ML20303A012

Draft Operating Test (Section a, Section B, Section C) (Folder 2)

ML20303A012
Person / Time
Site:	Millstone
Issue date:	07/02/2020
From:	Dominion Energy
To:	NRC Region 1
Jackson, D
Shared Package
ML19105A205	List: ML20302A234 ML20302A235 ML20303A011 ML20303A012 ML20303A014 ML20303A016 ML20303A032 ML20303A144 ML20307A010 ML20307A019 ML20307A064
References
CAC 000500
Download: ML20303A012 (304)

Text

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Shutdown Safety Assessment Time to Core Boil JPM Number: JPM-A1R Revision: 3/0 Initiated:

John W. Riley - Signature on File 04/28/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/22/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 05/28/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 10/21/08 Created JPM for LOIT NRC Exam 0/0 09/07/11 Revised JPM for procedure change to OU-M2-201 1/0 JWR 08/20/2012 Revised JPM to latest format. Made editorial changes. Changed 1/1 initial conditions to 14 inches above Hot Leg centerline to eliminate confusion over RCS level.

09/10/2014 djj Updated to new procedure Revision 1/2 05/11/2015 - RJA Updated to new format and latest procedure revision. 2 07/17/2016 jwr Changed conversion of 14 inches above RCS Hot Leg centerline to 2/1 RCS water level in feet ( - 6 ft ) from critical to non-critical since it is not used to calculate time-to-boil.

04/28/2020 jwr Changed the number from A2R to A1R for the 2020 ILT NRC 3/0 exam. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP-2 Examinee:

JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil System: Administrative Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): NUTIMs # 119-01-044 Applicable To: SRO STA RO X PEO K/A Number: 2.1.25 K/A Rating: 3.9 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the examinee has determined the appropriate RCS Time to Core Boil is between 62 and 63 minutes.

Required Materials: OU-M2-201,Shutdown Safety Assessment Checklist, revision 24.

(procedures, equipment, etc.)

General

References:

OU-M2-201,Shutdown Safety Assessment Checklist, revision 24.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: A1R Revision : 3/0 Initial Conditions: The plant is in MODE 5 on day 28 refuel outage with the following conditions:

• Core is reloaded with 72 fresh FUEL ASSEMBLIES

• RCS Temperature to SDC, T351X, is stable at 1000F and is expected to remain stable for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• A Train Protected

• RCS Level is 14 inches above Centerline (LI-122 RCS Narrow Range)

Initiating Cues: The US has directed you to perform an RCS Time to Core Boil calculation per OU-M2-201, Attachment 2, Millstone Unit 2 Heatup Calculations.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 OU-M2-201, Attachment 2 NOTE: RCS temperature should be obtained from RCS to SDC temperature, T-351X.

Examinee reads the NOTE and understands that the Y N S U Otherwise unheated junction thermocouples or current RCS temperature should be obtained from CETs may be used (if either is available). If T-351X.

RCS temperature is expected to increase, an RCS temperature of up to 5 ºF greater than the current RCS temperature can be used to bound expected conditions.

Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil STEP Performance: Standard: Critical: Grade:

1. 2

1. Record time after reactor shutdown (in

• Examinee refers to initial conditions to obtain: Y N S U days), current RCS temperature (ºF) and

1. Reactor shutdown in days = 28 RCS Water Level (Feet from the vessel flange). 2. Current RCS temperature = 100 0F

• Examinee records data on Attachment 2 Y N S U

• Examinee refers to Table 2.

o Examinee reads and understands NOTEs Y N S U on Table 2.

• From initial conditions, examinee converts 14 Y N S U inches above RCS Hot Leg centerline to RCS water level in feet ( - 6 ft ).

• Examinee records RCS level of -6 feet on Y N S U Attachment 2.

Cue:

Comments: RCS water level can be recorded as 14 inches above Centerline or -6 feet. It is not critical.

STEP Performance: Standard: Critical: Grade:

1. 3 NOTE: When using this table, the more

• Examinee refers to Table 1. Y N S U conservative value should be used, so interpolation is not necessary (i.e., on the 23rd

• Examinee reads and understands NOTE. Y N S U day shutdown, use day 20 heatup rate).

• Examinee uses the conservative value of 25 Y N S U

2. Record RCS Heatup Rate from Table 1. days and obtains a value of 2.161 0F/min

• Examinee records the value on Attachment 2 Y N S U Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil STEP Performance: Standard: Critical: Grade:

1. 4

3. Determine Core Condition Multiplier,

• Examinee determines from the initial Y N S U MULT1 using one of the following and conditions that the Core was reloaded (After Record below: completion of Fuel Shuffle) and uses a value of 1.182

• Before Core Offload = 1.000

• Examinee records value on Attachment 2. Y N S U

• Before Fuel Shuffle Complete = 1.000

• After start of Core Reload = 1.182

• After completion of Fuel Shuffle = 1.182 Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil STEP Performance: Standard: Critical: Grade:

1. 5

4. Determine Water Level Multiplier, MULT2,

• Examinee refers to initial conditions and Y N S U using one of the following and record below: determines RCS level is 14 inches above the

• IF reactor vessel level is > 78 inches Hot Leg centerline. (RCS loops are not above Hot Leg centerline AND steam filled.)

generator U-tubes are NOT voided,

• Examinee refers to Table 2. Y N S U MULT2 = 2.529 (RCS Filled condition at 7.64 feet); otherwise, use MULT2

• Examinee reads and understands Notes. Y N S U consistent with RCS level above mid

• Using the Note about conservative values, the Y N S U loop reference point from Table 2. examinee selects 6 above Hot Leg centerline

• IF reactor vessel level has been raised to (6 on RCS Wide Range LI-112 (inches)).

support Refueling Operations, use (Examinee uses 6 inches instead of 18 inches.)

MULT2 consistent with RCS level above

• Examinee obtains a MULT2 of 1.019 and Y N S U mid loop reference point from Table 2. records on Attachment 2.

NOTE: When using this table, the more conservative value should be used, so interpolation is not necessary (i.e., when refuel pool is filled 3.5 above flange, use 3 above flange correction factor).

NOTE: For initial Draindown use RCS Filled condition (MULT2=2.529) until L-112 indicates 78 above centerline of hotleg (at the reactor vessel flange). Reactor vessel upper plenum and steam generator U-tubes are not voided until this level is reached. After this level is reached, use MULT2 based on RCS level above mid loop reference point.

Cue:

Comments:

8

PERFORMANCE INFORMATION JPM Number: A1R Revision: 3/0 Task

Title:

Shutdown Safety Assessment Time to Core Boil STEP Performance: Standard: Critical: Grade

1. 6

5. Calculate and record RCS Time to Boil.

• Examinee performs calculations Y N S U RCS Time to Boil = MULT1 x MULT2 x 62.4 min = 1.182 x 1.019 x {(212°F -100°F/

{(212°F - RCS Temperature (°F)) / RCS 2.161°F/min)} (62-63 Minutes)

Heatup Rate (°F/min)}

• Examinee records calculated value on Y N S U Attachment 2.

Cue:

Comments: An answer of 62 to 63 minutes is acceptable.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

9

VERIFICATION OF JPM COMPLETION JPM Number: A1R Revision: 3/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: A1R Revision: 3/0 Initial Conditions: The plant is in MODE 5 on day 28 refuel outage with the following conditions:

• Core is reloaded with 72 fresh FUEL ASSEMBLIES

• RCS Temperature to SDC, T351X, is stable at 1000F and is expected to remain stable for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• A Train Protected

• RCS Level is 14 inches above Centerline (LI-122 RCS Narrow Range)

Initiating Cues: The US has directed you to perform an RCS Time to Core Boil calculation per OU-M2-201, Attachment 2, Millstone Unit 2 Heatup Calculations.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Borated Water Source Monthly Surveillance JPM Number: A2R Revision: 1/0 Initiated:

John W. Riley - Signature on File 05/27/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/10/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/10/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2014 NRC JPM 0 04/23/2020 jwr Changed the number from ADMIN RO-3 A2R 2020 ILT NRC 1/0 exam. Modified JPM by raising RWST concentration and changing B BAST level. This made the usable volumes combined with the concentrations of the BASTs still not acceptable. But if the examinee uses total volume, without the required 685 gallons subtracted, the BASTs would be acceptable.

This was an Admin JPM given in the 2014 ILT exam that has been modified.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance System: Administrative - Borated Water Sources Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): 119-01-044 Applicable To: SRO X STA RO X PEO K/A Number: 2.1.25 K/A Rating: 3.9 / 4.2 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, the examinee will have completed the monthly borated water sources verification surveillance, SP 2601A and documented findings on surveillance form SP 2601A-009. They will determine that each individual BAST concentration is not sufficient for functionality per the TRM and determine that the weighted average of the concentration of the combined contents of both BASTs meets TRM requirements.

Required Materials:

• SP 2601A, Borated Water Sources Verification, Rev 019-02 (Steps 4.2.1 thru (procedures, equipment, etc.) 4.2.9 circle/slashed)

• SP 2601A-009, Surveillance Form, Borated Water Sources Verification, Monthly (Steps 4.2.9 b and c initialed)

• Unit 2 Technical Requirements Manual (prepare additional copies of TRM Figure 3.1-1 to replace the copy in the TRM if the applicant marks it up)

• Unit 2 Technical Specifications And Bases General

References:

• Unit 2 Technical Requirements Manual

• Unit 2 Technical Specifications And Bases 3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

4

JPM WORKSHEET JPM Number: A2R Revision : 1/0

• The plant has just completed an outage and has transitioned from MODE 5 to MODE 4.

• The Shift Manager has determined that the Monthly Borated Water Source Verification surveillance needs to be performed.

• The PPC Minimum BAST Volume calculation is not available.

• The PPC indicates A BAST level is 76.3%.

• The PPC indicates B BAST level is 95.0%.

• Steps 4.2.1 through 4.2.9 of SP-2601A are complete and chemistry has just provided the following tank concentration data:

A BAST Concentration 3.2 wt %

A BAST Concentration 5595 ppm B BAST Concentration 2.85 wt %

B BAST Concentration 4983 ppm RWST Concentration 2120 ppm from control board marker (C-01)

Initiating Cues: The Unit Supervisor directs you to perform SP2601A Borated Water Sources Verification Monthly Surveillance, beginning at Step 4.2.10 and document the results on Surveillance Form SP 2601A-009.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Examinee obtains a copy of SP 2601A, Borated Examinee obtains form. Y N S U Water Sources Verification and associated form SP-2601-009.

Cue:

Comments: Examiner to provide a copy of procedure 2601A, form 2601A-009 and the Unit 2 Technical Requirements Manual to examinee.

STEP Performance: Standard: Critical: Grade:

1. 2 4.2.10 RECORD new A BAST boron Examinee fills in concentration in wt% (3.2%) Y N S U concentration (wt% boric acid, and, if and ppm (5595 ppm) on the surveillance form provided, ppm boron) on SP 2601A-009. from initial conditions.

4.2.11 IF needed for PPC calculator AND not Examinee marks step as N/A. Y N S U provided by Chemistry Department, CONVERT A BAST boron concentration wt% to ppm as follows and RECORD on SP 2601A-009:

ppm = wt% x 1748.4 ppm/wt%

4.2.12 RECORD A BAST level (%) from PPC Examinee records A BAST level (76.3%) on Y N S U on SP 2601A-009. the surveillance form from the given data Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 3 4.2.13 CALCULATE A BAST volume in Examinee calculates A BAST volume (4345 Y N S U gallons as follows and RECORD on SP to 4360 gallons) and records on SP 2601A-009.

2601A-009:

Calculated BAST volume (gals) = (Level

% ÷ 100) x 5,706 (gals)

NOTE Examinee reads the note. Y N S U 10% level is the minimum BAST level for reliable charging pump suction. 685 gallons (10% disallowed + 2% instrument error) is subtracted from the tank volume to calculate usable volume.

4.2.14 CALCULATE usable A BAST volume Examinee calculates usable A BAST volume Y N S U as follows and RECORD on SP 2601A- (3660 to 3675 gallons) and records on SP 009: 2601A-009.

Usable A BAST volume (gals) =

Calculated volume - 685 (gals) 4.2.15 RECORD the most recently determined Records the RWST concentration (2120 ppm) Y N S U RWST boron concentration on SP 2601A- on SP 2601-009.

009, from SP 2601A-001, or control board marker (C-01).

Cue:

Comments: RWST concentration provided in initial conditions.

7

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 4 4.2.16 COMPARE A BAST boron Examinee determines A BAST Y N S U concentration and usable volume to one of concentration and usable volume does NOT the following acceptance criteria and fall within the acceptable operating zone INITIAL SP 2601A-009: specific in TRM Figure 3.1-1. Examinee checks NO box and initials for step 4.2.16 on

• Within acceptable operating zone 2601A-009.

specified in TRM Figure 3.1-1

• Within acceptable range determined by Note: 3675 gallons and 3.2% concentration PPC MINIMUM BAST VOLUME falls between the 2200 ppm and 2300 CALCULATION display from PRI ppm RWST lines.

SYS menu 4.2.17 IF boron concentration and usable volume Examinee determines CR is required and that Y N S U is not within Acceptance Criteria, Refer additional information is needed to assess To Attachment 1 and perform required whether action is required per TRM 3.1.2.8.

actions.

Cue:

Comments:

(1) Per initial conditions, the PPC Minimum BAST Volume Calculation is not available.

(2) If necessary (per Attachment 1, Step 3), direct the examinee to continue with the surveillance procedure.

8

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 5 4.2.18 RECORD new B BAST boron Examinee fills in concentration in wt% Y N S U concentration (wt% boric acid, and, if (2.85%) and ppm (4983 ppm) on the provided, ppm boron) on SP 2601A-009. surveillance form from initial conditions.

4.2.19 IF needed for PPC calculator AND not Examinee marks step as N/A. Y N S U provided by Chemistry Department, CONVERT B BAST boron concentration wt% to ppm as follows and RECORD on SP 2601A-009:

ppm = wt% x 1748.4 ppm/wt%

4.2.20 RECORD B BAST level (%) from PPC Examinee records B BAST level (95.0%) Y N S U on SP 2601A-009. on the surveillance form from the given data 4.2.21 CALCULATE B BAST volume in Examinee calculates B BAST volume (5410 Y N S U gallons as follows and RECORD on SP to 5435 gallons) and records on SP 2601A-2601A-009: 009.

Calculated BAST volume (gals) = (Level

% ÷ 100) x 5,706 (gals)

Cue:

Comments:

9

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 6 NOTE Y N S U 10% level is the minimum BAST level for Examinee reads the note.

reliable charging pump suction. 685 gallons (10% disallowed + 2% instrument error) is subtracted from the tank volume to calculate usable volume.

4.2.22 Calculate usable B BAST volume as Examinee calculates usable B BAST volume follows and RECORD on SP 2601A-009: (4725 to 4750 gallons) and records on SP Usable B BAST volume (gals) = 2601A-009.

Calculated volume - 685 (gals) 4.2.23 RECORD the most recently determined Records the RWST concentration (2120 ppm)

RWST boron concentration on SP 2601A- on SP 2601-009.

009, from SP 2601A-001, or control board marker (C-01).

Cue:

Comments: RWST concentration provided in initial conditions.

10

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 7 4.2.24 COMPARE B BAST boron Examinee determines B BAST concentration Y N S U concentration and usable volume to one of and usable volume does NOT fall within the the following acceptance criteria and acceptable operating zone specific in TRM INITIAL SP 2601A-009: Figure 3.1-1. Examinee checks NO box and initials for step 4.2.24 on 2601A-009.

• Within acceptable operating zone specified in TRM Figure 3.1-1 Note: 3675 gallons and 3.2% concentration

• Within acceptable range determined by falls between the 2200 ppm and 2300 PPC MINIMUM BAST VOLUME ppm RWST lines.

CALCULATION display from PRI SYS menu 4.2.25 IF boron concentration and usable volume Examinee determines CR is required and that Y N S U is not within Acceptance Criteria, Refer additional information is needed to assess To Attachment 1 and perform required whether action is required per TRM 3.1.2.8.

actions.

Cue:

Comments:

(1) Per initial conditions, the PPC Minimum BAST Volume Calculation is not available.

(2) If necessary (per Attachment 1, Step 3), direct the examinee to continue with the surveillance procedure.

11

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 8 NOTE

1. Input to the PPC calculator requires boron Examinee reads the note. Y N S U concentration in units of ppm.

2. Manual calculation of final boron concentration (Cf) of the combined BASTs is done using wt% needed for comparison to TRM Table 3.1-1.

4.2.26 IF A OR B BAST is not within TRM Examinee determines combined usable volume Y N S U Figure 3.1-1 or PPC calculation, of both BASTs, Vf = 8395 to 8415 gallons.

PERFORM the following:

a. CALCULATE the combined usable volume (Vf) of both BASTs in gallons as follows and RECORD on SP 2601A-

-009:

Vf (gals) = Usable A BAST volume (step 4.2.13) + Usable B BAST volume (step 4.2.21)

Cue:

Comments:

12

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 9

b. CALCULATE the final boron Examinee determines Cf = 2.95 to 3.05 wt % Y N S U concentration (Cf) of the combined BASTs as follows and RECORD on SP 2601A-009:

Cf (wt%) = Ca x Va + Cb x Vb Vf Vf Where:

Ca = A BAST conc (wt%) (step 4.2.9)

Va = Usable A BAST volume (gals)

(step 4.2.13)

Cb = B BAST conc (wt%) (step 4.2.17)

Vb = Usable B BAST volume (gals)

(step 4.2.21)

Vf = Combined usable BAST volume (gals) (step 4.2.25.a.)

Cue:

Comments:

13

PERFORMANCE INFORMATION JPM Number: A2R Revision: 1/0 Task

Title:

Borated Water Sources Monthly Surveillance STEP Performance: Standard: Critical: Grade:

1. 10

c. COMPARE combined BAST volume and Examine compares combined BAST volume Y N S U boron concentration to TRM Figure 3.1-1 and concentration to TRM Figure 3.3-1.

or PPC calculation and INITIAL SP Examinee checks YES box and initials step Y N S U 2601A-009. 4.2.26c of SP 2601A-009.

d. IF A AND B BAST combined volume Examinee determines surveillance acceptance Y N S U and boron concentration is not within TRM criteria met. Combined usable volume Figure 3.1-1 or PPC Acceptance Criteria, sufficient to meet requirements of TRM 3.1.2.8 Refer To Attachment 1 and perform Figure 3.1-1. No action required per TRM required actions. 3.1.2.8.

Note: With the RWST at 2120 ppm and Cf = 3.01 approximately 4,700 gallons of BAST is required for acceptable operation. And there is 8,406 gallons of usable volume available.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

14

VERIFICATION OF JPM COMPLETION JPM Number: A2R Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 15

STUDENT HANDOUT JPM Number: A2R Revision: 1/0 Initial Conditions:

• The plant has just completed an outage and has transitioned from MODE 5 to MODE 4.

• The Shift Manager has determined that the Monthly Borated Water Source Verification surveillance needs to be performed.

• The PPC Minimum BAST Volume calculation is not available.

• The PPC indicates A BAST level is 76.3%.

• The PPC indicates B BAST level is 95.0%.

• Steps 4.2.1 through 4.2.9 of SP-2601A are complete and chemistry has just provided the following tank concentration data:

A BAST Concentration 3.2 wt %

A BAST Concentration 5595 ppm B BAST Concentration 2.85 wt %

B BAST Concentration 4983 ppm RWST Concentration 2120 ppm from control board marker (C-01)

Initiating Cues: The Unit Supervisor directs you to perform SP2601A Borated Water Sources Verification Monthly Surveillance, beginning at Step 4.2.10 and document results on Surveillance Form SP 2601A-009.

16

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable JPM Number: A3R Revision: 0/0 Initiated:

John W. Riley - Signature on File 04/27/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/22/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 05/26/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE jwr 04/27/2020 New RO Admin JPM for the 2020 ILT NRC examination 0/0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable System: AC Electrical Distribution Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s):

Applicable To: SRO STA RO X PEO K/A Number: 2.2.44 K/A Rating: 4.2 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: The examinee will perform an AC Electrical Sources Inoperability Assessment for one EDG Inoperable in preparation for an Emergency Diesel Generator pre-lube and air-roll. They will determine that conditions are acceptable to perform this work.

Required Materials:

• SP 2619G, AC Electrical Sources Inoperability, revision 007, effective (procedures, equipment, etc.) 8/15/19, pages 1-4, 7-9

• SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, revision 003, effective 8/15/19.

• Photographs of Main Control Board C-08.

• Technical Specification LCO 3.0.5.

General

References:

• SP 2619G, AC Electrical Sources Inoperability, revision 007, effective 8/15/19.

• SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, revision 003, effective 8/15/19.

• Technical Specification LCO 3.0.5.

3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

4

JPM WORKSHEET JPM Number: A3R Revision : 0/0 Initial Conditions:

• The plant is at 100% power.

• An air-roll and pre-lube of the A Emergency Diesel Generator (EDG) is scheduled to be performed.

• There is no Technical Specification equipment Inoperable.

Initiating Cues:

• The Unit Supervisor (US) has directed you to perform surveillance SP 2619G-002, TS 3.8..1.1.b - One EDG Inoperable to support the air-roll and pre-lube of the A EDG.

• The US will provide an authorized SP 2619G-002, TS 3.8..1.1.b - One EDG Inoperable surveillance form.

• It is one hour before the air-roll and pre-lube of the A EDG is to be performed.

• The US will enter Technical Specifications when and as required per steps 4.3.2, 4.3.3, and 4.3.4.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 4.3 T/S 3.8.1.1.b. - One EDG Inoperable Examinee determines step 4.3.1 is N/A. Y N S U 4.3.1 IF EDG is inoperable due to extended Steps 4.3.2 and 4.3.3 are part of the initiating cue.

maintenance outage up to 14 days, Go To Section 4.7.

4.3.2 WHEN required, ENTER T/S LCO The US will enter Technical Specifications 3.8.1.1.b. when and as required.

4.3.3 IF the TDAFP is inoperable, Refer To TS Examinee will N/A this step since the TDAFW LCO 3.8.1.1.b.3 for required action pump is Operable.

Cue: The US will enter Technical Specification when and as required.

Comments:

• Provide examinee with an authorized SP 2619G-002 form, section 4.3 of SP 2619 procedure, C-08 photographs (consider using large boards in the classroom - just take them down and move them) and LCO 3.0.5.

• The examinee may or may not review these steps. Either is acceptable.

6

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 2 4.3.4 Refer To TS LCO 3.0.5 and Perform the Examinee may or not review TS LCO 3.0.5.

following:

a. DETERMINE any additional actions.

Determines no additional actions are required. Y N S U

b. ENSURE opposite Facility Redundant Determine opposite Facility Redundant SSCs Y N S U SSCs are OPERABLE and are OPERABLE and DOCUMENT on DOCUMENT on SP2619-G-002.

SP2619-G-002.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 3 4.3.5 Within one hour prior to or after entering For the Unit 2 RSST; examinee checks no Y N S U this condition, PERFORM the following: validate alarms on C-08 and supply breakers (A302 and A411) available, Green lights only

a. ENSURE two of the following and lit. Checks box on 2619G-002 indicating DOCUMENT on SP 2619G-002:

available.

• Unit 2 RSST For Unit 2 NSST; examinee N/As identifying Y N S U

• Unit 2 NSST with the generator that the NSST is not available.

links removed AND backfeed For Unit 3 to Unit 2 4,160V tie is energized; Y N S U lineup established examinee checks 24E SPLY VOLTS and

• Unit 3 to Unit 2 4,160V tie is 24E BUS VOLTS indicating approximately energized 4,160 volts. Indications at C-08 under 4.16 KV, Unit 3. Checks box on 2619G-002 indicating available.

Cue:

Comments: These boxes are checked after performing step 4.3.5 b since the 4.3.5.b is the actual check of what is available.

7

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 4

b. Refer To SP 2619G-002 and Examinee goes to page 3 under Unit 2 RSST to PERFORM Off-site AC Sources Bus 24C and 24D (top of page)

Alignment for two of the following:

• Vital 4,160V buses from Unit 2 For UNIT 2 RSS FDR 24C/24D RSST Y N S U 4,160V tie Voltage records voltage from C-08 under 4.16 KV RSST from meter RSST VOLTS.

For RSS SPLY BKR, 22S3-24C (A302) Y N S U and 22S3-24D-2 (A411) observes breaker racked up and indicating by green light only lit and checks boxes for breaker status.

• Unit 2 NSST feed to 4,160V buses Examinee goes to Unit 2 NSST to Bus 24C and Y N Y N 24D on page 3 (below Unit 2 RSST to Bus 24C and 24D).

For Unit 2 NSST feed to 4,160V buses N/As section since the plant is not in a backfeed alignment when online.

• Vital 4,160V buses from Unit 3 Examinee goes to Unit 3 to Unit 2, 4,160 Tie to Y N Y N 4,160V tie 24E on page 4 (top).

For 24E/34B TIE BKR, observes breaker is racked up and indicating by green light only lit and checks box.

For 24E Supply and Bus Voltage records voltage from C-08 under 4.16 KV under UNIT 3 from meters 24E SPLY VOLTS and 24E BUS VOLTS.

Cue:

Comments:

8

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 5

• Vital 4,160V buses from Unit 3 Examinee goes to AND Unit 3 RSST OR Unit 3 Y N S U 4,160V tie (Continued) NSST on page 4 (two lower sections).

Examinee calls Unit 3 and requests the status Y N S U of the Unit 3 RSST and NSST.

Examinee indicates results by checking the Y N S U four (4) results boxes for bus 34B to 24E.

Examinee N/As Unit 3 RSST 34A to 24E Y N S U section and Unit 3 NSST section since these were not used.

Cue: When examinee calls Unit 3 and requests the status of the Unit 3 RSST and NSST state the following; RSST A is energized with no valid alarm 34B1-2 (34B to 24E) closed RSSA-34D-2 (RSSA to 34D) breaker racked up and indicating 34C-1T-2 (34D to 34B) closed Comments:

• The examinee may go to page 2 and check the Available boxes for the RSST Energized / No Valid Alarms / Supply Breakers available and Unit 3 to Unit 2, 4,160V Tie Energized / No Valid Alarms / Supply Breaker available and N/A Unit 2 box. And then initial for the Acceptance Criteria for Any 2 of 3 Off-Site AC sources available. These need to be checked and initialed prior to completing the JPM.

• N/As of sections not used is not a critical.

9

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 6

c. ENSURE TDAFP is OPERABLE and Examinee initials box on page 2 of 2619G-002 Y N S U DOCUMENT on SP 2619G-002 indicating the TDAFP is Operable.

Cue:

Comments: Initiating cues state that the plant is at 100% power and that no Technical Specification equipment is Inoperable. Note that the initiating cue could result in the examinee initially this box early and this is acceptable.

STEP Performance: Standard: Critical: Grade:

1. 7 NOTE Step 4.3.5.d is a One-Time-Change that will Examinee reads note and step. Determine step is Y N S U remain in effect until an isolation transformer or not applicable since the A EDG is not being more reliable HVAC unit is installed. made inoperability due to maintenance.

d. PERFORM the following

1) IF A EDG is inoperable due to maintenance, Refer To OP 2349C, New Compuer Room and Old Computer Room HVAC Ventilation, and ENSURE B Unit X201-X203 is not in service.

2) IF B EDG is inoperable due to maintenance, Refer To OP 2349C, New Compuer Room and Old Computer Room HVAC Ventilation, and ENSURE A Unit X200-X202 is not in service.

Cue:

Comments:

10

PERFORMANCE INFORMATION JPM Number: A3R Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 8

e. IF EDG Outage is expected to exceed Examinee determines that since an Air-roll and Y N S U one shift, ENSURE the following Pre-lube is not expected to exceed one shift that equipment is posted as Protected this step is not applicable.

Equipment in accordance with OP-MP-601, Protected Equipment.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 9 4.3.6 IF the EDG became inoperable due to Examinee determines that the EDG did become Y N S U preplanned preventative maintenance or inoperable due to preplanned preventative testing, PERFORM the following: maintenance or testing and checks box on 2619G-002 for Preplanned Preventative

a. DOCUMENT on SP 2619G-002 Maintenance or Testing Met and initials.

b. Go To step 4.3.8 Then goes to step 4.3.8.

Cue:

Comments: The examinee should return the completed SP 2619G-002 form at this point, with the Performed by signed and Date/Time filled in. These are not critical but are expected.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

11

VERIFICATION OF JPM COMPLETION JPM Number: A3R Revision: 0/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 12

STUDENT HANDOUT JPM Number: A3R Revision: 0/0 Initial Conditions:

• The plant is at 100% power.

• An air-roll and pre-lube of the A Emergency Diesel Generator (EDG) is scheduled to be performed.

• There is no Technical Specification equipment Inoperable.

Initiating Cues:

• The Unit Supervisor (US) has directed you to perform surveillance SP 2619G-002, TS 3.8..1.1.b - One EDG Inoperable to support the air-roll and pre-lube of the A EDG.

• The US will provide an authorized SP 2619G-002, TS 3.8..1.1.b - One EDG Inoperable surveillance form.

• It is one hour before the air-roll and pre-lube of the A EDG is to be performed.

• The US will enter Technical Specifications when and as required per steps 4.3.2, 4.3.3, and 4.3.4.

13

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Perform a Waste Gas Pressure Drop Calculation and Flow Rate Determination JPM Number: A4R Revision: 0/0 Initiated:

John W. Riley - Signature on File 04/28/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/22/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 05/22/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE jwr 04/28/2020 New RO Admin JPM for the 2020 ILT NRC examination 0/0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A4R Revision: 0/0 Task

Title:

Perform a Waste Gas Pressure Drop Calculation and Flow Rate Determination System: Waste Gas Disposal System Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s):

Applicable To: SRO STA RO X PEO K/A Number: 2.3.11 K/A Rating: 3.8 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: The examinee will calculate the pressure drop of the A Waste Gas Decay Tank and then determine the discharge flow rate using and a Flow Rate vs Pressure Drop graph.

Required Materials: SP 2617BA, A WGDT Gaseous Waste Discharge, revision 006, effective (procedures, equipment, etc.) 7/16/2019, Attachments 1-4.

General

References:

SP 2617BA, A WGDT Gaseous Waste Discharge, revision 006, effective 7/16/2019.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: A4R Revision : 0/0 Initial Conditions:

• The A Waste Gas Decay Tank is being discharged using SP 2617BA, A WGDT Gaseous Waste Discharge

• The discharge has commenced.

• The first two times and associated pressures have been recorded on Attachment 1, Pressure Drop Calculation and Flow Rate Determination.

Initiating Cues: Calculate the pressure drop using SP 2617BA, Attachment 1, Pressure Drop Calculation and Flow Rate Determination.

Determine the discharge flow rate using SP 2617BA, Attachment 1, Pressure Drop Calculation and Flow Rate Determination and Attachments 2, 3 or 4, as applicable.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: A4R Revision: 0/0 Task

Title:

Perform a Waste Gas Pressure Drop Calculation and Flow Rate Determination START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 SP 2617BA, Attachment 1 Y N S U NOTE Placekeeping is covered for repeat steps 4 and 5

• Examine reads the note.

by documenting required data during steps 1, 2, and 3 in the table below.

1. RECORD Time and Pressure in Table

• Examine observes that Times and Pressures below. have been recorded on Attachment 1.

Cue:

Provide SP 2617BA, Attachment 1, Pressure Drop Calculation and Flow Rate Determination with Times and Pressures to the examinee.

Provide SP 2617BA, Flow Rate vs Pressure Drop Attachments 2, 3 or 4 to the examinee.

Comments:

5

PERFORMANCE INFORMATION JPM Number: A4R Revision: 0/0 Task

Title:

Perform a Waste Gas Pressure Drop Calculation and Flow Rate Determination STEP Performance: Standard: Critical: Grade:

1. 2

2. CALCULATE pressure drop rate using Examinee calculates the pressure drop using: Y N S U above formula 2 1

=

2 1 115.00 123.90 8.9

0231 0220 11 Pressure drop = 0.81 (acceptable 0.80 to 0.825)

Cue:

Comments: Drop in pressure is expressed positive value.

6

PERFORMANCE INFORMATION JPM Number: A4R Revision: 0/0 Task

Title:

Perform a Waste Gas Pressure Drop Calculation and Flow Rate Determination STEP Performance: Standard: Critical: Grade:

1. 3

3. Using Attachment 2, 3, or 4, as applicable,

• Examinee reviews Attachment 2, 3, and 4 and Y N S U Determine flow rate and RECORD in Table determines that Attachment 4, Flow Rate vs.

below. Pressure Drop (High Scale) is the correct chart.

• Examinee uses the calculated pressure drop (0.81 psig/minute) to determine Flow Rate.

Examinee determines Flow Rate:

Flow Rate = 2020 scfh (acceptable 1950 to 2050) Y N S U

• Examinee records Flow Rate in Table. Y N S U Cue:

Comments:

This JPM is complete once Attachment 1 is handed back to the examiner with the pressure drop calculated and flow rate determined.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: A4R Revision: 0/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 10 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: A4R Revision: 0/0 Initial Conditions:

• The A Waste Gas Decay Tank is being discharged using SP 2617BA, A WGDT Gaseous Waste Discharge

• The discharge has commenced.

• The first two times and associated pressures have been recorded on Attachment 1, Pressure Drop Calculation and Flow Rate Determination.

Initiating Cues: Calculate the pressure drop using SP 2617BA, Attachment 1, Pressure Drop Calculation and Flow Rate Determination.

Determine the discharge flow rate using SP 2617BA, Attachment 1, Pressure Drop Calculation and Flow Rate Determination and Attachments 2, 3 or 4, as applicable.

9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door JPM Number: A1S Revision: 0/0 Initiated:

John W. Riley - Signature on File 06/25/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/30/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/30/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE jwr 06/25/2020 New SRO Admin JPM for the 2020 ILT NRC examination 0/0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door System: Control Room Boundary and Fire Barriers Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): EO 322007 (06341-MB)

Applicable To: SRO X STA RO PEO K/A Number: 2.1.27 K/A Rating: 4.0 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: The examinee will determine that the Main Control Room Access door (Door ID 204-36-001) is INOPERABLE and that it is a TRM Fire Door and a Control Room A/C Boundary using OP 2356, Doors. They will then refer to the Technical Requirements Manual (TRM) and Technical Specifications (TS) and enter TRM 3.7.10 and T/S 3.7.6.1.c.

Required Materials:

• OP 2356, Doors, revision 011-00, effective 05/20/2019.

(procedures, equipment, etc.)

• Technical Specifications.

• Technical Requirements Manual.

General

References:

• OP 2356, Doors, revision 011-00, effective 05/20/2019.

• Technical Specifications.

• Technical Requirements Manual.

• AOP 2588A, Mitigating Actions For Control Room Envelope Boundary Breach, Rev 0.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: A1S Revision : 0/0 Initial Conditions:

• The Plant is at 100% power.

• The Main Control Room Access door, Door ID 204-36-001 (Security Door 147) is not capable of closing and latching.

• A security guard has responded and is now at the Main Control Room Access door.

Initiating Cues:

• You are the Unit Supervisor (US).

• The Shift Manager will make any reportability determinations.

• State the US actions required for the Inoperability of the Main Control Room Access door. Document your actions below:

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 The Unit Supervisor (US) uses OP 2356, Doors, The examinee reviews OP 2356, Doors, and uses it Y N S U Attachment 1, Unit 2 Door Attributes to identify identify the Main Control Room Access door, the Main Control Room Access door, Door Door ID 204-36-001 (Security Door 147)

ID 204-36-001 (Security Door 147) requirements.

requirements.

Cue: Examinee may request AOP 2588A, Mitigating Actions For Control Room Envelope Boundary Breach. State it is not required.

Comments: Provide examinee with the following (these can be at the examinees work location or made available through DocTop Web on a computer that does not have internet access);

(1) OP 2356, Doors.

(2) Millstone Unit 2 Technical Specifications.

(3) Millstone Unit 2 Technical Requirements Manual.

STEP Performance: Standard: Critical: Grade:

1. 2 The Unit Supervisor (US) uses OP 2356, Doors, Examinee utilizes OP 2354, Doors, Attachment 1, Y N S U Attachment 1, Unit 2 Door Attributes to identify Unit 2 Attributes and identifies; the Main Control Room Access door and identifies the following attributes for the
   Security door door;
   TRM Fire Door

Control Room A/C Boundary

• Security door

• TRM Fire Door

• Control Room A/C Boundary Cue:

Comments:

5

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door STEP Performance: Standard: Critical: Grade:

1. 3 4.2 TRM Fire Doors (TFD) Examinee goes to section 4.2, TRM Fire Doors Y N S U (TFD), identifies the door is a Unit 2 door and NOTE reads the note.

1. Site personnel are responsible for ensuring doors are closed and latched after passage to maintain barrier integrity.

2. C SP 600.25, Fire Door Inspections, contains the required attributes for TRM fire doors.

3. Additional signs are not allowed to be attached to Fire Doors or Fire Door frames.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door STEP Performance: Standard: Critical: Grade:

1. 4 4.2.2 IF the door is a Unit 2 door, PERFORM the following:

a. Refer To Unit 2 TRM, 3.7.10,
Examinee refers to Unit 2 TRM, 3.7.10, Y N S U Penetration Fire Barriers, and Penetration Fire Barriers, and states they ENTER applicable TRM Action would ENTERS TRM 3.7.10.

Statement.

b. IF Fire Door is required to be locked
Examinee determines this step is not Y N S U AND the only action performed is to applicable since the only action is not to unlock the door to provide temporary unlock the door.

access, Refer To SP 2619A, Control Room Shift Checks, and INITIATE Note: Table 7-1 Barrier Fire Watch Matrix Fire approved temporary log SP 2619A- Watch Determination - Index of Fire Areas/Zones 006, Fire Watch and Penetration identifies Fire Watch requirements. The Main Log, requiring verification that the Control Room has detection (SUPPR OR door is closed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. DETECTION column D1).

c. REQUEST a fire watch as indicated by
Examinee states they would use control room Y N S U the TRM action statement. staff as Fire Watch or request Fire Watch for the Main Control Room.

d. LOG door status in the Shift Turnover
Examinee states they would Log door status in Y N S U Report. the Shift Turnover Report.

e. INITIATE Condition Report to
Examinee states they would have a Condition Y N S U Security I&C for door repair. Report written.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door STEP Performance: Standard: Critical: Grade:

1. 5 4.8 Control Room Air Condition Boundary Examinee goes to section 4.8, Control Room Air Y N S U Doors (C) Condition Boundary Doors (C) and reads the note.

NOTE Site personnel are responsible for ensuring doors are closed and latched after passage to maintain barrier integrity.

Cue:

Comments:

8

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door STEP Performance: Standard: Critical: Grade:

1. 6 4.8.2 IF a required CRAC boundary door is
   Examinee refers to T/S 3.7.6.1.c and states Y N S U designed to close and latch AND the door they would enter the T/S. Stating the action is not capable of closing and latching, requirements, as follows, is not critical but is PERFORM the following: expected.

a. Refer To T/S 3.7.6.1.c, Plant Systems, C.1 Immediately initiate action to implement Control Room Emergency Ventilation mitigating actions or be in HOT System, for applicability and STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and COMMENCE appropriate actions. COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

AND C.2 Verify, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, mitigating actions ensure CRE occupant exposures to radiological and chemical hazards will not exceed limits, and mitigating actions are taken for exposure to smoke hazards or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

AND C.3 Restore CRE boundary to OPERABLE status within 90 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Cue:

Comments:

9

PERFORMANCE INFORMATION JPM Number: A1S Revision: 0/0 Task

Title:

SRO Assess the Inoperability of the Main Control Room Vital Access Door STEP Performance: Standard: Critical: Grade:

1. 7

b. ENTER TSAS and door status in Shift
Examinee states they would enter TSAS and Y N S U Turnover Report. door status in the Shift Turnover Report.

c. Refer To RAC 14, Non- Emergency
Examinee states the Shift Manager will Y N S U Station Events, Attachment 1, Plant evaluate reportabilty. This was stated in the Operation/Equipment/Technical initiating cue.

Specification Events, and evaluate reportability for loss of safety function.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

10

VERIFICATION OF JPM COMPLETION JPM Number: A1S Revision: 0/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 11

STUDENT HANDOUT JPM Number: A1S Revision: 0/0 Initial Conditions:

• The Plant is at 100% power.

• The Main Control Room Access door, Door ID 204-36-001 (Security Door 147) is not capable of closing and latching.

• A security guard has responded and is now at the Main Control Room Access door.

Initiating Cues:

• You are the Unit Supervisor (US).

• The Shift Manager will make any reportability determinations.

• State the US actions required for the Inoperability of the Main Control Room Access door. Document your actions below:

12

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Loss of Containment Closure JPM Number: A2S Revision: 1/0 Initiated:

John W. Riley - Signature on File 06/10/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/10/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 1/11/11 (mjc) Updated to include Work Practice evaluation. 0/1 07/12/2016 jwr Updated to latest JPM Template. Made editorial changes to 0/2 enhance the flow of the JPM.

04/29/2020 jwr Changed the number from JPM-A-08-02 to A2S for the 2020 ILT 1/0 NRC exam. Modified JPM by changing the component that results in the loss of Containment Closure. Made numerous editorial changes to standardize JPM format. The governing lineup (2614B-

02) has changed substantially. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation.

These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP-2 Examinee:

JPM Number: A2S Revision:

Task

Title:

Loss of Containment Closure System: Containment Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): Vision ID #s 573473, 236286 Applicable To: SRO X STA RO PEO K/A Number: 2.1.36 K/A Rating: 4.1 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, the examinee will have identified a loss of Containment closure, entered the appropriate TSAS and initiate actions to suspend all operations involving movement of irradiated fuel assemblies in the containment.

Required Materials:

• AOP 2515, Loss of Containment Integrity, revision 000-05, effective (procedures, equipment, etc.) 12/10/08.

• Unit 2 Technical Specifications

• Unit 2 Technical Requirement Manual

• SP 2614B-002, Containment Closure Verifications Steam Generator Secondary Side, revision 006, effective 07/30/2019

• P&ID 25203-26005 SH 2, Feed System General

References:

• AOP 2515, Loss of Containment Integrity, revision 000-05, effective 12/10/08.

• Unit 2 Technical Specifications

• Unit 2 Technical Requirement Manual

• SP 2614B-002, Containment Closure Verifications Steam Generator Secondary Side, revision 006, effective 07/30/2019.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: A2S Revision : 1/0 Initial Conditions:

• The plant is in MODE 6 with refuel off load in progress.

• Containment closure is set with closure plans (administrative controls) established for the following:

• CTMT Equipment Hatch

• CTMT Personnel Hatch

• CTMT Purge Valves

• The following plant conditions exist:

• A LPSI pump and A SDC HX in service

• T351Y, SDC return temperature is 90OF

• #1 Steam Generator secondary side manways are open for inspection

• CH D WR Nuclear Instrument is out of service

• You are the Unit Supervisor on watch in the Control Room.

Initiating Cues:

• The Auxiliary Building PEO calls to reports that workers have removed the cover and disc from Main Feedwater Check valve 2-FW-5A and that the valve is open.

• What are your actions as the Unit Supervisor on watch in the Control Room?

Document your actions below; Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: A2S Revision: 1/0 Task

Title:

Loss of Containment Closure START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Review procedures, Technical Specification, and Refers to and reviews procedures, Technical Y N S U any other material to understand the impact of Specification, and any other material breach of the PEO report. Containment closure.

Cue:

Comments: Have the following available and provide when asked for; Feed System P&ID 25203-26005, SH. 2 Technical Specifications Technical Requirements Manual AOP 2515, Loss of Containment Intergrity SP 2614B-002, Containment Closure Verifications Steam Generator Secondary Side STEP Performance: Standard: Critical: Grade:

1. 2 Refer To TRM Table 3.6-1. Refers to TRM Table 3.6-1 and determines that the Y N S U Main Feedwater Check valve 2-FW-5A is required for Containment isolation on penetration 15.

Cue:

Comments: This is not required if the examinee has already has determined that 2-FW-5A is required for containment closure .

5

PERFORMANCE INFORMATION JPM Number: A2S Revision: 1/0 Task

Title:

Loss of Containment Closure STEP Performance: Standard: Critical: Grade:

1. 3 Refer To AOP 2515, Loss of Containment Examinee determines AOP 2515 is applicable and Y N S U Integrity. performs applicable JPM steps 3-10.

Cue:

Comments: Entry into AOP 2515 is not a critical task. If the examinee enters AOP 2515 JPM steps 3-10 should be performed. If AOP 2515 is not entered only JPM step 10 is required for success in this JPM. But not entering AOP 2515 should be identified as an Area For Improvement.

STEP Performance: Standard: Critical: Grade:

1. 4

1. Refer To MP-26-EPI-FAP06, Classification Examinee either requests FAP06 or directs Shift Y N S U and PARs, and DETERMINE reportability Manager DETERMINE reportability.

requirements.

Cue: As Shift Manager state that you will DETERMINE Reportability.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 5

2. IF in MODES 1-4 and ANY automatic Examinee determines this step is not applicable. Y N S U containment isolation valve is inoperable The initial conditions state that the plant is in Mode 6.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: A2S Revision: 1/0 Task

Title:

Loss of Containment Closure STEP Performance: Standard: Critical: Grade:

1. 6

3. IF the unit is in MODE 6 with movement of Examinee goes to Step 17. Y N S U irradiated fuel assemblies inside containment in progress, Go To step 17.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 7

17. DIRECT the Refuel SRO to place ANY Examinee directs the Refuel SRO to place ANY Y N S U fuel assembly being handled in containment fuel assembly being handled in a safe location.

in a safe location.

18. STOP ALL operations involving movement Examinee directs the Refuel SRO once the fuel Y N S U of irradiated fuel in containment. assembly is a safe location to stop all operations involving movement of irradiated fuel in containment.

Cue: State as Refuel SRO that a used fuel assembly is being moved in containment. It is currently over its new location. It will be lowered into its new location and all activities associated with refueling in containment will stop. I will call when the movement is complete.

Comments: Spent Fuel Pool activities may continue as desired. Technical Specifications Definition 1.12 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe location.

7

PERFORMANCE INFORMATION JPM Number: A2S Revision: 1/0 Task

Title:

Loss of Containment Closure STEP Performance: Standard: Critical: Grade:

1. 8 Section 3, Step 19

19. IF ANY flow path exists between the Examinee directs Work Control to perform step 19. Y N S U containment atmosphere and the outside The Secondary Work Control SRO(s) control atmosphere, that is not covered by a closure Secondary Side closure.

plan, PERFORM ONE of the following:

• ISOLATE the penetration by means of a manual or automatic isolation valve, blind flange, or equivalent.

• ESTABLISH administrative controls necessary to make closure available.

Cue: State as Work Control that we are initiating action to close the penetration. You will notify the US and make Narrative Log entries associated with the action taken.

Comments: The Containment Closure Coordinators as defined in OP 2264 administers performance of SP 2614B (Licensed SRO).

STEP Performance: Standard: Critical: Grade:

1. 9

20. As necessary, Refer To SP 2614B, Examinee directs the Work Control Containment Y N S U Penetration Isolation Verification - Closure Coordinator to perform step 20.

Refueling and OP 2264, Conduct of Outages. and DOCUMENT containment penetration configuration control.

Cue: State as the Work Control Containment Closure Coordinator that you are taking action to perform step 20.

Comments: The Containment Closure Coordinators as defined in OP 2264 administers performance of SP 2614B.

8

PERFORMANCE INFORMATION JPM Number: A2S Revision: 1/0 Task

Title:

Loss of Containment Closure STEP Performance: Standard: Critical: Grade:

1. 10

21. As necessary, Refer to Technical Examinee declares entry into TSAS 3.9.4. Y N S U Specification 3.9.4 for Containment Penetrations.

Examinee directs the Refuel SRO to place ANY Y N S U fuel assembly being handled in a safe location and immediately suspend all operations involving movement of irradiated fuel assemblies in the containment Cue: State as Refuel SRO that a used fuel assembly is being moved in containment. It is currently over its new location. It will be lowered into its new location and all activities associated with refueling in containment will stop. I will call when the movement is complete.

Comments: Entry into 3.9.4 ACTION requirement is required for success in this JPM.

Placing the fuel assembly being handled in a safe location and immediately suspending all operations involving movement of irradiated fuel assemblies in the containment is also required for success in the JPM.

These may have been done in JPM step #7 (AOP 2515, steps 17 & 18) if AOP 2515 was entered.

Note that Spent Fuel Pool activities may continue if desired.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

9

VERIFICATION OF JPM COMPLETION JPM Number: A2S Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 mins Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: A2S Revision: 1/0 Initial Conditions:

• The plant is in MODE 6 with refuel off load in progress.

• Containment closure is set with closure plans (administrative controls) established for the following:

• CTMT Equipment Hatch

• CTMT Personnel Hatch

• CTMT Purge Valves

• The following plant conditions exist:

• A LPSI pump and A SDC HX in service.

• T351Y, SDC return temperature is 90OF

• #2 Steam Generator secondary side manways are open for inspection

• CH D WR Nuclear Instrument is out of service

• You are the Unit Supervisor on watch in the Control Room.

Initiating Cues:

• The Auxiliary Building PEO calls to reports that workers have removed the cover and disc from Main Feedwater Check valve 2-FW-5A and that the valve is open.

• What are your actions as the Unit Supervisor on watch in the Control Room?

Document your actions below; 11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Review AC Electrical Sources Inoperability Assessment for One EDG Inoperable JPM Number: A3S Revision: 0/0 Initiated:

John W. Riley - Signature on File 06/6/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/30/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/30/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE jwr 04/27/2020 New SRO Admin JPM for the 2020 ILT NRC examination 0/0 2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A3S Revision: 0/0 Task

Title:

Review AC Electrical Sources Inoperability Assessment for One EDG Inoperable System: AC Electrical Distribution Time Critical Task: YES NO Validated Time (minutes): 10 Task Number(s):

Applicable To: SRO X STA RO PEO K/A Number: 2.2.44 K/A Rating: 4.2 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:

Task Standards: The examinee will review an AC Electrical Sources Inoperability Assessment for one EDG Inoperable in preparation for an Emergency Diesel Generator pre-lube and air-roll. They will determine that conditions will not allow the surveillance to be accepted. The reasons are that the Turbine Driven Auxiliary Feedwater pump has been removed from service and the B Containment Spray pump has been determined to be inoperable.

Required Materials: SP 2619G, AC Electrical Sources Inoperability, revision 007, effective (procedures, equipment, etc.) 8/15/19, pages 1-4, 7-9 SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, revision 003, effective 8/15/19.

Photographs of Main Control Board C-08.

Technical Specifications.

General

References:

SP 2619G, AC Electrical Sources Inoperability, revision 007, effective 8/15/19.

SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, revision 003, effective 8/15/19.

Technical Specifications.

3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

4

JPM WORKSHEET JPM Number: A3S Revision : 0/0 Initial Conditions: The plant is at 100% power.

An air-roll and pre-lube of the A Emergency Diesel Generator (EDG) is scheduled to be performed.

The BOP performed surveillance SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable to support the air-roll and pre-lube of the A EDG in the last half hour.

The B Containment Spray pump surveillance was just completed and it was determined the pump is not OPERABLE.

A steam leak in the Turbine Driven Auxiliary Feedwater (TDAFW) pump room required closure of the TDAFW steam supply valves MS-201 and MS-202.

Initiating Cues: As the Unit Supervisor review for acceptance SP 2619G-002, TS 3.8.1.1.b

- One EDG Inoperable to support the air-roll and pre-lube of the A EDG.

If the surveillance cant be accepted state your reason(s) why below.

Simulator Requirements: N/A 5

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

6

PERFORMANCE INFORMATION JPM Number: A3S Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 The Unit Supervisor (US) reviews the The examinee reviews the completed SP 2619G- Y N S U surveillance. 002, TS 3.8.1.1.b - One EDG Inoperable.

Cue:

Comments: Provide examinee with the following; (1) Completed SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable.

(2) SP 2619G, AC Electrical Sources Inoperability, section 4.3 TS 3.8.1.1.b - One EDG Inoperable, with prerequisites and precautions.

(3) C-08 photographs (consider using large boards in the classroom).

(4) A copy of Technical Specifications.

7

PERFORMANCE INFORMATION JPM Number: A3S Revision: 0/0 Task

Title:

AC Electrical Sources Inoperability Assessment for One EDG Inoperable STEP Performance: Standard: Critical: Grade:

1. 2 Identify that surveillance requirements are not Examinee may or not review TS LCO 3.0.5.

met due to the following; 4.3.4 Refer To TS LCO 3.0.5 and Perform the following:

b. ENSURE opposite Facility Redundant Examinee determines opposite Facility Y N S U SSCs are OPERABLE and Redundant SSCs are not OPERABLE. The DOCUMENT on SP2619-G-002. B Containment Spray pump is an opposite Facility Redundant SSC and is not OPERABLE.

4.3.5 Within one hour prior to or after entering this condition, PERFORM the following:

c. ENSURE TDAFP is OPERABLE and Examinee determines the TDAFW pump is not Y N S U DOCUMENT on SP 2619G-002 OPERABLE as a result of the closure of MS-202 and MS-202.

Cue:

Once examinee identifies the above problems with the surveillance and states the surveillance cant be accepted this JPM is complete.

If the examinee states the surveillance cant be performed and doesnt state why, request reasons the surveillance cant be accepted.

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: A3S Revision: 0/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: A3S Revision: 0/0 Initial Conditions: The plant is at 100% power.

An air-roll and pre-lube of the A Emergency Diesel Generator (EDG) is scheduled to be performed.

The BOP performed surveillance SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable to support the air-roll and pre-lube of the A EDG in the last half hour.

The B Containment Spray pump surveillance was just completed and it was determined the pump is not OPERABLE.

A steam leak in the Turbine Driven Auxiliary Feedwater (TDAFW) pump room required closure of the TDAFW steam supply valves MS-201 and MS-202.

Initiating Cues: As the Unit Supervisor review for acceptance SP 2619G-002, TS 3.8.1.1.b

- One EDG Inoperable to support the air-roll and pre-lube of the A EDG.

If the surveillance cant be accepted state your reason(s) why below.

10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit JPM Number: A4S Revision: 3/0 Initiated:

John W. Riley - Signature on File 06/06/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/09/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 11/19/08 Revised JPM for LOIT 2008 NRC Exam 2/0 12/13/08 Incorporate NRC comments 2/0 jwr 06/06/2020 Changed the number from A3S to A4S for the 2020 ILT NRC 3/0 exam. Modified JPM from an Aerated Radioactive Liquid Waste Discharge to a Clean Radioactive Liquid Waste Discharge. This was done because most liquid radwaste is now processed through Clean Radioactive Liquid Waste. This results in essentially no more Aerated Radioactive Liquid Waste Discharges. Changing to a Clean Radioactive Liquid Waste discharge changed the radiation monitor and the required recirculation time. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A4S Revision: 3/0 Task

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit System: Radiation Control Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): NUTIMs #119-02-026 Applicable To: SRO X STA RO PEO K/A Number: 2.3.6 K/A Rating: 3.8 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: In-Plant:

Task Standards: At the completion of this JPM, the examinee will have discovered a plant operating condition that will NOT allow authorizing the radioactive liquid waste discharge.

Required Materials:

• SP 2617D Clean Radioactive Liquid Waste Discharges, Section 4.1, rev 001, (procedures, equipment, etc.) effective 9/20/16,

• SP 2864 001, Millstone Unit 2 Liquid Discharge Permit, rev 003-04, effective 9/9/14, Number L-EFF2-20200609-575-B

• SP 2617D-001, Clean Radioactive Liquid Waste Discharge, rev 000-04, effective 3/7/15.

General

References:

• SP 2617D Clean Radioactive Liquid Waste Discharges, Section 4.1, rev 001, effective 9/20/16,

• SP 2864 001, Millstone Unit 2 Liquid Discharge Permit, rev 003-04, effective 9/9/14

• SP 2617D-001, Clean Radioactive Liquid Waste Discharge, rev 000-04, effective 3/7/15.

• SP 2852-001, MP2 Liquid Radwaste Effluent Rad Monitor Inoperable, rev 004-00, effective 10/30/09 3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

4

JPM WORKSHEET JPM Number: A4S Revision : 3/0 Initial Conditions:

• The date is June 9, 2020.

• SP 2617D, steps 4.1.1 through 4.1.15 were completed by the Auxiliary Building PEO at 0535.

• There are NO other radioactive discharges in progress.

• SG blowdown is 40 gpm on each Steam Generator.

• Chemistry took the BCWMT sample at 0530; o One sample was provided o The results of the sample were acceptable.

• AWMT level is 92% and stable.

• The Mixer is out of service and was not used.

• The plant is at 100% power with all Circulating Water pumps at 100%

speed.

• RM-9049 is out of service and not available for the discharge.

• REMODCM IV.C.1.b has been reviewed for applicability for the Inoperability of RM-9049.

• The B CWMT was placed on recirculation at 0100.

• The discharge of the B CWMT is planned to start at 0700.

Initiating Cues:

• Chemistry has provided you with Chemistry Form 2864-001, Millstone Unit 2 Liquid Discharge Permit No. L-EFF2-20200609-575-B for the B Clean Waste Monitor Tank discharge for authorization.

• SP 2617D, Clean Radioactive Liquid Waste Discharge procedure and SP 2617D-001 are also provided.

• Your task is to review this discharge permit package and document below what must be accomplished to authorize the discharge.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: A4S Revision: 3/0 Task

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Prior to authorizing the B CWMT discharge, Examinee reviews Y N S U the US/SM must review Chemistry Form 2864-

• Chemistry Form 2864-001, Millstone Unit 2 001, Millstone Unit 2 Liquid Discharge Permit Liquid Discharge Permit No. L-EFF2-No. L-EFF2-20200609-575-B, when received 20200609-575-B from the Chemistry Department.

• SP 2617D-001, Clean Radioactive Liquid Waste Discharge, authorized and partially filled out to match initial conditions

• SP 2617D Clean Radioactive Liquid Waste Discharge, Steps 4.1.1 through 4.1.15 completed.

Cue:

(1) Provide Millstone Unit 2 Liquid Discharge Permit No. L-EFF2-20200609-575-B.

(2) Provide SP 2617D-001, Clean Radioactive Liquid Waste Discharge, authorized and partially filled out to match initial conditions.

(3) Provide SP 2617D Clean Radioactive Liquid Waste Discharge, Steps 4.1.1 through 4.1.15 completed.

If the examinee determines that the discharge CANNOT be authorized, ask Why not? And direct examinee to continue review.

Comments: The discharge cant be authorized because of the following; (1) The sample was taken without the required 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 45 minutes on recirculation.

(2) Two independent Chemistry samples were not taken, as required when the radiation monitor (RM-9049) is not OPERABLE.

6

PERFORMANCE INFORMATION JPM Number: A4S Revision: 3/0 Task

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit STEP Performance: Standard: Critical: Grade:

1. 2 4.1.17 WHEN SP 2864-001 (Discharge Permit) Examinee reviews SP 2864-001 Discharge Permit is authorized, SM or US Refer To SP and SP 2617D-001.

2617D-001 and PERFORM the following:

• IF discharge is to be performed with Examinee determines that radiation monitor is Y N S U radiation monitor NON NON FUNCTIONAL and that two FUNCTIONAL, ENSURE two independent samples have not been analyzed.

independent samples have been And does not INITIAL SP 2617D-001 first analyzed for the CWMT, as specified item in step 4.1.17.

on SP 2852-001, Unit 2 Liquid Radwaste Effluent Rad Monitor Inoperative, and INITIAL.

• IF RM-9049 is not OPERABLE, Refer Examinee notes the initial conditions specified Y N S U To REMODCM \ IV.C.1.b. for that REMODCM \ IV.C.1.b. has been applicability. reviewed for applicability due to RM 9049 being not OPERABLE.

• IF Unit 2 dilution flow is less than Examinee determines Unit 2 dilution flow is Y N S U 100,000 gpm, ENSURE Unit 3 is not greater than 100,000 gpm and this step is not discharging radioactive liquid waste. applicable.

Cue: If the examinee determines that the discharge CANNOT be authorized, ask Why not? And direct examinee to continue review.

Comments: The discharge cant be authorized because of the following; (1) The sample was taken without the required 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 45 minutes on recirculation.

(2) Two independent Chemistry samples were not taken, as required when the radiation monitor (RM-9049) is not OPERABLE.

7

PERFORMANCE INFORMATION JPM Number: A4S Revision: 3/0 Task

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit STEP Performance: Standard: Critical: Grade:

1. 3 4.1.11: (continued)

• REVIEW plant conditions and Examinee reviews plant conditions from Y N S U AUTHORIZE discharge. initial conditions and determines that Chemistry has not provided (2) independent samples and this is required when the radiation monitor is not Operable.

The examinee, if he reviews SP 2617D may see that step 4.1.16 is not complete.

Cue: If the examinee determines that the discharge CANNOT be authorized, ask Why not?

Comments: The discharge cant be authorized because of the following; (1) The sample was taken without the required 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 45 minutes on recirculation.

(2) Two independent Chemistry samples were not taken, as required when the radiation monitor (RM-9049) is not OPERABLE.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: A4S Revision: 3/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 9

STUDENT HANDOUT JPM Number: A4S Revision: 3/0 Initial Conditions:

• The date is June 9, 2020.

• SP 2617D, steps 4.1.1 through 4.1.15 were completed by the Auxiliary Building PEO at 0535.

• There are NO other radioactive discharges in progress.

• SG blowdown is 40 gpm on each Steam Generator.

• Chemistry took the BCWMT sample at 0530;

• One sample was provided

• The results of the sample were acceptable.

• AWMT level is 92% and stable.

• The Mixer is out of service and was not used.

• The plant is at 100% power with all Circulating Water pumps at 100%

speed.

• RM-9049 is out of service and not available for the discharge.

• REMODCM IV.C.1.b has been reviewed for applicability for the Inoperability of RM-9049.

• The B CWMT was placed on recirculation at 0100.

• The discharge of the B CWMT is planned to start at 0700.

Initiating Cues:

• Chemistry has provided you with Chemistry Form 2864-001, Millstone Unit 2 Liquid Discharge Permit No. L-EFF2-20200609-575-B for the B Clean Waste Monitor Tank discharge for authorization.

• SP 2617D, Clean Radioactive Liquid Waste Discharge procedure and SP 2617D-001 are also provided.

• Your task is to review this discharge permit package and document below what must be accomplished to authorize the discharge.

What must be accomplished to authorize the discharge:

10

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

EAL Classification and PARs / Notification JPM Number: A5S Revision: 1/0 Initiated:

John W. Riley - Signature on File 04/30/2020 Developer Date Reviewed:

Matt Morrissette - Signature on File 06/09/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 09/22/2016 New Classification and PARs JPM 0 11/04/2016 Added time limit for PARs / Notification 0/1 jwr 04/30/2020 Changed the number from JPM-190 to A5S for the 2020 ILT NRC 1/0 exam. PAR is different based on Control Room Protective Action Recommendations change. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: A5S Revision: 1/0 Task

Title:

EAL Classification and PARs / Notification System: Emergency Plan Time Critical Task: YES NO (15 minutes is allowed for CLASSIFICATION then an additional 15 minutes for / Notification.)

Validated Time (minutes): 30 Task Number(s): NUTIMS # 000-05-205 Applicable To: SRO X STA RO PEO K/A Number: 2.4.41 K/A Rating: 4.6 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: X In-Plant:

Task Standards: At the completion of this JPM, the examinee has correctly classified the proposed event and provided the appropriate Protective Action Recommendation.

Required Materials:

• MP-26-EPI-FAP06-002, Millstone Unit 2 Emergency Action Levels, rev. 012 (procedures, equipment, etc.)

• MP-26-EPI-FAP06-005, Control Room Protective Action Recommendations, rev. 008

• MP-26-EPI-FAP01-001, Control Room - Director of Station Emergency Operations (CRDSEO), rev. 014

• Incident Report Form (IRF)

• MP2 MET Tower Data General

References:

• MP-26-EPI-FAP06-002, Millstone Unit 2 Emergency Action Levels, rev. 012

• MP-26-EPI-FAP06-005, Control Room Protective Action Recommendations, rev. 008

• MP-26-EPI-FAP01-001, Control Room - Director of Station Emergency Operations (CRDSEO), rev. 014 3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

4

JPM WORKSHEET JPM Number: A5S Revision : 1/0 Initial Conditions: Plant conditions are as follows:

Plant Conditions TIME INFORMATION SOURCE 0 min. AOP 2569 Steam Generator Tube Leak was entered. US 3 min. Crew has entered AOP 2575 Rapid Down Power due to SGTL exceeding Tech. US Specs.

6 min. Main Steam Line Radmonitor RM-4299A in ALARM reading 2.2 R/hr US RCS parameters were validated and the US directs a Reactor Trip 21 min. EOP 2525 Standard Post Trip Actions were completed and the US transitioned US to EOP 2534 Steam Generator Tube Rupture.

22 min. The RO reports Main Steam Line Radmonitor RM-4299A in ALARM reading RO 2.5 R/hr and rising slowly.

32 min. The following Plant Conditions were noted prior to the cooldown of EOP 2534 Crew Steam Generator Tube Rupture:

• SIAS and CIAS fully actuated.

• RCS TCOLD 530°F and stable.

• RCS Pressure 1800 psia and slowly dropping.

Initiating Cues: You are the on-duty Shift Manger. Your task(s) are to;

1. Determine the NRC and state posture code classification for the event described above.

a. As required, provide any additional recommendations. You are to consider all plant conditions during the scenario.

b. Your classification should reflect the most severe classification level reached.

2. Determine the appropriate Protective Action Recommendation (PAR), if any apply.

3. Complete the attached IRF, starting with line 5.

Simulator Requirements: N/A 5

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

6

PERFORMANCE INFORMATION JPM Number: A5S Revision: 1/0 Task

Title:

EAL Classification and PARs / Notification START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Examinee obtains MP-26-EPI-FAP06-002 Based on the information provided the examinee Y N S U Millstone Unit 2 Emergency Action Levels classifies the event as a General Emergency; State and classifies the event within 15 MINUTES Posture Code, Alpha, based on OG1.

OFFSITE DOSE-OG1 RM-4299A Reading >2 R/hr for 15 minutes

---

TIME CRITICAL----------------- Classifies The Event Within 15 Minutes Y N S U START TIME: ____________

Determines Classification within 15 MINUTES after classifying the event. END TIME: ____________

Completes IRF through Major EAL heading. Examinee fills out IRF through Major EAL heading. Y N S U Cue: State that this is a TIME CRITICAL JPM and provide the Student with the following; Student handout (Initial Conditions and initiating cue).

Millstone Unit 2 Emergency Action Level (EAL) tables (MP-26-EPI-FAP06-002)

Control Room Protective Action Recommendation (MP-26-EPI-FAP06-005)

Control Room - Director of Station Emergency Operations (CRDSEO) (MP-26-EPI-FAP01-001)

Incident Report Form (IRF).

MP2 MET tower data Note: All the material above, except the Student handout (Initial Conditions and Initiating Cue), should be put at the students work location before starting. If steam table are requested provide them.

When the examinee has all the above material and has read the Initial Conditions and Initiating Cue, record the start time.

Specify to the examinee that once he/she has determined the classification, that it should be provided to the examiner immediately.

Comments: Initial Classification is a TIME CRITICAL TASK to be performed in <15 minutes from when the Examinee has read the Initial Conditions. The IRF should be completed but is not critical.

7

PERFORMANCE INFORMATION JPM Number: A5S Revision: 1/0 Task

Title:

EAL Classification and PARs / Notification STEP Performance: Standard: Critical: Grade:

1. 2 PAR from Control Room Protective Action Using MP-26-EPI-FAP06-005, Control Room Y N S U Recommendations, MP-26-EPI-FAP06-005. Protective Action Recommendations, examinee determines the following:

• General Emergency Declared Determines that Alpha - 5 mile PARs are

• General Emergency Alpha Declared warranted.

• Rapidly Progressing Severe Accident NO.

• Does CTMT Radiation Exceed Table 1 Values? NO

• Do 5 Mile Doses Exceed Table 2 PAGS?

NO

• Hostile Action Impediment (Note 7) NO Examinee determines the PAR is: Y N S U

• GE-Alpha(Note 3) - Required to meet critical task.

Evacuate Zones A, B, G, H. All other zones:

Monitor and Prepare - Desired but not critical.

---

TIME CRITICAL----------------- PAR determined within 15 minutes of examinee Y N S U providing Classification to examiner Determines PARs / Notification within 15 START TIME: ____________

MINUTES after classifying the event. END TIME: ____________

Cue:

Comments: Record start and end time for determining PAR. Notification is TIME CRITICAL TASK to be performed in <15 minutes from Initial Classification TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

8

VERIFICATION OF JPM COMPLETION JPM Number: A5S Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? START END Yes No CLASSIFICATION TIME _____ _____ (15 minutes is allowed for classification.)

NOTIFICATION TIME _____ _____ (15 minutes for Notification following classification.)

Actual Time to Complete: (Minutes) Grade Validated Time (minutes): 30 CLASSIFICATION S U NOTIFICATION S U Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT

STUDENT HANDOUT JPM Number: A5S Revision: 1/0 Initial Conditions: Plant conditions are as follows:

Plant Conditions TIME INFORMATION TIME 0 min. AOP 2569 Steam Generator Tube Leak was entered. 0 min.

3 min. Crew has entered AOP 2575 Rapid Down Power due to SGTL exceeding Tech. 3 min.

Specs.

6 min. Main Steam Line Radmonitor RM-4299A in ALARM reading 2.2 R/hr 6 min.

RCS parameters were validated and the US directs a Reactor Trip 21 min. EOP 2525 Standard Post Trip Actions were completed and the US transitioned 21 min.

to EOP 2534 Steam Generator Tube Rupture.

22 min. The RO reports Main Steam Line Radmonitor RM-4299A in ALARM reading 22 min.

2.5 R/hr and rising slowly.

32 min. The following Plant Conditions were noted prior to the cooldown of EOP 2534 32 min.

Steam Generator Tube Rupture:

• SIAS and CIAS fully actuated.

• RCS TCOLD 530°F and stable.

• RCS Pressure 1800 psia and slowly dropping.

Initiating Cues: You are the on-duty Shift Manger. Your task(s) are to;

1. Determine the NRC and state posture code classification for the event described above.

a. As required, provide any additional recommendations. You are to consider all plant conditions during the scenario.

b. Your classification should reflect the most severe classification level reached.

2. Determine the appropriate Protective Action Recommendation (PAR), if any apply.

3. Complete the attached IRF, starting with line 5.

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Respond to an ATWS JPM Number: S1 Revision: 5/0 Initiated:

John W. Riley - Signature on File 04/29/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/21/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 05/22/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2006-317 Update JPM to include HUP evaluations and new format 3 6/23/06 JWR 07/08/2011 Updated to new Template, added specific failure criteria (time) and 4 incorporated minor editorial changes.

JWR 09/10/2012 Made minor editorial changes and updated evaluation format. 4/1 SMD 11/04/2015 Updated to current format and standards. 4/2 MRP 07/25/2016 Minor editorial change to remove TIG-04 reference 4/3 jwr 04/27/2020 Changed the number from JPM- 069 to S1 for the 2020 ILT NRC 5/0 exam. Updated to latest format. Changed manual trip using the manual trip pushbuttons to a critical step. Specified opening MG set feeder breakers as the Alternate Path. Removed work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S1 Revision: 5/0 Task

Title:

Respond to an ATWS System: ATWS Time Critical Task: YES NO Validated Time (minutes): 5 Task Number(s): 000-05-218 Applicable To: SRO X STA RO X PEO K/A Number: 029-EA1.12 K/A Rating: 4.1/4.0 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: Examinee recognizes that that the reactor should have automatically shutdown, attempts to trip the reactor by pressing the manual trip pushbuttons, then takes Response Not Obtained action to trip the reactor by opening the CEDM MG set feeder breakers.

Required Materials:

(procedures, equipment, etc.)

General

References:

EOP 2525, Standard Post Trip Actions, revision 028-00, effective 12/29/16.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S1 Revision : 5/0 Initial Conditions:

• Plant is at 100% power.

• No equipment is out of service.

Initiating Cues:

• You are the RO.

• Monitor your panels and carry out any required actions.

• I will act as the Unit Supervisor.

Simulator Requirements:

• Initiate at a normal 100% power IC and enter the following:

• Insert RP04A, B, C & D (Manual Trip Failure).

• Insert RP27B (Overrides all RPS automatic trips, including ATWS).

• Insert RC13D ('D' RCP shaft break) on trigger #1.

• Place simulator in Run.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: S1 Revision: 5/0 Task

Title:

Respond to an ATWS START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Respond to alarms indicating the need for a

• Examinee observes the low flow trip alarms Y N S U reactor trip. (RED) on C-04.

• Examinee announces that the reactor should have tripped and didnt.

• Examinee states that they are tripping the reactor.

Cue:

Comments:

Initiate event by activating malfunction RC 13D, (D RCP Shaft Break) on Trigger #1.

The examiner should time from when the RED trip alarms are received on C04. The examinee not tripping the reactor within a minute of the receipt of these alarms would constitute a comment for area for improvement.

Examinee may state the need to trip the plant, or that he (she) is tripping the plant.

STEP Performance: Standard: Critical: Grade:

1. 2 Manually trip the reactor.

• Examinee locates and pushes all four the Y N S U manual trip pushbuttons RX TRIP TCB buttons on C-04

• Examinee observes the core mimic, CEAPDS, and/or PPC and announces that the reactor did not trip.

Cue:

Comments:

If asked by examinee for permission to trip the plant, respond with understand you the recommendation.

The examinee not tripping the reactor within a minute of the receipt of these alarms would constitute a comment for area for 5

PERFORMANCE INFORMATION JPM Number: S1 Revision: 5/0 Task

Title:

Respond to an ATWS improvement.

STEP Performance: Standard: Critical: Grade:

1. 3 OPEN CEDM MG set feeder breakers Examinee takes the hand switches on C-04 for both Y N S U

'A' & 'B' MG sets to the trip position.

Observes the MG Set green lights only lit, and performs the following:

• Observes reactor power lowering by checking Y N S U power range and/or wide range power indication on C-04 and/or RPS.

• Observe SUR negative by SUR meters on Y N S U C-04.

• Observes that no CEAs are stuck out by Y N S U checking mimic, CEAPDS, and/or pulse counter on C-04.

• When queried reports that the reactor is Y N S U tripped, power is lowering, startup rate is negative, and all CEAs are in.

Cue: After the CEDM MG set breakers are open, prompt the operator, Report status of the reactor.

Comments:

• This is the Alternate Path (opening the CEDM feeder breakers). The primary path was pushing the manual trip pushbuttons.

• May state that an ATWS occurred. Automatic trip failure and manual trip was successful. This is helpful for the Shift Manger for Classification.

• The examinee not tripping the MG Set Breakers would constitute a failure of the JPM.

• When the examinee has completed this step, reported that the reactor is tripped, and the JPM is complete TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

6

PERFORMANCE INFORMATION JPM Number: S1 Revision: 5/0 Task

Title:

Respond to an ATWS 7

VERIFICATION OF JPM COMPLETION JPM Number: S1 Revision: 5/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 5 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: S1 Revision: 5/0 Initial Conditions:

• Plant is at 100% power.

• No equipment is out of service.

Initiating Cues:

• You are the RO.

• Monitor your panels and carry out any required actions.

• I will act as the Unit Supervisor.

9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Raising #1 SIT Level Using the A HPSI Pump JPM Number: S2 Revision: 6/0 Initiated:

John W. Riley - Signature on File 05/04/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/21/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 05/22/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE N/A Update format and make changes to add procedure step and 4/2 initiating cues to reflect new procedure revision for UT inspection.

6/27/16 jwc Update format and make changes to reflect new procedure 5/0 revision.

Changed Task number from # 044-703-01 to 01-006-01-077 (Vision ID# 235567) NOTE: 01-006-01-077 not selected for 2015-16 training. Changed setup required due to changing simulator platform to TREX.

jwr 05/04/2020 Changed the number from 025 to S2 for the 2020 ILT NRC 6/0 exam. Changed inputs to make level go to 55% in the new THOR model. Change on pressure is lowered in the THOR model. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump System: ECCS Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): 01-006-01-077 (Vision ID# 235567)

Applicable To: SRO X STA RO X PEO K/A Number: 006A1.13 K/A Rating: 3.5/3.7 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: Raise #1 SIT level using 'A' HPSI pump per OP 2306O section 4.1.

Required Materials: OP 2306O, Safety Injection Tanks, RCS 1750 psi, revision 007-00, effective (procedures, equipment, etc.) 09/29/2019.

General

References:

OP 2306O, Safety Injection Tanks, RCS 1750 psi, revision 007-00, effective 09/29/2019.

ARP 2590A-37, SAFETY INJECTION TANK 1 LEVEL HI, revision 001, effective 1/4/18.

ARP 2590A-38, SAFETY INJECTION TANK 1 LEVEL LO, revision 001, effective 6/24/19.

ARP 2590A-40, SAFETY INJECTION TANK 1 PRES LO, revision 001, effective 6/24/19.

ARP 2590A-053, SIS TO LOOP 1A PRES HI, revision 003, effective 1/4/18.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S2 Revision : 6/0 Initial Conditions: Plant is at 100% power.

The #1 SIT Low level alarm (C01-B10) and pressure alarm (C01-D10) have annunciated.

Initiating Cues: The #1 SIT level is low, with a corresponding lower than normal pressure.

Raise the level in the #1 SIT with the 'A' HPSI pump using OP 2306O.

Raise the level in the #1 SIT to between 56% - 56.5% with pressure between 200 - 210 psig.

I will act as the PEO and the US.

Sampling of the SIT is not required.

The cause of level reduction has been identified.

Performance of UT exams is NOT required.

Simulator Requirements: Initialize in IC-284 (exam password protected - this has initial conditions established) or equivalent full power IC and establish #1 SIT level at 55% and pressure at ~ 198 psig, as follows:

1. Open Insight on the Top Bar.

2. Open OPEN Folder.

3. Open Common THOR Insight Files.

4. Open Change common tank values.

5. At top for thilevch type 996 and hit enter

6. Again for thllevch type 0.55 and hit enter.

7. Go to Run.

8. Verify SIT #1 level at ~ 55% on L311.

9. Install SIT #1 vent valve SI-613 fuse in remotes by selecting SIR13 and placing it in IN and insert.

10. Observe on MCB that SI-613 green light lit, start a trend of P311, and open vent SI-613 until pressure lowers to ~198 psig.

11. Verify the values for the #1 SIT level and pressure are ~ 55% and

~198 psig respectively on the main control board and PPC (L311 and P311).

12. Once vented to lower pressure remove SIT #1 vent valve SI-613 fuse in remotes by selecting SIR13 and placing it in OUT and insert.

13. Verify annunciators C01-B10 SAFETY INJECTION TANK 1 LEVEL LO and C01-D10 SAFETY INJECTION TANK 1 PRESS LO lit.

14. Ensure Facility 1 Header Stop, 2-SI-656 key is removed and placed in key locker.

4

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 OP 2306O, 4.1 Raising SIT Level The examinee states that the initiating cue does not Y N S U require this step to be performed. Examinee N/As 4.1.1 IF the cause of the SIT level reduction is the step.

unknown, PERFORM the following:

a. ENSURE a Condition Report is issued for performing troubleshooting to determine the leak path.

b. Refer To SP 2604Z and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, PERFORM applicable steps to confirm the following piping is full:

Associated SIS header to Loop piping penetration(s) (UT Points 15, 16, 17, or 18)

Containment Spray pump discharge headers (UT points 26 and 27)

Cue: The initiating cue stated that UT exam is not required Comments:

1. Provide section 4.1, Raising SIT Level, of OP 2306O, Safety Injection Tanks, RCS 1750 psi to examinee. This JPM can be started in the briefing room where the procedure can be reviewed prior to entering the simulator.

2. If a task preview is performed in the briefing room this step may be N/Ad prior to the examinee entering the simulator.

3. As stated in the Ops Standards and Expectations Handbook steps may be N/Ad if the conditional statement is FALSE.

6

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 2 4.1.2 DETERMINE desired SIT(s) level using one of the following criteria:

IF sampling is not required, do not fill The examinee determines desired level is 58.8%. Y N S U greater than 58.8% (alarm C-01 59%)

NOTE The following C-01 alarms are expected at 59%

Examinee reads and understands NOTE. Y N S U SIT level:

SAFETY INJECTION TANK 1 LEVEL HI (A-10)

SAFETY INJECTION TANK 2 LEVEL HI (A-11)

SAFETY INJECTION TANK 3 LEVEL HI (A-12)

Examinee N/As the second bullet. Sampling is Y N S U SAFETY INJECTION TANK 4 LEVEL HI (A-13) not required per the initiating cue.

IF sampling is required, do not fill greater than 59.6% (PPC high alarm 59.7%).

Cue: If examinee asks about A HPSI pump pre-start and post-start checks, responds that they are SAT.

Comments: The initiating cue stated that sampling was not required and to raise the level in the #1 SIT to between 56% - 56.5% and pressure between 200 - 210 psig.

7

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 3 NOTE

1. The facility one Header Stop (2-SI-656) is Examinee reads and understands the NOTE. Y N S U the only HPSI HDR Stop that can be opened The examinee states SIS TO LOOP 1A PRESS HI, with the D/P caused by having a running (C-01, window A-14) is an expected alarm.

HPSI Pump. The HPSI HDR Stop must be closed, prior to starting a HPSI Pump, to prevent the pressure wave, which will cause perturbations in the downstream piping and valves.

2. The following alarms are expected after reopening 2-SI-656:

SIS TO LOOP 1A PRESS HI, (C-01, window A-14)

SIS TO LOOP 1B PRESS HI, (C-01, window B-14)

SIS TO LOOP 2A PRESS HI (C-01, window C-14)

SIS TO LOOP 2B PRESS HI (C-01, window D-14)

Cue:

Comments:

8

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 4 4.1.3 LOG entry into TSAS 3.5.2.a, The examinee informs the evaluator that entry into Y N S U Emergency Core Cooling Systems." TSAS 3.5.2.a is required.

Cue: Evaluator states TSAS 3.5.2.a has been entered.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 5 4.1.4 CLOSE 2-SI-656 HPSI HDR A STOP. Examinee closes 2-SI-656. Y N S U Closure indicated by GREEN indicating light lit and RED indicating light not lit.

Cue:

Comments: 2-SI-656 is the Faciliy1 HPSI Header Stop Valve.

9

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 6 4.1.5 WHEN HPSI pump is started, CHECK When the examinee starts the A HPSI pump and Y N S U the following (C-01): verifies proper amps and discharge pressure.

Motor amperage 20 to 30 amps Nominal discharge pressure 1250 to 1300 psig 4.1.6 START one of the following HPSI The examinee starts the A HPSI pump. Y N S U pumps (C-01).

P-41A, HPSI PP A IF aligned to Facility 1, P-41B, HPSI PP B Cue:

Comments:

Initiating Cue is to use the A HPSI pump.

The examinee should call up a trend of #1 SIT level and pressure (L311 and P311). They may set up a trend of all SIT levels and pressures to ensure the fill of #1 SIT is not affecting the other SITs.

The pump discharge pressure and amps should be ~1295 psia and 28 amps respectively.

STEP Performance: Standard: Critical: Grade:

1. 7 4.1.7 WAIT 10 seconds. Examinee waits > 10 seconds and opens 2-SI-656 Y N S U 4.1.8 OPEN 2-SI-656 HPSI HDR A STOP. HPSI HDR A STOP."

Cue:

Comments: The four SIS TO LOOP PRES HI annunciators are expected after the HPSI header stop is opened.

10

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 8 4.1.9 LOG out of TSAS 3.5.2.a, Emergency Examinee requests that the US log out of TSAS Y N S U Core Cooling Systems. 3.5.2.a.

Cue: Evaluator states as US, that TSAS 3.5.2.a has been exited.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 9 CAUTION Recirculation header must not be subjected to Examinee reads and understands the Caution and Y N S U pressure above 300 psig as indicated on recognizes/states the Note is N/A.

RECIRC HDR PRESS, PI-305."

NOTE When raising pressure during reactor startup before containment reaches operating temperature, SIT pressure should be limited to 220 psig to allow for thermal expansion.

Cue:

Comments:

11

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 10 4.1.10 IF filling SIT #1, PERFORM the following (C-01):

a. OPEN SI-611, FILL & DRN. Examinee opens 2-SI-611. Indication of Y N S U RED light lit and GREEN light not lit.

b. THROTTLE open SI-618, HDR-1A Examinee opens 2-SI-618 and monitors for #1 Y N S U CK VLV LKG DRN STOP" not to SIT pressure and level change as well as exceed 300 psig, indicated on PI- recirculation header pressure.

305, RECIRC HDR PRESS.

c. WHEN any of the following occur, Examinee closes 2-SI-618 when level in the Y N S U CLOSE SI-618: #1 SIT is between 56% - 56.5% and pressure L311 SI TK 1 LVL" at desired is between 200 - 210 psig (this was the level (PPC) desired level and pressure from the initiating cue).

P311 SI TK 1 PRESS" pressure 225 psig (PPC)

PI-311, SIT 1 PRESS" pressure 225 psig PPC SIT high level alarm (59.8%)

d. CLOSE SI-611, FILL & DRN. Examinee closes 2-SI-611. Indication of Y N S U GREEN light lit and RED light not lit.

Cue: If asked about the level to go to, specify that the examinee has been provided the required information.

Comments:

1. A momentary excursion of recirculation header pressure (PI-305) above 300 psig does not constitute a failure of this step.

2. The initiating cue specified level in the #1 SIT be raised to between 56% - 56.5% and pressure be raised to between 200 - 210 psig.

12

PERFORMANCE INFORMATION JPM Number: S2 Revision: 6/0 Task

Title:

Raising #1 SIT Level Using the A HPSI Pump STEP Performance: Standard: Critical: Grade:

1. 11 Examinee N/As steps 4.11 - 4.13. SITs 2, 3, Y N S U

& 4 are not being filled. N/A of these steps is not critical.

4.1.14 IF no longer required, STOP HPSI pump Examinee stops the A HPSI pump. Y N S U (C-01).

Cue: When the A HPSI pump is stopped (step 4.1.14) state that this JPM is complete.

Comments: Taking the A HPSI pump handswitch pass stop to PTL will cause the HPSI PUMPS MISALIGNED annunciator to come in. It will clear once it is taken to stop.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

13

VERIFICATION OF JPM COMPLETION JPM Number: S2 Revision: 6/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 14

STUDENT HANDOUT JPM Number: S2 Revision: 6/0 Initial Conditions: Plant is at 100% power.

The #1 SIT Low level alarm (C01-B10) and pressure alarm (C01-D10) have annunciated..

Initiating Cues: The #1 SIT level is low, with a corresponding lower than normal pressure.

Raise the level in the #1 SIT with the 'A' HPSI pump using OP 2306O.

Raise the level in the #1 SIT to between 56% - 56.5% with pressure between 200 - 210 psig.

I will act as the PEO and the US.

Sampling of the SIT is not required.

The cause of level reduction has been identified.

Performance of UT exams is NOT required.

15

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling JPM Number: S3 Revision: 3/0 Initiated:

John W. Riley - Signature on File 05/13/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/22/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 05/26/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2014 Updated JPM to Current Template. Revised Reference to EOP 2 2540D, HR-3. Modified to include all steps to initiate Once-Through-Cooling to comply with NRC guidance on Alternate Path JPMs.

7/6/16 jwc-jwr Minor Editorial changes. Reformatted to latest JPM template. 2/1 Minor changes due to procedure changes.

05/13/2020 jwr Changed the number from 118 to S3 for the 2020 ILT NRC exam. Changed simulator requirements slightly to lower steam 3/0 generator level quicker when establishing initial conditions.

Made editorial changes and standardized format. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling System: RCS Time Critical Task: YES NO Validated Time (minutes): 8 Task Number(s): 171-300-05-01 Applicable To: SRO X STA RO X PEO K/A Number: 074EA1.05 K/A Rating: 3.9/4.1 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: Examinee performs Contingency Action step of EOP 2540D, HR-3, to OPEN PORVs in response to Key Switch Failure.

Required Materials: EOP 2540D, Functional Recovery of Heat Removal, revision 025-00, effective (procedures, equipment, etc.) 02/01/19.

General

References:

EOP 2540D, Functional Recovery of Heat Removal, revision 025-00, effective 02/01/19.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S3 Revision : 3/0 Initial Conditions:

• The plant is undergoing a Loss of all Feedwater and a LOCA in containment.

• The crew is in EOP 2540 Functional Recovery.

• Steam Generators 1 & 2 levels are < 290 inches and Main and Auxiliary Feedwater are not expected to be restored prior to one SG reaching 70 inches and the other SG reaching 165 inches.

• SIAS, CIAS, & EBFAS have initiated.

• Annunciators are in Alarm Silent.

Initiating Cues: The crew has entered EOP 2540, Functional Recovery:

• The Unit Supervisor directs you to Initiate Once-Through-Cooling Using EOP 2540D, HR-3.

• I will act as the Unit Supervisor.

Simulator Requirements: Initialize in IC-283 (includes items listed below) or any 100% power IC (IC-23) and include the following Remotes/Malfunctions/IOs:

• Enter malfunctions ED08A & ED08B on Event 30 (Failure of 6.9 KV Bus Xfer on trip).

• Enter malfunctions FW20A, FW20B, and FW20C (AFW Pumps Tripped).

• Enter malfunctions RC06A & RC06B @ 0% (PORVs failed closed).

• Enter overrides 02A2A2S12, RC-402 PORV Key Switch Failure (CLOSE)

• Enter override 02A2A2S13, RC-404 PORV Key Switch Failure (CLOSE).

• Enter remote RPR18 CH. A & B RPS High Pressure B/S Removed (OUT)

Trigger 2.

• Enter malfunction RC02A at 200 #/s @ 2250 psid with a trigger on event

30. This is a severity to cause a small break where pressure stabilizes at approximately HPSI shutoff (#1 Hot leg LOCA).

• With the simulator operating at 100% manually trip a Main Feedwater pump and allow the plant to auto trip on low Steam Generator level.

This lowers level to < 300 inches much faster.

• Carry out all actions of EOP 2525, Standard Post Trip Actions including 2541, Appendix 4, Followup Action, Attachment 4A.

• Place annunciators in Alarm Silent.

• Verify RCPs are stopped and both PORV block valves are open.

• Place the simulator in freeze after both steam generator wide range levels are < 300 inches.

• Verify procedure used for previous examinee is clean or replaced.

Check BOP and RO EOP 2540D, HR-3, pages 1-4 clean.

• When the examinee is on station and has stated that he/she is ready, place the simulator in run.

4

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 EOP 2540D HR-3, 3.0 SUCCESS PATH: HR- Examinee reads and acknowledges NOTE. Y N S U 3 ONCE-THROUGH-COOLING NOTE OTC should be initiated prior to ONE steam generator wide range level reaching 70 inches, AND ONE steam generator wide range level reaching 165 inches if ANY of the following exist:

1. Main or auxiliary feedwater is not expected to be restored.

2. Less than TWO trains of HPSI, PORVs and ADVs are available.

3. Less than THREE charging pumps are available.

Cue:

Comments: Examine should use the EOPs at the RO or BOP station to perform the required actions.

6

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling STEP Performance: Standard: Critical: Grade:

1. 2 Establish Once-Through-Cooling Examinee has been directed in the initiating cues to Y N S U initiate OTC. Examinee may review step and

1. CHECK if Once-Through- Cooling (OTC) is independently determine he/she meets OTC required by ANY of the following conditions:

initiation criteria due to Main or Auxiliary

• ONE steam generator wide range level Feedwater is not expected to be restored.

less than or equal to70 inches AND the REMAINING steam generator wide range level is less than or equal to 165 inches

• RCS TCold rises uncontrollably by 5°F or more Cue: If asked state that the Unit Supervisor directs you to Initiate Once-Through-Cooling, using EOP 2540D, HR-3 at the current SG levels since Main and Auxiliary Feedwater are not expected to be restored prior to one SG reaching 70 inches and the other SG reaching 165 inches.

Comments: Initial conditions stated Steam Generators 1 & 2 levels are < 290 inches and Main and Auxiliary Feedwater are not expected to be restored prior to one steam generator reaching 70 inches and the other SG reaching 165 inches.

7

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling STEP Performance: Standard: Critical: Grade:

1. 3 Establish Once-Through-Cooling

2. IF OTC is required AND steam generator level is not restoring, THEN ESTABLISH heat removal via OTC by performing ALL of the following:

a. DEENERGIZE ALL pressurizer heaters: Examinee places all proportional heaters to Off Y N S U then to Auto. Examinee observes heaters are

• PLACE BOTH proportional heaters tripped by observing green lights lit.

in OFF then return to AUTO

• PLACE ALL backup heaters in Examinee places all backup heaters in Pull to Y N S U PULL TO LOCK. Lock.

b. IF the main condenser is available, Examinee determines Main Condenser is not Y N S U THEN OPEN ALL steam dump valves. available and N/As opening steam dump valves.

c. OPEN BOTH ADVs. Examinee opens both ADVs. Y N S U

d. CHECK ALL RCPs stopped. Examinee verifies all RCPs stopped. Breaker Y N S U green lights on and no pump amps.

e. CHECK SIAS actuated. Examinee verifies SIAS actuated. C01 Y N S U annunciators.

f. CHECK BOTH trains of HPSI pumps Examinee verifies both HPSI pumps running. Red Y N S U OPERATING. breaker light on, pump amps, discharge pressure, etc.

Cue:

Comments: Main Condenser is not available.

8

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling STEP Performance: Standard: Critical: Grade:

1. 4

g. CHECK ALL HPSI loop injection valves OPEN.

Examinee verifies all HPSI loop injection valves Y N S U

• SI-617, Loop 1A are open. Red lights on Green lights off.

• SI-627, Loop 1B

• SI-637, Loop 2A

• SI-647, Loop 2B

• SI-616, Loop 1A

• SI-626, Loop 1B

• SI-636, Loop 2A

• SI-646, Loop 2B

h. CHECK ALL available charging pumps Examinee verifies all available Charging pumps Y N S U OPERATING. running. Red breaker lights on with flow.

i. CHECK BOTH PORV block valves Examinee verifies both PORV Block valves open Y N S U OPEN by Red lights lit and Green lights not lit.

• RC- 403

• RC- 405

j. OPEN BOTH PORVs. (keys #187) Examinee takes both PORV handswitches Y N S U to OPEN and observes their failure to open

• RC- 402 by both green lights only still lit.

• RC- 404 Cue: ALTERNATE PATH BEGINS HERE Comments: When examinee attempts to open each PORV, the valves will not open.

9

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling STEP Performance: Standard: Critical: Grade:

1. 5 REPORT the failure of the PORVs to open. Examinee informs the Unit Supervisor that both Y N S U PORVs failed to open with their handswitches and that they are taking CONTINGENCY ACTIONS.

Cue: As the Unit Supervisor, acknowledge the report.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 6 CONTINGENCY ACTIONS j.1 PERFORM the following to open BOTH Examinee states that they would pull two RPS Y N S U PORVs channels high pressure trip modules.

1) WITHDRAW TWO RPS high pressure Examinee goes to the RPS cabinets, identifies the trip bistables. high pressure trip module(s), states they would unscrew (2) high pressure trip module(s) and pull them out.

Cue: When examinee begins to simulate pulling high pressure trip units, inform him/her that Channel A & B must be used, and the respective channels high pressure trip units have been pulled.

Comments: Booth instructor Activates Remote Function RPR 18, Event Trigger 2, to pull B/Ss at this time TOGETHER with Removal of RC06A and RC06B. This will OPEN both PORVs.

NOTE: The examinee cannot physically remove the modules in the simulator. The Simulator Instructor must enter RPR18 to disconnect Channel A and B high pressure trip modules. Physical removal of any trip unit from the RPS panels results in activation of all of that trip unit's functions. Removal of two high pressurizer pressure trip units will cause a Reactor trip and PORVs to open.

10

PERFORMANCE INFORMATION JPM Number: S3 Revision: 3/0 Task

Title:

Respond to PORV Key Switch Failure while Performing Once-Through-Cooling STEP Performance: Standard: Critical: Grade:

1. 7 Establish Once-Through-Cooling

k. CHECK at least ONE PORV open. Examinee observes that both PORVs open by their Y N S U red lights only lit.

• RC- 402

• RC- 404 Cue:

Comments: Examinee may also verify valves open by changing Quench Tank level, pressure and temperature.

Examinee should state OTC has been initiated. Examinee not stating this is not critical.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

11

VERIFICATION OF JPM COMPLETION JPM Number: S3 Revision: 3/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 10 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 12

STUDENT HANDOUT JPM Number: S3 Revision: 3/0 Initial Conditions:

• The plant is undergoing a Loss of all Feedwater and a LOCA in containment.

• The crew is in EOP 2540 Functional Recovery.

• Steam Generators 1 & 2 levels are < 290 inches and Main and Auxiliary Feedwater are not expected to be restored prior to one SG reaching 70 inches and the other SG reaching 165 inches.

• SIAS, CIAS, & EBFAS have initiated.

• Annunciators are in Alarm Silent.

Initiating Cues: The crew has entered EOP 2540, Functional Recovery:

• The Unit Supervisor directs you to Initiate Once-Through-Cooling Using EOP 2540D, HR-3.

• I will act as the Unit Supervisor.

13

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Evaluate RCP Upper Oil Reservoir Problem JPM Number: S4 Revision: 1/0 Initiated:

John W. Riley - Signature on File 04/30/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/21/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 05/26/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE New JPM requiring trip of the reactor, C RCP, and alternate 11/03/2017 0/0 path in EOP2525 requiring trip of the A RCP.

10/18/2019 Reviewed for use for 2019 AOT. 0/1 jwr 04/30/2020 Changed the number from 302 to S4 for the 2020 ILT NRC 1/0 exam. Substantially changed the malfunction. Went from a 75 gpm ramped over 6 minutes to a 8 gpm ramp over 5 minutes.

This allows the PPC alarm and annunciator to come in and provides enough time to use procedure to address the issue. Also added a malfunction to raise bearing temperatures to more accurately match Reactor and RCP trip criteria and an annunciator override for RCP cooling water flow low. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem System: RCP Time Critical Task: YES NO Alternate Path JPM: YES NO Validated Time (minutes): 15 Task Number(s): 235300 Applicable To: SRO X STA RO X PEO K/A Number: 010/A2.02 K/A Rating: 3.9/3.9 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of this JPM, examinee has evaluated C RCP indications and reported that the upper lube oil level is lowering with conditions meeting trip criteria for the C RCP and the examinee will trip the reactor and secure the C RCP. The examinee will perform standard post trip actions in EOP 2525 and will recognize a stuck open spray valve and will secure the A RCP.

Required Materials: ARP 2590B-147 (BA-27), RCP C UPR OIL RSVR LEVEL LO, revision (procedures, equipment, etc.) 001, effective 05/11/16.

AOP 2586, RCP Malfunctions, revision 004.

EOP 2525, Standard Post Trip Actions, revision 028-00, effective12/29/16.

General

References:

ARP 2590B-147 (BA-27), RCP C UPR OIL RSVR LEVEL LO, revision 001, effective 05/11/16.

AOP 2586, RCP Malfunctions, revision 004.

EOP 2525, Standard Post Trip Actions, revision 028-00, effective12/29/16.

3

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

JPM WORKSHEET JPM Number: S4 Revision : 1/0 Initial Conditions: The plant is in MODE 1 at 100% power.

Initiating Cues: You are the RO I will act as the US.

Simulator Requirements: Reset to IC-282. This has the initial conditions established (70.9 % RCP upper reservoir level with 5 gpm leak) and run such that when the simulator is placed to run the PPC alarm for upper guide bearing will come in ` 30 seconds, OR select any 100% power IC (IC-23) or equivalent and load the following:

Enter malfunction RC12C 5 gpm severity on trigger 1 (this lowers C RCP upper reservoir oil level).

Enter malfunction CC06C 62% block severity on a 3 minute ramp -

also on trigger 1 (this lowers cooling flow to the bearing and results in temperature on the bearings rising, simulating the expected response if oil level was to lower).

Enter malfunction C03-D25A annunciator override OFF (this prevents the RCP C CLR WTR FLOW LO alarm from coming in, thereby supporting that it is an oil level problem not a cooling water problem).

Enter malfunction RX01A 100% OPEN on Event 30 (CEA 42 <168 steps). This fails open the 2-RC-100E Spray valve on the reactor trip.

Ensure simulator procedures are clean or replaced; EOP 2525 (RO desk)

AOP 2586 (RO desk)

ARP 2590B-147 (RO desk)

NOTE: Using IC-282, with lower reservoir level at 70.9% and a 5 gpm leak rate the PPC alarm comes in ~ 30 seconds after trigger 1 is activated. The PPC Priority alarm and temperature increase comes in ~ 3 minutes after the trigger.

4

• * * *NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

5

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 ARP 2590B-083 Examinee refers to ARP 2590B, BA-27. Y N S U Respond to RCP C UPR OIL RSVR LEVEL Reads Setpoint: 60%.

LO annunciator (BA-27 on C-02/3).

AUTOMATIC FUNCTIONS Reads AUTOMATIC FUNCTIONS none.

1. None Cue:

Comments: PPC alarms associated with C RCP are expected. It is acceptable for the examinee to go straight to AOP 2586.

STEP Performance: Standard: Critical: Grade:

1. 2 CORRECTIVE ACTIONS Y N S U

1. CHECK C RCP upper reservoir oil Examinee uses the PPC or the Indications behind level indication and DETERMINE rate of C04R switches to determined C RCP Upper Oil lowering level (C-04R or PPC) (Normal Reservoir level and notes lowering level.

range, 75 to 85%).

Cue:

Comments: It is not necessary for the examinee to address all alarming annunciators. It is only Critical that the examinee refer to AOP 2586 and examinee may get there through any one of the alarming annunciators.

6

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade:

1. 3

2. IF oil level is relatively constant, Examinee determines that oil level is not is not Y N S U PERFORM the following: relatively constant and that this step is not applicable.

3. If C RCP upper reservoir oil level is Examinee determines that C RCP upper reservoir Y N S U lowering, Go To AOP 2586, RCP oil level is lowering and goes to AOP 2586, RCP Malfunctions. Malfunctions.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 4 AOP 2586, RCP Malfunctions Examinee transitions to AOP 2586 and performs Y N S U Action/Expected Response the following:

NOTE: Foldout page shall be monitored Examinee opens foldout page for monitoring.

throughout this procedure.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade

1. 5

1. Check RCP Trip Criteria Met

a. CHECK RCP Trip Criteria based on a Examinee reviews PPC data for Upper Oil Level Y N S U change of the following parameters: and acknowledges RCP trip criteria is met or is rapidly approaching the criteria.

RCP Seal Criteria RCP Vibration RCP Oil Level and Temperature

b. PERFORM the following: Examinee determines Trip Criteria for C RCP, Y N S U by Upper Oil Reservoir Low Level on the PPC, is

1. TRIP the Reactor met and performs the following:

2. TRIP the associated RCP Trips the reactor

3. GO TO EOP 2525, Standard Post Trips the C RCP Trip Actions Goes to EOP 2525, Standard Post Trip AND Actions CONTINUE with actions of this procedure beginning with step 7 Cue: As Unit Supervisor If / When examinee recommends tripping the reactor and the C RCP - direct reactor trip and trip of C RCP.

Comments: Fold out page RCP and Reactor Trip Criteria is ANY RCP oil level is trending outside normal band of 75% to 85% AND bearing temperature is increasing.

8

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade:

1. 6 Reactivity Control --- Reactor Trip

___1. ENSURE Reactor trip by ALL of the of Examinee determines that the reactor is tripped by Y N S U the following: observing all of the following:

ALL CEAs fully INSERTED.

ALL CEAs fully INSERTED Reactor power is dropping.

Reactor power is dropping SUR is negative.

SUR is negative Cue: As Unit Supervisor (1) State going to EOP 2525 and silencing alarms, carry out your immediate operator actions, THEN (2) State status of the reactor, THEN once examinee has specified items in standard (3) State reactor is tripped Comments:

(1) It is acceptable for another instructor or NRC examiner to perform the role of the Unit Supervisor.

(2) The US may vocalize the performance of the BOP steps in order to allow time for the examinee to complete their actions or skip BOP steps.

9

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade:

1. 7 RCS Inventory Control

___4. ENSURE RCS Inventory Control Examinee determines that RCS Inventory Control Y N S U met by ALL of the following conditions: is established with Pressurizer level trending to 35 to 70% and RCS subcooling greater than or equal

a. CHECK BOTH of the following to 30 °F.

conditions exist:

Pressurizer level is between 20 to 80%.

Pressurizer level is trending to 35 to 70%.

b. CHECK RCS subcooling is Greater than or equal to 30 °F.

Cue: As Unit Supervisor (1) State Value and trend of Pressurizer level, THEN repeat or paraphrase back RO response, THEN (2) State Restore Pressurizer level to 35 to 70%, and once RO repeats or paraphrases back state correct (3) State Value and trend RCS Subcooling, THEN repeat or paraphrase back RO response.

Comments: It is acceptable for another instructor or NRC examiner to perform the role of the Unit Supervisor.

10

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade

1. 8 RCS Inventory Control

___5. ENSURE RCS Pressure Control met by BOTH of the following:

CHECK that pressurizer Examinee checks pressurizer pressure and Y N S U pressure is 1900 to 2350 psia. observes pressure is less than 1900 psia or pressure is > 1900 psia and is continuing to CHECK that pressurizer trend down.

pressure is trending to 2225 to 2300 psia.

Examinee and goes to the RNO for manual Y N S U operation of pressurizer heaters and spray valves.

Cue: As Unit Supervisor (1) State Value and trend of Pressurizer pressure, THEN repeat or paraphrase back RO response, THEN (2) State Restore Pressurizer pressure to 2225 to 2300 psia, and once RO repeats or paraphrases back state correct.

Comments: It is acceptable for another instructor or NRC examiner to perform the role of the Unit Supervisor.

11

PERFORMANCE INFORMATION JPM Number: S4 Revision: 1/0 Task

Title:

Evaluate RCP Upper Oil Reservoir Problem STEP Performance: Standard: Critical: Grade

1. 8 RCS Inventory Control

___5.1 IF the Pressurizer Pressure Control Examinee determines the Pressurizer Pressure Y N S U System is not operating properly in Control system is not operating properly by automatic, THEN RESTORE and pressure continuing to lower.

MAINTAIN pressurizer pressure between 2225 to 2300 psia by performing ANY of the following:

a. OPERATE the Pressurizer Examinee identifies that 2-RC-100E spray Y N S U Pressure Control System. valve indicates open causing pressurizer

b. Manually OPERATE pressure to lower and takes action to attempt to Pressurizer heaters and spray close the spray valve in manual.

valves.

___5.2 IF ANY pressurizer spray valve will Examinee trips the A RCP as pressurizer Y N S U not close, pressure continues to lower.

THEN STOP RCPs as necessary.

Cue: As Unit Supervisor (1) State Status of Pressurizer Pressure Control System, THEN repeat back examinee response.

(2) State Status of Pressurizer Spray valves, THEN repeat back examinee response.

Comments:

(1) The failure of the Spray valve 2-RC-100E is the ALTERNATE PATH.

Securing additional RCPs (B and / or D) does not constitute a failure of the JPM but would be a comment..

STOP TIME: _________

TERMINATION CUE: The evaluation for this JPM is concluded.

12

VERIFICATION OF JPM COMPLETION JPM Number: S4 Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Alternate Path JPM: YES NO Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 13

STUDENT HANDOUT JPM Number: S4 Revision: 1/0 Initial Conditions: Plant is in MODE 1 at 100% power Initiating Cues: You are the RO I will act as the US.

14

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

JPM Number: S5 Revision: 2/0 Initiated:

John W. Riley - Signature on File 05/04/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 05/21/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 05/26/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 12/10/19 BJF Updated JPM to newest procedure revisions 1/0 jwr 05/04/2020 Changed the number from 160 to S5 for the 2020 ILT NRC exam. 2/0 Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

System: Containment Air Recirculation Time Critical Task: YES NO Validated Time (minutes): 15 minutes Task Number(s): (022-01-117, 022-004-01-01)

Applicable To: SRO X STA RO X PEO K/A Number: 022 A4.01 K/A Rating: 3.6/3.6 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: At the completion of this JPM, the examinee has successfully stopped and restarted an OPERABLE CAR Fan.

Required Materials: OP 2313A, Containment Air Recirculation and Cooling System, revision (procedures, equipment, etc.) 010-00, 02/08/2016.

ARP 2590A-012, CTMT AIR RECIRC FAN D TRIP, revision 001-00, effective 02/20/2017.

General

References:

OP 2313A, Containment Air Recirculation and Cooling System, revision 010-00, 02/08/2016.

ARP 2590A-012, CTMT AIR RECIRC FAN D TRIP, revision 001-00, effective 02/20/2017.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S5 Revision: 2/0 Initial Conditions: A, B and C CAR Fans are operating.

The plant is at 100% power Electrical PMs are scheduled for the B CAR Fan.

Initiating Cues: The Unit Supervisor has directed you to stop the B CAR Fan and start D CAR Fan in fast speed.

Simulator Requirements: Initialize at any 100% power IC ENSURE A, B and C CAR Fans are running in fast speed.

INSERT Malfunction CH01D to trip D CAR Fan on Trigger 1. This does not get activated until the D CAR fan is started.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

START TIME: __________

STEP Performance Standard: Critical: Grade:

1. 1 OP 2313A, Section 4.2 4.2.5 IF stopping B CAR fan, PERFORM the following (C-01):

a. PLACE B CAR fan to STOP and Examinee places B CAR Fan handswitch in Y N S U HOLD for approximately two seconds. STOP and holds for 2 seconds.

b. WHEN two seconds elapse, RELEASE Examinee releases B CAR Fan handswitch Y N S U B CAR fan switch. after ~ 2 seconds.

Examinee verifies amps are zero and green Y N S U light is lit indication fan is stopped.

Cue:

Comments: Starting a fourth CAR Fan in fast speed constitutes a failure of this JPM.

STEP Performance: Standard: Critical: Grade:

1. 2 4.2.6 IF isolating RBCCW flow to X35B B Examinee determines this step is NOT Y N S U CAR COOLER, PERFORM the Applicable.

following (C-01):

Cue:

Comments: Isolation of RBCCW flow to a cooler is not required for breaker PMs.

5

PERFORMANCE INFORMATION JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

STEP Performance: Standard: Critical: Grade:

1. 3 OP 2313A, Section 4.4 Examinee reads and acknowledges caution. Y N S U CAUTION To prevent overpressurizing CAR fan ducting, no more than three will be operated simultaneously in fast speed.

Cue:

Comments:

STEP Performance: Standard Critical: Grade:

1. 4 4.4.2 IF starting D CAR fan in fast speed, PERFORM the following:

a. ENSURE the following, open (C-01): Examinee verifies the following are open: Y N S U RB-28.2D, NORM OUTLET RB-28.2D, NORM OUTLET RB-28.3D, EMERG OUTLET RB-28.3D, EMERG OUTLET

b. ENSURE RB-28.1D, CLR D INLET, RB-28.1D, CLR D INLET is locked locked open (C-01). open

c. CHECK B RBCCW header flow less Examinee verifies B RBCCW header flow Y N S U than 8,000 gpm (C-06, PPC). less than 8,000 gpm.

Cue:

Comments:

(1) These valves are normally open.

(2) B RBCCW header flow less than 8,000 gpm may have been checked during the task preview, if so it doesnt need to be checked again.

6

PERFORMANCE INFORMATION JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

STEP Performance: Standard: Critical: Grade:

1. 5 (3) PLACE D CAR fan to START Examinee places D CAR Fan HS to START Y N S U HIGH and OBSERVE red FAST HIGH and observes red FAST SPEED SPEED indicating light lit (C-01). indicating light momentarily lit and motor amps zero.

Annunciator CTMT AIR RECIRC Examinee refers to ARP 2590A-012 CTMT Y N S U FAN D TRIP, D-3 on C-01 alarms. AIR RECIRC FAN D TRIP on C-01.

(4) IF D CAR fan high vibration alarm Examinee presses the CAR FAN VIB RESET Y N S U annunciates, PRESS CAR FAN VIB B & D button on C-01 and observe alarm RESET B & D button (C-01). clear.

Cue: BOOTH OPERATOR Activate Trigger 1 to trip the D CAR fan when the D CAR fan is started.

Comments:

(1) The tripping of the D CAR fan creates an Alternate Path.

(2) The ARP does not have to be referred to. Only going to OP 2313A is acceptable. The first step of the ARP is to refer to OP 2313A.

STEP Performance: Standard: Critical: Grade:

1. 6 ARP 2590A-012

1. Refer To OP 2313A, Containment Air Examinee returns to OP 2313A, Section 4.2 to Y N S U Recirculation and Cooling System, and start the idle (B) CAR Fan.

PERFORM applicable actions to start idle CAR fan.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

STEP Performance: Standard: Critical: Grade:

1. 7 OP 2313A, Section 4.2 Examinee reads and acknowledges caution. Y N S U CAUTION To prevent overpressurizing CAR fan ducting, no more than three will be operated simultaneously in fast speed.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 8 4.2.2 IF starting B CAR fan in fast speed, PERFORM the following:

a. ENSURE the following, open (C-01): Examinee verifies the following are open: Y N S U RB-28.2B, NORM OUTLET RB-28.2B, NORM OUTLET RB-28.3B, EMERG OUTLET RB-28.3B, EMERG OUTLET

b. ENSURE RB-28.1B, CLR B INLET, RB-28.1B, CLR D INLET is locked locked open (C-01). open.

c. CHECKB RBCCW header flow less Examinee verifies B RBCCW header flow Y N S U than 8,000 gpm (C-06, PPC). less than 8,000 gpm.

Cue:

Comments:

(1) The valves are normally open and were left open when the B CAR was removed from service.

(2) If B RBCCW header flow less than 8,000 gpm was checked earlier it doesnt need to be checked again.

8

PERFORMANCE INFORMATION JPM Number: S5 Revision: 2/0 Task

Title:

Shifting Containment Air Recirculation Units (Alternate Path)

STEP Performance: Standard: Critical: Grade:

1. 9

d. PLACE B CAR fan to START Examinee places B CAR Fan HS to START Y N S U HIGH and OBSERVE red FAST HIGH.

SPEED indicating light lit (C-01). Examinee observes red FAST SPEED Y N S U indicating light lit and motor amps indicate.

e. IF B CAR fan high vibration alarm Examinee presses the CAR FAN VIB RESET Y N S U annunciates, PRESS CAR FAN VIB B & D button on C-01 and observe alarm RESET B & D button (C-01). clear.

Cue:

Comments: Once the examinee starts the B CAR fan and acknowledges the vibration alarm, if it annunciates, this JPM is complete.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

9

VERIFICATION OF JPM COMPLETION JPM Number: S5 Revision: 2/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT Evaluator: ______________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: S5 Revision: 2/0 Initial Conditions: A, B and C CAR Fans are operating.

The plant is at 100% power Electrical PMs are scheduled for the B CAR Fan.

Initiating Cues: The Unit Supervisor has directed you to stop the B CAR Fan and start D CAR Fan in fast speed.

11

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Cross-Tying 480 Volt Busses JPM Number: S6 Revision: 9/0 Initiated:

John W. Riley - Signature on File 04/23/20 Developer Date Reviewed:

Brian Bergin - Signature on File 05/21/20 Technical Reviewer Date Approved:

Trad Horner - Signature on File 05/28/20 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2006-0317 Upgrade JPMs to new format. 6/0 JWR 07/11/2011 Update to new Template and minor editorial changes. 6/1 JWR 07/29/2012 Format change on verification of JPM completion page. 6/2 Incorporated minor editorial changes. Validation completed 7/29/2012.

07/07/2015 Update to newest template and latest procedure revision. 7/0 09/06/2019 MRP Updated to VISION numbering and latest procedural guidance 8/0 JWR 04/23/2020 Changed the number from JPM-053 to S6 for the 2020 ILT NRC 9/0 exam. Made editorial changes and standardized format. Changes to specify procedure and section to be used in initiating cue, providing procedure steps marked as complete consistent with the initiate cue, and specifying to remove the sync handswitch and move it to another slot. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP 2 Examinee:

JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses System: 480 Volt Load Centers (2344A)

Time Critical Task: YES NO Validated Time (minutes): 10 Task Number(s): Vision 235479 (062-01-394)

Applicable To: SRO X STA RO X PEO K/A Number: 062 A4.01 K/A Rating: 3.3/3.1 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: The examinee successfully cross-ties 480 volt busses 22A and 22B, with 22B supplying bus 22A Required Materials: OP 2344A, 480 Volt Load Centers, revision 031, section 4.13 Cross Tying (procedures, equipment, etc.) Between 480Volt Bus 22A and 22B General

References:

OP 2344A, 480 Volt Load Centers, revision 031

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S6 Revision : 9/0 Initial Conditions:

• Pressurizer Group 1 and 2 Backup Heaters are in Pull to Lock and Caution tagged.

• A & B TBCCW Pump hand switches are Caution tagged.

Initiating Cues:

• The Unit Supervisor has directed you to cross-tie 480 volt busses 22A and 22B, with 22B supplying 22A.

• The Unit Supervisor specifies the use of OP 2344A, section 4.13 Cross Tying Between 480 Volt Bus 22A and 22B.

• The cross tying of the busses is being performed in preparation for tagging and replacement of the Bus 22A Transformer.

Simulator Requirements:

• Place Group 1 and 2 Pressurizer Backup Heaters in Pull to Lock.

• Place Caution Tags on Group 1 and 2 Backup Heaters.

• Ensure A and C TBCCW pumps are running (both A and B TBCCW pumps must NOT be running).

• Ensure A & B TBCCW Pump hand switches are Caution tagged.

• Provide examinee with procedure OP 2344A, section 4.13 Cross Tying Between 480 Volt Bus 22A and 22B with step 4.13.1 circled and slashed (indicating step complete).

• Provide examinee with procedure OP 2344A prerequisites and precautions.

• Take sync select handswitch out SYN SEL SW 22A/22B and move to another slot.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 OP 2344A Y N S U CAUTION Current greater than 1,800 amps on 480 volt bus The Examinee reads and acknowledges the 22A exceeds the ratings of the 4,160/480 volt Caution.

transformer.

Cue:

Comments:

Provide examinee with OP 2344A, 480 Volt Load Centers, Section, 4.13 Cross Tying Between 480 Volt Bus 22A and 22B, and prerequisites and precaution.

The procedure can be provided outside the simulator to allow the examinee to perform a task preview prior to entering the simulator to lessen JPM simulator time.

5

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 2 4.13.1 PERFORM the following to avoid Examinee determines that this step is already Y N S U exceeding 1,800 amp transformer limit: complete as stated in the Initial Conditions.

• PLACE associated Pressurizer backup heaters, (Group 1 and 2), in PULL TO LOCK and TAG.

• CONFIGURE TBCCW pumps as necessary so A and B pumps are not both running.

• Yellow TAG A and B TBCCW pump handswitches with the following information: d 22B are cross-tied. Refer to OP-2344A step 4.13.1 prior to starting pump.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 3 4.13.2 IF Bus 22A will be supplying Bus 22B, Examinee determines that this step is Not Y N S U PLACE SYN SEL SW 22A/22B in Applicable. The 22A transformer is to be removed CL TIE/TRIP B. (C-08) from service; therefore, Bus 22B will be supplying Bus 22A.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 4 4.13.3 IF Bus 22B will be supplying Bus 22A,

• Examinee places the sync selector hand switch Y N S U PLACE SYN SEL SW 22A/22B in into the SYN SEL SW 22A/22B opening.

CL TIE/TRIP A. (C-08)

• Examinee rotates the SYN SEL SW Y N S U 22A/22B to the CL TIE/TRIP A position on C-08.

Cue:

Comments: When the sync switch SYN SEL SW 22A/22B is turned on it will activate annunciator C-08 D-4 SYNC SELECTOR SWITCH ON after 55 seconds.

STEP Performance: Standard: Critical: Grade:

1. 5 4.13.4 ENSURE Bus voltages are matched. Examinee ensures bus voltages are matched using Y N S U 22A and 22B Volt Meters on C-08.

Cue: If the examinee observes a slight difference in bus voltages, state that voltages are matched sufficiently to cross-tie.

Comments:

7

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 6 4.13.5 Using 22A/22B TIE BKR, 22A-1T-2 Examinee closes 22A/22B TIE BKR, 22A-1T-2 Y N S U (B0111), breaker control switch, (B0111) by momentarily rotating the associated CLOSE B0111 (C-08). handswitch to the CLOSE position.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 7 4.13.6 ENSURE 22A/22B TIE BKR, 22A- Examinee observes 22A/22B TIE BKR, 22A-1T-2 Y N S U 1T-2 (B0111) has closed and the (B0111) red light only lit and then observes that applicable supply breaker has opened. 22A SPLY BKR, 24A1-1X3-2 (B0102) is open by its green light only lit.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 8 4.13.7 TURN SYN SEL SW 22A/22B to Examinee momentarily rotates the SYN SEL SW Y N S U OFF. (C-08). 22A/22B to the OFF position.

Cue:

Comments:

8

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 9 4.13.8 IF current on 480 volt supply bus

• Examinee observes Bus 22B ammeter on C-08 Y N S U greater than 1,800 amps, OPEN B0111, and verifies current indication is <1,800 amps.

22A/22B TIE BKR, 22A-1T-2.

• Examinee determines that this step is NOT Y N S U Applicable.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 10 CAUTION Examinee reads and acknowledges the Caution. Y N S U Current greater than 1,600 amps indicated on 22A-1T-2 AMMETER PHASE B (local, above B0111 cubicle) exceeds the rating of the cross-tie breaker.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 11 4.13.9 IF current on 480 volt supply bus is Examinee determines that Bus 22B ammeter on C- Y N S U greater than 1,600 amps (C-08), 08 current indication is <1,600 amps; therefore, CHECK current, as indicated on 22A- this step is NOT Applicable.

1T-2 AMMETER PHASE B (local above B0111 cubicle) less than 1,600 amps.

Cue:

Comments:

9

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 12 4.13.10 IF current indicated on 22A-1T-2 Examinee determines that this step is also NOT Y N S U AMMETER PHASE B is greater than Applicable because the previous step is Not 1,600 amps, OPEN 22A/22B TIE Applicable.

BKR, 22A-1T-2 (B0111) (C-08).

OR Examinee dispatches a PEO to obtain a reading on 22A-1T-2 AMMETER PHASE B and determines from the report that the step is Not Applicable due to the current reading less than 1600 amps.

Cue: Current indication on 22A-1T-2 AMMETER PHASE B (local above B0111 cubicle) indicates less than 1,600 amps. (If an actual value is desired, state that the ammeter is reading approximately 1,200 amps.)

Comments:

STEP Performance: Standard: Critical: Grade

1. 13 4.13.11 PERFORM one of the following to

• Examinee determines that Bus 22B is the Y N S U reduce wear on the off-service load supplying; therefore, step a. is NOT center transformer (C-08): Applicable.

a. IF Bus 22A is supplying Bus 22B,

• Examinee momentarily rotates 24A/22A FDR Y N S U OPEN 24B/22B FDR BKR 24B4-2 BKR 24A1-2 (A103) to the TRIP position (A204).

• Examinee verifies the associated green light Y N S U

b. IF Bus 22B is supplying Bus 22A, only lit and the associated red light out on OPEN 24A/22A FDR BKR 24A1-2 breaker A103.

(A103).

Cue:

Comments:

10

PERFORMANCE INFORMATION JPM Number: S6 Revision: 9/0 Task

Title:

Cross-Tying 480 Volt Busses STEP Performance: Standard: Critical: Grade:

1. 14 4.13.12 PERFORM the following to match breaker indication flags with actual breaker position (C-08):

a. IF Bus 22A is supplying Bus 22B,

• Examinee determines that Bus 22B is Y N S U PLACE 22B SPLY BKR 24B4- supplying the bus; therefore, Step a. is NOT 1X3-2 (B0209) in TRIP and Applicable allow to spring return to NEUTRAL.

b. IF Bus 22B is supplying Bus 22A,

• Examinee momentarily rotates B0102, 22A Y N S U PLACE 22A SPLY BKR 24A1- SPLY BKR 24A1-1X3-2, to the Trip position 1X3-2 (B0102) in TRIP and and allows the switch to spring return to allow to spring return to Neutral.

NEUTRAL.

• Examinee verifies the green light only lit and Y N S U red light out and the breaker flag is green.

Cue:

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

11

VERIFICATION OF JPM COMPLETION JPM Number: S6 Revision: 9/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 10 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 12

STUDENT HANDOUT JPM Number: S6 Revision: 9/0 Initial Conditions:

• Pressurizer Group 1 and 2 Backup Heaters are in Pull to Lock and Caution tagged.

• A & B TBCCW Pump hand switches are Caution tagged.

Initiating Cues:

• The Unit Supervisor has directed you to cross-tie 480 volt busses 22A and 22B, with 22B supplying 22A.

• The Unit Supervisor specifies the use of OP 2344A, section 4.13 Cross Tying Between 480 Volt Bus 22A and 22B.

• The cross tying of the busses is being performed in preparation for tagging and replacement of the Bus 22A Transformer.

13

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Reset SIAS JPM Number: S7 Revision: 1/0 Initiated:

John W. Riley - Signature on File 05/13/2020 Developer Date Reviewed:

Brian Bergin - Signature on File Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 05/28/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 07/22/2015 - RJA Created new JPM to Reset SIAS 0 6/9/16- JWC Minor editorial changes. 0/1 Changed the number from JPM-281(A) to S7 for the 2020 ILT NRC exam. Updated for procedure changes; added forcing sprays 05/13/2020 jwr 1/0 and a caution on ECCS pumps on running on recirculation.

Changed malfunction to ensure it locked and prevented reset.

Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS System: Engineered Safety Features Actuation System Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): 013-01-010 (Vision ID# 235949)

Applicable To: SRO X STA RO X PEO K/A Number: 013A4.02 K/A Rating: 4.3/4.4 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: The examinee will attempt to reset SIAS following an inadvertent ESFAS actuation using AOP 2571, Section 4.0, and take contingency actions per Step 4.3.d.1 for the inability to reset SIAS.

Required Materials: AOP 2571, Inadvertent ESFAS Actuation, revision 007, effective 08/03/2017.

(procedures, equipment, etc.)

General

References:

AOP 2571, Inadvertent ESFAS Actuation, revision 007, effective 08/03/2017.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S7 Revision : 1/0 Initial Conditions:

• The plant is at 100% power.

• An inadvertent Facility 1 SIAS has been diagnosed.

• AOP 2585, Immediate Operator Action, is complete for Section 16, Inadvertent ESAS.

• The BOP has adjusted Turbine load as needed to maintain Tcold on program.

Initiating Cues: The Unit Supervisor has directed you to reset the SIAS using AOP 2571, Inadvertent ESFAS Actuation, Section 4.0,Inadvertent SIAS Actuation.

Simulator Requirements:

• Initialize to IC-287 (has initial conditions and malfunction) or any normal 100% power IC (IC-23 normally used) and perform actions below;

• Insert Malfunction ES02I to input an inadvertent SIAS on Facility 1.

• Place simulator in run.

• Complete Immediate Operator Actions, section 16.0, of AOP 2585; Check Pressurizer pressure > 1,714 psia Check Containment pressure < 4.42 psig Secure Letdown by closing 2-CH-515 Secure Charging by placing all Charging pumps in PTL.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 4.0 Inadvertent SIAS Actuation Examinee obtains AOP 2571. Y N S U 4.1. Using independent indications, CHECK ALL the following:

• Pressurizer pressure greater than 1,714

• Examinee determines that Pressurizer pressure Y N S U psia. or trip function bypassed is greater than 1714 psia.

• Containment pressure less than 4.42

• Examinee determines CTMT pressure is less Y N S U psig than 4.42 psig.

4.2 INITIATE forcing pressurizer sprays as

• Examinee initiates forcing pressurizer sprays. Y N S U follows: (C-03)

a. PLACE Group 1 through Group 4 backup heaters to CLOSE.

b. LOWER setpoint of selected controller to obtain 50% output signal:

• PRESS CNTL-X, PIC-100X

• PRESS CNTL-Y, PIC-100Y

c. MONITOR pressurizer pressure.

Cue: If examinee states that annunciator D-13, PZR PRESSURE SELECTED CHANNEL DEVIATION HI LO will be received when initiating Forcing Sprays state Understand , PZR PRESSURE SELECTED CHANNEL DEVIATION HI LO annunciator will be received when Forcing Sprays.

Comments: Step 4.1 is part of the Immediate Operator Action for an inadvertent ESAS actuation.

5

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 2 NOTE:

If a spurious signal is present that cannot be Examinee reads and acknowledges the Note and Y N S U reset, then ESAS is inoperable. Caution.

CAUTION

1. Opening service water valves to TBCCW requires close monitoring of total service water header flow.

2. ECCS pumps running on minimum flow recirculation for extended periods can be damaged and must be monitored more frequently.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 3 4.3. IF an inadvertent SIAS actuation occurred, PERFORM the following as required:

a. PLACE ALL charging pumps in Pull-

• Examinee observes that all Charging Pumps Y N S U To-Lock. (C-02) are in the Pull-To-Lock position.

b. Refer To Attachment 1, Temperature

• Examinee determines from Initial Conditions Y N S U vs. Power Program, and ADJUST that the BOP is maintaining Tcold on program.

turbine load as necessary to maintain Tcold on program.

c. OVERRIDE SIAS start signals and

• Examinee observes that the Boric Acid Pumps Y N S U STOP the boric acid pumps. (C-02) (Z2) are NOT running.

d. Refer To Attachment 2, Resetting

• Examinee obtains AOP 2571, Attachment 2 Y N S U ESFAS, Section 1.0, Resetting SIAS, and commences actions.

CIAS, and EBFAS, and ATTEMPT to reset SIAS.

Cue:

Comments: A Facility 1 SIAS will NOT automatically start the Boric Acid Pumps.

7

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade

1. 4 Attachment 2 Resetting ESFAS 1.0 Resetting SIAS, CIAS, and EBFAS Examinee observes that all of the following Y N S U annunciators on C-01 are clear (windows are NOT 1.1. CHECK at least THREE of the following lit).

four annunciators reset:

• CTMT PRES HI A (A-21, C-01)

• CTMT PRES HI A (A-21, C-01)

• CTMT PRES HI B (B-21, C-01)

• CTMT PRES HI B (B-21, C-01)

• CTMT PRES HI C (C-21, C-01)

• CTMT PRES HI C (C-21, C-01)

• CTMT PRES HI D (D-21, C-01)

• CTMT PRES HI D (D-21, C-01) 1.2 CHECK pressurizer pressure greater than Examinee determines that all observed Pressurizer Y N S U 1850 psia. pressure indications are greater than 1850 psia.

1.3 PRESS SIAS ACTUATION RESET Examinee proceeds to Actuation Cabinet 5 and Y N S U (Actuation Cabinet 5). momentarily presses the SIAS ACTUATION RESET button.

Cue:

Comments:

Not being able to reset SIAS results in the examinee having to take an ALTERNATE PATH under the Contingency Actions.

8

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 5 NOTE Actuation modules SIAS GROUP 1 AM515, 3 Examinee reads and acknowledges the Note. Y N S U AM516 and 5 AM518 will not extinguish if an undervoltage signal is present.

1.4. OBSERVE ALL of the following SIAS Examinee observes that none of the SIAS Group Y N S U actuation module TRIP lights Actuation Module TRIP lights reset. (The red light extinguished (Actuation Cabinet 5): remains lit on each module.)

• SIAS GROUP 1 AM515

• SIAS GROUP 2 AM514

• SIAS GROUP 3 AM516

• SIAS GROUP 4 AM517

• SIAS GROUP 5 AM518

• SIAS GROUP 6 AM519

• SIAS GROUP 7 AM520

• SIAS GROUP 8 AM521

• SIAS GROUP 9 AM522

• SIAS GROUP 10 AM523

• SIAS GROUP 11 AM524

• SIAS GROUP 12 AM525 Cue: Acknowledge any reports. If required, direct examinee to continue with the procedure.

Comments:

The examinee should determine from the failure of the Actuation Module TRIP lights to reset, that Facility 1 SIAS CANNOT be reset.

This results in the examinee having to take an ALTERNATE PATH under the Contingency Actions.

9

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 6 1.5. PRESS SIAS ACTUATION RESET

• Examinee may determine that Facility 2 SIAS Y N S U (Actuation Cabinet 6). was NOT actuated; therefore, this step is Not Applicable. OR examinee may proceed to Actuation Cabinet 6 and momentarily press the NOTE SIAS ACTUATION RESET button.

Actuation modules SIAS GROUP 1

• Examinee may read and acknowledge the Note. Y N S U AM615, 3 AM616, 5 AM618 and 12 AM625 will not extinguish if an undervoltage signal is present.

Cue:

Comments: The examinee may or may NOT press the SIAS ACTUATION RESET push button on Actuation Cabinet 6. If the examinee does press the SIAS ACTUATION RESET button (per procedure rules of usage), then the subsequent Note and Step 1.6 should also be performed.

10

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 7 1.6. OBSERVE ALL of the following SIAS Examinee may observe that all the SIAS Group Y N S U actuation module TRIP lights Actuation Module red TRIP lights are NOT lit.

extinguished (Actuation Cabinet 6):

• SIAS GROUP 1 AM615

• SIAS GROUP 2 AM614

• SIAS GROUP 3 AM616

• SIAS GROUP 4 AM617

• SIAS GROUP 5 AM618

• SIAS GROUP 6 AM619

• SIAS GROUP 7 AM620

• SIAS GROUP 8 AM621

• SIAS GROUP 9 AM622

• SIAS GROUP 10 AM623

• SIAS GROUP 11 AM624

• SIAS GROUP 12 AM625 Cue:

Comments: Examinee may or may NOT perform Step 1.6.

STEP Performance: Standard: Critical: Grade

1. 8 1.7. IF SIAS cannot be reset Go To Step 4.3.d.1 Examinee determines from step 1.4 that SIAS Y N S U contingency action. CANNOT be reset and proceeds to Contingency Action Step 4.2.d.1.

Cue:

Comments: Procedure required and Administrative Change. Step 4.2.d.1 is actually step 4.3.d.1 11

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 9 d.1 IF SIAS signals cannot be reset, PERFORM Because the SIAS signal CANNOT be reset, the Y N S U the following: examinee requests another member of the crew to determine the applicability of Technical

1) Refer To Technical Specification 3.0.3.

Specification 3.0.3.

Cue: Technical specification 3.0.3 has been referenced. Not applicable for only one facility.

Comments: ALTERNATE PATH begins here STEP Performance: Standard: Critical: Grade:

1. 10

2) OVERRIDE and OPEN the following Examinee momentarily rotates the hand switch for Y N S U valves as required: SW-3.2B, TBCCW heat exchanger SW inlet, to the CLOSE position, then to the OPEN position and

• SW-3.2A, TBCCW heat exchanger observes that only the red OPEN light is lit.

SW inlet (Z2)

• SW-3.2B, TBCCW heat exchanger SW inlet (Z1)

3) OVERRIDE and STOP the following: One at a time, the examinee momentarily rotates Y N S U the hand switch for the A HPSI and A LPSI

• Running HPSI pumps Pump breakers, to the START position, then to the

• Running LPSI pumps STOP position and observes that only the green Stopped light is lit.

Cue:

Comments:

12

PERFORMANCE INFORMATION JPM Number: S7 Revision: 1/0 Task

Title:

Reset SIAS STEP Performance: Standard: Critical: Grade:

1. 11

4) CLOSE LPSI injection valves as One at a time, the examinee momentarily rotates Y N S U required: the hand switch for each of the Facility 1 LPSI Injection Valves, to the OPEN position, then to the

• SI-615, loop 1A (Z1)

CLOSE position and observes that only the green

• SI-625, loop 1B (Z1) CLOSE light is lit.

• SI-635, loop 2A (Z2)

• SI-645, loop 2B (Z2)

Cue: All remaining steps will be performed by another crew member.

Comments: The remaining steps are NOT required for successful completion of this JPM.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

13

VERIFICATION OF JPM COMPLETION JPM Number: S7 Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 14

STUDENT HANDOUT JPM Number: S7 Revision: 1/0 Initial Conditions:

• The plant is at 100% power.

• An inadvertent Facility 1 SIAS has been diagnosed.

• AOP 2585, Immediate Operator Action, is complete for Section 16, Inadvertent ESAS.

• The BOP has adjusted Turbine load as needed to maintain Tcold on program.

Initiating Cues: The Unit Supervisor has directed you to reset the SIAS using AOP 2571, Inadvertent ESFAS Actuation, Section 4.0, Inadvertent SIAS Actuation.

15

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Respond to a Trip of the A RBCCW Pump JPM Number: S8 Revision: 1/0 Initiated:

John W. Riley - Signature on File 5/15/2020 Developer Date Reviewed:

Brian Bergin - Signature on File 5/21/2020 Technical Reviewer Date Approved:

Trad A. Horner - Signature on File 5/28/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 06/12/2015 - RJA Developed new JPM to respond to the loss of the A RBCCW 0 Pump (Immediate Operator Action) and failure of the spare pump to start.

07/14/16 jwr Editorial comments and more detail in setup. 0/1 08/21/16 HSS Change the opening of 2-RB-251A as a non critical step. 0/2 Changed the number from JPM-278(A) to S8 for the 2020 ILT NRC exam. Modified JPM to such that the standby pump does not start and the examinee must take contingency actions to restart a 05/15/20 jwr RBCCW pump to restore RBCCW. Made editorial changes and 1/0 standardized format. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: S8 Revision: 1/0 Task

Title:

Respond to a Trip of the A RBCCW Pump System: RBCCW Time Critical Task: YES NO Validated Time (minutes): 10 Task Number(s): 000-04-218 Applicable To: SRO X STA RO X PEO K/A Number: 2.4.49 K/A Rating: 4.6/4.4 Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: Simulator: X In-Plant:

Task Standards: The examinee will recognize the loss of the A RBCCW and perform Immediate Operator Actions to start the B RBCCW Pump on Facility 1. The B RBCCW Pump will fail to start (on the first attempt). The examinee will then take Contingency Actions to restart the A or B RBCCW pump.

Required Materials: AOP 2585, Immediate Operator Actions, revision 003-00, effective 11/16/2017.

(procedures, equipment, etc.)

General

References:

AOP 2585, Immediate Operator Actions, revision 003-00, effective 11/16/2017.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: S8 Revision : 1/0 Initial Conditions:

• The plant is operating at 100% power, in a normal configuration.

• The RO has temporarily left the Control Room.

Initiating Cues:

• As the BOP, respond to any secondary plant condition.

• I will act as the US.

Simulator Requirements: Reset to IC-288. This IC has the initial conditions built into it or reset to any normal 100% power IC and load the following:

• Insert Malfunction CC01B (B RBCCW pump trip ) - this will prevent the pump from starting)

• Insert CC01A (A RBCCW Pump trip) on Trigger 1.

• Both pump trips are removed immediately after the first attempt to start the B RBCCW pump.

NOTE: The RBCCW Pump Overload/Trip Annunciators will not be in for either the A or B RBCCW pumps so a pump restart (as directed by the Shift Manager) should be attempted per the Contingency Actions.

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: S8 Revision: 1/0 Task

Title:

Respond to a Trip of the A RBCCW Pump START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 Observe the trip of the A RBCCW Pump.

• Examinee observes numerous annunciators and Y N S U determines they are caused by a trip of the A RBCCW Pump.

• Examinee reports the trip of the A RBCCW Pump and the initiation of Immediate Operator Actions.

Cue: BOOTH OPERATOR - When the examinee assumes the shift, insert Trigger 1 (CC01A, A RBCCW Pump trip).

Comments: The A RBCW Pump Overload/Trip Annunciator is not lit 5

PERFORMANCE INFORMATION JPM Number: S8 Revision: 1/0 Task

Title:

Respond to a Trip of the A RBCCW Pump STEP Performance: Standard: Critical: Grade:

1. 2 12.0 Loss of RBCCW Pump 12.1. IF standby pump is available, PERFORM the following:

a. ENSURE RBCCW pump suction

• Examinee observes the green lights are lit and Y N S U and discharge header cross-ties the red lights are out for the B Pump Suct, B closed to opposite facility. Hdr, RB-211D and the B/C X-Tie, RB-251B.

(Valves are Closed)

b. ENSURE RBCCW pump suction

• Examinee observes the red light is lit and the Y N S U and discharge header cross-ties green light is out for the B Pump Suct, RB-open to desired facility. 211C (Valve is Open).

• Examinee places the A/B X-Tie, RB-251A, Y N S U hand switch in the OPEN position and observes the red light lights and the green light goes out (Valve is Open).

c. START standby RBCCW pump.

• Examinee momentarily places the B Y N S U RBCCW hand switch in the START position and observes that the green light goes out, the red light momentarily lights and goes out, and the amber light remains lit.

• Examinee observes that the B RBCCW Y N S U Pump is NOT running (No running amps, No A RBCCW Header flow)

Cue: BOOTH OPERATOR - Remove Trip of B RBCCW pump (CC01B) and A RBCCW pump (CC01B) after B RBCCW pump start is attempted.

Acknowledge reports and concur with recommendations. If required, direct to continue with Immediate Operator Actions.

Comments:

6

PERFORMANCE INFORMATION JPM Number: S8 Revision: 1/0 Task

Title:

Respond to a Trip of the A RBCCW Pump STEP Performance: Standard: Critical: Grade:

1. 3 12.1.1. IF RBCCW Pump Overload/Trip not lit, Examinee observes that the B RBCCW Pump Y N S U as directed by the Shift Manager, RESET Overload/Trip annunciator is NOT lit.

and ATTEMPT ONE restart.

Examinee requests Shift Manager direction, and once Shift Manager directs, examinee attempts one restart of the A and / or B RBCCW Pump.

The A and B RBCCW pumps will start if a restart is attempted.

Cue:

• If examinee states that no pump Overload/Trip alarm is lit THEN State that the Shift Manager has granted permission for one restart attempt.

• If examinee requests a restart of the B RBCCW Pump, direct one restart attempt of the B RBCCW pump.

• If examinee requests a restart of the A RBCCW Pump, direct one restart attempt of the A RBCCW pump.

• Acknowledge reports and concur with recommendations if different than above.

Comments:

• Step 12.1.1 is the ALTERNATE PATH.

• By procedure one restart should be attempted.

• The pump will start if it is taken directly to start or if taken to stop to reset the handswitch and then to start. Either is acceptable. The critical piece is the pump starts.

• A restart of the A or B RBCCW pump completes this JPM.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

7

VERIFICATION OF JPM COMPLETION JPM Number: S8 Revision: 1/0 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 10 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 8

STUDENT HANDOUT JPM Number: S8 Revision: 1/0 Initial Conditions:

• The plant is operating at 100% power, in a normal configuration.

• The RO has temporarily left the Control Room.

Initiating Cues:

• As the BOP, respond to any secondary plant condition.

• I will act as the US.

9

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Local Manual Operation of a FRV JPM Number: P1 Revision: 9 Initiated:

John W. Riley - Signature on File 04/15/20 Developer Date Reviewed:

John Wadsworth - Signature on File 06/11/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2006-317 Update JPM with HUP evaluation and new format. 6/0 08/03/06 6/5/2007 Minor Changes due to new FRV Controllers (lights) Updated JPM 6/1 Work Practice Evaluation attachment to reflect current revision.

JWR 08/16/2011 New JPM template and minor editorial changes. 6/2 JWR 09/06/2012 Made minor editorial changes and updated evaluation format. 6/3 MJF 10/18/14 Added questions to JPM for NLCT AOT. 6/4 JMA Upgrade to latest JPM Format 7 5/15/19 Upgrade to current JPM format, add Vision number, incorporate 8 steps in the latest revision (step 4.7.3 allows BOP to take manual SGFP speed control) 04/15/20 Changed the number from JPM-063 to P1 for the 2020 ILT NRC 9 exam. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP-2 Examinee:

JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV System: Main Feedwater Time Critical Task: YES NO Validated Time (minutes): 15 Task Number(s): 234835 Applicable To: SRO X STA RO X PEO X K/A Number: 2.1.30 K/A Rating: 3.9/3.4 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: Examinee has simulated taking local manual control of the #1 Feedwater Regulating Valve per OP 2385.

Required Materials: OP 2385 Feedwater Control system Operation, section 4.7 Local Operation of (procedures, equipment, etc.) No. 1 FRV, revision 15, effective date 10/10/18.

General

References:

OP 2385 Feedwater Control system Operation, revision 15, effective date 10/10/18.

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: P1 Revision : 9 Initial Conditions:

• The I & C department has to perform work on the #1 Steam Generator Water Level Control System which requires taking local manual control of the #1 Feedwater Regulating valve (FRV).

• The BOP has taken manual control of the #1 FRV in accordance with step 4.7.2.

• The BOP has taken manual control of both Steam Generator Feed Pumps (SGFP) speeds at C05 in accordance with step 4.7.3.

• The US has directed you to establish communications with the control room and take local manual control of the #1 FRV in accordance with OP 2385 Feedwater Control System Operation.

• TSAS 3.7.1.6 Main Feedwater Isolation Components has been entered.

Initiating Cues:

• The plant is at 100% and all plant conditions are normal.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 CAUTION: Examinee reads CAUTION. Y N S U

1. To remain within the Main Steam Line Break inside Containment analysis, operation with FRV bypass valve (s) open when greater than 25% power is not allowed.

2. During this mode of operation, the FRV override from TURBINE TRIP" or HI-HI SG LEVEL" signal does not function.

Cue: Provide procedure section 4.7 Local Operation of No. 1 FRV of OP 2385 with steps 4.7.1 through 4.7.3 complete.

Comments: Based on the initiating cue, the examinee may proceed to step 4.7.4 (JPM step 8), after overtly noting that procedure is complete through step 4.7.3.

STEP Performance: Standard: Critical: Grade:

1. 2 NOTE: This Section is required when Examinee reads NOTE. Y N S U malfunctions occur which prevent movement of No. 1 FRV from the Control Room and operation of the Feedwater System is required.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 3 4.7.1 IF in MODEs 1, 2, or 3, ENTER TSAS Examinee notes that the initiating cue stated that Y N S U 3.7.1.6. TSAS 3.7.1.6 has been entered.

Cue: Tech Spec 3.7.1.6 has been entered.

Comments:

5

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 4 4.7.2 ENSURE the following (C-05): Examinee notes that the initiating cue stated that Y N S U the #1 FRV is in manual at C05.

• REG VLV, LIC-5268, controller in manual (red light, lit)

• MSTR, LIC-5272, controller in manual (red light, lit)

• BYPASS, LIC-5215, controller in AUTO (green light, lit)

Cue: BOP reports that the #1 FRV is in manual at C05.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 5 CAUTION: Examinee reads CAUTION. Y N S U

1. BOTH SGFPs must be in manual speed control.

2. Control of feed flow should be accomplished with manipulation of one SGFP speed adjustment at a time.

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 6 NOTE: SGFP speed can be used to adjust flow Examinee reads NOTE. Y N S U by raising or lowering speed slightly (2 to 10 rpm). SG level will not be stable as level will slowly rise or lower. SG level is controllable by speed adjustment that will provide adequate control of SG level within a range of 65 to 75%.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 7 4.7.3 IF desired to adjust SGFP speed to aid in Examinee notes the initiating cue stated that both Y N S U SG level control, PERFORM the following SGFP speeds are in manual control.

(C-05):

a. PRESS SGFP A MANUAL pushbutton and CHECK MANUAL light, lit.

b. PRESS SGFP B MANUAL pushbutton and CHECK MANUAL light, lit.

c. IF desired to adjust A SGFP speed, PRESS SGFP A SPEED RAISE or LOWER pushbutton, as applicable and MAINTAIN the following:

• SG levels between 65 and 75%

• FRV DP between 40 and 150 psid

d. IF desired to adjust B SGFP speed, PRESS SGFP B SPEED RAISE or LOWER pushbutton, as applicable and MAINTAIN the following:

• SG levels between 65 and 75%

• FRV DP between 40 and 150 psid Cue:

BOP reports that both SGFP speeds are in manual control.

Comments:

8

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 8 4.7.4 STATION Operator at 2-FW-51A, #1 S/G Examinee proceeds to the FRV area and states that Y N S U FEED REGULATING VALVE," and they would plug the headphones that are there into ESTABLISH communications (54 6 TB). the maintenance jack, which is located next to the instrument rack, or equivalent and contact the control room.

Cue: Headphones plugged in or Ascom party line established; Control room (BOP) is on the maintenance line or Ascom party line.

Comments: Examinee may opt to take a set of headphones/Ascom phones to the field from the control room or the PEO ready area. If the PEO wants to test the Ascom phones, state that its already done satisfactorily.

STEP Performance: Standard: Critical: Grade:

1. 9 4.7.5 At 2-FW-51A, #1 S/G FEED Examinee states that they would remove the Y N S U REGULATING VALVE," PERFORM the handwheel anti- rotational restraint.

following (54 6 TB):

a. REMOVE handwheel anti- rotational restraint.

Cue: Restraining device is removed.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 10 CAUTION: Feed Regulating valve may move in Examinee reads the caution and understands the Y N S U the closed direction when engaging the large valve may move in the closed direction when manual handwheel. engaging the large manual handwheel.

Cue:

Comments: The BOP will have established a critical parameter for #1 steam generator water level when taking manual control of SGFP speed and #1 FRV, and would use SGFP speed to maintain #1 steam generator water level.

9

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 11 4.7.5 At 2-FW-51A, #1 S/G FEED Examinee states that they would turn the large Y N S U REGULATING VALVE," PERFORM the handwheel for 2-FW-51A in the clockwise following (54 6 TB): direction until it will not turn any further.

b. TURN large handwheel clockwise to its limit of travel.

Cue: Large handwheel for 2-FW-51A rotated clockwise to hard stop.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 12 4.7.5 At 2-FW-51A, #1 S/G FEED Examinee states that they would turn the small Y N S U REGULATING VALVE," PERFORM the handwheel in the counter-clockwise direction until following (54 6 TB): it will not turn any further.

c. TURN small handwheel counterclockwise until tight, locking large handwheel in engaged" position.

Cue: Small handwheel turned counterclockwise; handwheel at its limit of travel.

Comments:

10

PERFORMANCE INFORMATION JPM Number: P1 Revision: 9 Task

Title:

Local Manual Operation of a FRV STEP Performance: Standard: Critical: Grade:

1. 13 4.7.5 At 2-FW-51A, #1 S/G FEED Examinee locates 2-FW-39A and states that they Y N S U REGULATING VALVE," PERFORM the would open it by turning its knob counterclockwise following (54 6 TB): until it will not turn any further.

d. OPEN 2-FW-39A, `A' FEED REGULATING EQUALIZING STOP."

Cue: Knob turning counterclockwise; Knob at its limit of travel.

Comments: As BOP, acknowledge that #1 FRV is in local manual and instruct examinee to standby for instructions.

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

11

VERIFICATION OF JPM COMPLETION JPM Number: P1 Revision: 9 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 12

STUDENT HANDOUT JPM Number: P1 Revision: 9 Initial Conditions:

• The I & C department has to perform work on the #1 Steam Generator Water Level Control System which requires taking local manual control of the #1 Feedwater Regulating valve (FRV).

• The BOP has taken manual control of the #1 FRV in accordance with step 4.7.2.

• The BOP has taken manual control of both Steam Generator Feed Pumps (SGFP) speeds at C05 in accordance with step 4.7.3.

• The US has directed you to establish communications with the control room and take local manual control of the #1 FRV in accordance with OP 2385 Feedwater Control System Operation.

• TSAS 3.7.1.6 Main Feedwater Isolation Components has been entered.

Initiating Cues:

• The plant is at 100% and all plant conditions are normal.

13

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Placing INV-1 in Service JPM Number: P2 Revision: 10 Initiated:

John W. Riley - Signature on File 04/16/20 Developer Date Reviewed:

John Wadsworth - Signature on File 06/11/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE 2006-265 Revise format and addition of HUP standards 8 07/07/2015 Revised to latest format and procedure revision. 9 04/16/20 Changed the number from JPM-056 to P2 for the 2020 ILT NRC 10 exam. This JPM is classified as modified for this exam. Inverter

1. 1 has been replaced and no JPM existed for the new inverter.

Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP 2 Examinee:

JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service System: 120 Volt Vital Instrument AC System Time Critical Task: YES NO Validated Time (minutes): 20 Task Number(s): 062-01-203 Applicable To: SRO X STA RO X PEO X K/A Number: 2.1.30 K/A Rating: 4.4/4.0 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: The examinee will place Inverter 1 in service.

Required Materials: OP 2345B, 120 Volt Vital Instrument AC System, revision 022, effective (procedures, equipment, 12/27/18, sections 4.1 Startup of INV-1 and 4.13 Placing VA-10 on Normal etc.) Supply INV-1 Picture inside the Inverter cabinet showing the AUTO-RETRANSFER switch.

General

References:

OP 2345B, 120 Volt Vital Instrument AC System, revision 022, effective 12/27/18

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: P2 Revision : 10 Initial Conditions:

• Inverter 1 is shutdown.

• The MAN/BYPASS switch is in AUTO.

• VA-10 is on its alternate source.

• No maintenance has been performed on INV-1.

Initiating Cues:

• The Unit Supervisor has directed you to start up INV-1 and place it in service supplying VA-10

• The Unit Supervisor has directed that OP 2345B, 120 Volt Vital Instrument AC System, sections 4.1 Startup of INV-1 and 4.13 Placing VA-10 on Normal Supply INV-1 be used.

• The Unit Supervisor has directed that another individual perform step 4.1.3 to close D0106, 125 VDC BUS 201A to INVERTER 1 (INV-1).

You are just to verify it has been closed.

Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 OP 2345B 4.1 Startup of INV-1 Examinee states they would position the following switches:

4.1.1. ENSURE the following (INV-1):

• DC INPUT breaker in OFF DC INPUT breaker in OFF Y N S U

• INVERTER OUTPUT breaker in INVERTER OUTPUT breaker in OFF Y N S U OFF

• BYPASS SOURCE AC INPUT BYPASS SOURCE AC INPUT breaker in Y N S U breaker in OFF OFF

• MANUAL BYPASS SWITCH in MANUAL BYPASS SWITCH in BYPASS Y N S U BYPASS TO LOAD TO LOAD

• BYPASS ALARM switch in BYPASS ALARM switch in ENABLE Y N S U ENABLE (UP) (UP)

Cue:

Provide OP 2345B sections 4.1, Startup of INV-1 and 4.13, Placing VA-10 on Normal Supply INV-1 to the examinee.

DC INPUT breaker is in OFF INVERTER OUTPUT breaker is in OFF BYPASS SOURCE AC INPUT breaker is in OFF MANUAL BYPASS SWITCH is in BYPASS TO LOAD BYPASS ALARM switch is in ENABLE (UP)

Comments: Steps are bulleted so they may be performed in any sequence.

5

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 2 4.1.2. ENSURE AUTO-RETRANSFER Examinee states that he/she would open the cabinet Y N S U switch in OFF (inside INV-1 cabinet). door an observe the AUTO-RETRANSFER switch. If not in the OFF position they would place the AUTO-RETRANSFER switch in the OFF position.

Cue: Provide a picture of Inverter 1 internals to the examinee. When the examinee locates the AUTO-RETRANSFER switch, inform them that the switch is positioned in OFF.

Comments: DO NOT allow the examinee to open the cabinet door.

6

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 3 4.1.3 Refer To OP 2348B, 480 Volt AC and The initiating cues state that the Unit Supervisor Y N S U 125 Volt DC Breaker Operations, and has directed that another individual perform step CLOSE D0106, 125 VDC BUS 201A to 4.1.3 to close D0106, 125 VDC BUS 201A to INVERTER 1 (INV-1). INVERTER 1 (INV-1). You are just to verify it has been closed.

Examine locates D0106 on Bus 201A and verifies it is closed by observing CLOSED flag on breaker.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 4 NOTE Examinee reads NOTE. Y N S U L2 to ground light may come on when first starting inverter. This will clear after alarms are reset.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 5 4.1.4 PERFORM the following to start INV-1: Examinee locates the correct item and states what they would do as follows:

a. PRESS AND HOLD PRECHARGE PRESS AND HOLD PRECHARGE pushbutton. Y N S U pushbutton.

b. WHEN amber PRECHARGE lamp WHEN amber PRECHARGE lamp is lit, Y N S U is lit, CLOSE DC INPUT breaker. CLOSE DC INPUT breaker.

c. RELEASE PRECHARGE RELEASE PRECHARGE pushbutton. Y N S U pushbutton.

d. CLOSE BYPASS SOURCE AC CLOSE BYPASS SOURCE AC INPUT breaker. Y N S U INPUT breaker.

e. CLOSE INVERTER OUTPUT CLOSE INVERTER OUTPUT breaker. Y N S U breaker.

f. CHECK green IN SYNC light, lit. CHECK green IN SYNC light, lit. Y N S U

g. PRESS ALARM RESET PRESS ALARM RESET pushbutton. Y N S U pushbutton.

Cue:

PRECHARGE pushbutton has been pressed and is being held.

Amber PRECHARGE lamp is lit.

DC INPUT breaker is closed.

PRECHARGE pushbutton is released.

BYPASS SOURCE AC INPUT breaker is closed.

INVERTER OUTPUT breaker is closed.

Green IN SYNC light is lit.

ALARM RESET pushbutton has been pushed.

Comments:

8

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 6 NOTE Examinee reads the note. Y N S U It may take several hours for the inverter output voltage to come into specified value.

Cue: Time compression will be used for this JPM.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 7 4.1.5 CHECK the following to verify proper Examinee checks the following to verify proper operation of INV-1: operation of INV-1:

• INVERTER OUTPUT voltage

• INVERTER OUTPUT voltage between Y N S U between 119.6 to 125 volts. 119.6 to 125 volts

• INVERTER OUTPUT frequency

• INVERTER OUTPUT frequency Y N S U approximately 60 hz (59.7 to 60.3 Hz) approximately 60 hz (59.7 to 60.3 Hz)

Cue:

Once student indications where INVERTER OUTPUT voltage meter is, state voltage is 124 volts (see what inverter is reading now when on line and maybe can just say voltage is as indicated).

Once student indications where INVERTER OUTPUT frequency meter is, state frequency is 60.1 Hz (see what inverter is reading now when on line and maybe can just say voltage is as indicated).

Comments:

9

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 8 4.1.6 IF desired, Refer To Section 4.13 and Examinee states that from the initial conditions this Y N S U PLACE INV-1 in service as normal supply is desired and progresses to section 4.13.

to VA-10.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 9 4.13 Placing VA-10 on Normal Supply INV-1 Examine states that INV-1 is has just been started Y N S U up and is now ON and proceeds with placing 4.13.1 IF INV-1 is off, Refer To Section 4.1 and VA-10 on its Normal Supply.

START INV-1.

Cue:

Comments: INV-1 is on its Normal Supply.

10

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 10 4.13.2 IF desired to transfer VA-10 from INV-5 Examinee:

to INV-1, PERFORM the following (INV-1):

a. ENSURE BYPASS SOURCE AC Checks that BYPASS SOURCE AC INPUT Y N S U INPUT breaker is closed. breaker is closed. Closed earlier in step 4.1.14.d.

b. CHECK the following: Checks Y N S U

• Green IN SYNC light lit

• Green IN SYNC light lit

• Amber BYPASS SOURCE

• Amber BYPASS SOURCE SUPPLYING SUPPLYING LOAD light lit LOAD light lit

• Green INVERTER SUPPLYING

• Green INVERTER SUPPLYING LOAD LOAD light, not lit light, not lit Cue: State the following when the examinee indicates the correct indication (may state it is as seen).

BYPASS SOURCE AC INPUT breaker is closed Green IN SYNC light lit Amber BYPASS SOURCE SUPPLYING LOAD light is lit Green INVERTER SUPPLYING LOAD light, not lit Comments: The BYPASS SOURCE AC INPUT breaker was closed earlier in step 4.1.14.d.

11

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 11 NOTE

1. MANUAL BYPASS SWITCH must only Examinee reads the note. Y N S U be manipulated when both sources are in sync.

2. Amber BYPASS SOURCE SUPPLYING LOAD light will remain lit until ALARM RESET button is pressed.

c. ENSURE MANUAL BYPASS

• Examinee states they would place MANUAL Y N S U SWITCH in NORMAL BYPASS SWITCH in NORMAL.

OPERATION position.

d. PRESS INVERTER TO LOAD

• Examinee states they would press the Y N S U pushbutton. INVERTER TO LOAD pushbutton.

e. PRESS ALARM RESET

• Examinee states they would press the Y N S U pushbutton. ALARM RESET pushbutton.

Cue:

MANUAL BYPASS SWITCH in NORMAL INVERTER TO LOAD pushbutton has been pressed ALARM RESET pushbutton has been pressed Comments:

12

PERFORMANCE INFORMATION JPM Number: P2 Revision: 10 Task

Title:

Placing INV-1 in Service STEP Performance: Standard: Critical: Grade:

1. 12 4.13.2 ENSURE AUTO RETRANSFER Examinee states they would open cabinet door and Y N S U switch to ON (inside INV-1 cabinet). place AUTO RETRANSFER switch to ON.

4.13.4 CHECK the following (INV-1): Examinee checks the following:

• Amber BYPASS SOURCE

• Amber BYPASS SOURCE SUPPLYING Y N S U SUPPLYING LOAD light, not lit LOAD light, not lit

• Green INVERTER SUPPLING

• Green INVERTER SUPPLING LOAD light Y N S U LOAD light lit lit 4.13.5 Refer to TSAS 3.8.2.1 and 3.8.2.2 and Examinee states they would contact the supervisor Y N S U LOG OUT as applicable. and state that the next step is to refer to TSAS 3.8.2.1 and 3.8.2.2 and LOG OUT as applicable.

Cue:

AUTO RETRANSFER switch has been placed to ON Amber BYPASS SOURCE SUPPLYING LOAD light, is not lit Green INVERTER SUPPLING LOAD light is lit Supervisor has been contacted that TSAS 3.8.2.1 and 3.8.2.2 can be logged out of Comments:

DO NOT allow the examinee to open the cabinet door.

Step 4.1.2 placed the ENSURE AUTO-RETRANSFER switch in OFF (inside INV-1 cabinet).

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

13

VERIFICATION OF JPM COMPLETION JPM Number: P2 Revision: 10 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 14

STUDENT HANDOUT JPM Number: P2 Revision: 10 Initial Conditions:

• Inverter 1 is shutdown.

• The MAN/BYPASS switch is in AUTO.

• VA-10 is on its alternate source.

• No maintenance has been performed on INV-1.

Initiating Cues:

• The Unit Supervisor has directed you to start up INV-1 and place it in service supplying VA-10

• The Unit Supervisor has directed that OP 2345B, 120 Volt Vital Instrument AC System, sections 4.1 Startup of INV-1 and 4.13 Placing VA-10 on Normal Supply INV-1 be used.

• The Unit Supervisor has directed that another individual perform step 4.1.3 to close D0106, 125 VDC BUS 201A to INVERTER 1 (INV-1).

You are just to verify it has been closed.

15

JOB PERFORMANCE MEASURE APPROVAL SHEET JPM

Title:

Aligning Firewater to MP2 A EDGs JPM Number: P3 Revision: 2 Initiated:

John W. Riley - Signature on File 04-21-2020 Developer Date Reviewed:

John Wadsworth - Signature on File 06/11/2020 Technical Reviewer Date Approved:

Trad Horner - Signature on File 06/11/2020 Supervisor, Nuclear Training Date 1

SUMMARY

OF CHANGES DATE DESCRIPTION REV/CHANGE JWR 07/28/2011 Initial Issue - new JPM. JPM written to address Industry flooding 0/0 issues and continued security focus.

JLB 06/18/2014 Revised to reflect changes in C OP 200.2 Rev. 004 - 02 1/0 jwr 04/21/20 Changed the number from JPM-260A/B to P3 for the 2020 ILT 2/0 NRC exam. This JPM is classified as modified for this exam.

The initial conditions (imminent threat to the Security of the Station to outage task to station an operator during an outage),

procedure used (changed from security procedure C OP 200.2 to OP 2346B) and extend of JPM (no longer have to go to the EDG) were changed. Removed JPM NLO questions, work practice evaluation and operator fundamentals evaluation. These are not applicable for a NRC JPM.

2

JPM WORKSHEET Facility: MP2 Examinee:

JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDGs System: Emergency Diesel Generator and Fire Water Systems Time Critical Task: YES NO Validated Time (minutes): 10 Task Number(s): 076-01-105 Applicable To: SRO X STA RO X PEO X K/A Number: 064-K1.02 K/A Rating: 3.1/3.6 Method of Testing: Simulated Performance: X Actual Performance:

Location: Classroom: Simulator: In-Plant: X Task Standards: At the completion of this JPM, the examinee has simulated aligning Alternate Cooling (Fire Water) to the A Emergency Diesel Generator in response to a loss of offsite power in MODE 5 with Service Water unavailable.

Required Materials: OP 2346A, A Emergency Diesel Generator, revision 037, section 4.14 Aligning (procedures, equipment, etc.) Fire water to A EDG.

General

References:

OP 2346A, A Emergency Diesel Generator, revision 037

• • • READ TO THE EXAMINEE ***

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. With the exception of the questions at the end, you may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.

3

JPM WORKSHEET JPM Number: P3 Revision : 2 Initial Conditions:

• The plant is in MODE 6

• The RCS is vented

• The Refuel Pool is at 16 feet

• The Emergency Diesels Generators are not operating

• 2-SW-231A A DG SERVICE WATER BYPASS (C06) is closed

• 2-SW-241, A DG SW FCV BYPASS, is closed.

• You are the operator stationed in the Auxiliary Building 146 vital area ready to take action to shift EDG cooling water to Fire Water Initiating Cues:

• The Unit Supervisor has directed you to align the A Emergency Diesel Generator to the Fire Water System utilizing OP 2346A, section 4.14 Aligning Fire water to A EDG starting at step 4.14.3

• Steps 4.14.1 and 4.14.2 have been completed and are signed off

• Another operator has been assigned to monitor Fire Tank levels Simulator Requirements: N/A

• * *

• NOTES TO TASK PERFORMANCE EVALUATOR * * * *

1. Critical steps for this JPM are indicated by checking Y. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".

3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").

4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).

4

PERFORMANCE INFORMATION JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDG START TIME: __________

STEP Performance: Standard: Critical: Grade:

1. 1 NOTE: Y N S U When stationed, the operator may perform Examinee reads the note.

addition tasks provided those tasks do not interfere with the ability to immediately respond if directed to align Fire Water to the EDG.

Cue: Provide procedure section 4.14 Aligning Fire Water to the A DG with steps 4.14.1 and 4.14.2 completed.

Comments: It is allowed to have this attachment available. A lamented copy is available at the Firewater valves to the EDGs 5

PERFORMANCE INFORMATION JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDG STEP Performance: Standard: Critical: Grade:

1. 2 4.14.1 IF the RCS in not vented AND the Examinee may or may not read step 4.14.1. Either Y N S U TDAFW pump is unavailable OR, the is acceptable since the initiating cue states this step RCS is vented AND the Refuel Pool is is complete.

less than full (35 6), PERFORM the following:

a. STATION an operator in the Auxiliary Building 146 vital area to be ready to take action to shift EDG cooling water to Fire Water when directed by the SM.

b. ENSURE the Unit 3 Diesel Fire Pump, M7-7, is available.

c. NOTIFY the following of the above actions:

• Security Shift Operations Supervisor (ext. 4620)

• Response Team Leader (ext. 3384)

Cue:

Comments:

6

PERFORMANCE INFORMATION JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDG STEP Performance: Standard: Critical: Grade:

1. 3 4.14.2 IF running unloaded OR synchronized to Examinee may or may not read step 4.14.2. Either Y N S U the grid, Refer To Section 4.6 and is acceptable since the initiating cue states this step PERFORM applicable actions to shut is complete.

down the A Diesel Generator.

Cue:

Comments:

STEP Performance: Standard: Critical: Grade:

1. 4 CAUTION Y N S U Using the Fire Water system to simultaneously Examinee reads the caution.

supply feedwater and DG, limits the ability to refill the Fire Water Storage Tank in a timely manner.

Cue:

Comments:

7

PERFORMANCE INFORMATION JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDG STEP Performance: Standard: Critical: Grade:

1. 5 4.14.3 PERFORM the following (146 Aux Bldg, EBFS Area):

a. ENSURE locked closed 2-SW-12A,

• Examinee checks position of 2-SW-12A and Y N S U B: HEADER TO A EDG HEAT states the valve is closed by observing indicator EXCH SUPPLY VALVE. position.

b. UNLOCK and CLOSE 2-SW-12B,

• Examinee simulates unlocking closing 2-SW- Y N S U A HEADER TO A EDG 12B. States they unlock then rotate the HEAT EXCH SUPPLY VALVE. handwheel clockwise to hard stop and check valve indicator indicates closed.

Cue:

2-SW-12A is closed.

2-SW-12B is unlocked and closed.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 6 4.14.4 CLOSE 2-SW-231A, A DG SERVICE 2-SW-231A is closed as reported in the initial Y N S U WATER BYPASS (C06) conditions.

4.14.5 ENSURE 2-SW-241, A DG SW FCV 2-SW-241 is closed as reported in the initial Y N S U BYPASS, is closed. conditions.

Cue: If asked state 2-SW-231A and 2-SW-241 are closed.

Comments:

8

PERFORMANCE INFORMATION JPM Number: P3 Revision: 2 Task

Title:

Aligning Firewater to MP2 A EDG STEP Performance: Standard: Critical: Grade

1. 7 4.14.6 UNLOCK and OPEN 2-SW-296, FIRE Examinee simulates unlocking and opening Y N S U WATER X-TIE TO A D/G SW 2-SW-296. They state they would unlock the valve HEADER. and take the butterfly valve handle to a parallel position (in line) to the valve.

Cue: 2-SW-296, FIRE WATER X-TIE TO A D/G SW HEADER is open.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 8 4.14.7 UNLOCK and OPEN 2-FIRE-258, FIRE Examinee simulates both unlocking 2-FIRE-258 Y N S U WATER TO SERVICE WATER and rotating the handwheel counter clockwise to CROSS-TIE (146 Aux Bldg). open the valve.

Cue: 2-FIRE-258, FIRE WATER TO SERVICE WATER CROSS-TIE is open.

Comments:

STEP Performance: Standard: Critical: Grade:

1. 9 4.18.8 NOTIFY the control room that Fire Water Examinee state that they would call the control to Y N S U has been aligned to supply A DG. inform them that Fire Water has been aligned to supply A DG.

Cue: Control room has been notified.

Comments:

TERMINATION CUE: The evaluation for this JPM is concluded.

STOP TIME: _________

9

VERIFICATION OF JPM COMPLETION JPM Number: P3 Revision: 2 Date Performed:

Student:

For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.

If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.

EVALUATION SECTION:

Time Critical Task? Yes No Validated Time (minutes): 15 Actual Time to Complete (minutes):

Evaluator: _____________________________________________________________________

Print / Sign Areas for Improvement / Comments:

Grade: SAT UNSAT 10

STUDENT HANDOUT JPM Number: P3 Revision: 2 Initial Conditions:

• The plant is in MODE 6

• The RCS is vented

• The Refuel Pool is at 16 feet

• The Emergency Diesels Generators are not operating

• 2-SW-231A A DG SERVICE WATER BYPASS (C06) is closed

• 2-SW-241, A DG SW FCV BYPASS, is closed.

• You are the operator stationed in the Auxiliary Building 146 vital area ready to take action to shift EDG cooling water to Fire Water Initiating Cues:

• The Unit Supervisor has directed you to align the A Emergency Diesel Generator to the Fire Water System utilizing OP 2346A, section 4.14 Aligning Fire water to A EDG starting at step 4.14.3

• Steps 4.14.1 and 4.14.2 have been completed and are signed off

• Another operator has been assigned to monitor Fire Tank levels 11

SIMULATOR SCENARIO #2 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 2 Op-Test No.: ES20LI2 Examiners: Operators: US ATC BOP Initial Conditions: IC-292, 100% Power, BOL, equilibrium Xe, 962 ppm Boron, 24E aligned to 24C B HPSI pump aligned for service Turnover: 100% Power, BOL, equilibrium Xe, 594 ppm Boron, 24E aligned to 24C, B HPSI pump aligned for service.

Priorities for shift:

1. Align A HPSI pump for service i.a.w. OP 2308, HPSI, Section 4.2, Shifting HPSI Pumps in MODE 1, 2 or 3 (greater than or equal to 1,750 psia)

2. Maintain the unit at 100% power Critical Tasks:

1. SGTR-05, Cooldown and depressurize the RCS to < 515F THOT.

2. SGTR-09, Isolate most affected S/G.

Event Malf. No. Event Type* Event Description No.

N/A N - ATC/US Align HPSI pumps A & C in service, B in PTL 1.

TS - US C - ATC/US

2. RHLI3002 B RWST level malfunction fails low TS-US

3. N/A C - BOP/US C Circulating Water pump trip (AOP 2517)

4. RX03B I - ATC/US Selected Channel (Y) Pressurizer level Transmitter fails low

5. FW39A C- All A Steam Generator Feed Pump vibrations Rapid Downpower

6. FW39A C - ATC/BOP A Steam Generator Feed Pump vibrations (TRIP CRITERIA)

7. SG02A M - All #1 S/G tube rupture on trip

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual 1 of 15

Appendix D Scenario Outline Form ES-D-1

1. Malfunctions after EOP entry (1-2) 1

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 0

6. Critical tasks (2-3) 2 Scenario Summary:

The crew will take the shift with the unit at 100% power, steady state, no equipment OOS (IC-292).

Event 1: The ATC swaps the alignment of the HPSI pumps to A pump in STBY, B pump in PTL. The US enters TS 3.5.2 during this evolution.

Event 2: The B RWST Level Channel, LI-3002, fails low. The US refers to ESAS Instrumentation Technical Specification 3.3.2.1, Table 3.3-3. Note that the Alarm response does not bypass the faulted channel but the TS states operation can continue with the channel in a bypassed condition. The US may direct the channel to be bypassed.

Event 3: The C Circulator trips. The BOP cross ties the C and D Waterboxes in accordance with AOP 2517, Circulating Water Malfunctions, Appendix A.

Event 4: The selected channel Pressurizer level transmitter (Ch. Y) fails low, causing a perturbation on the pressurizer level control system. The ATC performs immediate operator actions to take manual control of letdown. The ATC then works through the alarm response and swaps Pressurizer level control to channel X.

The TS LCOs are referenced in the ARP; the US should reference the LCO and determine that no TS are entered.

Event 5: The A Main Feed pump experiences high vibrations (3.8 mils HP and 4.4 mils LP bearings). The crew refers to ARP 2590D-016, SGFP A TURBINE VIBRATION, and then enters AOP 2575, Rapid Downpower to downpower the unit <65% power and remove the SGFP from service.

Event 6: After the downpower has been established, the A SGFP vibrations increase to 5 mils. The ATC trips the reactor, The BOP trips the turbine and the A SGFP and the crew enters EOP 2525, Standard Post Trip Actions.

Event 7: The crew diagnoses a Steam Generator Tube Rupture and transitions to EOP 2534, Steam Generator Tube Rupture. The scenario ends after the crew cools down to less than 515 THOT and isolates the affected (#1) S/G.

The scenario will end at the examiners discretion.

Page 2 of 15

Appendix D Scenario Outline Form ES-D-1 INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

Delay Ramp Event Severity Final Relative ID Num Description Time Time Trigger or Value Value Order MALFUNCTIONS C01-A16 RWST LEVEL HI LO 2 ON 1 C01-B17 RWST CH B LEVEL LO LO 2 ON 1 CW01C CW PUMP P-6C TRIP 4 ACTIVE 2 RX04D PZR LVL CNR (LIC-110Y) 3 0% 3 FW03A A SGFP VIBRATIONS 6 4.0 4 FW03A A SGFP VIBRATIONS 1 min 7 6.0 5 SG02A SG #1 TUBE RUPTURE 30 330 6 REMOTE FUNCTIONS OVERRIDES RHLI-3002 RWST LEVEL CHANNEL B 2 0% 1 ESLT-3002 RWST LEVEL 2 0% 1 14A3A6S2 RWST LVL SRAS BIS TRP 2 TRIP 1 ESATI-22_1 RWST LEVEL SENSOR ATI CH B 2 RED 1 ESBA105_1 RWST LVL RAS BIS TRIP SET 2 S2_RED 1 Page 3 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #1 Swap HPSI Pump alignment Examiner Note: OP 2308, High Pressure Safety Injection System, Section 4.2, Shifting HPSI Pumps in MODE 1, 2 or 3 (greater than or equal to 1,750 psia)

US Enter TSAS 3.5.2 LCO 3.5.2 ECCS SUBSYSTEMS - Tavg 300°F Two ECCS subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3*.

US ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Place B HPSI pump in Pull-to-Lock ATC Remove A HPSI pump from Pull-to-Lock US Exit TSAS 3.5.2 When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 4 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #2 B RWST level channel fails low Simulator Operator: When directed by Lead Examiner, Insert Trigger #1 RHLI3002, B RWST Level Channel (0%)

Indications:

RWST LEVEL HI LO (C-01, A-16)

RWST CH B LEVEL LO LO (C-01, B-17)

Examiner Note: ARP 2590A-066, RWST CH B LEVEL LO LO ARP 2590A-066, RWST CH B LEVEL LO LO

1. Compare RWST level channels to determine instrument failure occurred or actual ATC LO/LO level exists.

2. N/A - LO/LO condition does NOT exist

3. Instrument malfunction occurred:

US 3.1 Refer to Tech Spec LCO 3.3.2.1, Table 3.3-3 LCO 3.3.2.1 ESFAS INSTRUMENTATION:

The engineered safety feature actuation system instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an engineered safety feature actuation system instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

Parameter Total number Minimum Channels MODES Action of channels OPERABLE US RWST level - SRAS 4 3 1, 2, 3 4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ACTION 4 - With the number of OPERABLE channels one less than the Total Number of Channels and with the pressurizer pressure:

b. 1850 psia, operation may continue with the inoperable channel in the bypassed condition, provided the following condition is satisfied:

1. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1 provided BOTH of the inoperable channels are placed in the bypassed condition.

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 5 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #3 C Circulating Water pump trip Simulator Operator: WHEN directed by Lead Examiner, INSERT Trigger #3 CW01C, C CIRC WATER PUMP TRIP Indications:

CIRC WATER PUMP C OVERLOAD/TRIP (C-06/7, C-9)

Examiner Note: ARP 2590E-051, CIRC WATER PUMP C OVERLOAD/TRIP AOP 2517, Circulating Water Malfunctions Notify Security Go TO AOP 2517, Circulating Water Malfunctions US Reactor Trip criteria:

Both Circulating Water Pumps in one Condenser - OFF Condenser Backpressure GREATER THAN 6.5 in. Hg abs

1. Close Waterbox Inlet Valve, CIRC WATER INLET, CW-11F (P-6C)

2. Check available Circulators are operating at 100% speed

3. Establish Cross-tie flow through B Waterbox, D pump supplying BOP

4. Start Standby TBCCW pump

5. Check RBCCW temperature < 85F

6. Isolate C Waterbox When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 6 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #4 Selected Channel Pressurizer pressure Transmitter (Ch. Y) fails low Simulator Operator: WHEN directed by Lead Examiner, INSERT Trigger #4 RX03B, PZR PRESS CNTL (PT-100Y) 0%

Indications:

PRESSURIZER CH Y LEVEL HI/LO (C-02/3, A-39)

PZR PRESS SELECTED CHANNEL DEVIATION HI/LO (C-02/3, D-37)

Examiner Note: AOP 2585, Immediate Operator Actions ARP 2590B-217, PRESSURIZER CH Y LEVEL HI LO Performs Immediate Operator Actions for Pressurizer Level Control Malfunctions

1. Shift HIC-110 to MANUAL ATC

2. Adjust HIC-110 to stabilize Pressurizer Level

3. Go To ARP 2590B-217, PRESSURIZER CH Y LEVEL HI LO

4. Observe Pressurizer level and pressure

5. Shift Pressurizer heater control to Channel X and reset pressurizer heaters

6. Observe TAVE/TREF recorder for deviation in TAVE/TREF ATC

7. Place Charging PP Override to LEV 1

8. SHIFT Pressurizer level control to channel X

9. Restore Letdown to automatic Refer to the following LCOs TS 3.2.6 (for DNB)

TS 3.3.3.5 (for HSD)

US TS 3.3.3.8 (for Accident Monitoring)

TS 3.4.4 (for Pzr Level)

TRM 7.1.4 When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 7 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #5 A Steam Generator Feed Pump vibrations Simulator Operator: When directed by Lead Examiner, Insert Trigger #6.

FW03A, A SGFP vibrations (4.0 mils)

Indications:

SGFP A TURBINE VIBRATION (C-05, D-4)

Examiner Note: 2590D-016, SGFP A TURBINE VIBRATION

1. Check vibes on PPC Steam Generator Feed Pump (SGFP_01)

Main Turbine Bentley Nevada (BNTURB_AI)

2. Trip criteria NOT met (vibrations < 5 mils)

ATC 3. Vibration level on both HP bearing AND LP bearing > 3 mils and <5 mils

4. Refer To either of the following and REMOVE SGFP A from service:

AOP 2575, Rapid Down Power (will do this since > 65% power)

OP 2321, Main Feedwater System Page 8 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Examiner Note: AOP 2575, Rapid Downpower, is entered.

US Perform notifications ATC Initiate forcing sprays ATC Insert Group 7 CEAs BOP Reduce Turbine load US Determine Reactivity Plan Availability Borate from RWST using 2 Charging Pumps BOP Set up Turbine controls (Attachment G)

ATC Borate from the RWST Reduce turbine load when effects of boron are seen.

BOP Maintain TCOLD within 2 °F of program Maintain VCT parameters ATC Level 70 - 90%

Pressure < 30 psig CREW Maintain parameters as specified in Attachment A When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 9 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #6 A Steam Generator Feed Pump vibrations (increase to trip setpoint) REACTOR TRIP Simulator Operator: When directed by Lead Examiner, Insert Trigger #7.

FW03A, A SGFP vibrations (6.0 mils ramped over 1 minute)

Examiner Note: 2590D-016, SGFP A TURBINE VIBRATION

1. Check vibes on PPC Steam Generator Feed Pump (SGFP_01)

Main Turbine Bentley Nevada (BNTURB_AI)

2. IF both HP bearing AND LP bearing vibrations are greater than 3 mils AND either is ATC greater than 5 mils, PERFORM the following:

2.1 IF power level is greater than 70%, PERFORM the following:

2.1.1 TRIP reactor.

2.1.2 TRIP SGFP A.

2.1.3 Go To EOP 2525, Standard Post Trip Actions.

ATC/ Trips Reactor BOP Trips A SGFP Page 10 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Event #7 Steam Generator Tube Rupture (#1 S/G) on Reactor Trip Critical Task:

1. SGTR-05, Cooldown and depressurize the RCS to < 515F THOT.

2. SGTR-09, Isolate most affected S/G.

Simulator Operator: When directed by Lead Examiner, Insert Trigger #5.

FW03A, A SGFP vibrations Indications:

SGFP A TURBINE VIBRATION (C-05, D-4)

Examiner Note: Crew trips the reactor and enters EOP 2525, Standard Post Trip Actions Reactivity Control Reactor Trip ATC Ensure Reactor Trip Reactivity Control Turbine Trip BOP Ensure Turbine trip BOP Reports status of Electrical plant. All busses energized BOP Reports status of RBCCW and Service Water. All headers operating.

RCS Inventory Control

a. Pressurizer level is between 20 to 80%, trending to 35 to 70%.

ATC RESPONSE NOT OBTAINED Actions taken to start 3rd charging pump and secure Letdown

b. RCS subcooling < 30 F Examiner Note: One RCP in each loop will be secured on SIAS, Pressure does not go below RCP NPSH.

RCS Pressure Control

a. CHECK that pressurizer pressure is 1900 to 2350 psia, trending to 2225 to 2300 psia.

RESPONSE NOT OBTAINED OPERATE the Pressurizer Pressure Control System. Manually OPERATE ATC pressurizer heaters and spray valves.

IF pressurizer pressure is less than 1714 psia AND SIAS actuated, THEN ENSURE ONE RCP in each loop is stopped.

TCOA: IF Pressurizer pressure lowers to less than the minimum of Fig. 2 RCP NPSH Curve THEN STOP ALL RCPs Page 11 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Core Heat Removal ATC a. CHECK at least 1 RCP is operating, AND loop T < 10 F

b. RCS subcooling > 30 F RCS Heat Removal

a. At least one S/G has BOTH of the following conditions met:

Level 10% to 80%.

BOP Main feedwater or TCOA: TWO auxiliary feedwater pumps operating to restore level between 40% and 70%.

b. RCS TCOLD is being maintained between 530 F to 535 F

c. BOTH S/G pressures are 880 to 920 psia.

Containment Isolation

a. CTMT pressure < 1.0 psig ATC

b. No primary plant radiation monitors have unexplained alarm or indicate an unexplained rise in activity

c. No primary plant radiation monitors have unexplained alarm or indicate an unexplained rise in activity BOP RESPONSE NOT OBTAINED

c. IF feed is available to BOTH steam generators, THEN THROTTLE feed to the steam generator with the highest radiation readings to maintain level 40 to 45%.

Containment Temperature and Pressure Control ATC a. CTMT temperature < 120 F

b. CTMT pressure < 1.0 psig ATC Perform Appendix 4, Reactor Trip Subsequent Actions BOP Diagnose the event Diagnostic Flowchart directs operator to EOP 2534, Steam Generator Tube Rupture due to:

Unexplained level rise in one SG US Unexplained feed flow mismatch between SGs Unexplained loss of RCS inventory Abnormal RAD in secondary plant with normal CTMT conditions Page 12 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Examiner Note: Crew transitions to EOP 2534, Steam Generator Tube Rupture Confirm Diagnosis Sample S/Gs for Activity and Boron US Classify the Event Implement Placekeeping SIAS Actuation SIAS will have been actuated on low RCS pressure Optimize Safety Injection ATC RCP Trip Strategy 2 RCPs will be tripped after SIAS actuation RCP Operating Limits Critical Task: SGTR-05, Cooldown and depressurize the RCS to < 515F THOT.

Examiner Note: BOP commences 40-60 /hour cooldown using condenser steam dumps BOP Commence Cooldown to THOT < 515 Reduce and Control RCS Pressure ATC Block MSI Actuation Block SIAS Actuation Critical Task: SGTR-09, Isolate most affected S/G.

Page 13 of 15

Op-Test No.: __ ES20LI2___ Scenario No.: __2__

Time Position Applicants Actions or Behavior Determine Most Affected Steam Generator Isolate Most Affected Steam Generator

a. RECORD in the placekeeper, time AND TCOLD of the operating loop.

__________Time

__________TCOLD F

b. ENSURE ALL of the following for the #1 ADV:

ADV controller, PIC- 4223, setpoint at 920 psia ADV controller, PIC- 4223, is in A ADV, MS- 190A, is closed

c. ENSURE the MSIV, MS- 64A, is closed.

d. ENSURE the MSIV BYPASS, MS- 65A, is closed.

e. CLOSE turbine driven aux feed pump supply valve, MS- 201.

f. CLOSE BYPASS VALVE, LIC- 5215, main feedwater regulating bypass valve.

BOP

g. ENSURE, the main feedwater block valve, FW- 42A, is closed.

h. PLACE main feed isolation air assisted check valve, FW- 5A to CLOSE.

i. ENSURE the steam generator blowdown isolation valve, MS- 220A, is closed.

j. PLACE BOTH auxiliary feed OVERRIDE/MAN/START/RESET handswitches in PULL- TO- LOCK.

k. CLOSE the aux feedwater regulating valve, FW- 43A.

l. PLACE aux feed isolation air assisted check valve, FW- 12A, to CLOSE.

m. CLOSE main steam leg low point drain, MS- 265B.

n. CHECK the main steam safety valves are closed.

o. RECORD time #1 steam generator is isolated:

______________Time When the event has been addressed to the lead examiners satisfaction, the scenario is complete.

Page 14 of 15

DATE-TIME SHIFT TURNOVER REPORT Today - 0515 PREPARED BY: Unit Supervisor SHIFT 18:00 - 6:00 PLANT STATUS:

Mode: 1 Reactor Power: 100 %

Megawatts: Thermal: 2699.5 MWTH PZR Pressure: 2250 psia Electric: 900 MWe RCS T-AVE: 532 Identified: 0.001 gpm Core Burnup: 1000 MWD/MTU Unidentified: 0.004 gpm Protected Train: A Date/Time: Today/0530 Intake: GREEN Active Tracking Records and Action Statements Equipment/Reason Time in LCO Action Date Action Requirement Time Left LCO OD Compensatory Actions / Temp Logs Watch Open Date Reason Position PLANT SYSTEMS APC System Notes Main Steam 2-MS-239, #2 S/G Safety Valve, has indication of weeping. The organization is investigating.

CROSS UNIT SYSTEM STATUS SURVEILLANCES / EVOLUTIONS IN PROGRESS REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES / SPREAD SHEET FOR ADDITIONAL INFO)

Rod Height ARO Xenon Trend Stable Current Boron 594 Blend Ratio SHIFT PRIORITIES

1. Swap HPSI pumps to A in STBY, B in PTL 2.

3.

SIMULATOR SCENARIO #3 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 3 Op-Test No.: ES20LI2 Examiners: Operators: SRO ATC BOP Initial Conditions: IC-292, 100% Power, MOL, equilibrium Xe, 594 ppm Boron, 24E aligned to 24C 2-MS-239 is weeping by seat, organization is determining status Turnover: 100% Power, BOL, equilibrium Xe, 962 ppm Boron, 24E aligned to 24C Critical Tasks:

1. SPTA-01, SPTA-01, Establish Reactivity control by tripping the Reactor.

2. ESDE-05, Establish RCS temperature control.

3. ESDE-04, Isolate AFW to the affected S/G.

4. ESDE-06, Throttle HPSI when conditions allow.

Event Malf. No. Event Type* Event Description No.

1. N/A N - ATC/US Swap Control Room Air Conditioning from recirculation to normal mode ED06B C - All Loss of Non-Vital 480 VAC Load Center 22B 2.

TS - US MS07B C - All #2 S/G Main Steam Safety Valve leakage Rapid Downpower 3.

TS- US

4. MS01B M - All #2 S/G Excess Steam Demand inside CTMT (TRIP CRITERIA)

RP04A-D

5. C - ATC/US Failure of Manual trip, failure of ALL RPS trips RP27B

6. RH06A C - ATC/US A' CS pump fail, B CS MOV binding

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual 1 of 15

Appendix D Scenario Outline Form ES-D-1

1. Malfunctions after EOP entry (1-2) 1

2. Abnormal events (2-4) 2

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 2

6. Critical tasks (2-3) 4 Scenario Summary:

The crew will take the shift with the unit at 100% power, steady state, no equipment OOS (IC-293).

Event 1: The ATC uses OP 2315A, Control Room Air Conditioning System, to swap A CRAC system from recirculation mode to normal mode of operation.

Event 2: Non-Vital 480 Volt Load Center Bus 22B de-energizes. The BOP responds to annunciator 480V BUS 22B SUPPLY BREAKER B0102 TRIP (C-08, B-14) and refers to AOP 2503B, Loss of Non-Vital 480 VAC Bus 22B. The BOP performs actions to ensure the Steam plant pumps are powered from 22A with the 22B powered pumps are off or in PTL. The ATC re-aligns the chillers.

Event 3: #2 S/G Main Steam Safety Valve, 2-MS-239, is weeping and its OPERABILITY is being evaluated by the organization. The SM calls and tells the US the safety is inoperable and to take appropriate action The US refers to LCO 3.7.1.1, SAFETY VALVES, and determines that with an inoperable MSSV, power needs to be reduced to within the limits of Table 3.7-1 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The US directs entry into AOP 2575, Rapid Downpower to reduce power to < 85% due to the inoperable MSSV.

Event 4: An Excess Steam Demand occurs inside CTMT requiring a reactor trip. The crew enters EOP 2525, Standard Post Trip Actions. The US diagnoses the event and transitions to EOP 2536, Excess Steam Demand.

Event 5: Reactor Protection System trip signal doesnt trip the reactor. The ATC trips the reactor by pushing the manual Reactor Trip pushbuttons.

Event 6: The A Containment spray pump fails to start on the ESAS generated Containment Spray signal. The B CTMT Spray Pump discharge valve fails to open. The ATC recognizes the fault and starts the A Containment Spray pump and/or opens the B CTMT Spray Pump discharge valve.

The scenario will end at the examiners discretion.

INPUT

SUMMARY

Page 2 of 15

Appendix D Scenario Outline Form ES-D-1 Either INPUT or VERIFY the following functions:

Delay Ramp Event Severity or Final Relative ID Num Description Trigger Order Time Time Value Value MALFUNCTIONS RP27A NO RPS TRIP EXCEPT ATWS 0 RP27B NO RPS AUTO TRIP 0 MS07B MS STM #2 SAFETY VALVE FAIL 9000 0 ED06B LOSS OF 480V BUS 22B 3 1 MS01B MN STM HDR #2 RUPTURE IN CTMT 5 1.5 2 RH06A CTMT SPRAY PP 43A TRIP 30 ACTIVE 3 RH15B MECH. BINDING OF CS-4.1B 30 100% 3 REMOTE FUNCTIONS CHR05 RESET CHILLERS 169A/B, 196A/B 15 RESET MSR13 2-MS-202 STATUS 17 RI OVERRIDES Page 3 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Event #1 Swap Control Room Air Conditioning from recirculation mode to normal mode Examiner Note: OP 2315, Control Room Air Conditioning System, Section 4.3, Shifting Train A CRACS to Normal Mode from Recirculation Mode Place/Ensure Handswitch to O.A.

ATC Secure Filter Fan , F-32A Ensure proper system alignment (fans & dampers)

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 4 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Event #2 Loss of Non-Vital 480 VAC Load Center 22B Simulator Operator: When directed by Lead Examiner, Insert Trigger #3 ED06B, LOSS OF 22B ACTIVE Indications:

480V BUS 22B SUPPLY BKR B0209 TRIP (C-08, B-14) 480V BUS 22A/B/C/D GROUND (C-08, A-16)

Examiner Note: ARP 2590F-054, 480V BUS 22B SUPPLY BKR B0209 TRIP SRO ARP directs crew to AOP 2503B, Loss of Non-Vital 480V AC Bus 22B Examiner Note: AOP 2503B, Loss of Non-Vital 480V AC Bus 22B Ensure the following equipment in service:

A TBCCW pump, P-7A C TBCCW pump, P-7C BOP A hydraulic fluid pump, P-81A A stator coolant pump, P-65A A steam packing exhauster, F-7A A water box priming pump, F-6A PLACE the following equipment in STOP or PULL TO LOCK as applicable:

B TBCCW pump, P-7B BOP B hydraulic fluid pump, P-81B B steam packing exhauster, F-7B B water box priming pump, F-6B SRO/ Determine through the NOTE and CAUTION that there is a fault on bus 22B BOP Go To step 3.14 Dispatch Operator to swap loads BOP Isophase Cooling Main Transformer cooling Simulator Operator: Acknowledge direction as given by BOP (no actions required)

Page 5 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Isolate Bus 22B ENSURE the following breakers open:

BOP A204, 24B/22B FDR BKR 24B4-2 B0209, 22B SPLY BKR 24B4-1X3-2 B0111, 22A/22B TIE BKR 22A-1T-2 LOG entry into TS LCO 3.7.1.6, Main Feedwater Isolation Components, for loss of power SRO to FW-38B, MFP discharge and FW-42B, MF block valves.

Examiner Note: LCO 3.7.1.6 LCO 3.7.1.6 MAIN FEEDWATER ISOLATION COMPONENTS (MFICS)

Each feedwater isolation component listed in Table 3.7-3 shall be OPERABLE.

FW-38B B FP Discharge MOV FW-42B B FW Block MOV APPLICABILITY: MODES 1, 2 & 3 ACTION:

a. With one feedwater isolation component inoperable in either or both feedwater flow paths, either:

1. Restore the inoperable component(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or

2. Close or isolate the inoperable feedwater isolation valve(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and verify that the inoperable feedwater isolation valve(s) is closed or isolated once per 7 days, or

3. Secure or isolate the feedwater pump(s) with inoperable feedwater pump trip circuitry within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify that the inoperable feedwater pump(s) is secured or isolated once per 7 days, or

4. Be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Examiner Note: The next step can be skipped, as desired Refer To OP 2330C, Chilled Water System, and ENSURE the following:

BOP P149A, A non-vital chill water pump is in service X196A, A non-vital chiller in service When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 6 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Event #3 Main Steam Safety Valve leakage (#2 S/G)

Simulator Operator: When directed by Lead Examiner, Call the crew with the following message:

This is the Shift Manager, 2-MS-239, has been determined by surveillance review that its setpoint was set outside the Tech Spec allowable lift setting.

Indications:

PPC alarm (already in alarm)

Examiner Note: LCO 3.7.1.1 LCO 3.7.1.1 SAFETY VALVES All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 4.7-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one or more required main steam line code safety valves per steam generator inoperable,

1. Reduce THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to less than or equal to the applicable SRO percent of RATED THERMAL POWER listed in Table 3.7-1, MINIMUM NUMBER OF MAXIMUM POWER MAXIMUM ALLOWABLE MSSVs PER STEAM (Percent Of RATED POWER LEVEL-HIGH GENERATOR REQUIRED THERMAL POWER) TRIP SETPOINT (Percent OPERABLE Of RATED THERMAL POWER) 8 100 106.6 (Ceiling) 7 85 94.6 SRO Determines power needs to be reduced to < 85% within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Simulator Operator: If SRO decides to reduce power using OP 2204, CALL the crew as the Shift Manager and direct the plant be downpowered using AOP 2575, Rapid Downpower.

Page 7 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Examiner Note: AOP 2575, Rapid Downpower, is entered.

SRO Perform notifications ATC Initiate forcing sprays ATC Insert Group 7 CEAs BOP Reduce Turbine load SRO Determine Reactivity Plan Availability Borate from RWST using 2 Charging Pumps BOP Set up Turbine controls (Attachment G)

ATC Borate from the RWST and insert CEAs per the reactivity plan

1. Reduce turbine load when effects of boron are seen.

BOP

2. Maintain TCOLD within 2 °F of program Maintain VCT parameters ATC Level 70 - 90%

Pressure < 30 psig CREW Maintain parameters as specified in Attachment A When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 8 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Event #4 Excess Steam Demand inside CTMT (#2 S/G )

Event #5 Failure of RPS trips Event #6 A CTMT Spray pump does not start B CTMT Spray valve mechanically binds and does not open Critical Task:

1. SPTA-01, SPTA-01, Establish Reactivity control by tripping the Reactor.

2. ESDE-05, Establish RCS temperature control.

3. ESDE-04, Isolate AFW to the affected S/G.

Simulator Operator: When directed by Lead Examiner, Insert Trigger #5.

MS01B, #2 S/G Excess Steam Demand inside CTMT (1.5 Mlbm/hr.)

Indications:

Lowering RCS pressure and temperature Increasing CTMT pressure and temperature Examiner Note: EOP 2525, Standard Post Trip Actions Critical Task: SPTA-01, SPTA-01, Establish Reactivity control by tripping the Reactor.

Reactivity Control Reactor Trip Ensure Reactor Trip RESPONSE NOT OBTAINED ATC IF Reactor trip breakers are CLOSED, THEN INSERT CEAs by ANY of the following methods:

1) PUSH the RX TRIP TCBS buttons.

Reactivity Control Turbine Trip BOP Ensure Turbine trip Maintenance of Vital Auxiliaries BOP All busses energized NOTE: Bus 22B is not reported in EOP 2525 Maintenance of Vital Auxiliaries BOP RBCCW and Service Water headers operating.

Page 9 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior RCS Inventory Control Pressurizer level < 20%

a. Pressurizer level is between 20 to 80%, trending to 35 to 70%.

ATC RESPONSE NOT OBTAINED Actions taken to start 3rd charging pump and secure Letdown

b. RCS subcooling > 30 F RCS Pressure Control

a. CHECK that pressurizer pressure is 1900 to 2350 psia, trending to 2225 to 2300 psia.

RESPONSE NOT OBTAINED OPERATE the Pressurizer Pressure Control System. Manually OPERATE ATC pressurizer heaters and spray valves.

IF pressurizer pressure is less than 1714 psia AND SIAS actuated, THEN ENSURE ONE RCP in each loop is stopped.

TCOA: IF Pressurizer pressure lowers to less than the minimum of Fig. 2 RCP NPSH Curve THEN STOP ALL RCPs Core Heat Removal ATC a. CHECK at least 1 RCP is operating, AND loop T < 10 F

b. RCS subcooling > 30 F Critical Task: ESDE-04, Isolate AFW to the affected S/G.

RCS Heat Removal

a. At least one S/G has BOTH of the following conditions met:

Level 10% to 80%.

Main feedwater or TCOA: TWO auxiliary feedwater pumps operating to restore level between 40% to 70%.

b. RCS TCOLD is being maintained between 530 F to 535 F RESPONSE NOT OBTAINED (no actions to take)

c. BOTH S/G pressures are 880 to 920 psia.

BOP RESPONSE NOT OBTAINED c.1 IF ANY steam generator pressure is less than 572 psia AND an excess steam demand event is in progress, THEN PERFORM the following to isolate AFW to the most affected SG:

1) PLACE BOTH auxiliary feed OVERRIDE/MAN/START/RESET hand switches in PULL TO LOCK.

2) CLOSE applicable Aux Feed Reg valve:

2-FW-43A 2-FW-43B Page 10 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Critical Task: ESDE-05, Establish RCS temperature control.

c. BOTH S/G pressures are 880 to 920 psia.

RESPONSE NOT OBTAINED c.3 IF ANY steam generator pressure is less than 572 psia AND an excess steam demand event is in progress, THEN PERFORM the following BOP 1) CLOSE the ADV for the most affected steam generator.

2) IF the most affected steam generator has boiled dry, as indicated by CET temperature rising, THEN OPERATE the ADV for the least affected steam generator to stabilize CET temperature.

Containment Isolation

a. CTMT pressure < 1.0 psig RESPONSE NOT OBTAINED

a. IF containment pressure is greater than or equal to 4.42 psig, THEN ENSURE ALL of the following:

SIAS actuated. (C01)

ATC CIAS actuated. (C01)

EBFAS actuated. (C01)

MSI actuated. (C01)

b. No primary plant radiation monitors have unexplained alarm or indicate an unexplained rise in activity

c. No primary plant radiation monitors have unexplained alarm or indicate an unexplained rise in activity Examiner Note:

A CTMT Spray pump does not start B CTMT Spray valve mechanically binds Page 11 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior Containment Temperature and Pressure Control

a. CTMT temperature < 120 F RESPONSE NOT OBTAINED

a. ENSURE ALL available normal cooling and ventilation systems are OPERATING:

CAR fans operating on the facility with an operating train of RBCCW CTMT Aux Circ fans

b. CTMT pressure < 1.0 psig RESPONSE NOT OBTAINED

b. IF containment pressure is greater than or equal to 4.42 psig, THEN ENSURE ALL of the following:

ATC SIAS actuated. (C01)

CIAS actuated. (C01)

EBFAS actuated. (C01)

MSI actuated. (C01)

b. IF containment pressure is greater than or equal to 9.48 psig, THEN ENSURE ALL of the following:

CSAS actuated. (C01)

ALL operating containment spray pumps are delivering at least 1300 gpm each.

ATC takes action to start A CTMT Spray pump (may try to open 2-CS-4.1B but it is bound up).

ATC Perform Appendix 4, Reactor Trip Subsequent Actions BOP Diagnose the event Diagnostic Flowchart directs operator to EOP 2536, Excess Steam Demand due to:

SRO Pressurizer Pressure lowering < 1900 psi Subcooling > 30F S/G pressure < 880 psi Examiner Note: Crew transitions to EOP 2536, Excess Steam Demand Confirm Diagnosis Sample S/Gs and RCS SRO Classify the Event Implement Placekeeping Page 12 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior SIAS Actuation SIAS will have been actuated on low RCS pressure Optimize Safety Injection ATC Close MSIVs to Isolate Leak RCP Trip Strategy 2 RCPs will be tripped after SIAS actuation RCP Operating Within Limits Determine Most Affected Steam Generator Isolate Most Affected Steam Generator

a. CHECK ESDE Leak Path - REMAINS UNISOLATED

b. CHECK #1 Steam Generator - MOST AFFECTED

c. ISOLATE #1 Steam Generator by performing the following:

Number 1 Steam Generator

1. CLOSE #1 ADV by both of the following: (C-05 or C-21)

ATMOS DUMP CNTL, PIC-4223 in M ATMOS DUMP, MS-190A - CLOSED

2. PLACE ADV Quick Open Permissive switch to OFF.

3. CHECK MSIV MS-64A - CLOSED (C-05)

4. CHECK BYPASS, MS-65A - CLOSED (C-05)

BOP 5. CLOSE TDAFP SPLY VLV, MS-201 (C-05)

6. CHECK BLDN ISOL VLV, MS-220ACLOSED (C-05)

7. PLACE both Auxiliary Feed OVERRIDE/MAN/START/RESET handswitches in PULL TO LOCK (C-05)

8. CLOSE AFW FCV, FW-43A (C-05)

9. CLOSE AFW ISOL CK, FW-12A (C-05)

10. CLOSE FW REG BYPASS VLV, LIC-5215 (C-05)

11. CHECK BLK VLV, FW-42A (B1211) - CLOSED (C-05)

12. CLOSE FW ISOL, FW-5A (C-05)

13. CLOSE MAIN STM LEG LOW PT DR, MS-265B (C-06/7)

14. CHECK Main Steam Safety Valves - CLOSED (C-05, PPC or Local)

15. RECORD time #1 Steam Generator isolated:

Page 13 of 15

Op-Test No.: __ ES20LI3___ Scenario No.: __3__

Time Position Applicants Actions or Behavior When the event has been addressed to the lead examiners satisfaction, the scenario is complete.

Page 14 of 15

DATE-TIME SHIFT TURNOVER REPORT Today - 0515 PREPARED BY: Unit Supervisor SHIFT 18:00 - 6:00 PLANT STATUS:

Mode: 1 Reactor Power: 100 %

Megawatts: Thermal: 2699.5 MWTH PZR Pressure: 2250 psia Electric: 900 MWe RCS T-AVE: 532 Identified: 0.001 gpm Core Burnup: 1000 MWD/MTU Unidentified: 0.004 gpm Protected Train: A Date/Time: Today/0530 Intake: GREEN Active Tracking Records and Action Statements Equipment/Reason Time in LCO Action Date Action Requirement Time Left LCO OD Compensatory Actions / Temp Logs Watch Open Date Reason Position PLANT SYSTEMS APC System Notes CROSS UNIT SYSTEM STATUS SURVEILLANCES / EVOLUTIONS IN PROGRESS REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES / SPREAD SHEET FOR ADDITIONAL INFO)

Rod Height ARO Xenon Trend Stable Current Boron 962 Blend Ratio SHIFT PRIORITIES

1. Swap CRAC from recirculation to normal mode

2. Maintain the unit at 100% power 3.

SIMULATOR SCENARIO #4 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 4 Op-Test No.: ES20LI4 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power, MOL, 594 ppm boron, equilibrium Xe., 24E aligned to 24C Turnover: 100% Power, BOL, 962 ppm boron, equilibrium Xe., 24E aligned to 24C Critical Tasks:

1. HR-01, Establish RCS heat removal.

2. ESDE-04, Isolate AFW to the affected S/G.

3. ESDE-05, Establish RCS temperature control.

Event Malf. No. Event Event Description No. Type*

1. N/A N - ATC/US Pressurizer Heater Capacity Test C - ATC/US

2. RP24D Channel 'D' CTMT pressure instrument fails high TS - US

3. RX11D C - BOP/US #2 S/G Alternate steam flow failure C - All

4. RD0368 #68 Control Element Assembly drop Rapid downpower TS - US

5. MS02B M - All #2 S/G Excess Steam Demand

6. TC10A C - BOP Turbine trip fails FW20B A AFW pump trips, C - All

7. FW20C TDAFW trips 2540 (ESD/LOAF)

RH06A Bus 24D trip 8.

9.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 18

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 2

6. Critical tasks (2-3) 3 Scenario Summary:

The crew will take the shift with the unit at 100% power, steady state, no equipment OOS (IC-21).

Event 1: The ATC performs surveillance SP 2602E, Pressurizer Heater Capacity test.

Event 2: The channel 'D' CTMT pressure instrument fails high, the crew responds to annunciators CTMT PRES HI D (C-01, D-21) and CTMT PRES HI HI D (C-01, D-22). The ATC bypasses the channel D high pressure bistables on RPS and ESAS.

Event 3: The #2 S/G Alternate steam flow instrument fails high. The BOP recognizes and takes actions to stabilize the plant. AOP 2585, Immediate Operator Actions, is entered which directs them to ARP 2590D-064, SG LEVEL SETPOINTDEVIATION HI/LO. The BOP uses OP 2385, Feedwater Control System Operation, and OP2321, Main Feedwater to restore the system back to automatic operation.

Event 4: CEA # 68 drops. The BOP takes action to stabilize temperature by reducing turbine load. AOP 2585, Immediate Operator Actions is entered and the crew is directed to AOP 2556, CEA Malfunctions.

Appendix D directs a down power the unit to < 70 % within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using only boration. AOP 2575, Rapid Downpower, is entered and a plant down power to < 70% commences by boration only.

Event 5: An Excess Steam Demand occurs on #2 S/G outside CTMT. EOP 2525, Standard Post Trip Actions, is entered.

Event 6: The turbine fails to trip with the reactor; the BOP trips the turbine with the manual pushbuttons.

Event 7: On the trip, Bus 24D becomes faulted (no B AFW pump). The BOP will start the A AFW pump and TDAFW pump. Both pumps subsequently trip. An Excess Steam Demand combined with a Loss Of All Feedwater is diagnosed and the crew transitions to EOP 2540, Functional Recovery where the RCS Heat Removal safety function is restored by Feeding the S/Gs with Condensate.

The scenario will end at the examiners discretion.

2 of 33

Appendix D Scenario Outline Form ES-D-1 INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

Delay Ramp Event Severity or Final Relative ID Num Description Time Time Trigger Value Value Order MALFUNCTIONS TC10B TURB TRIP (RX TRIP) ACTIVE 0 RP24D PT-8116 Xmitter Fail (D CTMT Press) 2 60 1 RX11D #2 S/G Alternate steam flow failure 3 100 2 RD0368 #68 Control Element Assembly drop 4 0 3 SG02B #2 S/G Excess Steam Demand 7 0.9 FW20B A Aux Feed pump trips 7 min 30 FW20C Turbine Driven feed pump trip 5 min 30 ED05 Bus 24D trip 30 REMOTE FUNCTIONS FWHSFW_9 FW LO (DO Green) 3 NG 2 OVERRIDES 3 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Event #1 Pressurizer Heater Capacity Test Examiner Note: SP 2602E, Pressurizer Heater Capacity Test

1. PLACE selected pressurizer controller in AUTO and LOWER selected pressure controller output signal to minimum (0%).

2. RECORD each positions current from GROUP 1 HTR AMPS

3. RECORD each positions current from GROUP 2 HTR AMPS ATC 4. PLACE selected pressurizer controller in AUTO and VERIFY pressurizer pressure returns and stabilizes at selected pressure setpoint.

5. RECORD bus voltage from 22E and 22F

6. CALCULATE Group 1 and Group 2 average currents.

7. CALCULATE Group 1 and Group 2 total kW.

8. COMPARE heater power (kW) data to Acceptance Criteria When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

4 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Event #2 Channel 'D' CTMT pressure instrument fails high Simulator Operator: When directed by Lead Examiner, Insert Trigger #2.

RP24D, Channel 'D' CTMT pressure instrument failure 60 psig Indications:

CONTAINMENT PRESSURE HI B (C-01, B-21)

CONTAINMENT PRESSURE HI HI B (C-01, B-22)

Examiner Note: ARP 2590A-086, CONTAINMENT PRESSURE HI HI B (ARP 2590A-082 has same actions)

1. Reactor is NOT tripped

2. No SIAS or MSI actuation

3. IF alarm is due to instrument malfunction, PERFORM the following:

ATC CS pumps are NOT operating.

OBTAIN necessary keys and PERFORM applicable actions to bypass channel B" Containment pressure bistables on RPS and ESAS.

4. Refer To the following Technical Specifications LCOs and DETERMINE applicability:

SRO 3.3.1.1, Table 3.3-1, Reactor Trip Setpoints - NOT applicable 3.3.2.1, Table 3.3-3 5 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Examiner Note: SRO enters TSAS 3.3.2.1.a, Table 3.3-3 ACTION 2.a LCO 3.3.2.1 ESFAS INSTRUMENTATION The engineered safety feature actuation system instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an engineered safety feature actuation system instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

Parameter Total number Minimum Channels MODES Action of channels OPERABLE CTMT press. - SIAS 4 3 1, 2, 3 2 CTMT press. - CSAS 4 3 1, 2, 3 2 CTMT press. - MSI 4 3 1, 2, 3 2 CTMT press. - CIAS 4 3 1, 2, 3 2 CTMT press. - EBFAS 4 3 1, 2, 3 2 ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

6 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Event #3 #2 S/G Alternate steam flow failure Simulator Operator: When directed by Lead Examiner, Insert Trigger #3 RX11D , #2 S/G Alternate steam flow failure 100%

FWHSFW_9, FW LO (DO Green) NOT LIT Examiner Note: OP 2585, Immediate Operator Actions Takes immediate operator actions to stabilize S/G level

1. Place SGFPs in MANUAL BOP 2. Place affected Feed Regulating Valve in MANUAL

3. Restore SGFP Speeds to normal value

4. Stabilize S/G level Review AOP 2585 actions with BOP.

SRO Go To ARP 2590D- 064, SG LEVEL SETPOINT DEVIATION HI/LO (C- 05, D- 16).

Examiner Note: ARP 2590D-064, SG LEVEL SETPOINT DEVIATION HI/LO (C- 05, D- 16).

Note - the first 5 steps repeat actions already taken

1. Adjust SGFP speeds to MAINTAIN affected FRV D/P at 40 to 150 psid.

2. OBSERVE affected side green transmitter lights to determine if any of the following has caused the deviation (C-05):

Level transmitter failure Steam flow transmitter failure (#2 ALT light is NOT illuminated)

BOP Feed flow transmitter failure

3. TURN associated transmitter control switch from BOTH to MAIN

4. Restore S/G level to normal band

5. Refer To OP 2385, Feedwater Control System Operation, and PLACE Feedwater Control System in Automatic.

6. Refer To OP 2321, Main Feedwater System, and PLACE SGFP controller(s) in AUTO.

Examiner Note: OP 2385, Feedwater Control System Operation, Section 4.4, Operation of No. 2 FW Control System During Normal Operation 7 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior

1. IF No. 2 FRV controller is in manual operation and manual operation is no longer required, PLACE 2 FRV controller in Master Manual as follows (C-05):

a. ADJUST MSTR, LIC-5274, as necessary to match red and black/white needles on REG VLV, LIC-5269.

b. PRESS REG VLV, LIC-5269, controller A pushbutton and ENSURE green light, lit.

c. ADJUST MSTR, LIC-5274, as necessary to maintain S/G level in band.

2. To place No. 2 FRV controllers in automatic control, PERFORM the following:

a. ENSURE the following:

1. No.2 FRV control is in Master Manual control

2. S/G level is at desired setpoint

b. CHECK the following:

1. REG VLV, LIC-5269, controller in AUTO (green light, lit)

BOP

2. BYPASS LIC-5216, controller in AUTO (green light, lit)

c. ENSURE the following:

1. MSTR, LIC-5274, controller level setpoint equal to actual SG level by adjust thumbwheel on MSTR, LIC-5274, controller as necessary

2. Feed flow and steam flow are matched

d. PRESS MSTR, LIC-5274, controller A pushbutton and ENSURE green light, lit.

e. IF steam flow greater than 945,000 lbm/hr (about 15% power), CHECK yellow 3E light below M pushbutton on MSTR, LIC-5274, controller, lit (3 element control).

f. N/A

g. N/A

h. As necessary, ADJUST MSTR, LIC-5274, controller level setpoint and MAINTAIN No. 2 SG level within desired operating band with No. 2 FRV.

Examiner Note: OP 2321, Main Feedwater System, Section 4.7, Shifting SGFP Speed Control Mode 8 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior

1. To place A SGFP in automatic speed control, PERFORM the following:

a. ADJUST speed as necessary to achieve one of the following by using the SPEED LOWER or RAISE pushbuttons:

Difference between actual speed and auto speed setpoint less than or equal to 100 rpm AND discharge pressure greater than the Minimum Discharge Pressure Setpoint Actual pump discharge pressure within 25 psig of the Minimum Discharge Pressure Setpoint AND actual speed greater than Auto Speed Setpoint

b. PRESS CONTROL AUTO pushbutton and ENSURE AUTO pushbutton, lit.

2. To place A SGFP in automatic speed control, PERFORM the following:

a. ADJUST speed as necessary to achieve one of the following by using the SPEED LOWER or RAISE pushbuttons:

Difference between actual speed and auto speed setpoint less than or equal to 100 rpm AND discharge pressure greater than the Minimum Discharge Pressure Setpoint Actual pump discharge pressure within 25 psig of the Minimum Discharge Pressure Setpoint AND actual speed greater than Auto Speed Setpoint

b. PRESS CONTROL AUTO pushbutton and ENSURE AUTO pushbutton, lit.

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

9 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Event #4 Control Element Assembly #68 drop Rapid Downpower Simulator Operator: When directed by Lead Examiner, Insert Trigger #4 RD0368, #68 Control Element Assembly drop Indications:

Multiple C-04 alarms Lowering RCS temperature Examiner Note: Examiner Note: OP 2585, Immediate Operator Actions Takes immediate operator actions for a dropped CEA

1. CHECK only one CEA dropped.

BOP

2. LOWER main turbine load to stabilize TCOLD.

3. Slowly RESTORE Tc within +/ - 2 F of program.

Review AOP 2585 actions with BOP SRO Go To AOP 2556, CEA Malfunctions.

Examiner Note: AOP 2556, CEA Malfunctions

1. CHECK Reactor Trip Criteria Met - NOT met Two or more CEAs are dropped OR One CEA is dropped, and one or more CEAs are misaligned GREATER THAN 10 Steps, but less than 20 Steps OR SRO Two or more CEAs are Untrippable

2. Stabilize The Plant

3. Notify The Following Of Plant Conditions:

I&C OMOC RE

4. Check CEA Dropped Attachment D, Dropped or Misaligned CEA First two steps completed in AOP 2585

1. RECORD CEA Drop Time __________

SRO 2. RECORD CEA number __________

3. Using ATTACHMENT F, CEA Positions Data Sheet, RECORD CEA Positions In Accordance With Tech Spec Surveillance Requirement: 4.1.3.1.1 10 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Power Level > 70%

SRO Enter LCO 3.1.3.1.A.1 Use AOP 2575 to reduce power to < 70% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Examiner Note: LCO 3.1.3.1.A.1 LCO 3.1.3.1 CEA POSITION All CEAs shall be OPERABLE with each CEA of a given group positioned within 10 steps (indicated position) of all other CEAs in its group, and the CEA Motion Inhibit and the CEA Deviation Circuit shall be OPERABLE.

APPLICABILITY: MODES 1*(1) and 2(1).

ACTION:

INOPERABLE EQUIPMENT REQUIRED ACTION A. One or more CEAs trippable and A.1 Reduce THERMAL POWER to < 70%

misaligned from all other CEAs in its group of the maximum allowable THERMAL by > 10 steps and < 20 steps. POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore CEA(s)

OR misalignment within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or otherwise be One CEA trippable and misaligned from all in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

other CEAs in its group by 20 steps.

Examiner Note: AOP 2575, Rapid Downpower, is entered. (CEA motion NOT used due to dropped CEA)

SRO Perform notifications ATC Initiate forcing sprays SRO Determine Reactivity Plan Availability Borate from RWST using 2 Charging Pumps BOP Set up Turbine controls (Attachment G)

ATC Borate from the RWST

1. Reduce turbine load when effects of boron are seen.

BOP

2. Maintain TCOLD within 2 °F of program Maintain VCT parameters ATC Level 70 - 90%

Pressure < 30 psig CREW Maintain parameters as specified in Attachment A When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

11 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Event #5 Excess Steam Demand (#2 S/G, outside CTMT),

Event #6 Failure of Turbine trip Event #7 Bus 24D fault A Aux. Feedwater Pump trip Turbine Driven Feed Pump trip Simulator Operator: When directed by Lead Examiner, Insert Trigger #7 SG02B, #2 S/G ESD ACTIVE (0.9)

Indications:

Lowering RCS pressure and temperature Increasing Enclosure Building P (until Blowout panels open, then P lowers)

Examiner Note: Crew trips reactor and enters EOP 2525, Standard Post Trip Actions Reactivity Control Reactor Trip ATC Ensure Reactor Trip Reactivity Control Turbine Trip Ensure Turbine trip RESPONSE NOT OBTAINED BOP PERFORM the following:

a. TRIP turbine.

b. IF turbine can NOT be tripped, THEN CLOSE MSIVs.

Maintenance of Vital Auxiliaries

a. CHECK vital and non-vital busses energized.

24D - DEAD RESPONSE NOT OBTAINED BOP

a. IF EITHER bus 24C or 24D is not energized THEN PERFORM ALL of the following for associated bus

6) IF the diesel generator output breaker can not be closed, THEN TRIP the Diesel Generator 12 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Maintenance of Vital Auxiliaries

b. CHECK that BOTH facilities of service water are operating.

RESPONSE NOT OBTAINED No Facility 2 Service Water is available BOP

c. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

RESPONSE NOT OBTAINED

c. IF a service water pump is not running, THEN PLACE the associated RBCCW pump in PULL TO LOCK.

RCS Inventory Control Pressurizer level < 20%

a. Pressurizer level is between 20 to 80%, trending to 35 to 70%.

ATC RESPONSE NOT OBTAINED Actions taken to start 3rd charging pump and secure Letdown

b. RCS subcooling > 30 F RCS Pressure Control

a. CHECK that pressurizer pressure is 1900 to 2350 psia, trending to 2225 to 2300 psia.

RESPONSE NOT OBTAINED OPERATE the Pressurizer Pressure Control System. Manually OPERATE ATC pressurizer heaters and spray valves.

IF pressurizer pressure is less than 1714 psia AND SIAS actuated, THEN ENSURE ONE RCP in each loop is stopped.

TCOA: IF Pressurizer pressure lowers to less than the minimum of Fig. 2 RCP NPSH Curve THEN STOP ALL RCPs Core Heat Removal ATC a. CHECK at least 1 RCP is operating, AND loop T < 10 F

b. RCS subcooling > 30 F 13 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Critical Task: STPA-06, Establish RCS heat removal, Start the Turbine Driven AFW pump.

RCS Heat Removal

a. At least one S/G has BOTH of the following conditions met:

Level 10% to 80%.

Main feedwater or TCOA: TWO auxiliary feedwater pumps operating to restore level between 40% and 70%.

BOP RESPONSE NOT OBTAINED

a. RESTORE level to between 40% to 70% in at least ONE steam generator using ANY of the following:

TDAFW Pump. Refer To Appendix 6, TDAFW Pump Normal Startup.

b. RCS TCOLD is being maintained between 530 F to 535 F RESPONSE NOT OBTAINED (no actions to take)

Critical Task: ESDE-04, Isolate AFW to the affected S/G.

c. BOTH S/G pressures are 880 to 920 psia.

RESPONSE NOT OBTAINED c.1 IF ANY steam generator pressure is less than 572 psia AND an excess steam demand event is in progress, THEN PERFORM the following to isolate AFW to the most affected SG:

BOP 1) PLACE BOTH auxiliary feed OVERRIDE/MAN/START/RESET hand switches in PULL TO LOCK.

2) CLOSE applicable Aux Feed Reg valve:

2-FW-43A 2-FW-43B Critical Task: ESDE-05, Establish RCS temperature control.

c. BOTH S/G pressures are 880 to 920 psia.

RESPONSE NOT OBTAINED c.3 IF ANY steam generator pressure is less than 572 psia AND an excess steam demand event is in progress, THEN PERFORM the following BOP 1) CLOSE the ADV for the most affected steam generator.

2) IF the most affected steam generator has boiled dry, as indicated by CET temperature rising, THEN OPERATE the ADV for the least affected steam generator to stabilize CET temperature.

14 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Containment Isolation

a. CTMT pressure < 1.0 psig

b. No primary plant radiation monitors have unexplained alarm or indicate an ATC unexplained rise in activity

c. No primary plant radiation monitors have unexplained alarm or indicate an unexplained rise in activity Containment Temperature and Pressure Control ATC a. CTMT temperature < 120 F

b. CTMT pressure < 1.0 psig ATC Perform Appendix 4, Reactor Trip Subsequent Actions BOP Diagnose the event Diagnostic Flowchart directs operator to EOP 2540, Functional Recovery due to:

1. LOAF diagnosed Neither S/G has adequate feed flow SRO Pressurizer Pressure lowering < 1900 psi Subcooling > 30F

2. Excess Steam Demand diagnosed S/G pressure < 880 psi Examiner Note: Crew transitions to EOP 2540, Functional Recovery No SIAS Sample S/Gs US Place H2 Analyzers Perform Resource Assessment Trees (RATS)

Prioritize Safety Functions Resource Assessment Tree Evaluation Reactivity Control RC-1 MET DC Power DC-1 MET AC Power AC-1 MET US Inventory Control IC-1 MET Pressure Control PC-1 MET Heat Removal HR-3 MET Containment Isolation CI-1 MET CTMT Temperature and CTPC-1 MET Pressure Control 15 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior Examiner Note: US performs RATs and determines HR-3 the correct path. The crew transitions to EOP 2540D, Functional Recovery of Heat Removal Check Once Through Criteria ONE steam generator wide range level less than or equal to 70 inches AND the REMAINING steam generator wide range level is less than or equal to 165 inches SRO RCS TCOLD rises uncontrollably by 5°F or more RESPONSE NOT OBTAINED

1. Proceed to step 4 Monitor SG Pressure Block MSI Actuation -N/A SRO Optimize Safety Injection Close Steam Dump Valves and ADVs Restore SG Inventory - USE Appendix 16, LOAF Response.

Examiner Note: Crew transitions to EOP 2541 APP-16, Appendix 16, LOAF Response

1. PERFORM the following:

a. STOP ALL RCPs.

b. PLACE TIC-4165, steam dump TAVG controller, in manual and closed.

ATC

c. PLACE pressurizer spray valve controllers in manual and CLOSE:

HIC-100E HIC-100F

2. Conserve S/G Inventory by closing the following:

a. MS-220A BOP b. MS-220B

c. MS-191A

d. MS-191B

3. When Feed established, limit feed rate to 650 gpm until level shows a rising trend, then BOP feed at any desired rate.

Critical task: HR-01, Establish RCS heat removal 16 of 33

OpTest No.: __ ES20LI4___ Scenario No.: __4__

Time Position Applicants Actions or Behavior

4. No Feed line break indicated

5. No Aux Feed line break indicated

6. Motor driven feed pumps are NOT available

7. Feed not restored

8. Turbine Driven feed pump NOT available

9. Feed not restored

10. Main feedwater pumps NOT available BOP 11. Feed not restored

12. Ensure a Condensate Pump is running

13. Establish a flowpath from the hotwell to the A S/G

a. Open FW-38A, SGFP discharge valve

b. Close SGFP Minimum Flow Valves

c. Open CNM-2, CPF bypass

d. Open A FRV Bypass valve (LIC-5215)

e. Ensure FW-5A open Examiner Note: Feed flow will be established when the Feed Reg Valve Bypass valve is open due to low S/G pressure

14. Block SIAS - N/A

15. Block - MSI ATC

16. N/A

17. Commence Emergency Boration When the event has been addressed to the lead examiners satisfaction, the scenario is complete.

17 of 33

DATE-TIME SHIFT TURNOVER REPORT Today - 0515 PREPARED BY: Unit Supervisor SHIFT 18:00 - 6:00 PLANT STATUS:

Mode: 1 Reactor Power: 100 %

Megawatts: Thermal: 2699.5 MWTH PZR Pressure: 2250 psia Electric: 900 MWe RCS T-AVE: 532 Identified: 0.001 gpm Core Burnup: 1000 MWD/MTU Unidentified: 0.004 gpm Protected Train: A Date/Time: Today/0530 Intake: GREEN Active Tracking Records and Action Statements Equipment/Reason Time in LCO Action Date Action Requirement Time Left LCO OD Compensatory Actions / Temp Logs Watch Open Date Reason Position PLANT SYSTEMS APC System Notes CROSS UNIT SYSTEM STATUS SURVEILLANCES / EVOLUTIONS IN PROGRESS REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES / SPREAD SHEET FOR ADDITIONAL INFO)

Rod Height ARO Xenon Trend Stable Current Boron 594 Blend Ratio SHIFT PRIORITIES

1. Perform SP 2602E, Pressurizer Heater Capacity test

2. Maintain the unit at 100% power 3.

SIMULATOR SCENARIO #5 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 5 Op-Test No.: ES20LI5 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power IC-48, steady state, 962 ppm boron, Equilibrium Xe Ch-X PZR Level OOS, Ch-Y PZR Level in service.

B Charging pump is aligned to 22F (Facility 2)

Turnover: 100% Power, steady state, 24E is aligned to 24C.

Critical Tasks:

1. [RC-3] Establish Reactivity Control (ATC).

2. Depressurize and establish SI flow Event Malf. No. Event Event Description No. Type*

1 N - ATC/US Swap CEDM Cooling Fans 2 FW05 C - BOP/US Condensate Demineralizer high P.

C - ALL 3 Pressurizer Safety Valve leakage Rapid Downpower TS - US CVR50, CH-192, RWST to CVCS, Failed Closed, requires borating from 4 C - ATC/US BAST CVR51 ES02D, 5 M - ALL #2 MSIV goes closed causing a plant trip.

ED06E, On the trip, 480 VAC bus 22E de-energizes causing loss of A Chg.

RD0206 Pump and 2 CEAs fail to insert, requiring Emergency Boration. B 6 RD0207 C - ATC/US CV04B charging pump trips. Requires transition to EOP 2540/2540A, to recover Reactivity Safety Function.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 11

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 2

6. Critical tasks (2-3) 2 Scenario Summary:

The crew will take the shift with the unit at 100% power, steady state, P18C RTO Event 1: The ATC swaps CEDM Cooling fans in accordance with OP2313A, CEDM Cooling.

Event 2: Condensate Demineralizer P rises. The BOP performs the required actions per AOP 2585, Immediate Operator Actions, to bypass the demineralizers.

Event 3: A RCS Safety Valve starts leaking at 0.125 gpm. The Alarm Response Procedure is entered and the crew determines a safety valve is leaking. The valve is declared inoperable and a plant shutdown required. The crew enters AOP 2575, Rapid Downpower, and commences a plant shutdown.

Event 4: When the ATC attempts to borate from the RWST, CH-192 fails to open, requiring the operators to borate from the Boric Acid Storage Tanks.

Event 5: #2 MSIV closes causing a plant trip.

Event 6: Vital 480 VAC bus 22E will de-energize on the trip (loss of A charging pump) 4 CEAs will fail to insert requiring Emergency Boration. Shortly after the plant trip, the B charging pump trips causing a loss of Emergency Boration. The crew to transitions to EOP 2540/2540A, Functional Recovery of Reactivity Control, and depressurizes the RCS to allow use of the HPSI pumps for Emergency Boration.

The scenario will end at the examiners discretion.

Page 2 of 11

Appendix D Scenario Outline Form ES-D-1 INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

Delay Ramp Event Severity or Final Relative ID Num Description Time Time Trigger Value Value Order MALFUNCTIONS RD0206 CEA SD-6 Stuck fully withdrawn Active 0 RD0207 CEA SD-7 Stuck fully withdrawn Active 0 RD0208 CEA SD-8 Stuck fully withdrawn Active 0 RD0209 CEA SD-9 Stuck fully withdrawn Active 0 RC05A Pressurizer Safety Valve leakage 2 0.125 1 FW05 Condensate Demin HI P 5 min 5 100% 3 C05-C08 MSIV 2 Air Pressure Low 6 Active 4 MS06B MS-64B Spurious Closure 1 min 6 4 ED06E Loss of Bus 22E 30 Active 5 C02-C13 B Charging Pp Lube Oil Pres Lo 30 sec 30 Cry-Wolf 6 CV04B B Charging pump trip 30 sec 30 Active 6 REMOTE FUNCTIONS CVR11 P18B KIRK KEY 22F 0 CVR 10 P18C Status RO 0 CVR50 CH-192 Operational Mode E-0 MANUAL 2 CVR51 RWST Isolation Valve CH-192 (% open) E-0 0% 2 OVERRIDES Page 3 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Event #1 Swap CEDM Cooling fans Examiner Note: OP 2313 CEDM Cooling System, Section 4.1, Operation of CEDM Cooling Fans CHECK the following not lit (ensures RBCCW flow to cooler):

IF starting A CEDM COOLER A FLOW LO" (C-04, window AA-11)

ATC IF starting B CEDM COOLER B FLOW LO" (C-04, window AB-11)

IF starting C CEDM COOLER C FLOW LO" (C-04, window BA-11)

Start a CEDM Cooling fan ATC Secure a different CEDM Cooling fan When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 4 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Event #2 Condensate Demineralizer high P Simulator Operator: Simulator Operator: When directed by Lead Examiner, Insert Trigger #2.

FW05, CONDENSATE DEMIN HI DP (5 minute ramp, 100% severity)

Indications:

CONDENSATE DEMIN SYSTEM TROUBLE (C-05, A-16)

COND DEMIN DP, CND-PDI20B, rising PSID (normally ~ 50 psid)

Examiner Note: Actions are taken without a procedure i.a.w. OP 2585, Immediate Operator Actions.

Open CNM-2, COND DEMIN BYP.

BOP Observe COND DEMIN DP, CND-PDI20B lowering Observe SGFP Suction pressures rising Enter OP 2585, Immediate Operator Actions BOP Ensure actions were taken SRO Dispatch PEO to check ARP 2593E- 017, CONDENSATE POLISHER SYS DIFFERENTIAL PRESSURE HIGH (CPF, window E- 3)

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 5 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Event #3 Pressurizer Safety Valve, RC-200, leakage Rapid Downpower Simulator Operator: When directed by Lead Examiner, Insert Trigger #2.

RC05A, Pressurizer Safety Valve leakage (Severity = 0.125)

Indications:

Annunciator PRESSURIZER SAFETY VALVE RC200 DIS TEMP (C-02/3. A-42)

AVMS RC-200, Z-200, red light A SAFETY VLV DIS TEMP, TI-107 Quench Tank Level and Temperature increase Examiner Note: Alarm Response 2590B-229, PRESSURIZER SAFETY VALVE RC200 DIS TEMP, is entered.

Technical Specification 3.4.2 Verifies Alarm is valid by the following:

Quench tank parameters (C-03)

BOP AVMS (Acoustic Valve Monitor) (RC-05E)

Valve tailpiece temperatures (C-03)

RCS leak rate (PPC)

Refers to Technical Specification 3.4.3, finds it not applicable. PORV is determined not to be leaking.

SRO Determines Safety Valve is inoperable due to leakage, refers to Technical Specification 3.4.2, and determines a plant downpower is required.

LCO 3.4.2 SAFETY VALVES All pressurizer code safety valves shall be OPERABLE with a lift setting* of +/-2500 PSIA 3%.**

APPLICABILITY: MODES 1, 2, 3, and 4 with all RCS cold leg temperatures > 275°F ACTION: With one inoperable pressurizer code safety valve, restore the inoperable valve to SRO OPERABLE status within 15 minutes. If the inoperable valve is not restored to OPERABLE status within 15 minutes, or if two pressurizer code safety valves are inoperable, be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 4 with any RCS cold leg temperature 275°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• The lift setting pressure shall correspond to ambient conditions of the valve(s) at nominal operating temperature and pressure.

• • The lift setting shall be within } 1% following pressurizer code safety valve testing.

When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 6 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Event #4 2-CH-192 Failed Closed Examiner Note: AOP 2575, Rapid Downpower, is entered.

US Perform notifications ATC Initiate forcing sprays ATC Insert Group 7 CEAs BOP Reduce Turbine load SRO Determine Reactivity Plan Availability Borate from RWST using 2 Charging Pumps BOP Set up Turbine controls (Attachment G)

ATC Start 2nd Charging Pump and balance charging & Letdown Examiner Note: When borating from RWST, CH-192, RWST ISOLATOIN VALVE, does not open. The crew is directed to return to step 4 and select boration from the BAST.

Borate From RWST

a. CHECK Boration From RWST -SELECTED

b. CHECK VCT MAKEUP BYPASS,CH-196 - CLOSED (C-02/3)

c. CHECK RWST TO CHG SUCT,CH-504 - OPEN (C-02/3)

ATC

d. OPEN RWST ISOL, CH-192 (C-02/3) -

RESPONSE NOT OBTAINED

d. IF RWST ISOL, CH-192 CANNOT be opened, THEN RETURN TO step 4 to select boration from BAST.

SRO Determine Reactivity Plan Availability Borate from BAST ATC Borate from the BAST

1. Reduce turbine load when effects of boron are seen.

BOP

2. Maintain TCOLD within 2 °F of program Maintain VCT parameters ATC Level 70 - 90%

Pressure < 30 psig CREW Maintain parameters as specified in Attachment A When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 7 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Event #5 MSIV (#2) closes causing a plant trip.

Event #6 4 CEAs will fail to insert requiring Emergency Boration.

Vital 480 VAC bus 22E will de-energize on the trip (loss of A charging pump)

B Charging Pump trip CRITICAL TASK: Manually shut down the reactor. [CT-2 (BOP) & CT-3 (ATC), RC-3]

With more than one CEA not fully inserted on a reactor trip, the ATC is required to ensure boric acid is being injected into the RCS at >/= 40 gpm for the time required to ensure shutdown margin if met. This requires an RCS cooldown (BOP) and de-pressurizing (ATC) to allow HPSI injection flow.

TIME SRO direction to perform:____________

TIME >/= 40 gpm Boric Acid Inj.:____________

Simulator Operator: WHEN directed by Lead Examiner, INSERT Trigger #7 C05-C08, MSIV 2 Air Pressure Low ACTIVE MS06B , MS-64B Spurious Closure ACTIVE (1 minute delay)

Indications:

MAIN STEAM ISOLATION VALVE 2 AIR PRESSURE LO (C-05, C-8)

There are no indications of MSIV air pressure in the Control Room Examiner Note: ARP 2590D-031, MAIN STEAM ISOLATION VALVE 2 AIR PRESSURE LO BOP Opens Alarm Response SRO Dispatch PEO to investigate alarm (MSIV will go closed prior to PEO arriving on the scene)

Examiner Note: #2 MSIV closes after one minute of annunciator alarming Crew recognizes MSIV going closed and manually trips the reactor.

ENSURE Reactor Trip by all the following:

ALL CEAs fully INSERTED.

ATC RESPONSE NOT OBTAINED

b. IF more than ONE CEA is not fully inserted, THEN USE Appendix 3, Emergency Boration, and COMMENCE emergency boration.

Examiner Note: Bus 22E (A Charging pump) de-energizes on the plant trip.

B Charging Pump trips 30 sec. after the plant trip ATC Cannot perform Appendix 3 with no charging pumps available.

BOP Ensure Turbine trip Page 8 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior Reports status of Electrical plant. All busses energized BOP NOTE: Bus 22E is not reported in EOP 2525 BOP Reports status of RBCCW and Service Water. All headers operating.

RCS Inventory Control - met

a. Pressurizer level is between 20 to 80%, trending to 35 to 70%.

ATC RESPONSE NOT OBTAINED No charging, actions taken to secure Letdown

b. RCS subcooling > 30 F RCS Pressure Control - met ATC a. CHECK that pressurizer pressure is 1900 to 2350 psia, trending to 2225 to 2300 psia.

RCS pressure normal Core Heat Removal - met ATC a. CHECK at least 1 RCP is operating, AND loop T < 10 F

b. RCS subcooling > 30 F RCS Heat Removal - met

a. At least one S/G has BOTH of the following conditions met:

Level 10% to 80%.

BOP Main feedwater or TCOA: TWO auxiliary feedwater pumps operating to restore level between 40% to 70%.

b. RCS TCOLD is being maintained between 530 F to 535 F

c. BOTH S/G pressures are 880 to 920 psia.

Containment Isolation - met ATC CTMT pressure < 1.0 psig No rad monitors have unexplained rise or in alarm Containment Temperature and Pressure Control - met ATC CTMT temperature < 120 F CTMT pressure < 1.0 psig ATC Perform Appendix 4, Reactor Trip Subsequent Actions BOP Diagnose the event US Diagnostic Flowchart directs operator to EOP 2540, Functional Recovery, due to Reactivity Control Safety Function not being met.

Examiner Note: Crew transitions to EOP 2540, Functional Recovery Page 9 of 11

Op-Test No.: ES20LI5 Scenario No.: 5 Time Position Applicants Actions or Behavior No SIAS Sample S/Gs US Place H2 Analyzers Perform Resource Assessment Trees (RATS)

Prioritize Safety Functions Resource Assessment Tree Evaluation Reactivity Control RC-3 MET DC Power DC-1 MET AC Power AC-1 MET US Inventory Control IC-2 MET Pressure Control PC-1 MET Heat Removal HR-1 MET Containment Isolation CI-1 MET CTMT Temperature and CTPC-1 MET Pressure Control Examiner Note: US performs RATs and determines RC-3 the correct path. The crew transitions to EOP 2540A, Functional Recovery of Reactivity Control ATC Starts a HPSI Pump Crew Depressurize the RCS ATC Block SIAS Initiation ATC Block MSI Initiation RC-3 Acceptance Criteria Condition 1 Boration in progress at greater than 40 gpm Reactor power dropping CREW SUR negative Condition 2 Reactor power less than 1 x 10-4 %

Reactor power stable or dropping When the event has been addressed to the lead examiners satisfaction, proceed to the next event.

Page 10 of 11

DATE-TIME SHIFT TURNOVER REPORT Today - 0515 PREPARED BY: Unit Supervisor SHIFT 18:00 - 6:00 PLANT STATUS:

Mode: 1 Reactor Power: 100 %

Megawatts: Thermal: 2699.5 MWTH PZR Pressure: 2250 psia Electric: 900 MWe RCS T-AVE: 532 Identified: 0.001 gpm Core Burnup: 1000 MWD/MTU Unidentified: 0.004 gpm Protected Train: A Date/Time: Today/0530 Intake: GREEN Active Tracking Records and Action Statements Equipment/Reason Time in LCO Action Date Action Requirement Time Left LCO OD Compensatory Actions / Temp Logs Watch Open Date Reason Position PLANT SYSTEMS APC System Notes CVCS B Charging Pump aligned to 22F PLCS Channel X level controller OOS CROSS UNIT SYSTEM STATUS SURVEILLANCES / EVOLUTIONS IN PROGRESS REACTIVITY BRIEFING (SEE REACTIVITY THUMBRULES / SPREAD SHEET FOR ADDITIONAL INFO)

Rod Height ARO Xenon Trend Stable Current Boron 962 Blend Ratio SHIFT PRIORITIES

1. Swap CEDM Cooling fans to A & C running

2. Maintain the unit at 100% power 3.