notes that the authorized dose limit is 3000 mrem (c) Determines margin to limit: 3000 - 1800 = 1200 mrem (d) Calculates Stay Time: 1200 mrem / 400 mrem/hour = 3.0 hours0 days 0 hours 0 weeks 0 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:

Currently authorized to 3 Rem/Year.

Can get extended to 5 Rem/year with worker, manager, RP Manager and Site VP approval.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Determine Stay time Page 4 of 8 STEP 2:

Answer to second question by the Shift Manager:

Finally, assuming that I am able to receive the maximum dose limit extension for you, up to the federal limit, 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.

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:

Authorized to receive 3 Rem/Year.

Can get extended to 5 Rem/year with worker, manager, RP Manager and Site VP approval.

A candidate may state 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for part (d), as this is the projected time to complete the job. Follow-up question concerning how the candidate arrived at 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months may be necessary to determine if the candidate is documenting actual stay time vice job completion time.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2015-301 Determine Stay time Page 5 of 8 STEP 3:

Reports task is complete.

STANDARD:

(a) Verbal or written status report that the work cannot be done without assistance if a dose limit extension is not given and that with the extension the work can be performed without assistance.

EVALUATORS NOTE:

Acknowledge the completion of the task.

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

Surry 2015-301 Determine Stay time Page 6 of 8 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 will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 Based on the dose that you have received this year, you have already been authorized to receive 3,000 mrem for the current year.

Initiating Cues:

I need you to answer the following questions regarding the work:

1. Assuming the job will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months can you complete the job without requiring another dose extension, and how long you will be able to perform work in that area?

2. Assuming that I am able to receive the maximum dose limit extension for you, up to the federal limit, inform me how long you will be able to perform work in that area, and if you will be able to complete the job.

Record your answers on the attached page and inform me when you have completed.

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 will take approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 Based on the dose that you have received this year, you have already been authorized to receive 3,000 mrem for the current year.

Initiating Cues:

I need you to answer the following questions regarding the work:

1. Assuming the job will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months can you complete the job without requiring another dose extension, and how long you will be able to perform work in that area?

2. Assuming that I am able to receive the maximum dose limit extension for you, up to the federal limit, inform me how long you will be able to perform work in that area, and if you will be able to complete the job.

Record your answers on the attached page and inform me when you have completed.

Shift Manager Questions and Operator Answers (TO BE GIVEN TO APPLICANT)

Question #1:

Assuming the job will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months can you complete the job without requiring another dose extension, and how long you will be able to perform work in that area.

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, up to the federal limit, inform me how long you will be able to perform work in that area, and will you be able to complete the job.

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)