Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML15007A437
Person / Time
Site:	Millstone
Issue date:	10/30/2014
From:	Cote M; Dominion Nuclear Connecticut
To:	Peter Presby; Operations Branch I
Shared Package
ML14043A009	List: ML14107A421; ML14262A252; ML14303A708; ML15007A395; ML15007A419; ML15007A437; ML15008A062; ML15008A196; ML15008A205; ML15008A229; ML15009A074; ML15156A603;
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JOB PERFORMANCE MEASURE ADMIN R0-1

JPM Number: ADMIN R0-1 Rev. __0=---

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN R0-1 Task

Title:

Shutdown Safety Assessment Time to Core Boil System: Administrative Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 20 Task No.(s): NUTIMS 119-01-044 KJA No. 2.1.20 KJA Rating 4.6/4.6 Method of Testing:

Simulated Performance:

- -X- - Actual Performance:

Location:

Simulator: In-Plant:

Classroom:

- -X- - ---- ----

Task Standards: At the completion of this JPM the examinee has determined the appropriate RCS Time to Core Boil.

Required Materials OU-M2-201, Shutdown Safety Assessment Checklist, Rev 9

{procedures, equipment):

General

References:

OU-M2-201, Shutdown Safety Assessment Checklist, Rev 9 JPM based on Bank JPM A1R Rev 1/1 (8/20/2012)

Page 1 of8

JPM Number: ADMIN R0-1 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator Not Applicable Requirements: I I Initial Conditions:

The plant is in MODE 5 on Day 21 of a scheduled 30 day refueling outage.

The core has been reloaded and a total of 72 spent fuel bundles were replaced in the vessel when the core was reloaded.

RCS temperature by T-351X is 110°F.

Train "A" is protected.

Preparations for "Vacuum Fill of the Reactor Coolant System" OP 2301 G are underway.

RCS level is 14 inches above the Hot Leg centerline.

Initiating Cues: The US has directed you to perform an RCS Time to Core Boil calculation per OU-M2-201, Section 3.2, Heatup Calculations.

Page 2 of8

JPM Number: ADMIN R0-1 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (YIN) (S/U)

1. Examinee obtains a copy of OU-M2-201 N/A N "Shutdown Safety Assessment Checklist" and refers to section 3.2 "Heatup Calculations".

Cue:

Comments: Examiner to provide copy of OU-M2-201 to examinee.

I

2. NOTE Examinee reads and acknowledges notes. N I

Notes ...

before ...

Step 3.2 ...

Cue:

Comments:

3. Heatup Calculations NA N Step 3.2 Cue:

Comments:

4. IF a Time to Core Boil determination Examinee refers to Attachment and N is desired, THEN PERFORM the performs instructions Step 3.2.1 following:

a. REFER to Attachment 2, Millstone Unit 2 RCS Time to Boil Calculation, and FOLLOW instructions.

b. RECORD results on Attachment 2.

Cue:

Comments:

Page 3 of8

JPM Number: ADMIN R0-1 Rev. 0

5. NOTE: Examinee reads and understands the N RCS temperature should be obtained from NOTE. Examinee understands that the Note RCS to SOC temperature, T-351X. RCS temperature should be from T-351X.

before Otherwise, unheated junction Att 2, Step thermocouples or CETs may be used (if 1 either is available). If RCS temperature is expected to increase, an RCS temperature of up to 5 °F greater than the current RCS temperature can be used to bound expected conditions.

Cue:

Comments:

6. Record time after reactor shutdown (in Examinee refers to initial conditions and y days), current RCS temperature (°F) and Attachment 2 notes to obtain values and Att 2 Step 1 RCS Water Level (Feet from reactor vessel flange). .

records on Attachment 2:

Reactor shutdown in days = 21 days

Current RCS temperature = 11 0°F

. RCS level = -6 feet Applicant may record actual level of -5.3 feet on data sheet but must use conservative "MULT 2" value of 1.019, associated with -6.0 feet in the calculation of time to boil.

Cue:

Comments: Per notes on Table 2 of Attachment 2, the L-1121evel above hot leg centerline should be based on the mid-loop I reference point (-6.5 feet) and the more conservative value should be used. Since 14 inches above RCS hot leg I centerline corresponds to a value between -5 and -6 feet (-5.33 feet) above the RV flange, the value of -6 feet should 1 be used.

7. Record RCS Heatup Rate from Table 1. Examinee refers to Table 1. Examinee y reads NOTE and uses the conservative Att 2 value of 20 days to obtains a value of Step 2 2.393 °F/min and records the value on Attachment 2 Page 4 of8

JPM Number: ADMIN R0-1 Rev. 0 Cue:

Comments:

8. Determine Core Condition Multiplier, Examinee determines from the initial y MULT1 using one of the following and conditions that the Core was Reloaded, Att 2 Step 3 ..

Record below:

Before Core Offload= 1.000 uses MULT1 of 1.182 and records on Attachment 2 .

Before Fuel Shuffle Complete= 1.000

After start of Core Reload = 1.182

After com_pletion of Fuel Shuffle = 1.182 I Cue:

Comments:

9. Determine Water Level Multiplier, MULT2 Examinee refers to initial conditions, y I I

using one of the following and Record determines RCS loops not filled and refers Att 2 below: to Table 2 using RCS level determined '

Step 4

IF reactor vessel upper plenum AND previously at 14 inches above the Hot steam generator U-tubes are not voided, Leg centerline and obtains a MULT 2 of MULT2 = 2.529 ("RCS Filled" 1.019 and records on Attachment 2.

condition at 7.64 feet) otherwise use MULT2 consistent with RCS level above Using the note about conservative values mid loop reference point from the examinee selects 6" above Hot Leg Table 2. centerline (6" on RCS Wide Range Ll-112). Uses 6 inches instead of 18 inches.

Cue:

Comments:

10. Calculate and record RCS Time to Boil. RCS Time to Boil = MULT1 x MULT2 x y

{(212oF- RCS Temperature (oF)) I RCS Att 2 Heatup Rate (°F/min)}

Step 5 Examinee performs calculations 51.3 min (50 to 52 minutes acceptable)

= 1.182 X 1.019 X {(212°F -110°F) I 2.393°F/min}

And records on Attachment 2 Cue:

Comments: - - --- -

Page 5 of8

JPM Number: ADMIN R0-1 Rev. 0 Terminating Cue: When the time to boil has been calculated, the JPM is complete.

STOP TIME:

Page 6 of8

JPM Number: ADMIN R0-1 Rev. __o __

VERIFICATION OF JPM COMPLETION

Title:

Shutdown Safety Assessment Time to Core Boil Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 7 of8

JPM Number: ADMIN R0-1 Rev.

-- 0 -

EXAMINEE HANDOUT Initial Conditions:

The plant is in MODE 5 on Day 21 of a scheduled 30 day refueling outage.

The core has been reloaded and a total of 72 spent fuel bundles were replaced in the vessel when the core was reloaded.

RCS temperature by T-351X is 110°F.

Train "A" is protected.

Preparations for "Vacuum Fill of the Reactor Coolant System" OP 2301 G are underway.

RCS level is 14 inches above the Hot Leg centerline.

Initiating Cues: The US has directed you to perform an RCS Time to Core Boil calculation per OU-M2-201, Section 3.2, Heatup Calculations.

JOB PERFORMANCE MEASURE Admin R0-2

JPM Number: Admin R0-2 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: Admin R0-2 Task

Title:

Perform ECP Manual Calculation System: NA Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 40 Task No.(s): _N:....:A:....:.-_ _ _ _ _ _ _ _ _ _ _ _ _ _ __

KIA No. KIA System 001, A4.10: KIA Rating _ _ _ 3._5_ _

Method of Testing:

Simulated Performance: Actual Performance: -------- X Location:

Classroom: X Simulator: In-Plant:

Task Standards: The examinee will perform a manual ECP calculation and determine critical boron concentration of 1316 .:t 5 ppm ( 1311 ppm to 1321 ppm) and and will calculate correct limits on CEA position at criticality.

Required Materials: OP 2208,Reactivity Calculations, Rev. 015 (procedures, equipment) ETE-MP-2014-1069, MS2 Cycle 23 Reactor Engineering Curve and Data Book, Rev. 000 ECP Reference Data Sheet, completed with current data ECP Data and Analysis Sheet OP 2208 Attachment 1 ECP Reference Data Sheet with the following information filled in:

OP 2208 Attachment 1 Filled-in Data up to an exposure of 5525 MWDIMTU Date I Time 9110114 I 0800 Power 100%

Page 2 of17

JPM Number: Admin R0-2 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Tavg 572 OF Burn up 4425 MWD/MTU RCS Boron 957 ppm Xenon 2.615%

Samarium 0.780%

Controlling Regulating Group 7 at 180 steps Desired Critical Position CEA Group 7 at 55 steps General

References:

OP 2208, Reactivity Calculations ETE-MP-2014-1069, MS2 Cycle 23 Reactor Engineering Curve and Data Book, Rev. 000 Page 3 of 17

JPM Number: Admin R0-2 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* * *NOTES TO EXAMINER****

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

ISimulator Requirements:

none Initial Conditions:

The plant tripped on 9/13/2014 at 0800

The estimated time of criticality is 9/19/2014 at 1400

CVBURNUP on the PPC is 4522 MWD/MTU

Current boron concentration is 1100 ppm

At the scheduled time of criticality, Tave will be 535°F

Desired critical position: CEA Group 7 at 55 steps Initiating Cue: You are the Unit Reactor Operator. The Unit Supervisor directs you to perform a manual ECP calculation. You are to prepare and complete the ECP Data and Analysis Sheet for approval.

Page 4 of 17

JPM Number: Admin R0-2 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. CHECK the following: Examinee requested information is on N

Reactor Engineering Department has Attachment 1 OP 2208 completed and provided critical position Step 4.1.1 data on Attachment 1, "ECP Reference Data Sheet"

Chemistry Department has been requested to sample and determine present RCS boron concentration Cue:

Comments:

2. All data is recorded and calculated on OP Examinee reads the note and proceeds. N 2208-001, "ECP Data and Analysis Sheet.

OP 2208 Note Cue:

Comments:

3. Refer to Attachment 1 and TRANSFER Examinee copies data from Attachment 1 N Reference Critical Data. to OP 2208-001.

OP 2208 Step 4.1.2 Cue: I Comments:

I

4. Record the following Estimated Status at Examinee records date, time and RCP N Criticality Data: temperature per the initial conditions '

OP 2208

Date and time given.

Step 4.1.3

RCP temperature (Tavg)

9/19/2014, 1400

535°F

- - ~--

Page 5 of 17

JPM Number: Admin R0-2 Rev. 0 Cue:

Comments:

5. OBTAIN present burnup from one of the Examinee obtains present burnup from N following and RECORD: initial conditions. 4522 MWD/MTU OP 2208 * "CVBURNUP" (PPC)

Step 4.1.4

Reactor Engineering Department Cue:

Comments:

6. Unless otherwise specified by Reactor Examinee checks current burnup is less N Engineering Department, CHECK core than 1OOOMWD/MTU from reference.

OP 2208 burnup change from reference data Reference burnup is 4425 MWD/MTU Step 4.1.5 specified on Attachment 1, to present current burnup is 4522 MWD/MTU.

burnup, does not exceed 1,000 MWD/MTU. 4522-4425 =97, which is <1000.

Cue:

Comments:

7. When sample results are obtained, Examinee refers to initial conditions. Boron N RECORD present boron concentration. concentration is 11 00 ppm.

OP 2208 Step 4.1.6 Cue:

Comments:

8. Examinee reads note and continues. N The Desired Critical CEA Position should OP 2208 maintain a minimum rod insertion worth Note between 0.5% to 0.9% for "pull to critical" Cue:

Comments:

9. Refer to Attachment 1 and RECORD Examinee records desired CEA position as N Desired Critical CEA Position. CEA group 7 at 55 steps.

OP 2208 Step 4.1.7 ------

Page 6 of 17

JPM Number: Admin R0-2 Rev. 0 Cue:

Comments:

y

10. DETERMINE Power Defect as follows:

1. RECORD Reference Critical Data Examinee uses Reference Critical Data power value of 100% and determines a I OP 2208 power value. Power Defect of 1.363 Step 4.1.8 2. Refer to RE Curve and Data Book and DETERMINE Power Defect at (Acceptance band 1.347 to 1.379)

Reference Critical Data power value and Reference Burnup.

3. Record Power Defect.

Cue:

Comments:

Page 7 of 17

JPM Number: Admin R0-2 Rev. 0

11. DETERMINE Xenon Defect as follows: Examinee uses reference critical data y

1. RECORD Reference Critical Data xenon worth of 2.615.

OP 2208 xenon worth.

Step 4.1.9 2. Refer to one of the following and Examinee uses RE curve RE-C-01 to DETERMINE estimated xenon worth at determine estimated xenon worth at criticality: criticality of 0.

"Xenon-Samarium Post Trip Report" (printed automatically on Examine calculated xenon defect to be Control room printer following 2.615.

reactor trip)

RE Curve and Data Book

"XENON-SAMARIUM DEMAND" program on PPC

Reactor Engineering Department

3. IF any of the following conditions exist, REQUEST Reactor Engineering Department assistance to account for xenon reactivity worth inaccuracies:

The plant was not at or near full power equilibrium prior to shutdown.

The predicted xenon reactivity worth at the estimated time of criticality is greater than 0.5% (500pcm)

4. RECORD estimated xenon worth at criticality.

5. CALCULATE Xenon Defect as follows and Record:

Reference Estimated Critical Data - xenon = Xenon xenon worth worth Defect Cue:

Comments:

Page 8 of 17

JPM Number: Admin R0-2 Rev. 0

12. DETERMINE Samarium Defect as follows: Examinee records reference critical data y

1. RECORD Reference Critical Data samarium worth from Attachment 1.

OP 2208 samarium worth.

Step 4.1.1 0 I 2. Refer to one of the following and Examinee determines estimated samarium DETERMINE estimated samarium worth at criticality from RE-C-03 to be worth at criticality: 1.131.

"Xenon-Samarium Post Trip Report" (printed automatically on Control 0.780-1.131= -0.351 Room printer following reactor trips)

RE Curve and Data Book Examinee calculated Samarium Defect to

"XENON-SAMARIUM DEMAND" be -0.351.

program on PPC

Reactor Engineering Department I (Acceptance band -0.359 to -0.343)

3. RECORD estimated samarium worth at criticality

4. CALCULATE Samarium Defect as follows and RECORD:

Reference Estimated Critical data - samarium = Samarium samarium worth Defect worth Cue:

Comments:

13. Determine CEA Worth Defect as follows: Examinee obtains Reference Critical Data y

1. Refer to RE Curve and Data Book and CEA Position worth from Attachment 1as OP 2208 Determine CEA worth for the following Gp 7 at 180 steps. Worth at this position is Step 4.1.11 and RECORD: 0.

Reference Critical Data CE Position Examine determines desired critical

Desired Critical CEA Position position as Gp 7 at 55 steps. Worth at this

2. CALCULATE CEA Worth Defect as position is 0. 705.

follows and RECORD:

Reference Desired Examinee calculated CEA defect too be Critical Data - Critical = CEA - 0.705.

CEA Position CEA Position Worth worth worth Defect (Acceptance band -0.707 to -0.703)

Page 9 of17

JPM Number: Admin R0-2 Rev. 0 Cue:

Comments:

14. DETERMINE Boron Defect as follows: Examinee obtains Reference Critical Data y

1. RECORD Reference Critical Data boron concentration from attachment 1.

OP 2208 boron concentration 957 ppm Step 4.1.12 2. RECORD present boron concentration Examinee obtains present boron

3. Refer to RE Curve and Data Book and concentration from initial conditions.

DETERMINE the Inverse Boron Worth 1100 ppm as present burnup 957-11 00= -143

4. RECORD Inverse Boron Worth Examinee determines inverse boron worth

5. CALCULATE Boron Defect as follows of 115.2 (Acceptance band 115.1 to 115.3 and RECORD: ppm).

-143/115.2=-1.241 (Acceptance band -1.242 to -1.240)

Cue:

Comments:

15. DETERMINE Plutonium Buildup worth as Examinee determines plutonium buildup y follows: worth at criticality from RE-E-04 to be OP 2208 1. Refer to RE Curve and Data Book and 0.203.

Step 4.1.13 DETERMINE Plutonium Buildup worth at criticality (Acceptance band 0.199 to 0.207)

2. RECORD Plutonium Buildup worth at criticality Cue:

Comments:

16. DETERMINE the sum of all defects as Examinee enters all previously calculated y follows: reactivity defects.

OP 2208 1. ENTER a// previously calculated Step 4.1.14 reactivity defects. Examinee calculates the sum of defects to

2. CALCULATE the sum of all reactivity be 1.872.

defects and RECORD.

(Acceptance band 1.853 to 1.894)

Cue:

Page 10 of 17

Rev.

JPM Number: Admin R0-2 - -

Comments:

17. DETERMINE the Boron Equivalent of Examinee records the previously y Defects as follows: calculated sum of defects and inverse OP 2208 1. RECORD the following: boron worth on OP 2208-001.

Step 4.1.15

Sum of defects

Inverse Boron Worth at present Examinee calculates boron equivalent:

burn up 1.872 X 115.2 =215.654

2. CALCULATE Boron Equivalent of Defects as follows and RECORD: (Acceptance band 213.280 to 220.685)

Sum of Inverse Boron Boron Defects X Worth = Equivalent Of Defects I Cue:

Comments:

18. There is a reactivity change due to fuel Examinee reads note and continues. N I burn up. If the difference between present OP 2208 burnup and reference burnup is less 200 NOTE MWD/MTU this reactivity change does not need to be accounted for.

Cue:

Comments:

Page 11 of 17

JPM Number: Admin R0-2 Rev. 0

19. I DETERMINE Boron Equivalent of Examinee determines difference in present y Reactivity Change Due to Burnup as burnup and Reference Critical Data OP 2208 I follows: burnup is less than 200 MWD/MTU and Step 4.1.16 1. IF the difference between present records 0.

burnup and Reference Critical Data burnup is less than or equal to 200 MWD/MTU, RECORD "N/A" in this section and Go To step 4.1.17.

2. IF the difference between present burnup and Reference Critical Data burn up is greater than 200 MWD/MTU, Refer ToRE Curve and Data Book and PERFORM the following:

DETERMINE the predicted critical boron concentration at present burnup and RECORD

DETERMINE the predicted critical boron concentration at Reference Critical Data burnup and RECORD.

3. CALCULATE Boron Equivalent of Reactivity Change Due to Burnup as follows and RECORD:

Boron cone Boron cone Boron at present - at reference = equiv burn up Critical Data Reactivity burn up change due to burn up Cue:

Comments:

Page12of17

JPM Number: Admin R0-2 Rev. 0

20. DETERMINE Required Boron Change for Examinee records Boron Equivalent of y Criticality as follows: Defects: 215.654 OP 2208 1. RECORD the following:

step 4.1.17

Boron Equivalent of Defects Examinee records Boron Equivalent of

IF any Boron Equivalent of Reactivity Change due to Burnup: 0 Reactivity Change Due to Burnup

2. CALCULATE required boron change Examinee calculates Required Boron as follows and RECORD: change: 215.654 Boron Boron Equivalent Required Equivalent + of Reactivity = Boron (Acceptance band 213.280 to 220.685)

Of Defects Change due to Change Burn up Cue:

Comments:

21. DETERMINE Critical Boron Concentration Examinee records present concentration y as follows: from initial conditions: 1100 ppm OP 2208 1. RECORD the following:

Step 4.1.18

Present boron concentration

Required boron change Examinee calculates critical boron

2. CALCULATE critical boron concentration: 1100 + 215.654 = 1315.654 concentration as follows and RECORD: (Acceptance band 1311 to 1321)

Present Required Critical Boron + Boron = Boron Concentration Change Concentration Cue:

Comments: - - * - - -

Page 13 of 17

JPM Number: Admin R0-2 Rev. 0

22. DETERMINE Limits on CEA Position at Examinee r~cords desired critical CEA y Criticality as follows: position worth: 0. 705 OP 2208 1. RECORD calculated CEA worth for Step 4.1.19 Desired Critical CEA position Examinee calculates CEA worth at

2. CALCULATE CEA worth at minimum minimum insertions: 0. 705 - 0.5 = 0.205 insertion as follows and RECORD:

CEA worth CEA worth Examinee calculates CEA worth at for desired - 0. 5% = at minimum =

maximum insertion: 0.705 + 0.5 1.205 Critical CEA insertion Position Examinee refers toRE Curve RE-D-01

3. CALCULATE CEA worth at maximum and determines CEA position for insertion as follows: minimum insertion of 0.205% delta rho:

CEA worth CEA worth Group 7 at 135 steps for desired + 0. 5% = at maximum (Acceptance band 130 to 140)

Critical CEA insertion Position Examinee refers to RE Curve RE-D-01

4. Refer to RE Curve and Data Book and and determines CEA position for PERFORM the following: maximum insertion of 1.205% delta rho:

DETERMINE CEA position (group Group 6 at 78 steps and step) at minimum insertion and (Acceptance band 72 to 84)

RECORD

DETERMINE CEA position (group and step) at maximum insertion and RECORD

IF CEA position at maximum insertion is below 0% POlL, RECORD CEA Group 4 at 72 steps.

Cue:

Comments:

23. SIGN "ECP Calculated By" section and Examinee completes step. N RECORD date and time OP 2208 Step 4.1.20 Cue: I JPM is complete.

Page 14 of 17

JPM Number: Admin R0-2 Rev. 0 I Comments: I -1 Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page15of17

Form Approval JPM ANSWER KEY- ADMIN R0 DO NOT GIVE TO EXAMINEES Approval Date Effective Date 8/27/09 9/9/09 ECP Data and Analysis Sheet Reference Critical Data Dat1_ Time Power Xenon 9/10/2014 0800 100 % 2.615 %~Q TAVG Burnup Boron Samarium 572 OF 4425 MWD/MTU 957 ppm 0.780 %~Q Controlling Regulating Group 7 at 180 steps Estimated Status at Criticality Date/Time TAVG Burnup (present) 9/10/2014 I 1400 535 OF 4522 MWD/MTU Desired Critical CEA Position Boron (present)

CEAGroup 7 at 55 steps ppm Power Defect Reference Critical Data power value Power Defect at Reference Critical Data Power Defect 100 % power value (RE- E-02)

Xenon Defect Reference Critical Data xenon worth Estimated xenon worth at criticality (PPC, RE-C-01 *, or Rx. Eng.)

Xenon Defect

1 lc~)

2.615 0 % ~Q 2.615 Samarium Defect Reference Critical Data Estimated samarium worth at criticality Samarium Defect samarium worth (PPC, RE-C-03 *, or Rx. Eng.)

0.780 %~Q 1.131 CEA Worth Defect (RE-D-01)*

=======9 I

Reference Critical Data Desired Critical CEA Worth Defect CEA Position worth CEA Position worth 0 0.705 Boron Defect Reference Critical Data Present Inverse Boron Worth boron concentration boron concentration (RE-F-02)*

957 ppm 1100 ppm 115.2

Refer to RE Curve and Data Book OP 2208-001 Rev. 007-03 Page 1 of 3

JPM ANSWER KEY- ADMIN R0 DO NOT GIVE TO EXAMINEES ECP Data and Analysis Sheet Plutonium Buildup Worth Plutonium Buildup Worth at Criticality (RE- E-04)

Pu Buildup Worth 0.203 0.203 % ~Q Sum of Defects CEA Power Samarium Sum of Defect Defect Defects 1.363%~g Boron Equivalent of Defects Sum of Inverse Boron Worth Boron Equivalent Defects (RE-F-02)

of Defects 1.872 % ~g 115.2 ppm/% ~g Boron Equivalent ofReactivity Change Due to Burnup (RE-F-01)*

(N/A if present burnup minus Reference Critical Data burn up is~ 200 MWD/MTU)

I@

================~

Critical Boron Critical Boron Concentration at Boron Equivalent of Reactivity Concentration Reference Critical Data burnup Change Due to Burnup at present burn up ppm ppm Required Boron Change For Criticality Boron Equivalent

==========

Boron Equivalent of Reactivity Required of Defects Change Due to Burnup (if any) Boron Change 215.654 ppm 0 ppm Critical Boron Concentration Present boron concentration Required Boron Change Critical Boron Concentration 1100 ppm 215.654 ppm ppm Limits on CEA Position at Criticality Desired Critical CEA Worth Insertion CEA Position (RE- D-01)

IG)

CEA Position worth r-------,-------~

Group Steps 0.205 %~g Minimum 7 135 0.705 minimum band=> 130 to 140 steps maximum band => 72 to 84 steps OP 2208-001 Rev. 007-03 Page 2 of3

JPM Number: Admin R0-2 Rev. 0 VERIFICATION OF JPM COMPLETION

Title:

Perform ECP Manual Calculation Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 16 of 17

Attachment 1 ECP Reference Data Sheet (Sheet I of I)

The following is recommended for use as reference data in support of OP 2208-001, ECP Data and Analysis Sheet, up to an exposure of MWD/MTU:

Date/Time 9/10/14 1 0800 Power 100 %

572 Burn up 4425 MWD/MTU RCS Boron _ _957 _ _ _ ppm Xenon 2.615 Samarium 0.780 %8g Controlling 7 at 180 steps Regulating Group Current version of ECP software - 18.0.0 MP2 Data File CKSUM -----------

Desired Critical Position: CEA group 7 at

- - steps Boron-10 atom percent for reactor startup following Hot Zero Power Shutdown _ _ _ _ a/o I Boron -10 atom percent for reactor startup following Cold Shutdown _ _ _ _ a/o Reactivity Bias for reactor startup pcm Performed By:

Date Reviewed By:

Date The most recently completed attachment is retained in RE Cw1'e and Data Book.

OP 2208 Level of Use STOP THINK REVIEW Rev. 015-01 Continuous 35 of 48

JPM Number: Admin R0-2 Rev. __0=----

EXAMINEE HANDOUT Initial Conditions:

The plant tripped on 9/13/2014 at 0800

The estimated time of criticality is 9/19/2014 at 1400

CVBURNUP on the PPC is 4522 MWD/MTU

Current boron concentration is 1100 ppm

At the scheduled time of criticality, Tave will be 535°F

Desired critical position: CEA Group 7 at 55 steps Initiating Cue: You are the Unit Reactor Operator. The Unit Supervisor directs you to perform a manual ECP calculation. You are to prepare and complete the ECP Data and Analysis Sheet for approval.

JOB PERFORMANCE MEASURE ADMIN R0-3

JPM Number: ADMIN R0-3 Rev. ----'0'-----

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN R0-3 Task

Title:

Borated Water Sources Monthly Surveillance System: Administrative Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 20 Task No.(s): NUTIMS 119-01-044 KIA No. 2.2.12 K/ARating 3.7/4.1 Method of Testing:

Simulated Performance: - -X- - Actual Performance: - - - -

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, documented findings on surveillance form SP 2601 A-009, determines that each individual BAST concentration is not sufficient for functionality per the TRM and determines 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 (procedures. equipment): (Steps 4.2.1 thru 4.2.8 circle/slashed)

SP 2601A-009, Surveillance Form, Borated Water Sources Verification, Monthly (Steps 4.2.8b and c initialed)

Unit 2 Technical Specifications And Bases 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)

General

References:

Unit 2 Technical Specifications And Bases Unit 2 Technical Requirements Manual Page 1 of 11

JPM Number: ADMIN R0-3 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER** * *

1. Critical steps for this JPM are indicated with a "Y'. For the examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly.

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

3. If necessary, question examinee for details of simulated actions/observations

{I.e. "What are you looking at?" or "What are you observing?").

ISimulator Requirements:

None Initial Conditions:

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

The Shift Manager discovered that the Monthly Borated Water Source Verification surveillance was missed and has directed performance of the surveillance.

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 92.9%.

Steps 4.2.1 through 4.2.8 of SP-2601 A 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 1755 ppm Initiating Cue: The Unit Supervisor directs you to perform SP2601A Borated Water Sources Verification Monthly Surveillance, beginning at Step 4.2.9.

Document results on Surveillance Form SP 2601A-009.

Page 2 of 11

JPM Number: ADMIN R0-3 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. Examinee obtains the copy of SP 2601A, N/A N Borated Water Sources Verification and associated documentation SP-2601-009 Cue:

Comments: Examiner to provide copy of procedure and form to examinee.

2. RECORD new "A" BAST boron Examinee fills in concentration in wt% y concentration (wt% boric acid, and, if (3.2%) and ppm (5595 ppm) on the Step 4.2.9 provided, ppm boron) on SP 2601A-009. surveillance form from initial conditions.

Cue:

Comments:

3. lE needed for PPC calculator AND not N/A N provided by Chemistry Department, CONVERT "A" BAST boron concentration Step 4.2.10 wt% to ppm as follows and RECORD on SP 2601A-009:

ppm =wt% x 1748.4 ppm/wt%

Cue:

Comments: Chemistry has already provided concentration in both units. The PPC calculation is not available.

4. RECORD "A" BAST level (%) from PPC on Examinee records "A" BAST level y SP 2601A-009. (76.3%) on the surveillance form from Step 4.2.11 the given data Cue:

Comments: - - -

Page 3 of 11

JPM Number: ADMIN R0-3 Rev. - - 0

5. CALCULATE "A" BAST volume in gallons Calculates "A" BAST volume (4345 to y as follows and RECORD on SP 2601A-009: 4360 gallons) and records on SP 2601A-Step 4.2.12 009.

Calculated BAST volume (gals)= (Level%

+ 100) x 5,706 (gals)

Cue:

Comments:

6. NOTE Reads the note. N 10% level is the minimum BAST level for Note reliable charging pump suction. 685 before gallons (10% disallowed+ 2% instrument Step 4.2.13 error) is subtracted from the tank volume to calculate usable volume.

Cue:

Comments:

7. Calculate usable "A" BAST volume as Calculates usable "A" BAST volume (3660 y follows and RECORD on SP 2601A---009: to 3675 gallons) and records on SP Step 4.2.13 2601A-009.

Usable "A" BAST volume (gals) =

Calculated volume --- 685 (gals)

Cue:

Comments:

8. RECORD the most recently determined Records the RWST concentration (1755 y RWST boron concentration on SP 2601A--- ppm) on SP 2601-009.

Step 4.2.14 009, from SP 2601A---001, or control board marker (C---01 ).

Cue:

Comments: RWST concentration[.>rovided in initial conditions. __ --

Page 4 ofll

JPM Number: ADMIN R0-3 Rev. ___ 0 _

9. COMPARE "A" BAST boron concentration Determines "A" BAST concentration and y and usable volume to one of the following usable volume do NOT fall within the Step 4.2.15 acceptance criteria and INITIAL SP 2601A-- acceptable operating zone specific in TRM

-009: Figure 3.1-1.

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

Within acceptable range determined by concentration falls close to the 2200 ppm PPC "MINIMUM BAST VOLUME RWST line. I CALCULATION" display from "PRI SYS" menu Cue:

Comments: Per initial conditions, the PPC Minimum BAST Volume Calculation is not available.

10. lE boron concentration and usable volume Determines CR is required. Determines N is not within Acceptance Criteria, Refer To additional information needed to assess Step 4.2.16 Attachment 1 and perform required actions. whether action is required per TRM 3.1.2.8 Cue: If necessary (per Attachment 1, Step 3), direct the examinee to continue with the surveillance procedure.

Comments:

11. RECORD "B" BAST boron concentration Examinee fills in concentration in wt% y (wt% boric acid, and, if provided, ppm (2.85%) and ppm (4983 ppm) on the Step 4.2.17 boron) on SP 2601A---009. surveillance form from initial conditions.

Cue:

Comments:

12. lE needed for PPC calculator AND not N/A N provided by Chemistry Department, Step 4.2.18 CONVERT "B" BAST boron concentration wt% to ppm as follows and RECORD on SP 2601A-009:

ppm = wt% x 1748.4 ppm/wt%

Cue:

Comments: Chemistry has already provided concentration in both units. The PPC calculation is not available.

Page 5 of 11

JPM Number: ADMIN R0-3 Rev. _ _ 0_

13. RECORD "B" BAST level (%) from PPC on Examinee records "8" BAST level y SP 2601A-009. {92.9%) on the surveillance form from Step 4.2.19 the given data Cue:

Comments:

14. CALCULATE "B" BAST volume in gallons Calculates "B" BAST volume {5295 to y as follows and RECORD on SP 2601A-009: 5310 gallons) and records on SP 2601A-Step 4.2.20 009.

Calculated BAST volume (gals)= (Level%

+ 100) x 5, 706 (gals)

Cue:

Comments:

15. NOTE Reads the note. N 10% level is the minimum BAST level for Step 4.2.21 reliable charging pump suction. 685 gallons (1 0% disallowed+ 2% instrument error) is subtracted from the tank volume to calculate usable volume.

Cue:

Comments:

16. Calculate usable "B" BAST volume as Calculates usable "B" BAST volume {461 0 y follows and RECORD on SP 2601A---009: to 4625 gallons) and records on SP Step 4.2.21 2601A-009.

Usable "A" BAST volume (gals)=

Calculated volume --- 685 (gals)

Cue:

Comments: - - - - -

Page 6 of 11

JPM Number: ADMIN R0-3 Rev. 0

17. RECORD the most recently determined N/A N RWST boron concentration on SP 2601A---

Step 4.2.22 009, from SP 2601 A---001, or control board marker (C---01 ).

Cue: I Comments: RWST concentration provided in initial conditions and recorded earlier in Step 4.2.14 I

18. COMPARE "B" BAST boron concentration Determines "B" BAST concentration and y I and usable volume to one of the following usable volume do NOT fall within the Step 4.2.23 acceptance criteria and INITIAL SP 2601A-- acceptable operating zone specific in TRM

-009: Figure 3.1-1.

Within acceptable operating zone specified in TRM Figure 3.1-1 Note: 4625 gallons and 2.85%

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

CALCULATION" display from "PRI SYS" menu Cue:

Comments: Per initial conditions, the PPC Minimum BAST Volume Calculation is not available.

19. 1E boron concentration and usable volume Determines CR is required. Determines N is not within Acceptance Criteria, Refer To additional information needed to assess Step 4.2.24 Attachment 1 and perform required actions. whether action is required per TRM 3.1.2.8 Cue: If necessary (per Attachment 1, Step 3), direct the examinee to continue with the surveillance procedure.

Comments:

20. NOTE Reads the note. N

1. Input to the PPC calculator requires Step 4.2.25 boron 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.

Cue:

Comments: --- - -

Page 7 of 11

JPM Number: ADMIN R0-3 Rev. 0

21. !E "A" OR "B" BAST is not within TRM N/A N Figure 3.1---1 or PPC calculation, Step 4.2.25 PERFORM the following:

Cue:

Comments:

22. CALCULATE the combined usable volume Determines combined usable volume of y (Vf) of both BASTs in gallons as follows and =

both BASTs, Vf 8185 to 8385 gallons Step RECORD on SP 2601A---009:

4.2.25.a Vf (gals)= Usable "A" BAST volume (step 4.2.13) +Usable "B" BAST volume (step I 4.2.21) I Cue:

Comments:

23. CALCULATE the final boron concentration Determines Cf = 3 .:!:. 0.01 wt % y (Cf) of the combined BASTs as follows Step and RECORD on SP 2601 A---009:

4.2.25.b Cf (wt%) = Ca x Va + Cb x Vb VfVf Where:

Ca ="A" BAST cone (wt%) (step 4.2.9)

Va =Usable "A" BAST volume (gals)

(step 4.2.13)

Cb = "B" BAST cone (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: - - -

Page 8 of 11

JPM Number: ADMIN R0-3 Rev. 0

24. COMPARE combined BAST volume and Compares values. N boron concentration to TRM Figure 3.1---1 Step or PPC calculation and INITIAL SP 2601A--

4.2.25.c -009.

Cue:

Comments:

25. IF "A" AND "B" BAST combined volume and Determines surveillance acceptance y boron concentration is not within TRM criteria met. Combined usable volume Step Figure 3.1---1 or PPC Acceptance Criteria, sufficient to meet requirements of TRM 4.2.25.d Refer To Attachment 1 and perform 3.1.2.8 Figure 3.1-1. No action required required actions. per TRM 3.1.2.8.

Note: 1720 ppm in RWST is higher than necessary with 8185 gallons BAST combined volume at 2.99% concentration Cue:

Comments:

Terminating Cue: When the surveillance is complete, the JPM is complete.

STOP TIME:

Page 9 of 11

JPM Number: ADMIN R0-3 Rev. -~0=----

VERIFICATION OF JPM COMPLETION

Title:

Borated Water Sources Monthly Surveillance Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes No X Validated Time (minutes): XX Actual Time to Complete (minutes): _ _ __

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 10 of 11

JPM Number: ADMIN R0-3 Rev. __oc...__

EXAMINEE HANDOUT Initial Conditions:

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

The Shift Manager discovered that the Monthly Borated Water Source Verification surveillance was missed and has directed performance of the surveillance.

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 92.9%.

Steps 4.2.1 through 4.2.8 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 1755 ppm Initiating Cue: The Unit Supervisor directs you to perform SP2601A Borated Water Sources Verification Monthly Surveillance, beginning at Step 4.2.9.

Document results on Surveillance Form SP 2601A-009.

JOB PERFORMANCE MEASURE ADMIN R0-4

JPM Number: ADMIN R0-4 Rev. __1__

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN R0-4 Task

Title:

Review RWP and Survey Map System: Administrative Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMS 404-01-004 KIA No. 2.3.7 KIA Rating _ _ 3._5__

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 reviewed the applicable RWP and survey map and determined the radiological requirements to perform the assigned task.

Required Materials Operations Blanket RWP No. 2140002 (procedures. equipment): HP Valve Locator (2 pages)

General

References:

RPM 5.2.2, Basic Radiation Worker Responsibilities Page 1 of6

JPM Number: ADMIN R0-4 Rev. 1

- - - 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

Initial Conditions:

The unit commenced a refueling outage 10 days ago.

The plant is in MODE 6.

A letdown heat exchanger post-maintenance tag removal and walkdown is required.

Based on previous experience, the walkdown is estimated to take 15 minutes.

Your available dose is 1000 mR.

Initiating Cues:

You have been directed to verify the Letdown heat exchanger has been properly returned to service following maintenance activities. You are to walk down the Letdown heat exchanger, remove tag and close 2-CH-445, Letdown HX Outlet Header Vent Valve and verify all tagging and maintenance materials have been removed from the heat exchanger area.

State the radiological requirements for entering this area. Include in your discussion:

1. Which RWP task Uob step) is appropriate for this assignment

2. Highest radiation level in the work area (including units of measure)

3. Highest contamination level in the immediate work area (including units of measure)

4. Protective clothing required in the immediate work area (including transition to and from the area)

5. Expected dose for this assignment area (including units of measure)

6. Whether or not a dose rate alarm expected for this task. If yes, identify any required actions.

7. Assuming significant difficulties are encountered, the longest possible stay time for this area, (including units of measure)

The examiner will act as Health Physics (HP) for any related questions.

Page 2 of6

JPM Number: ADMIN R0-4 Rev.

START

- TIME*

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. Review Operations Blanket RWP No. Examinee reviews Operations Blanket N 2140002 and Radiation Survey Figure 21 RWP No. 2140002 and Radiation Survey Figure 21 and answers the following questions:

Cue:

Provide examinee with Operations Blanket RWP No. 2140002 and Radiation Survey Figure 21 .

If required, state that the HP brief is complete .

If required, state that the examinee has obtained a key for the locked high rad area gate .

Comments:

Examinee may state that a briefing with HP is required prior to entry into the work area.

Examinee may also state the need to obtain a key for the locked high rad area gate .

The examinee may perform the following steps in any order.

2. 1. Determine which RWP task Uob Examinee states that task ljob step) No. 1 y step) is appropriate for this is appropriate for this task.

assignment.

Cue:

Comments: There is a lockable gate into the LID HX room, but the room is posted HRA, NOT LHRA.

3. 2. Determine the highest radiation Examinee states that the highest radiation y level in the work area. level in work area is 150 mrlhr.

Cue:

Comments:

4. 3. Determine the highest Examinee states that the highest y contamination level in the work contamination level in this area is less than area. 1,000 DPM/100cm 2

Cue:

Comments:

5. 4. Determine what protective clothing Examinee determines protective clothing N is required in the area. not required.

Cue:

Comments: Closing the vent valve cannot be performed in lab count as an "inspect only" task. Examinee may state the individual items that make up "full PCs" (Cotton liners, Booties, Coveralls, Shoe covers,_Rut~be_l"_gl()_ves_, Modesty ga!"rTlentsL_ _

Page 3 of6

JPM Number: ADMIN R0-4 Rev.

6. 5. Determine the expected dose for 0 Examinee states that the expected y this assignment. dose is 25 mrem.

Cue:

Comments: 100 mrem/hr Dose Rate X 1/4 hrs. (i.e.;15 min.)= 25mr, 100mrem/hr is highest area radiation level. 150mrem/hr is the contact rate on the heat exchanger.

7. 6. Determine a dose rate alarm is Examinee states that the RWP dose rate y expected for this task and, if so, any alarm for this task is 80 mrlhr and that the required actions. general area rate is 100mrlhr, so, Yes a rate alarm IS expected.

Per the RWP, "an *expected* DOSE RATE alarm must be authorized by HP Supervision, and you must be briefed beforehand on proper response to the alarm, and you must sign to acknowledg_e this brief."

Cue:

Comments:

8. 7. Determine the longest possible stay Examinee states that the longest allowable y time for this assignment. stay time by RWP limitations is 12 minutes.

Cue:

Comments: 25 mrem Dose Limit Alarm I 100 mrem/hr Dose Rate shows dose limit alarm reached in ~ hour or 15 minutes.

However, the RWP REQUIRES RCA exit upon reaching 80% of the dose alarm setpoint (20 mrem). At an assumed dose rate of 100 mrem/hr, the 80% exit threshold is reached in 12 minutes.

Terminating Cue: The JPM is complete.

STOP TIME:

Page 4 of6

JPM Number: ADMIN R0-4 Rev. 1 VERIFICATION OF JPM COMPLETION

Title:

Review RWP and Survey Map Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 5 of6

JPM Number: ADMIN R0-4 Rev. 1 EXAMINEE HANDOUT Initial Conditions:

The unit commenced a refueling outage 10 days ago.

The plant is in MODE 6.

A letdown heat exchanger post-maintenance tag removal and walkdown is required.

Based on previous experience, the walkdown is estimated to take 15 minutes.

Your available dose is 1000 mR.

Initiating Cues:

You have been directed to verify the Letdown heat exchanger has been properly returned to service following maintenance activities. You are to walk down the Letdown heat exchanger, remove tag and close 2-CH-445, Letdown HX Outlet Header Vent Valve and verify all tagging and maintenance materials have been removed from the heat exchanger area.

State the radiological requirements for entering this area. Include in your discussion:

1. Which RWP task Uob step) is appropriate for this assignment

2. Highest radiation level in the work area (including units of measure)

3. Highest contamination level in the immediate work area (including units of measure)

4. Protective clothing required in the immediate work area (including transition to and from the area)

5. Expected dose for this assignment area (including units of measure)

6. Whether or not a dose rate alarm expected for this task. If yes, identify any required actions.

7. Assuming significant difficulties are encountered, the longest possible stay time for this area, (including units of measure)

The examiner will act as Health Physics (HP) for any related questions.

JOB PERFORMANCE MEASURE Admin SR0-1

JPM Number: Admin SR0-1 Rev. 0 Facility: Millstone Unit 2 JPM Number: Admin SR0-1 Task

Title:

Review and Approve an ECP Manual Calculation System: ~N~A~---------------------------------------------

Time Critical Task: Yes

No X Alternate Path: Yes X

No Validated Time (minutes): 60 Task No.( s): _N:_A;_;_____________________

KIA No. KlA System 001, A4.1 0: KIA Rating ____3_.9___

Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: X Simulator: In-Plant:

Task Standards: The examinee will perform a review of a manual ECP calculation, identify errors and recalculate the correct critical boron concentration of 1316

!:. 5 ppm (1311 ppm to 1321 ppm) and determine that calculated limits on CEA position at criticality are correct.

Required Materials: OP 2208,Reactivity Calculations, Rev. 015 (procedures, equipment) ETE-MP-2014-1 069, MS2 Cycle 23 Reactor Engineering Curve and Data Book, Rev. 000 ECP Data and Analysis Sheet Provide applicant with a filled out OP 2208 Attachment 1 ECP Reference Data Sheet with the following information:

Data good until 5525 MWD/MTU

Date/Time 9/10/14 I 0800

Power 100%

Tave 572°F

Burnup 4425 MWD/MTU

RCS Boron 957 ppm

Xenon 2.615%

Samarium 0. 780 %

Controlling Regulating Group 7 at 180 steps

JPM Number: Admin SR0-1 Rev. 0

Desired Critical Position: CEA Group 7 at 55 steps General

References:

OP 2208, Reactivity Calculations ETE-MP-2014-1 069, MS2 Cycle 23 Reactor Engineering Curve and Data Book, Rev. 000

* *

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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* * *NOTES TO EXAMINER* * * *

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

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

3. If necessary, question examinee for details of simulated actions/observations

{I.e. "What are you looking at?" or "What are you observing?").

I Simulator none

~equirements:

Initial Conditions:

The plant tripped on 9/13/2014 at 1000

CVBURNUP on the PPC is 4522 MWD/MTU

The estimated time of criticality is 9/19/2014 at 1400

Current boron concentration is 1100 ppm

At the scheduled time of criticality, Tave is 535°F

Desired critical position: CEA Group 7 at 55 steps

The Unit Reactor Operator has manually calculated an ECP for the estimated time of criticality Initiating Cue: You are the Unit Supervisor. Per OP-2208, Steps 4.1.21 and 4.1.22, approve the ECP, record date and time, and record any comments concerning the ECP in the Remarks section. For any errors identified, recalculate the ECP.

JPM Number: Admin SR0-1 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. CHECK the following: Examinee requested information is on N

Reactor Engineering Department has Attachment 1 OP 2208 completed and provided critical position Step 4.1.1 data on Attachment 1, "ECP Reference Data Sheet"

Chemistry Department has been requested to sample and determine present RCS boron concentration Cue:

Comments:

2. All data is recorded and calculated on OP Examinee reads the note and proceeds. N 2208-001, "ECP Data and Analysis Sheet.

OP 2208 Note Cue:

Comments:

3. Refer to Attachment 1 and TRANSFER Examinee copies data from Attachment 1 N Reference Critical Data. to OP 2208-001.

OP 2208 Step 4.1.2 Cue:

Comments:

4. Record the following Estimated Status at Examinee records date, time and RCP N I

Criticality Data: temperature per the initial conditions OP 2208

Date and time given. I Step 4.1.3

RCP temperature (Tavg)

9/19/2014, 1400

535°F Cue:

JPM Number: Admin SR0-1 Rev. 0 Comments:

5. OBTAIN present burnup from one of the Examinee obtains present burnup from N following and RECORD: initial conditions. 4522 MWD/MTU OP 2208 * "CVBURNUP" (PPC)

Step 4.1.4

Reactor Engineering Department Cue:

Comments:

6. Unless otherwise specified by Reactor Examinee checks current burnup is less N Engineering Department, CHECK core than 1OOOMWD/MTU from reference.

OP 2208 burn up change from reference data Reference burnup is 4425 MWD/MTU Step 4.1.5 specified on Attachment 1, to present current burnup is 4522 MWD/MTU.

burn up, does not exceed 1,000 MWD/MTU. 4522-4425 = 97, which is <1000 Cue:

Comments:

7. When sample results are obtained, Examinee refers to initial conditions. Boron N RECORD present boron concentration. concentration is 1100 ppm.

OP 2208 Step 4.1.6 Cue:

Comments:

8. Examinee reads note and continues. N The Desired Critical CEA Position should OP 2208 maintain a minimum rod insertion worth Note between 0.5% to 0.9% for "pull to critical" Cue:

Comments:

9. Refer to Attachment 1 and RECORD Examinee records desired CEA position as N Desired Critical CEA Position. CEA group 7 at 55 steps.

OP 2208 Step 4.1.7 Cue:

Comments:

JPM Number: Admin SR0-1 Rev. 0

10. DETERMINE Power Defect as follows: Examinee uses Reference Critical Data y I

1. RECORD Reference Critical Data power value of 100% and determines a OP 2208 power value. Power Defect of 1.363 Step 4.1.8 2. Refer to RE Curve and Data Book and DETERMINE Power Defect at (Acceptance band 1.347 to 1.379)

Reference Critical Data power value and Reference Burnup.

3. Record Power Defect.

Cue:

Comments:

JPM Number: Admin SR0-1 Rev. 0

11. DETERMINE Xenon Defect as follows: Examinee uses reference critical data y

1. RECORD Reference Critical Data xenon worth of 2.615.

OP 2208 xenon worth.

Step 4.1.9 2. Refer to one of the following and Examinee uses RE curve RE-C-01 to DETERMINE estimated xenon worth at determine estimated xenon worth at criticality: criticality of 0.

"Xenon-Samarium Post Trip Report" (printed automatically on Examine calculated xenon defect to be Control room printer following 2.615.

reactor trip)

RE Curve and Data Book

"XENON-SAMARIUM DEMAND" program on PPC

Reactor Engineering Department

3. IF any of the following conditions exist, REQUEST Reactor Engineering Department assistance to account for xenon reactivity worth inaccuracies:

The plant was not at or near full power equilibrium prior to shutdown.

The predicted xenon reactivity worth at the estimated time of criticality is greater than 0.5% (500pcm)

4. RECORD estimated xenon worth at criticality.

5. CALCULATE Xenon Defect as follows and Record:

Reference Estimated Critical Data - xenon = Xenon xenon worth worth Defect Cue:

Comments:

JPM Number: Admin SR0-1 Rev. 0

12. 1 DETERMINE Samarium Defect as follows: Note: Samarium Defect on the data sheet y

1. RECORD Reference Critical Data is incorrectly shown as a positive value.

OP 2208 samarium worth. The reference critical and estimated Step 4.1.10 12. Refer to one of the following and criticality values were transposed, yielding DETERMINE estimated samarium a value of +0.351, vice the correct value of worth at criticality: -0.351. The applicant needs to identify the

"Xenon-Samarium Post Trip Report" error and correct as below.

(printed automatically on Control Room printer following reactor trips) Examinee records reference critical data

RE Curve and Data Book samarium worth from Attachment 1.

"XENON-SAMARIUM DEMAND" program on PPC Examinee determines estimated samarium

Reactor Engineering Department worth at criticality from RE-C-03 to be

3. RECORD estimated samarium worth at 1.131.

criticality

4. CALCULATE Samarium Defect as 0.780 -1.131= -0.351 follows and RECORD:

Reference Estimated Examinee calculated Samarium Defect to Critical data - samarium = Samarium be -0.351.

samarium worth Defect worth (Acceptance band -0.359 to -0.343)

Cue:

Comments:

13. Determine CEA Worth Defect as follows: Examinee obtains Reference Critical Data y

1. Refer to RE Curve and Data Book and CEA Position worth from Attachment 1as OP 2208 Determine CEA worth for the following Gp 7 at 180 steps. Worth at this position is Step 4.1.11 and RECORD: 0.

Reference Critical Data CE Position Examine determines desired critical

Desired Critical CEA Position position as Gp 7 at 55 steps. Worth at this

2. CALCULATE CEA Worth Defect as position is 0.705.

follows and RECORD:

Reference Desired Examinee calculated CEA defect too be Critical Data - Critical = CEA -0.705.

CEA Position CEA Position Worth worth worth Defect (Acceptance band -0.707 to -0. 703)

JPM Number: Admin SR0-1 Rev. 0 Cue:

Comments:

14. DETERMINE Boron Defect as follows: Note: Data sheet boron is incorrectly y

1. RECORD Reference Critical Data recorded as 975 ppm. The applicant needs OP 2208 boron concentration to identify the error and calculate as shown Step 4.1.12 2. RECORD present boron concentration below.

3. Refer to RE Curve and Data Book and DETERMINE the Inverse Boron Worth Examinee obtains Reference Critical Data as present burnup boron concentration from attachment 1.

4. RECORD Inverse Boron Worth 957 ppm

5. CALCULATE Boron Defect as follows Examinee obtains present boron and RECORD: concentration from initial conditions.

1100 ppm 957-1100=-143 Examinee determines inverse boron worth of 115.2.

-143/115.2 = -1.241 (Acceptance band -1.242 to -1.240)

Cue:

Comments:

15. DETERMINE Plutonium Buildup worth as Examinee determines plutonium buildup y follows: worth at criticality from RE-E-04 to be I OP 2208 1. Refer to RE Curve and Data Book and 0.203. I Step 4.1.13 DETERMINE Plutonium Buildup worth I

at criticality (Acceptance band 0.199 to 0.207)

I

2. RECORD Plutonium Buildup worth at I

criticality Cue:

Comments: - **-- -- - - - * - - - *-

JPM Number: Admin SR0-1 Rev. 0

16. DETERMINE the sum of all defects as Examinee enters all previously calculated y follows: reactivity defects.

OP 2208 1. ENTER a// previously calculated Step 4.1.14 reactivity defects. Examinee calculates the sum of defects to

2. CALCULATE the sum of all reactivity be 1.872.

defects and RECORD.

(Acceptance band 1.853 to 1.894)

Cue:

Comments:

17. DETERMINE the Boron Equivalent of Examinee records the previously y Defects as follows: calculated sum of defects and inverse OP 2208 1. RECORD the following: boron worth on OP 2208-001.

Step 4.1.15

Sum of defects

Inverse Boron Worth at present Examinee calculates boron equivalent:

burn up 1.872 X 115.2 =215.654

2. CALCULATE Boron Equivalent of Defects as follows and RECORD: {Acceptance band 213.280 to 220.685)

Sum of Inverse Boron Boron Defects X Worth = Equivalent Of Defects Cue:

Comments:

18. There is a reactivity change due to fuel ' Examinee reads note and continues. N burnup. If the difference between present OP 2208 burnup and reference burnup is less 200 NOTE MWD/MTU this reactivity change does not need to be accounted for.

Cue: JPM is complete.

Comments: - - - - -~ -

JPM Number: Admin SR0-1 Rev. 0

19. I DETERMINE Boron Equivalent of Examinee determines difference in present y Reactivity Change Due to Burnup as burnup and Reference Critical Data OP 2208 I follows:

Step 4.1.16 1. IF the difference between present burnup is less than 200 MWD/MTU and records 0.

burnup and Reference Critical Data burnup is less than or equal to 200 MWD/MTU, RECORD "N/A" in this section and Go To step 4.1.17.

2. IF the difference between present burnup and Reference Critical Data burnup is greater than 200 MWD/MTU, Refer ToRE Curve and Data Book and PERFORM the following:

DETERMINE the predicted critical boron concentration at present burnup and RECORD

DETERMINE the predicted critical boron concentration at Reference Critical Data burnup and RECORD.

3. CALCULATE Boron Equivalent of Reactivity Change Due to Burnup as follows and RECORD:

Boron cone Boron cone Boron at present - at reference = equiv burn up Critical Data Reactivity burn up change due to burnu12_

Cue:

Comments:

JPM Number: Admin SR0-1 Rev. 0

20. DETERMINE Required Boron Change for Examinee records Boron Equivalent of y I Criticality as follows: Defects: 215.654 '

OP 2208 1. RECORD the following:

step 4.1.17

Boron Equivalent of Defects Examinee records Boron Equivalent of

IF any Boron Equivalent of Reactivity Change due to Burnup: 0 Reactivity Change Due to Burnup

2. CALCULATE required boron change Examinee calculates Required Boron as follows and RECORD: change: 215.654 Boron Boron Equivalent Required Equivalent + of Reactivity = Boron (Acceptance band 213.280 to 220.685)

Of Defects Change due to Change Burnup Cue:

Comments:

21. DETERMINE Critical Boron Concentration Examinee records present concentration y as follows: from initial conditions: 1100 ppm OP 2208 1. RECORD the following:

Step 4.1.18

Present boron concentration

Required boron change Examinee calculates critical boron

2. CALCULATE critical boron =

concentration: 1100 + 215.654 1315.654 concentration as follows and RECORD: (Acceptance band 1311 to 1321)

Present Required Critical Boron + Boron = Boron Concentration Change Concentration Cue:

Comments: - - - - - - - - - - **-- - - - - - **- -- **- ---

JPM Number: Admin SR0-1 Rev. 0

22. DETERMINE Limits on CEA Position at Examinee records desired critical CEA y Criticality as follows: position worth: 0. 705 OP 2208 1. RECORD calculated CEA worth for Step 4.1.19 Desired Critical CEA position Examinee calculates CEA worth at

2. CALCULATE CEA worth at minimum minimum insertions: 0.705- 0.5 = 0.205 insertion as follows and RECORD:

CEA worth CEA worth Examinee calculates CEA worth at for desired - 0. 5% = at minimum =

maximum insertion: 0. 705 + 0.5 1.205 Critical CEA insertion Position Examinee refers to RE Curve RE-D-01

3. CALCULATE CEAworth at maximum and determines CEA position for insertion as follows: minimum insertion of 0.205% delta rho:

CEA worth CEA worth Group 7 at 135 steps for desired + 0. 5% = at maximum (Acceptance band 130 to 140)

Critical CEA insertion Position Examinee refers to RE Curve RE-D-01

4. Refer to RE Curve and Data Book and and determines CEA position for PERFORM the following: maximum insertion of 1.205% delta rho:

DETERMINE CEA position (group Group 6 at 78 steps and step) at minimum insertion and (Acceptance band 72 to 84)

RECORD

DETERMINE CEA position (group and step) at maximum insertion and RECORD

IF CEA position at maximum insertion is below 0% PDIL, RECORD CEA Group 4 at 72 steps.

Cue:

Comments:

23. SIGN "ECP Calculated By" section and Examinee completes step. N RECORD date and time OP 2208 Step 4.1.20 Cue: I JPM is complete.

JPM Number: Admin SR0-1 Rev. 0 I Comments: I I Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

JPM Number: Admin SR0-1 Rev.

-- 0 -

VERIFICATION OF JPM COMPLETION

Title:

Review and Approve an ECP Manual Calculation Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes

- - No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

JPM Number: Admin SR0-1 Rev. _ _co:...___

EXAMINEE HANDOUT Initial Conditions:

The plant tripped on 9/13/2014 at 0800

CVBURNUP on the PPC is 4522 MWD/MTU

The estimated time of criticality is 9/19/2014 at 1400

Current boron concentration is 11 00 ppm

At the scheduled time of criticality, Tave is 535°F

Desired critical position: CEA Group 7 at 55 steps

The Unit Reactor Operator has manually calculated an ECP for the estimated time of criticality Initiating Cue: You are the Unit Supervisor. Per OP-2208, Steps 4.1.21 and 4.1.22, approve the ECP, record date and time, and record any comments concerning the ECP in the Remarks section. For any errors identified, recalculate the ECP.

JOB PERFORMANCE MEASURE ADMIN SR0-2

JPM Number: ADMIN SR0-2 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN SR0-2 Task

Title:

Loss of Containment Closure System: Administrative Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 10 Task No.(s): NUTIMS 119-01-053, 000-04-213 KIA No. 2.1.36 KIA Rating _ _ 4_.1__

Method of Testing:

Simulated Performance: X Actual Performance:

Location:

Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM, the examinee will have identified a loss of Containment (CTMT) closure, entered appropriate Technical Specifications Action Statements (TSAS) and directed actions to complete in-progress irradiated fuel moves in CTMT and the Spent Fuel pool and then suspend all operations involving movement of irradiated fuel assemblies in CTMT.

Required Materials AOP 2515, Loss of Containment Integrity (delay)

(procedures. equipment): P&ID 25203-26005-00002, Feed System Unit 2 Technical Specifications And Bases General

References:

AOP 2515, Loss of Containment Integrity P&ID 25203-26005-00002, Feed System Unit 2 Technical Specifications And Bases Page 1 of8

JPM Number: ADMIN SR0-2 Rev. __a;___

* *

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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

I Simulator None Req Ulrements:

Initial Conditions:

The plant is in MODE 6 with fuel movement 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" SOC HX are in service.

);> T351 Y, SOC Return Temperature is gooF

);> #2 Steam Generator secondary side manways are open for inspection

You are the Unit Supervisor

The Aux Building PEO calls to report that workers erecting scaffolding in the Enclosure Building 38'6" West have accidentally broken off 2-FW-182, #2 Steam Generator Feedwater Header Drain Valve

!Initiating Cue: I Respond to the broken valve as the Unit Supervisor in the Control Room.

Page 2 of8

JPM Number: ADMIN SR0-2 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. Determine impact of broken valve 2-FW- Refers to P&ID, TRM Table 3.6-1 or other y 182, #2 Steam Generator Feedwater documentation and determines that 2-FW-Header Drain Valve, 182 is a containment isolation valve and that the current state is a breach of CTMT closure.

Cue: Provide examinee a copy of AOP 2515 Loss of Containment Integrity after he/she determines that a loss of containment integrity has occurred.

Comments: The review of reference items is not required for success in the JPM. The examinee must determine that this valve I

is a containment isolation valve. I

2. Refer to AOP 2515, Loss of Containment Enters AOP 2515 and directs initial steps N I I

Integrity of AOP 2515.

I Cue: If Unit Supervisor gives directions to Shift Manager, Health Physics or Chemistry, acknowledge directed action of AOP 2515.

Comments: Entry into AOP 2515 is not required for success in this JPM.

3. Perform Step 3 of AOP 2515 Determines that the unit is in MODE 6 with N movement of irradiated fuel assemblies inside containment in progress, and goes to Step 17.

Cue:

Comments: Entry into AOP 2515 is not required for success in this JPM.

4. Perform step 17 of AOP 2515 Directs the Refuel SRO to place ANY fuel y assembly being handled in containment in a safe location.

Cue: If directed to place fuel assembly in "safe location," provide examinee with Examinee Handout #2.

Comments: Entry into AOP 2515 is not required for success in this JPM.

Page 3 of8

JPM Number: ADMIN SR0-2 Rev. - - 0

5. Examinee reads the information provided Directs the Refueling SRO to complete the y I in Examinee Handout #2 fuel assembly movements in Containment I and in the Spent Fuel Pool.

Cue: !

Comments:

6. Perform step 18 of AOP 2515. Directs the Refueling SRO to stop all y operations involving CORE ALTERATIONS or movement of irradiated fuel in containment.

Cue:

Comments: This step and direction may be combined with step 5 above or completed in step 7 below. Entry into AOP 2515 is not required for success in this JPM.

7. Refers to T.S. LCO 3.9.4 for Containment Declares entry into TSAS 3.9.4 and y Penetrations/Refueling Operations ACTION immediately suspends all operations requirement involving movement of irradiated fuel assemblies in the containment.

Cue: If directed to "immediately suspend" all operations involving movement of irradiated fuel assemblies in the containment provide examinee with Examinee Handout #2.

Comments: Entry into Technical Specification 3.9.4 ACTION requirement is required for success in this JPM. The examinee may have already directed the suspension of all irradiated fuel assembly movement in containment and the completion of moves in progress in CTMT and Spent Fuel.

8. IF conditions have been met to provide the Directs the Refueling SRO to complete y JPM Handout #2, then the examinee reads both moves and then stop all operations Examinee Handout #2, involving CORE ALTERATIONS or movement of irradiated fuel in containment.

Cue: If examinee does not provide specific actions for suspending core alterations, provide examinee with Examinee Handout 2. --

Page 4 of8

JPM Number: ADMIN SR0-2 Rev. 0 Comments: I This step may have already been completed if the examinee used AOP 2515. Examinee DOES NOT need to direct completion of moves in progress in CTMT and Spent Fuel Pool and the subsequent stopping of all core alterations twice.

T.S 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 position.

Terminating Cue: When the examiner determines that response actions are complete, then the JPM is complete.

STOP TIME:

Page 5 of8

JPM Number: ADMIN SR0-2 Rev. 0 -

VERIFICATION OF JPM COMPLETION

Title:

Loss of Containment Closure Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 6 of8

JPM Number: ADMIN SR0-2 Rev. 0 EXAMINEE HANDOUT #2 *

EXAMINER NOTE: Provide this to examinee in accordance with CUE in JPM steps.

Initial Conditions:

In the Containment, a used fuel assembly is over its new core location and is ready to be lowered

In the Spent Fuel Pool, a used fuel assembly is in transit to its final SFP location.

Initiating Cue: The Refueling SRO requests guidance on what to do with the fuel assemblies.

JPM Number: ADMIN SR0-2 Rev. 0 -

EXAMINEE HANDOUT Initial Conditions:

The plant is in MODE 6 with fuel movement 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" SOC HX are in service.

).;> T351Y, SOC Return Temperature is gooF

).;> #2 Steam Generator secondary side manways are open for inspection

You are the Unit Supervisor

The Aux Building PEO calls to report that workers erecting scaffolding in the Enclosure Building 38'6" West have accidentally broken off 2-FW-182, #2 Steam Generator Feedwater Header Drain Valve,

!Initiating Cue: I Respond to the broken valve as the Unit Supervisor in the Control Room.

JOB PERFORMANCE MEASURE ADMIN SR0-3

JPM Number: ADMIN SR0-3 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN SR0-3 Task

Title:

Technical Specification Evaluation System: Administrative (Auxiliary Feedwater, AC Power Sources)

Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMS 119-01-044 2.2.40 KIA No. KIA Rating

- -4.7- -

Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: X Simulator: In-Plant:

Task Standards: Identify all required Technical Specification LCO Action Statements and entry and exit times and document on the Examinee Handout.

Required Materials Unit 2 Technical Specifications And Bases (procedures. equipment):

General

References:

Unit 2 Technical Specifications And Bases Page 1 of8

JPM Number: ADMIN SR0-3 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER * * * *

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

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

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

ISimulator

~equ1rements:

None Initial Conditions:

At 0030 the Unit was operating normally in MODE 1 at 100% power with no equipment out of service.

Since that time, the following events have occurred:

>- At 0100, Unit 3 SBO Diesel Generator unavailable (Note: Entry into TRM 7.1.22 Action a. is given on the handout).

>- At 0400, 'A' Diesel Generator was declared inoperable.

>- At 0600, 'B' Diesel Generator was declared inoperable

>- At 0700, 'A' Diesel Generator was returned to operable status.

>- At 1900, Main Steam Supply Valve to Turbine Driven Auxiliary Feed Water Pump (TDAFWP), MS-201 was declared inoperable

>- At 2030, 'B' Diesel Generator was returned to operable status.

>- At 2300, Main Steam Supply Valve to TDAFWP, MS-201 returned to operable status.

Initiating Cue: Identify all Technical Specification LCO required actions and entry/exit times. Document on the Examinee Answer Sheet.

Page 2 of8

JPM Number: ADMIN SR0-3 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. Identify LCO entry for 'A' Diesel Generator Documented entry into LCO 3.8.1.1, y being declared inoperable at time 0400. Required Action b.1, b.2, b.3 and b.5. for one diesel generator inoperable, at time 0400.

After verifying operability (cue below) of the TDAFWP, exit b.3.

Cue: Tell examinee that the TDAWFP has been verified operable by administrative actions. If asked, the Millstone Unit 3 diesel generators are operable.

Comments: There is no required LCO entry for the Unit 3 S80 diesel generator not available. The TRM entry has been entered into the worksheet.

LCO 3.8.1.1 Required Action b.4 is not entered because 14 day outage time specified is not used ( 14 day outage time applies to b. 4 and b.5, b.5 only if you are using it in b.4).

2. Identify LCO entry for '8' Diesel Generator Documented entry into LCO 3.8.1.1 y being declared inoperable at time 0600. Required Action e.1, e.2, and e.3 for two diesel generators inoperable at time 0600. I Cue:

I Comments:

3. Identify LCO 3.8.1.1 Required Actions e.1 Documented exit from LCO 3.8.1.1 y I and e.2 exit conditions met due to 'A' Diesel Required Actions e.1 and e.2 at 0700.

Generator being declared operable at time 0700.

Cue:

Comments: Action e.3 cannot be exited until the '8' EDG is restored. In this case, the time requirement for one inoperable diesel (Required ~ction b) is based on the initial loss of the '8' EDG, which in this case still allows you 71 hours8.217593e-4 days 0.0197 hours 1.173942e-4 weeks 2.70155e-5 months to restore.

Page 3 of8

JPM Number: ADMIN SR0-3 Rev. 0

4. Identify LCO entry for valve MS-201, Main Documented entry into LCO 3.7.1.2 y Steam Supply to TDAFWP P4 inoperable at Require Action a for TDAFWP inoperable time 1900. due to one steam supply being inoperable at time 1900.

Cue:

Comments:

5. Identify that an inoperable TDAFWP Documented entry into LCO 3.8.1.1 y requires re-entry into LCO 3.8.1.1 Required Required Action b.3 at time 1900.

Action b.3 because one diesel generator is still inoperable at time 1900. [Verify the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If this condition is not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .]

Cue:

Comments: Must restore TDAFWP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months because a diesel is inoperable.

6. Identify LCO 3.8.1.1 Required Actions b.1, Documented exit from LCO 3.8.1.1 y b.2, b.3, and e.3, exit conditions met due to Required Actions b.1, b2, b.3, and e.3,

'B' Diesel Generator being declared exit conditions at time 2030.

operable at time 2030.

Cue:

Comments:

7. Identify LCO 3.7.1.2 Required Action a exit Documented exit LCO 3. 7.1.2 Required y conditions met at time 2300. Action a at time 2300 due to steam supply to TDAFWP restored to operable and thus TDAFWP is operable at time 2300 Cue:

Comments: -*----*-*---

Page 4 of8

JPM Number: ADMIN SR0-3 Rev. 0 Terminating Cue: The JPM is complete when the examinee has evaluated Technical Specification requirements and documented the evaluation on the Examinee Answer Sheet.

STOP TIME:

Page 5 of8

JPM Number: ADMIN SR0-3 Rev. 0 VERIFICATION OF JPM COMPLETION

Title:

Technical Specification Evaluation Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 6 of8

JPM Number: ADMIN SR0-3 Rev. 0 EXAMINEE ANSWER SHEET Note: Use one line for each required action (Action c.1 and c.2 etc.)

Technical REQUIRED ACTION ENTRY TIME EXIT TIME Specification TRM 7.1.22 a. 0100 Use additional sheets if needed.

JPM Number: ADMIN SR0-3 Rev. 0 EXAMINEE HANDOUT*

Examiner: Provide Examinee with Answer Sheet from this packet.

Initial Conditions:

At 0030 the Unit was operating normally in MODE 1 at 100% power with no equipment out of service.

Since that time, the following events have occurred:

);> At 0100, Unit 3 SBO Diesel Generator unavailable (Note: Entry into TRM 7.1.22 Action a. is given on the handout).

);> At 0400, 'A' Diesel Generator was declared inoperable.

);> At 0600, 'B' Diesel Generator was declared inoperable

);> At 0700, 'A' Diesel Generator was returned to operable status.

);> At 1900, Main Steam Supply Valve to Turbine Driven Auxiliary Feed Water Pump (TDAFWP), MS-201 was declared inoperable

);> At 2030, 'B' Diesel Generator was returned to operable status.

);> At 2300, Main Steam Supply Valve to TDAFWP, MS-201 returned to operable status.

Initiating Cue: Identify all Technical Specification LCO required actions and entry/exit times. Document on the Examinee Answer Sheet.

JOB PERFORMANCE MEASURE Admin SR0-4

JPM Number: Admin SR0-4 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: Admin SR0-4 Task

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit System: Radiation Control Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMs #119-02-026 KIA No. 2.3.6 KIA Rating 3.8 Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: Simulator: In-Plant:

- -X- - ---- -----

Task Standards: The examinee will review the discharge permit and identify a plant operating condition that will NOT allow authorizing a radioactive liquid waste discharge.

Required Materials:

SP 2617 A Aerated and Clean Radioactive Liquid Waste (procedures, equipment) Discharges, Section 4. 1, Rev 030-05

SP 2864, Attachment 2, Evaluation of Rad Monitor Response Based on Isotopic Mix

OPS Form 2617A-001, Aerated and Clean Radioactive Liquid Waste Discharge, Rev 029-03

Chern Form 2864-1, Millstone Unit 2 Liquid Discharge Permit Number 2000

SP 2852-001, MP2 Liquid Radwaste Eff. Mon. lnop.

surveillance General

References:

SP 2617 A Aerated and Clean Radioactive Liquid Waste Discharges, Section 4.2 Page 2 of8

JPM Number: Admin SR0-4 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET

SP 2864, Attachment 2, Evaluation of Rad Monitor Response Based on Isotopic Mix

OPS Form 2617 A-001, Aerated and Clean Radioactive Liquid Waste Discharge

Chem Form 2864-1, Millstone Unit 2 Liquid Discharge Permit Number 2000 and Data Book, Rev. 000 Page 3 of8

JPM Number: Admin SR0-4 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* * *NOTES TO EXAMINER** * *

1. Critical steps for this JPM are indicated with a "Y'. For the examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly.

ISimulator Req u1rements:

none Initial Conditions:

SP 2617A, Section 4.1; steps 4.1.1 through 4.1.6 were completed by the Aux Building PEO at 0525.

There are NO other radioactive discharges are in progress .

The tide is outgoing .

SG blowdown is 40 gpm on each Steam Generator.

Chemistry sample results are acceptable .

AWMT level is 89% and stable .

100% power, equilibrium, steady state conditions.

RM-9116 was placed in bypass at 0245 this morning due to an instrument failure alarm. Chemistry has been informed.

The AWMT Mixer breaker was tagged for electrical PMs at 0535 this morning.

Chemistry has generated a Liquid Discharge Permit (and associated forms) for the Aerated Waste Monitor Tank.

Initiating Cue: You are to review the discharge permit 'package' and document below what must be accomplished to authorize the discharge.

Page 4 of8

JPM Number: Admin SR0-4 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)_

1. Prior to authorizing the AWMT discharge, Examinee reviews Chem Form 2864-1, N the SM must review Chem. Form 2864-1, Millstone Unit #2 Liquid Discharge Permit Millstone Unit #2 Liquid Discharge Permit No. 2000, and attachments to ensure they No. 2000, when received from the are properly filled out.

Chemistry Department.

Cue: 1

Provide Chern. Form 2864-1, associated attachments, and SP 2617AAerated and Clean Radioactive Liquid Waste Discharges to the examinee.

If the examinee determines that the discharge CANNOT be authorized, ask'Whynot'?

Comments: 1

The mixer was tagged (deenergized) 10 minutes after the AWMT was placed on recirculation. The required recirculation time is 30 minutes with the mixer and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months without the mixer.

With the radiation monitor inoperable, the discharge may be performed provided a second independent sample is analyzed and documented on Chern Form 2852-1. The second set of initials is missing on Chern Form 2852-1.

2. SP 2617A, Section 4.1

Examinee reviews SP 2617A, Aerated I Y WHEN SP 2864-001 (Discharge Permit) is and Clean Radioactive Liquid Waste authorized, SM or US Refer To SP 2617 A- Discharges, and compares the 001 and PERFORM the following: requirements to actual plant conditions

REVIEW plant conditions and stated in the Initial Conditions.

authorize discharge.

Examinee determines that the AWMT

ENSURE no other radioactive 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months recirculation requirement was y discharges are in progress (other than NOT met.

SG blowdown) and initial.

If discharge is to be performed with

Examinee reviews Chem Form 2852-1 y and determines that the second set of radiation monitor not OPERABLE, initials is missing for the second VERIFY 2 independent samples have independent sample.

been analyzed for AWMT, as specified '

Examinee determines that the y on Chem Form 2852-1, Unit 2 Liquid discharge CANNOT be authorized Radwaste Effluent Rad Monitor without the above errors corrected.

Inoperative, and INITIAL.

Cue: I

If the student queries the Chemist about the recirculation time, state that the Chemist was informed that the AWMT was placed on recirculation at 0625 with the mixer. The sample was taken after the required 30 minutes.

(See discharge permit)

If the student queries the Chemist about the second sample, state that the second sample was analyzed; however, the other Chemist forgot to initial Chemistry Form 2852-1.

Page 5 of8

JPM Number: Admin SR0-4 Rev. - - 0 Comments: To successfully complete this JPM, the examinee must determine that the discharge CANNOT be performed for either one of the above reasons.

The mixer was tagged (de-energized) 10 minutes after the AWMT was placed on recirculation. The required recirculation time is 30 minutes with the mixer and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months without the mixer.

Cue: JPM is complete.

Comments:

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 6 of8

JPM Number: Admin SR0-4 Rev. __0:___

VERIFICATION OF JPM COMPLETION

Title:

SRO Review and Approve a Radioactive Liquid Waste Release Permit Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 7 of8

JPM Number: Admin SR0-4 Rev. __0:.....__

EXAMINEE HANDOUT Initial Conditions:

SP 2617 A, Section 4.1; steps 4.1.1 through 4.1.6 were completed by the Aux Building PEO at 0525.

There are NO other radioactive discharges are in progress .

The tide is outgoing .

SG blowdown is 40 gpm on each Steam Generator .

Chemistry sample results are acceptable .

AWMT level is 89% and stable .

100% power, equilibrium, steady state conditions.

RM-9116 was placed in bypass at 0245 this morning due to an instrument failure alarm. Chemistry has been informed.

The AWMT Mixer breaker was tagged for electrical PMs at 0535 this morning.

Chemistry has generated a Liquid Discharge Permit (and associated forms) for the Aerated Waste Monitor Tank.

Initiating Cue: You are to review the discharge permit 'package' and document below what must be accomplished to authorize the discharge.

JOB PERFORMANCE MEASURE ADMIN SR0-5

JPM Number: ADMIN SR0-5 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: ADMIN SR0-5 Task

Title:

Classify the Event and Determine the PAR System: Administrative Time Critical Task: Yes X No Alternate Path: Yes No X Validated Time (minutes): 20 Task No.(s): NUTIMS 305-05-091 KIA No. 2.4.41 KIA Rating _ _ 4_.6__

Method of Testing:

Simulated Performance: X Actual Performance:

Location:

Classroom: X Simulator: In-Plant:

Task Standards: At the completion of this JPM the examinee will have determined the classification of the event, recommended protective action recommendations and properly completed the incident response form.

Reguired Materials MP-26-EPI-FAP06-002, "EAL Tables", Rev. 009 (procedures, eguipment): MP2-26-EPI-FAP07-001, "Incident Report Form", Rev. 001-03 MP-26-EPI-FAP01-001 "Control Room-Director of Station Emergency Operations (CR DSEO)", Rev. 010-01 MP-26-EPA-REF02 "MP2 EAL Technical Basis Document" MP-26-EPI-FAP06, "Classification and PARs", Rev. 009 MP-26-EPI-FAP06-005, "Control Room Protective Action Recommendations", Rev. 004 General

References:

MP-26-EPI-FAP06, "Classification and PARs", Rev. 009 Page 1 of7

JPM Number: ADMIN SR0-5 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER*** *

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

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

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

ISimulator Requirements:

None Initial Conditions: T = 0 min The plant is at 100% power. Wind speed is 12 mph from 33r.

T =1 min Crew observes lowering RCS pressure and increased mismatch between charging and letdown. The US directs a manual trip and implementation of EOP 2525.

T = 9 min EOP 2525 complete:

~ SIAS, CIAS and EBFAS are verified.

~ RCS pressure is at 900 psia and lowering.

~ Pzr level is off-scale low.

T = 10 min The crew enters EOP 2534.

T =14 min The SM I DSEO declares an ALERT.

T =25 min Safety injection has been established.

MSL Rad Monitors, RM 4299A and B, for No.1 S/G are reading 0. 7 Rlhr. Cntmt Hi Range Area Monitors, RM-8240 and 8241, are reading 1300 and 1280 Rlhr.

T = 27 min The crew enters EOP 2540 to address SGTR.

T =47 min RM-8240 and 8241, are reading 19,570 Rlhr.

Containment pressure is 3.2 psi and slowly lowering.

Page 2 of7

JPM Number: ADMIN SR0-5 Rev. 0 Initiating Cue: You are the Shift Manager I DSEO. Classify the event. If applicable, determine the appropriate PAR and notifications. Complete the Incident Response Form (MP-26-EPI-FAP0?-001 ). Inform me when you have made the classification.

NOTE: THIS IS A TIME-CRITICAL JPM.

Page 3 of7

JPM Number: ADMIN SR0-5 Rev. 0 JPM START TIME:

CRITICAL GRA I STEP PERFORMANCE STANDARD (Y/N) DE (S/U). I

1. Examinee obtains MP-26-EPI-FAP06-002 Examinee determines the classification is y I "Millstone Unit 2 Emergency Action Levels" OFFSITE RELEASES, BG1; GENERAL and classifies the event. EMERGENCY - ALPHA Basis for classification, 2 lost barriers, potential loss of the 3rd:

Under CNB4, Potential Loss of Containment Barrier on RM-8240 and 8241 > 1,200 Rlhr indicates

Under RCB4, Loss of Coolant Barrier based on leak greater than charging capacity with entry into 2540.

Under FCB3, Loss of Clad Barrier based on RM-8240/8241 reading >300 Rlhr Begin the EAL clock after the applicant has read the cue.

EAL Classification START TIME EAL Classification STOP TIME Cue:

Comments: Per MP-26-EPI-FAP06, Rev 009, Step 1.4.1 d, "A 15 minute requirement has been established as a reasonable time for assessing and classifying an emergency once indications are available that an EAL initiating condition has been exceeded. After the event has been classified, regulations require the prompt notification of off-site authorities within 15 minutes." - - * - -

Page 4 of7

JPM Number: ADMIN SR0-5 Rev. 0

2. Examinee obtains MP-26-EPI-FAP06-005 Makes PAR to evacuate a S-mile radius -10 y "Classification and PARs" and determines mile downwind from 317° to 339° (Sectors A the PAR. and B).

For conditions warranting a 10-mile PAR OR sheltering of all zones, perform the following:

Contact DEEP dispatcher Identify yourself and read applicable evacuation or shelter recommendations from Section B

IF dose projections or actual dose for thyroid (CDE) is greater than or equal to 5Rem at the site boundary, recommend the State implement Kl strategy for general public (N/A)

Request dispatcher to inform the DEEP Duty Officer that a PAR has been issued.

Log the date and time of notification The State must be notified within 15 minutes after a decision is made to issue or update a PAR.

Begin the notification clock after the applicant has classified the event.

Notification START TIME Notification STOP TIME Cue:

Comments:

Terminating Cue: When the examinee determines that response actions are complete, then the JPM is complete.

JPM STOP TIME:

Page 5 of7

JPM Number: ADMIN SR0-5 Rev. __0:....._..._

VERIFICATION OF JPM COMPLETION

Title:

Classify the Event and Determine the PAR Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 6 of7

JPM Number: ADMIN SR0-5 Rev. 0 -

EXAMINEE HANDOUT Initial Conditions: T = 0 min The unit is at 100% power. Wind speed is 12 mph from 33r.

T = 1 min Crew observes lowering RCS pressure and increased mismatch between charging and letdown. The US directs a manual trip and implementation of EOP 2525.

T = 9 min EOP 2525 complete:

~ SIAS, CIAS and EBFAS are verified.

~ RCS pressure is at 900 psia and lowering.

~ Pzr level is off-scale low.

T = 10 min The crew enters EOP 2534.

T = 14 min The SM I DSEO declares an ALERT.

T = 25 min Safety injection has been established.

MSL Rad Monitors, RM 4299A and B, for No.1 SIG are reading 0. 7 Rlhr. Cntmt Hi Range Area Monitors, RM-8240 and 8241, are reading 1300 and 1280 Rlhr.

T = 27 min The crew enters EOP 2540 to address SGTR.

T=47 min Containment radiation monitors are reading 19,570 Rlhr.

Containment pressure is 3.2 psi and slowly lowering.

Initiating Cue: You are the Shift Manager I DSEO. Classify the event. If applicable, determine the appropriate PAR and notifications. Complete the Incident Response Form (MP-26-EPI-FAP07-001 ). Inform me when you have made the classification.

NOTE: THIS IS A TIME-CRITICAL JPM.

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-1

JPM Number: S-1 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-1 Task

Title:

Respond to Control Element Assembly Malfunction System: Control Rod Drive System Time Critical Task: Yes No X Alternate Path: Yes

-X- No Validated Time (minutes): 20 Task No.(s): NUTIMS 000-04-097 KIA No. 000-003-AA 1.02 KIA Rating 3.6/3.4 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 completed the CEA exercise portion of AOP 2556, CEA Malfunctions, for a CEA lower than all other CEAs in its group, and has recommended that CEA #18 be placed on the HOLD bus following receipt of ACTM TROUBLE alarm.

Required Materials AOP 2556 CEA Malfunctions, Rev. 016-12 (procedures. equipment): ARP 2590C-111, ACTM TROUBLE, Rev. 000-02 General

References:

OP-AA-1 00, Conduct of Operations, Rev. 25, Attachment 2 UNIT 2 Technical Specifications JPM based on Bank JPM 208 (modified)

Page 1 of 12

JPM Number: S-1 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER** * *

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

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

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

Simulator

Initialize to a 100% power IC and perform the following:

Requirements:

Enter RD0318 at a severity of 75 to cause CEA #18 to drop partially into the core then remove malfunction

Perform AOP 2556 steps up to an including 4.15.

Display CVMWTH on C-04 PPC

Place the simulator in freeze

When the examinee is ready, place the simulator in run.

When examinee starts recovering the rod with a 10-step withdraw in JPM step 15, OVERRIDE Annunciator AB-15 on C-04, ACTM TROUBLE," ON".

During JPM step 15, if examinee fails to release the CEA control switch within ten seconds (5 inches of CEA travel) of receiving ACTM TROUBLE alarm, then insert MALF RD0118 to fully drop the rod.

Initial Conditions:

The plant is in MODE 1, at less than 70% power.

CEA #18 dropped into the core.

A recovery of CEA #18 has commenced. All steps of AOP 2556 up to, and including, step 4.15 have been completed.

I&C is in the East DC Switchgear room and will inform you if any problems are seen during the withdrawal.

Initiating Cues:

You have been directed by the Unit Supervisor to recover CEA #18 per AOP 2556 starting at step 4.16.

You are responsible for all operations on C04

All other actions will be handled by other watchstanders.

Examiner will act as the Unit Supervisor.

Page 2 of 12

JPM Number: S-1 Rev. _ _ 0_

START TIME:

CRITICAL GRADE I I

STEP PERFORMANCE STANDARD (YIN) (S/U)

1. MONITOR the following during CEA During CEA movement, the examinee N I movement: observes the following indications:

AOP2556

CEAPDS MONITOR

CEAPDS MONITOR Step 4.16

PPC CEA positions display, CEA

PPC CEA positions display, "CEA"

Core mimic

Core mimic Cue: If asked to provide oversight and peer-checks, acknowledge request and tell examinee to continue.

Comments: Step 4.17 is not applicable.

2. As desired, SELECT applicable CEA group Examinee should select the +/- 15 STEPS N

"+/- 15 STEPS" or "FULL SCALE" on on CEAPDS MONITOR for Group 2 when AOP2556 "CEAPDS MONITOR." initially withdrawing the CEA.

Step 4.18 Cue:

Comments:

3. PRESS MANUAL INDIVIDUAL, Ml and Examinee presses the MANUAL y CHECK light lit INDIVIDUAL, Ml button and observes light AOP2556 lit.

Step 4.19 Cue:

Comments:

4. PRESS applicable group "INHIBIT Examinee presses the Group 2 INHIBIT y BYPASS" and CHECK the following: BYPASS switch and observes it lit and that AOP2556

Appropriate group red "INHIBIT BA-19, CEA MOTION INHIBIT BYP Step 4.20 BYPASS" lit annunciator on C-04 is lit.

"CEA MOTION INHIBIT BYP" annunciator lit (BA-19 on C-04)

(depends on group selected)

Cue: - ------*---

Page 3 of 12

JPM Number: S-1 Rev. 0 Comments:

5. PRESS applicable "GROUP SELECTION." Examinee selects Group 2 by pressing y button 2 and observing it lit.

AOP2556 Step 4.21 Cue:

Comments:

6. LOG entry into Technical Specifications Examinee informs the Unit Supervisor to N LCO 3.1.3.1 Action B.1 (CMI bypassed) log into Technical Specifications LCO AOP2556 3.1.3.1 Action B.1 Step 4.22 Cue: Reply as the Unit Supervisor that the Technical Specifications have been logged.

Comments:

7. NOTE: Examinee reads note and does not N If recovering a Group 7 CEA, while a CMI become concerned during the next step condition exists, "CEA MOTION INHIBIT" when BA-18, CEA MOTION INHIBIT AOP2556 annunciator (BA-18 on C-04) clears when annunciator does not clear when the CEA NOTE system CEA MOTION INHIBIT BYPASS MOTION INHBIT BYPASS button is button is pressed and returns when pushed.

released, until the CMI condition has cleared. For all other groups the annunciator will remain lit until the CMI condition clears.

If CEA motion is attempted with a CMI active and not bypassed, a CEDS TROUBLE alarm will be received and all ACTMs receiving the motion demand will have a trouble alarm present.

Cue:

Comments: - - - - *- - -

Page 4 of 12

JPM Number: S-1 Rev. 0

8. PRESS and HOLD system "CEA MOTION Examinee presses and holds the system y INHBIT BYPASS" CEA MOTION INHIBIT BYPASS button.

AOP2556 Step 4.23 Cue:

Comments:

9. PRESS "INDIVIDUAL CEA SELECTION," Examinee selects the misaligned CEA by y for misaligned CEA. pressing button 18 AOP2556 Step 4.24 Cue:

Comments:

10. NOTE: Examinee reads note. N When CMI relay is bypassed for CEA AOP2556 movement, CMI should remain bypassed NOTE for at least 3 seconds after CEA motion is stopped (allows Coil Power Programmers

[CPP] operations to be completed).

Cue:

Comments:

Page 5 of 12

JPM Number: S-1 Rev. _ _0_

11. If CEA is lower than all other CEAs in its Examinee notes starting CEA position. y group, PERFORM the following:

AOP2556 Examine places and holds CEA control Step 4.25 a. OBSERVE starting CEA position switch to WITHDRAW and withdraws CEA I

b. PLACE and HOLD CEA control 6 to 9 steps.

I switch to "WITHDRAW." I

c. WITHDRAW CEA 6 to 9 steps. WHEN CEA has been withdrawn 6 to 9 I

d. WHEN CEA has been withdrawn 6 steps, examinee releases CEA control to 9 steps, RELEASE CEA control switch.

switch.

e. PLACE and HOLD CEA control Examinee places and holds CEA control switch to "INSERT." switch to INSERT and inserts CEA 3 to 5

f. INSERT CEA 3 to 5 steps. steps.

g. WHEN CEA has been inserted 3 to 5 steps, RELEASE CEA control WHEN CEA has been inserted 3 to 5 switch. steps, examinee releases CEA control switch.

Cue:

Comments:

12. h. PLACE and HOLD CEA control Examinee with draws CEA 3-5 steps and y switch to "WITHDRAW." then releases the CEA control switch.

AOP2556 i. WITHDRAW CEA 3 to 5 steps, not Step 4.25 to exceed 10 steps from starting Examinee waits at least 3 seconds since continued CEA position. CEA control switch last released to

j. WHEN CEA has been withdrawn 3 releases the CEA MOTION INHIBIT to 5 steps, RELEASE CEA control BYPASS button.

switch.

k. WHEN at least 3 seconds have Examinee observes completion time for elapsed since CEA control switch the CEA exercise was released, RELEASE system "CEA MOTION INHIBIT BYPASS."

I. OBSERVE time of CEA exercise completion.

m. Go To step 4.27.

Page 6 of 12

JPM Number: S-1 Rev. 0 Cue:

Comments:

13. CAUTION Examinee reads caution. N To prevent fuel damage due to xenon AOP2556 buildup and local power peaking, no CAUTION attempt must be made to withdraw CEA greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after misalignment occurs.

Cue:

Comments:

14. NOTE Examinee reads note. N

1. Alignment of the CEA to its group AOP2556 position must be performed as smoothly NOTE as possible. To accomplish this, the CEA is aligned in preferably equal increments, less than or equal to 10 steps each increment.

2. When CMI relay is bypassed for CEA movement, CMI should remain bypassed for at least 3 seconds after CEA motion is stopped (allows CPP operations to be completed).

3. If recovering a Group 7 CEA, CEA MOTION INHIBIT annunciator (BA-18, C-04) clears when system CEA MOTION INHIBIT BYPASS is pressed and returns when released until the CMI condition has cleared.

Cue: - - **- ----- -

Page 7 of 12

JPM Number: S-1 Rev. 0 Comments: I

15. ALIGN CEA to its group position as follows: Examinee verifies one minute has elapsed y I I

a. ENSURE at least 1 minute has from last CEA movement, observes CEA I AOP2556 elapsed from last movement of positions and then presses and holds the I Step 4.27 CEA. system CEA MOTION INHIBIT BYPASS I

b. OBSERVE present CEA positions. button.

c. PRESS and HOLD system "CEA MOTION INHIBIT BYPASS." Examinee withdraws CEA #18 less than or

d. PLACE and HOLD CEA control equal to 10 steps.

switch in applicable position:

1E CEA is lower than all other CEAs in its group, to WITHDRAW

1E CEA is higher than all other CEAs in its group, to INSERT

e. MOVE CEA less than or equal to 10 steps.

Cue:

ALTERNATE PATH BEGINS HERE Comments: Once the CEA is starts moving outward in step e above, the ACTM TROUBLE annunciator, AB-15 on C-04 will come in which causes examinee to take ALTERNATE PATH in step 16 of this JPM.

16. STOP all CEA motion. Examinee stops CEA motion and y references the ARP for the ACTM Trouble ARP2590C annunciator.

-111 Step 1 The examinee may release the system CEA MOTION INHIBIT BYPASS button and select the OFF button.

Cue: - - --- -- ***-- *****-***-

Page 8 of 12

JPM Number: S-1 Rev. 0 Comments: If examinee does not stop CEA motion within ten seconds of receiving CEO TROUBLE alarm, CEA #18 will drop to bottom of core. Once examinee reports that CEA 18 has dropped into the core terminate the JPM.

CEAPDS display in the simulator does not reflect ACTM Trouble alarm accurately. The screen would show a ACTM Trouble alarm in red on the bottom of the screen and an Abnormal Red flashing condition for CEDM 18 on the ACTM Trouble Alarms Screen.

17. REQUEST I&C Department investigate Examinee contacts I&C Department to N ACTM trouble condition. investigate ACTM trouble condition.

ARP2590C

-111 I Steg 2 I Cue: I&C reports that ACTM Motion Failure LED is lit, the TROUBLE LED is flashing constantly and ACTM ABNORMAL I VOLTAGE LED is lit on Control Element Drive Mechanism (CEDM) #18 ACTM. I I

I Comments:

18. IF alarm is momentary, PERFORM the Examinee determines alarm is NOT N following: momentary based on report from I&C that ARP2590C TROUBLE LED is flashing constantly.

-111 3.1 MONITOR all ACTMs and This step is not applicable.

Step 3 REPORT all abnormal red lights (East DC switchgear room).

3.2 IF desired, RESUME CEA motion.

Cue:

Comments:

19. IF alarm is constant, PERFORM the Examinee determines alarm is constant N following: and requests I&C monitor all ACTMs and ARP2590C REPORT all abnormal red lights.

-111 4.1 MONITOR all ACTMs and Step 4.1 REPORT all abnormal red lights (East DC switchgear room).

- L_ - - - - ---------- --

Page 9 of 12

JPM Number: S-1 Rev. 0 Cue: I&C acknowledges request to report all abnormal red lights on ACTMS.

I&C reports that the following red lights are lit on CEDM #18 ACTM: Motion Failure LED, TROUBLE LED is flashing constantly, ABNORMAL VOLTAGE LED and, Lower Gripper Engaged LED.

Comments:

20. If both of the following conditions exist: Examinee recommends to Unit Supervisor y to transfer CEA #18 to the hold bus.

ARP2590C

ACTM "TROUBLE" light is flashing Transfer needs to occur within 15 minutes

-111 constantly of receipt of ACTM TROUBLE alarm.

Step 4.2

ACTM "ABNORMAL VOLTAGE" light, "ON" PERFORM the following:

4.2.1 REQUEST I&C Department OR PEO AND licensed operator to PLACE CEA on hold bus within 15 minutes from receipt of the constant "ACTM TROUBLE" alarm as follows (East DC switchgear room):

Cue: Unit Supervisor acknowledges recommendation to transfer CEA #18 to the hold bus.

Comments:

Terminating Cue: Once the examinee has recommends placing CEA #18 on the hold bus, the JPM is complete.

STOP TIME:

Page 10 of 12

JPM Number: S-1 Rev. __0=---

VERIFICATION OF JPM COMPLETION

Title:

Respond to a Control Element Assembly Malfunction Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 11 of 12

JPM Number: S-1 Rev. __0;____

EXAMINEE HANDOUT Initial Conditions:

The plant is in MODE 1, at less than 70% power.

CEA #18 dropped into the core.

A recovery of CEA #18 has commenced. All steps of AOP 2556 up to, and including, step 4.15 have been completed.

I&C is in the East DC Switchgear room and will inform you if any problems are seen during the withdrawal.

Initiating Cues:

You have been directed by the Unit Supervisor to recover CEA #18 per AOP 2556 starting at step 4.16.

You are responsible for all operations on C04

All other actions will be handled by other watchstanders.

Examiner will act as the Unit Supervisor.

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-2

JPM Number: S-2 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-2 Task

Title:

Reset SIAS System: Engineered Safety Features Actuation System Time Critical Task: Yes No X Alternate Path: Yes X No Validated Time (minutes): 10 Task No.(s): _N:....;.U..=...T..:..I:.:..:M..:...::S=----------------

KIA No. 013 A2.06 KIA Rating 3.7/4.0 Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: Simulator: In-Plant:

- -X- - ----

Task Standards: The examinee will attempt to reset SIAS following an inadvertent ESFAS actuation using AOP 2571 and take contingency actions per Step 4.2.d for inability to reset SIAS.

Required Materials: AOP 2571, Inadvertent ESFAS Actuation, Rev. 005-003 (procedures, equipment)

General

References:

AOP 2571 Page 1 of9

JPM Number: S-2 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and Jog entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER** * *

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

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

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

Simulator

Initialize at a full power IC.

Requirements:

Override the Facility 1 SIAS/CIAS/EBFAS pushbutton on C-01 in the depressed position.

Complete AOP-2571 Steps 4.2.a, b, and c to place all charging pumps in PTL, ensure temperature on program, and to override and stop both BA pumps.

Initial Conditions: The plant is at 100% power. An inadvertent Facility 1 SIAS has occurred. All charging pumps have been placed in Pull-To-Lock and the Boric Acid Pumps have been stopped.

Initiating Cues: The Unit Supervisor directs you to perform Section 4.0 of AOP 2571, "Inadvertent ESFAS Actuation", to reset the SIAS.

Page 2 of9

JPM Number: S-2 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (YIN) (S/U)

1. Using independent indications, CHECK ALL Examinee verifies pressurizer pressure N the following: greater than 1, 714 psia and containment AOP 2571

Pressurizer pressure greater than pressure less than 4.42 psig Step 4.1 1, 714 psia. or trip function bypassed

Containment pressure less than 4.42 psig Cue: If asked to provide oversight and peer checks, acknowledge request and tell examinee to continue.

Comments:

2. If a spurious signal is present that cannot Examinee reads the note and proceeds. N be reset, then ESAS is inoperable.

AOP 2571 With all safeguards equipment running in Note the accident condition, a safe condition can be maintained until repair or a shutdown can be accomplished.

Cue:

Comments:

3. Opening service water valves to TBCCW Examinee reads the note and proceeds. N requires close monitoring of total AOP 2571 service water header flow.

Caution Cue:

Comments:

4. IF an inadvertent SIAS Examinee verifies that handswitches for N actuation occurred, Charging Pumps P18A, P18B, P18C have AOP 2571 PERFORM the following as required: already been placed in Pull-To-Lock.

Step 4.2a a. PLACE ALL charging pumps in I Pull-To-Lock. (C-02) I Cue: -**- *-***- ***- -

I Page 3 of9

JPM Number: S-2 Rev. 0 Comments:

I

5. b. Refer To Attachment 1, Examinee refers to Attachment 1 and N I "Temperature vs. Power determines that turbine load adjustment is I AOP 2571 Program," and not required. Temperature is already on I I

Step 4.2b ADJUST turbine load as necessary program. I to maintain Tave on program. I Cue:

Comments:

6. c. OVERRIDE SIAS start signals Examinee verifies the control switches N and STOP the boric acid pumps. P19A and P19B are in stop and observes AOP 2571 (C-02) (Z2) red light out and green light lit for pumps Step 4.2c BA PPA and BA PPB.

Cue:

Comments:

7. d. Refer To Attachment 2, Examinee refers to Attachment 2 Section 1 N "Resetting ESFAS,"

AOP 2571 Section 1.0, "Resetting SIAS, Step 4.2d CIAS, and EBFAS,"and ATTEMPT to reset SIAS.

Cue:

Comments:

8. CHECK at least THREE of the Examinee observes all annunciators reset. N following four annunciators reset:

Attach 1 * "CTMT PRES HI A" Step 1.1 (A-21, C-01)

"CTMT PRES HI B" (B-21, C-01)

"CTMT PRES HI C" (C-21, C-01)

"CTMT PRES HID"

(_D-21, C-01)

Cue:

Page 4 of9

JPM Number: S-2 Rev. 0 Comments:

9. CHECK pressurizer pressure Examinee observes pressurizer pressure N greater than 1850 psia. greater than 1850 psia.

Attach 1 Step 1.2 Cue:

Comments:

10. PRESS "SIAS ACTUATION Examinee depresses "SIAS ACTUATION y RESET" (Actuation Cabinet 5). RESET".

Attach 1 Step 1.3 Cue:

Comments: SIAS does NOT reset.

11. OBSERVE ALL of the following Examinee observes the SIAS does not N SIAS actuation module 'TRIP" lights reset.

Attach 1 extinguished (Actuation Cabinet 5):

Step 1.4 S "SIAS GROUP 1 AM515" S "SIAS GROUP 2 AM514" S "SIAS GROUP 3 AM516" I S "SIAS GROUP 4 AM517" I I

S "SIAS GROUP 5 AM518" I S "SIAS GROUP 6 AM519" S "SIAS GROUP 7 AM520" S "SIAS GROUP 8 AM521" S "SIAS GROUP 9 AM522" S "SIAS GROUP 10 AM523" S "SIAS GROUP 11 AM524" S "SIAS GROUP 12 AM525" Cue:

ALTERNATE PATH BEGINS HERE Comments: The examinee should recognize at this point that the SIAS will not reset and should return to Step 4.2.d in the body of the procedure to promptly take contingency actions. If the examinee continues with Attachment 1 Steps 1.5 thru 1.19, then upon completion he/she MUST return to Step 4.2.d in order to implement contingency actions for the failure of SIAS to reset. - - - **-

Page 5 of9

JPM Number: S-2 Rev. _ _0 __

12. IF SIAS signals cannot be reset, Examinee informs shift supervisor to refer N PERFORM the following: to Tech Spec 3.0.3 AOP 2571 1) Refer To Technical Step 4.2d.1 Specification 3.0.3.

1)

Cue: Inform the examinee that the Unit Supervisor will refer to Technical Specifications.

Comments:

13. OVERRIDE and OPEN the Examinee overrides and opens Facility 1 y following valves as required: SW-3.28 and observes red indicating AOP 2571

SW-3.2A, T8CCW heat lights lit.

Step 4.2d.1 exchanger SW inlet (Z2)

2)

SW-3.28, T8CCW heat exchanger SW inlet (Z1)

Cue:

Comments: Overrides b_y firstplacing valve handswitch in the CLOSED position.

14. OVERRIDE and STOP the Examinee overrides and stops running y following: HPSI and LPSI pumps.

AOP 2571

Running HPSI pumps Step 4.2d.1

Running LPSI pumps 3)

Cue:

Comments: Overrides by-first ~lacing Qum_phandswitch in the START position.

15. CLOSE LPSI injection The examinee overrides and closes y valves as required: Facility 1 valves:

AOP 2571

Sl-615, loop 1A (Z1)

Sl-615, loop 1A (Z1)

Step 4.2d.1

Sl-625, loop 18 (Z1)

Sl-625, loop 18 (Z1)

4)

Sl-635, loop 2A (Z2)

Sl-645, loop 28 (Z2 Cue:

Comments: Overrides by first placing the valve handswitch in the OPEN position.

Page 6 of9

JPM Number: S-2 Rev. 0

16. IF manual control of RBCCW temperature Examinee reads step and continues. N becomes necessary, Refer To OP 2326C, AOP 2571 "Off-Normal Service Water System Step 4.2d.1 Operations," for manual control of RBCCW

5) header temperature.

Cue:

Comments:

17. NOTIFY I&C department Examinee reads step and informs control N and GO To Step 4.4. room supervisor to notify I&C.

AOP 2571 Step 4.2d.1 6)

Cue: JPM is complete.

Comments:

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 7 of9

JPM Number: S-2 Rev. 0 VERIFICATION OF JPM COMPLETION

Title:

Reset SIAS Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes

- - No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 8 of9

JPM Number: S-2 Rev. _......:0=---

EXAMINEE HANDOUT Initial Conditions: The plant is at 100% power. An inadvertent Facility 1 SIAS has occurred. All charging pumps have been placed in Pull-To-Lock and the Boric Acid Pumps have been stopped.

Initiating Cues: The Unit Supervisor directs you to perform Section 4.0 of AOP 2571, "Inadvertent ESFAS Actuation", to reset the SIAS.

JOB PERFORMANCE MEASURE S-3

JPM Number: S-3 Rev. ----'0::.....__

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-3 Task

Title:

Perform Success Path HR-3, Once Through Cooling System: Pressure Control System Time Critical Task: Yes No X Alternate Path: Yes X No Validated Time (minutes): 8 Task No.(s): 171-300-05-01 KIA No. 01 O-OOO-A4.03 KIA Rating 4.0/3.8 Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: Simulator: X In-Plant:

-~---'-- ----

Task Standards: Examinee performs Section 3, Step 1 EOP 25400, Functional Recovery of Heat Removal, Success Path HR-3, Once Through Cooling to establish OTCC and opens both PORVs by use of contingency actions.

Required Materials EOP 25400, Functional Recovery of Heat Removal Rev 021-01 (procedures. equipment):

General

References:

JPM based on Bank JPM 118 Page 1 of8

JPM Number: S-3 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including Jogs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER * * * *

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

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

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

Simulator

Initialize at a normal 100% power IC Requirements:

Enter ED08A & ED08B@ BT1 (Failure of 6.9 KV Bus Xfer on trip)

Enter FW20A, FW20B, & FW20C (AFP trips)

Enter RC02A at severity to cause small break to stabilize pressure about at HPSI shutoff (#1 Hot leg LOCA)

Enter RC06A & RC06B @ 0% (PORVs failed closed)

Enter P02 (Spurious Rx trip)

Carry out all actions of EOP 2525, Standard Post Trip Actions

Place the simulator in freeze after both S/G wide range levels are at approximately 70 inches

When the examinee is on station and has stated that he/she is ready, place the simulator in run

During JPM Step 6, enter RPR18 to remove high pressure trip modules for RPS Channels A and B 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 Generator levels are approximately 70 inches.

SIAS, CIAS, & EBFAS have initiated.

Initiating Cues: You have been directed by the Unit Supervisor to perform EOP 25400 Functional Recovery of Heat Removal Success Path HR-3: Once Through Cooling.

Page 2 of8

JPM Number: S-3 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. NOTE Examinee reads and acknowledges note. N Once-Through-Cooling should be initiated EOP2540D prior to steam generator wide range level Section 3.0 reaching 70 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. At least one charging pump is not available.

Cue:

Comments:

2. IF steam generator level is not restoring a. Examinee notes that all y AND ANY of the following conditions exists: proportional heaters are tripped by I EOP2540D

At least one steam generator wide observing only green lights lit.

I Section 3.0 range level less than or equal to 70 Step 1.a-b inches b. Examinee places all backup

RCS TC rises uncontrollably by 5°F heaters in PULL TO LOCK.

or more ESTABLISH heat removal via once-through-cooling by performing ALL of the following:

a. ENSURE ALL proportional heaters are tripped.

b. ENSURE ALL backup heaters in PULL TO LOCK.

__ __Ql.Je:- -***-- ------------- - - - - *- -- - *-*****-

Page 3 of8

JPM Number: S-3 Rev. 0 Comments:

3. (continued) Examinee: Y

c. IF the main condenser is available, c. Observes that MSIVs are closed EOP2540D OPEN ALL steam dump valves to (condenser not available).

Section 3.0 greater than 50% open. d. Fully opens ADVs Step 1.c-i d. Fully OPEN ALL ADVs. e. Observes that ALL RCPs are

e. ENSURE that ALL RCPs are stopped.

'lstopped. f. Observes that SIAS is actuated.

f. ENSURE that SIAS is actuated. g. Observes that HPSI pumps have

g. ENSURE that HPSI pumps have started.

started. h. Observes that ALL HPSIIoop

h. ENSURE that ALL HPSI loop injection valves are open.

injection valves are open. i. Ensures that ALL charging

i. ENSURE that ALL available pumps are running.

charging pumps are running.

Cue:

Comments:

4. (continued) j. Examinee checks red lights lit for Y

i. ENSURE that BOTH PORV block PORV block valves.

EOP2540D valves are open k. Examinee takes both PORV Section 3.0 j. OPEN BOTH PORVs (key #187) handswitches to OPEN and Step 1.j-k observes their failure to open by both green lights only still lit.

Cue:

ALTERNATE PATH BEGINS HERE

___fomments: When examinee attem~ts to open each PO~V. the valves ~ill not open. _ _ _ _ _ __

Page 4 of8

JPM Number: S-3 Rev. 0

5. REPORT the failure of the PORVS to open. Examinee informs the Unit Supervisor that N both PORVs failed to open with their hand switches.

Cue: As the Unit Supervisor, acknowledge the report.

Comments:

6. PERFORM the following to open PORVs: Examinee obtains the high pressure trip y module bypass key.

EOP2540D 1. POSITION the bypass key in one Section 3.0 high pressure trip bistable and Examinee places the high pressure trip Step 1.k.1- SELECT BYPASS position on RPS. bypass key one channel's high pressure 2 trip module bypass key slot and turns it to

2. OPEN PORVs by pulling the high the right to bypass the trip module.

pressure trip bistable on the bypassed channel and on one other Examinee states that he would pull that channel. channel's high pressure trip module AND the high pressure trip module for another channel.

Cue: If necessary, cue examinee to use RPS channels A and B (simulator does not model the use of C/D channels for pullinq hi pressure trip units).

Cue: When examinee begins to simulate pulling high pressure trip units, inform him/her that the respective channel's high pressure trip trip units have been pulled.

Comments: 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 would cause a Reactor trip and PORVs to open. Use of the trip unit bypass key to bypass one of the "pulled" trip units would permit open/close control of the PORVs. The trip inhibit relay K29 and the PORV trip relays K27, K1 are located in the RPS auxiliary loqic drawers (4) and are activated by key number 6.

Page5of8

JPM Number: S-3 Rev. 0

7. (continued) Examinee turns the bypass key that was y inserted into the high pressure trip module EOP25400 3. OPERATE bypass key to open bypass key slot in step 6.

Section 3.0 PORVs.

Step 1.k.3 Examinee observes that both PORVs open by their red lights only lit I I

Cue:

Comments: -- -

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 6 of8

JPM Number: S-3 Rev. __0=---

VERIFICATION OF JPM COMPLETION

Title:

Perform Success Path HR-3, Once Through Cooling Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes

- - No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 7 of8

JPM Number: S-3 Rev.

-- 0 -

EXAMINEE HANDOUT 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 Generator levels are approximately 70 inches.

SIAS, CIAS, & EBFAS have initiated.

Initiating Cues: You have been directed by the Unit Supervisor to perform EOP 25400 Functional Recovery of Heat Removal Success Path HR-3: Once Through Cooling.

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-4

JPM Number: S-4 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-4 Task

Title:

Start 4th Reactor Coolant Pump System: Reactor Coolant System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMS 003-01-031 KIA No. 003 A2.02 KIA Rating 3. 7, 3.9 Method of Testing:

Simulated Performance: Actual Performance: X Location:

Classroom: Simulator: X In-Plant:

Task Standards: The examinee will start the RCP, monitor critical RCP parameters including alarms and secure the RCP per OP 2301 C and/or ARP 25908-179.

Required Materials OP 2301 C, Rev 019-07, marked up thru Step 4.5.11.

(procedures. eguipment): ARP 25908-179, Rev 000-01 "RCP D UPR OIL RSVR LEVEL LO" C02/03 8A-31 General

References:

OP 2301 C, Rev 019-07 "Reactor Coolant Pump Operations for Starting and Stopping RCP

OP 2201 "Plant Heatup" Page 1 of8

JPM Number: S-4 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator

Initialize at zero power, ARI. (IC-15) then trip rods.

Requirements:

Secure the 'D' RCP.

Cool RCS to - 505°F.

Ensure plant is stable.

Set up to insert malfunction RC12D (upper oil reservoir leak) at 20%

severity when examinee completes OP-2301C Step 4.5.19.

Initial Conditions:

A plant heat-up is in progress following an outage for unplanned maintenance.

The RCS is at approximately 1750 psia and Tc is> 500°F.

Three RCPs are running.

All parameters for the 'D' RCP are normal for this condition.

All prerequisites for starting the 'D' RCP have been verified met.

OP-2301 C, Section 4.5 is complete up through Step 4.5.11.

!Initiating Cues: I The US has directed you to start the 'D' RCP.

Page 2 of8

JPM Number: S-4 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. NOTE When starting RCPs at low RCS Examinee reads the NOTE and N pressure conditions (265 to 1,700 psia), determines the NOTE is Not Applicable.

RCP bleedoff flow low alarms may not clear due to insufficient bleedoff flow. As RCS pressure increases, bleed off flow increases and alarm should clear at approximately 1,700 psia.

Cue:

Comments:

2. 12. IF RCS pressure is greater than 1700 Examinee displays and monitors "D" RCP N psia, PERFORM the following: bleedoff flow on the PPC, or on C-04R.

Step

CHECK, "RCP 0 BLEEOOFF FLOW 4.5.12 LO" annunciator (CA-29) not lit (C- I 02/3).

OBSERVE controlled bleedoff flow on PPC or PR-150B (C-04R) between

0. 75 and 2 gpm.

Cue:

Comments:

3. 13. PLACE "RCP-0 LIFT PPS, Examinee places the 'D' RCP Lift Pp y P-51 0/530" switch to "START"(C-03). switch to start and observes the red light Step lit.

4.5.13 Cue:

Comments:

Page 3 of8

JPM Number: S-4 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

4. 14. ENSURE annunciator AB-30 "RCP D Examinee reviews the Board Alarms and N ANTIREV ROT FLOW LO," clear, Verifies C02/03 AB-18 is not lit.

Step 4.5.14 indicating bearing oil lift pump operation (C-03).

Cue:

Comments:

5. 15. WHEN the bearing oil lift pumps Examinee places the 'D' RCP switch on y have run for at least two minutes, C-03 to the start position and observes Step PLACE "RCP-D, P-400" switch to Red Light Lit.

4.5.15 "START" (C-03). I I

Cue: When the examinee indicates that the lift pp must run for 2 minutes, inform the examinee that 2 minutes have lapsed.

Comments:

6. 16. OBSERVE RCP amp meter as RCP Examinee observes the 'D' RCP amp N starts and VERIFY the following: meter pegs high and decays off on C-03.

Step a) Meter deflects to full scale high 4.5.16 when pump switch turned to start (C-03).

b) Meter decays to running current, between 450 and 600 amps depending on RCS temperature, as RCP accelerates to operating speed (about 20 seconds) (C-03).

Cue:

Comments:

7. 17. WHEN RCP is above 90% speed When annunciator C-04 BB-4 is not lit, y

["RCP LO SPEED TRIP CH D" examinee places the 'D' RCP Lift Pp.

Step annunciator (BB-4, on C-04) not lit], switch on C-03 to OFF.

4.5.17 PLACE "RCP-D LIFT PPS, P-51 D/530" to "AUTO" (C-03).

Cue:

L _ _ _ _ - - L_ -------- -------------

Page 4 of8

JPM Number: S-4 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Comments:

8. 18. IF less than four RCPs are running, Examinee reads the step and determines N CHECK the following for idle RCPs the step is NA since 4 RCPs are running.

Step (PPC).

4.5.18 Cue:

Comments:

9. 19. IF seal cavity OR bleedoff temperature Examinee reads step and determines step N limits are reached, PERFORM the is NA Step following:

4.5.19 Cue:

ALTERNATE PATH BEGINS HERE I

Comments: Booth operator - Insert Malfunction RC12D at 20% severity.

1 0. Annunciator C-03 BA31 energizes. Examinee observes annunciator C-03 N BA31 energizes informs the US and refers to or recommends referring to ARP 25908-179.

Cue: Acknowledge the recommendation and direct the examinee to implement the ARP 25908-179.

Comments:

11 . 1. Check 'D' RCP upper reservoir oil level Examinee displays the "RCP D Motor N indication and determine rate of level Data" display on the PPC and monitors ARP decrease (C-04R or PPC) (normal * "L 156" (Upper Reservoir Level) .

Step 1 range, 75 to 85% ). calculates the rate of level decrease or

"L 156" on C-04R calculates the rate of level decrease Cue: - - - * * - ----- - - * -

Page 5 of8

JPM Number: S-4 Rev.

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Comments:

1 2. 2. MONITOR "D" RCP bearing The examinee monitors "D" RCP bearing N temperatures and oil levels (C-04R or temperatures and oil level by:

ARP PPC).

Displaying the "RCP D Motor Data" Step 2 display on the PPC or

Monitoring parameters on C-04R Cue:

Comments:

1 3. 3. IF oil level is rapidly lowering AND Examinee secures the "D" RCP. y bearing temperature is increasing, ARP PERFORM the following:

Step 3

. TRIP reactor and turbine.

STOP "D" RCP . I

Refer To EOP 2525, "Standard I Post Trip Actions" and PERFORM I re_guired actions.

Cue: Acknowledge the recommendation and direct securing the "D" RCP Comments: Trip_Qing_ th~ r~ac!_or §lnd_ turbine ir} not applicable to plant conditio_ns_ - -- - - - -

Terminating Cue: The JPM is complete when applicant has secured the containment purge and the above step is complete.

STOP TIME:

Page 6 of8

JPM Number: S-4 Rev.

-- 0 -

VERIFICATION OF JPM COMPLETION

Title:

Start 41h Reactor Coolant Pump Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page7of8

JPM Number: S-4 Rev.

-- 0 -

EXAMINEE HANDOUT Initial Conditions:

A plant heat-up is in progress following an outage for unplanned maintenance.

The RCS is at approximately 1750 psia and Tc is> 500°F.

Three RCPs are running.

All parameters for the 'D' RCP are normal for this condition.

All prerequisites for starting the 'D' RCP have been verified met.

OP-2301 C, Section 4.5 is complete up through Step 4.5.11.

!Initiating Cues: I The US has directed you to start the 'D' RCP.

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-5

JPM Number: S-5 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-5 Task

Title:

Shifting Containment Air Recirculation and Cooling Units System: Containment Cooling System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMS 022-01-117 KIA No. 022 4.01 KIA Rating 3.6, 3.6 Method of Testing:

Simulated Performance: Actual Performance: X Location:

Classroom: Simulator: X In-Plant:

Task Standards: The examinee will stop and restart an OPERABLE CAR fan.

Required Materials OP 2313A, Rev 009-06 (procedures, equipment): ARP 2590A-012, Rev 000-01 "CTMT AIR RECIRC FAN D TRIP" C02/03 BA-31 General

References:

OP 2313A, Rev 009-06

ARP 2590A-012, Rev 000-01 "CTMT AIR RECIRC FAN D TRIP"

OP 2330A, RBCCW

MP-14-0PS-GDL02, Operations Standards Page 1 of8

JPM Number: S-5 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator

Initialize in any 100% power IC with "A", "B", and "C" CAR fans Requirements: operating in fast speed.

RBCCW may or may not be aligned to "D" CAR fan.

Ensure RBCCW header flows within normal range (6000gpm).

Insert malfunction CH01 D on BT39 to cause the "D" CAR Fan to trip when started during STEP 6 of JPM.

Initial Conditions:

The unit is operating at 100% power.

"A", "B", and "C" CAR fans are operating.

Electrical PMs are scheduled on the breaker for the "B" CAR fan.

Initiating Cues: The Unit Supervisor has directed you to align CAR fans such that "A", "C" and "D" are operating in fast speed and "B" CAR fan is secured in accordance with OP 2313A, "Containment Air Recirculation and Cooling System."

Page 2 of8

JPM Number: S-5 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. IF stopping "B" CAR fan, PERFORM the Examinee places "B" CAR fan to STOP, y following (C-01 ): holds for two seconds and releases Step PLACE "B" CAR fan to "STOP" and HOLD 4.2.5 for approximately two seconds.

WHEN two seconds elapse, RELEASE "B" CAR fan switch.

Cue:

Comments: The examinee must realize that 4 CAR fans may not be operated in fast speed simultaneously and must first stop "B" CAR fan. Starting a fourth CAR fan in fast constitutes failure of this JPM.

2. IF isolating RBCCW flow to 35B "B CAR Examinee may NOT opt to close the listed N COOLER," PERFORM the following (C-01): valves; however, if examinee closes the Step CLOSE RB-28.3B, "EMERG OUTLET" outlet valves, in order to pass this step, 4.2.6 OBTAIN key and CLOSE RB-28.1B, "CLR he/she should realize that RBCCW flows B INLET." need to be adjusted and that he/she must I CLOSE RB-28.2B, "NORM OUTLET." monitor RBCCW header flow and I MONITOR RBCCW System flow and pressure.

pressure (C-06, PPC)

Cue:

Comments: If the listed valves are closed, follow up with question on how flows would be adjusted.

Comments: Based on the reason for shifting CAR fans and the NOTE associated with this step, closing these valves is NOT necessary. If these valves are closed, flow should be adjusted to other components such as SFPC or other CAR fan if possible, to prevent exceeding a maximum pump discharge pressure of 140 psig or a low flow rate of 4000 gpm (prevent lifting relief valves).

3. IF starting "D" CAR fan in fast speed, Examinee observes only red lights lit for N PERFORM the following: RB-28.20 and RB-28.30 and flow Step a. ENSURE the following, open (C---01 ): indication on C-01.

4.4.2.a

RB-28.20, "NORM OUTLET"

RB-28.30, "EMERG OUTLET" Page 3 of8

JPM Number: S-5 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N} (S/U}

Cue:

Comments: Both normal and emergency outlet valves are normally open during operations.

4. ENSURE RB-28.1 D, "CLR D INLET," Examinee observes only red light lit for N locked open (C-01 ). RB-28.1 D (C-01 ).

Step 4.4.2.b Cue:

Comments: The CAR Cooler Inlet Valves are normally open during operations.

5. Check "B" RBCCW header flow less than Examinee observes "B" RBCCW header N 8,000 gpm (C-06, PPC) flow on C-06 or PPC less than 8,000 gpm.

Step 4.4.2.c Cue:

Comments:

6. PLACE "D" CAR fan to "START HIGH" Examinee places the handswitch for the y and observe red "FAST SPEED" indicating "D" CAR fan to "START HIGH" and Step light lit (C-01) observes the associated "fast speed" red 4.4.2.d light is only momentarily lit. The examinee observes the CTMT AIR RECIRC FAN D TRIP and the CTMT AIT RECIRC FAN D VIBRATION HI annunciators on C-01.

Cue:

ALTERNATE PATH BEGINS HERE Comments: Simulator Operator, insert malfunction for D fan triQ.

Comments: Attempting to start the fan in "slow" will not constitute failure of this JPM.

The examinee may or may not reset the CTMT AIR RECIRC FAN D VIBRATION HI annunciator MP-14-0PS-GDL02, Attachment 2 states, "To protect the plant or prevent a plant transient, the SM is authorized to reset any tripped device without knowing the cause." The loss of the "D" CAR fan is NOT an immediate concern.

Page 4 of8

JPM Number: S-5 Rev. 0 CRITICAL GRADE '

STEP PERFORMANCE STANDARD (Y/N) (S/U)

7. Obtain Annunciator Response Procedure Examinee obtains ARP 2590A-012, CTMT N for annunciator D-3 on C-01 and asks AIR RECIRC FAN D and asks the US/SM the US/SM to restart the "8" CAR fan to restart the "8" CAR fan.

Cue: If the examinee does NOT ask the US/SM to restart the "B" CAR fan, then ask the examinee to recommend actions re_garding_ the CAR system.

Comments:

8. IF starting "8" CAR fan in fast speed, Examinee observes red only lights lit for N PERFORM the following: R8-28.28 and 28.38.

Step a. ENSURE the following open (C-01 ):

4.2.2.a

R8-28.28, "NORM OUTLET"

R8-28.38, "EMERG OUTLET" Cue:

Comments:

9. ENSURE RB-28.1B, "CLR B INLET" locked Examinee observes red only light lit for N open (C-01). R8-28.18.

Step 4.2.2.b Cue:

Comments:

1 0. CHECK "8" R8CCW header flow less than Examinee observes "B" R8CCW header N 8,000 gpm (C-06, PPC). flow less than 8,000 gpm.

Step 4.2.2.c Cue:

Comments: - - -

Page 5 of8

JPM Number: S-5 Rev. _ _ 0_

CRITICAL GRADE I

STEP PERFORMANCE STANDARD (Y/N) (S/U) I 11 . PLACE "B" CAR fan to "START HIGH" and Examinee places the handswitch to y I

OBSERVE red "FAST SPEED" indicating "START HIGH" and observes the I Step light, lit (C-01 ). associated "fast speed" red light is lit. I 4.2.2.d Examinee observes the starting and I running currents on the ammeter for the "B" CAR fan.

Cue:

Comments: Attempting to start the fan in "slow" will not constitute failure of this JPM provided the fan is placed in "fast" prior to completion of the JPM. Failure to observe the ammeter does NOT constitute failure of this JPM.

1 2. IF "B" CAR fan high vibration alarm The examinee depresses the "CAR FAN N annunciates, PRES "CAR FAN VIS RESET VIS RESET B & D" pushbutton on C-01 Step B & D" button (C-01) and observes annunciator clearing on C-4.2.2.e 01.

Cue:

Comments:

Terminating Cue: The JPM is complete.

STOP TIME:

Page 6 of8

JPM Number: S-5 Rev. __0::_._

VERIFICATION OF JPM COMPLETION

Title:

Shifting Containment Air Recirculation and Cooling Units Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 7 of8

JPM Number: S-5 Rev. __0__

EXAMINEE HANDOUT Initial Conditions: * *The unit is operating at 100% power.

*"A", "B", and "C" CAR fans are operating.

Electrical PMs are scheduled on the breaker for the "B" CAR fan.

Initiating Cues: The Unit Supervisor has directed you to align CAR fans such that "A", "C" and "D" are operating in fast speed and "B" CAR fan is secured in accordance with OP 2313A, "Containment Air Recirculation and Cooling System."

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-6

JPM Number: S-6 Rev. _......:0=----

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-6 Task

Title:

Cross-Tie 480 Volt Busses System: AC Electrical Distribution System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 10 Task No.(s): NUTIMS 062-01-394 KIA No. 062-A4.01 KIA Rating 3.3/3.1 Method of Testing:

Simulated Performance:

Actual Performance:

- -X- -

Location:

Classroom: Simulator: In-Plant:

- -X- - ----

Task Standards: At the completion of this JPM, the examinee has cross-tied 480 Volt busses 22A and 228 with 228 supplying bus 22A.

Required Materials OP 2344A, 480 Volt Load Centers. Rev 023-06 (procedures. equipment):

General

References:

Page 1 of8

JPM Number: S-6 Rev. __o __

* *

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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and Jog entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator

Initialize to an IC in MODE 1.

Requirements:

Place Group 1 and Group 2 Pressurizer Backup Heaters in Pull to Lock and yellow tag them.

Ensure B and C TBCCW pumps running, A TBCCW pump in NUETRALINORMAL AFTER TRIP. Yellow tag on both the A and B TBCCW pump hand switches with the following information, "480V Buses 22A and 22B are cross-tied. Refer to OP2344A, step 4.13.1, prior to starting pump."

Place the simulator in run.

Initial Conditions:

The unit is in MODE 1.

Group 1 and Group 2 Pressurizer Backup Heaters are in Pull to Lock and tagged.

A and B TBCCW pumps are yellow tagged.

Initiating Cues: You have been directed by the Unit Supervisor to cross-tie 480 volt busses, 22A and 22B per OP 2344A, 480 Volt Load Centers, in preparation for tagging and replacement of Bus 22A Transformer.

Page 2 of8

JPM Number: S-6 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

'I

1. CAUTION Examinee reads and acknowledges the N Current greater than 1800 amps on 480 volt caution. I OP2344A bus 22A exceeds the ratings of the I I

4160/480 volt transformer Cue: I Comments: I

2. To avoid exceeding 1800 amp transformer Examinee marks step complete. N '

limit, PERFORM the following:

OP2344A

PLACE associated pressurizer Step 4.13.1 backup heaters, (Group 1 and Group 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 hand witches with the following information: ""480V Buses 22A and 22B are cross-tied. Refer to OP2344A, step 4.13.1, prior to starting pump."

Cue:

Comments: This step was covered in the Initial Conditions.

3. IF Bus 22A will be supplying Bus 22B, Examinee marks this step "N/A." N PLACE SYN SEL SW 22A/22B in CL OP2344A TIE/TRIP B. (C-08)

Step 4.13.2 Cue:

Comments: The request is for the 2~_!r~n~f~rn1e! to be removed from service, therefore, 22B will be supplying 22A.

Page 3 of8

JPM Number: S-6 Rev. 0

4. IF Bus 22B will be supplying Bus 22A, Examinee places SYN SEL SW 22A/22B y PLACE SYN SEL SW 22A/22B in CL in CL TIE/TRIP A.

OP2344A TIE/TRIP A. (C-08)

Step 4.13.3 Cue:

Comments: Alarm D-4, SYNC SELECTOR SWITCH ON, per design of the alarm circuit, will actuate 55 seconds after the sync I switch has been placed in ON. I

5. ENSURE Bus voltages are matched. Examinee should ensure bus voltages N I matched using "Incoming" and "Running" I I

OP2344A meters and/or using C-08 22A and 22B '

Step 4.13.4 Volt Meters.

Cue: Incoming and running voltages maybe differ slightly. If the examinee identifies this difference, state that voltages are matched sufficient to cross-tie.

Comments:

6. Using B0111, 22A/22B TIE BKR, 22A-1 T2, Examinee closes 22A/22B TIE BKR, 22A- y breaker control switch, CLOSE B0111. (C- 1T -2 (B0111) by taking its hand-switch to OP2344A 08) CLOSE.

Step 4.13.5 Cue:

Comments:

7. ENSURE B0111, 22A/22B TIE BKR, 22A- Examinee observes 22A/22B TIE BKR, N 1T -2, has closed and the applicable supply 22A-1T-2 (B0111) red light only lit and breaker has opened. then observes that 22A SPLY BKR, 24A 1-OP2344A 1X3-2 (B0102) is open by its green light Step 4.13.6 only lit.

Cue:

Comments: - - - *- - *- - - - -- *- *- *- -- --------

Page 4 of8

JPM Number: S-6 Rev. 0

8. TURN SYN SEL SW 22A/22B to OFF (C- Examinee places the SYN SEL SW N

08) 22A/22B to OFF.

OP2344A Step 4.13.7 Cue:

Comments: The sync switch on alarm (D-41 will clear.

9. IF current on 480 volt supply bus greater Examinee observes Bus 22B ammeter on N I

than 1800 amps, OPEN 80111, 22A/22B C-08 and verifies amps <1800. This step OP2344A TIE BKR, 22A-1T-2. should be "N/A."

Step 4.13.8 Cue:

Comments:

10. CAUTION The examinee reads and acknowledges N Current greater than 1600 amps indicated the caution.

OP2344A on 22A-1T-2 AMMETER PHASE B (local, above B0111 cubicle) exceeds the rating of the cross-tie breaker Cue:

Comments:

11. IF current on 480 volt supply bus is greater Examinee observes Bus 22B ammeter on N than 1600 amps (C-08), CHECK current, as C-08 and verifies amps <1600. This step OP2344A indicated on 22A-1T-2 AMMETER PHASE should be "N/A."

Step 4.13.9 B (local above B0111 cubicle) less than 1600 amps.

Cue:

Comments:

12. IF current indicated on 22A-1T-2 Examinee marks this step "N/A." N AMMETER PHASE 8 is greater than 1600 OP2344A amps, OPEN 80111, 22A/22B TIE BKR, Step 22A-1T-2. (C-08) 4.13.1 0 Cue: - - **-*--

Page 5 of8

JPM Number: S-6 Rev. 0 Comments:

13. To reduce wear on the off-service load Step 4. 13. 11. a should be "N/A." N center transformer, PERFORM one of the OP2344A following: (C-08) Examinee determines that Bus 22B is Step a. IF Bus 22A is supplying Bus 22B, supplying Bus 22A and takes switch A 103, 4.13.11 OPEN A204, 24B/22B FDR BKR 24A/22A FDR BKR 24A 1-2 to the Trip 24B4-2. position and verifies the green light only lit

b. IF Bus 22B is supplying Bus 22A, and red light out.

OPEN A 103, 24A/22A FDR BKR I

24A1-2.

Cue:

Comments:

14. To match breaker indication flags with Step 4.13.12.a is "N/A." N actual breaker position, PERFORM the OP2344A following: (C-08) Examinee determines that Bus 22B is Step a. IF Bus 22A is supplying Bus 22B, supplying Bus 22A and takes switch 4.13.12 PLACE B0209, 22B SPLY BKR B0102, 22A SPLY BKR 24A1-1X3-2, to 24B4-1X3-2, in TRIP and allow to the Trip position and allows switch to spring return to NEUTRAL. spring return to Neutral. Examinee verifies

b. IF Bus 22B is supplying Bus 22A, the green light only lit and red light out and PLACE B01 02, 22A SPLY BKR the breaker flag is green.

24A1-1X3-2, in TRIP and allow to spring return to NEUTRAL.

Cue:

Comments: - - - - - - - - - - - - * - - - -

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 6 of8

JPM Number: S-6 Rev. _ _:0::..__

VERIFICATION OF JPM COMPLETION

Title:

Cross-Tie 480 Volt Busses Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 7 of8

JPM Number: S-6 Rev. 0 EXAMINEE HANDOUT Initial Conditions:

The unit is in MODE 1.

Group 1 and Group 2 Pressurizer Backup Heaters are in Pull to Lock and tagged.

A and B TBCCW pumps are yellow tagged.

Initiating Cues: You have been directed by the Unit Supervisor to cross-tie 480 volt busses, 22A and 22B per OP 2344A, 480 Volt Load Centers, in preparation for tagging and replacement of Bus 22A Transformer.

JOB PERFORMANCE MEASURE S-7

JPM Number: S-7 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-7 Task

Title:

RPS Calibration with One Channel Inoperable for> 48 Hours System: Nuclear Instrumentation System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): 217-700-02-01 KIA No. 015A1.01 KIA Rating 3.5/3.8 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 performed a Power Range safety channel and Delta-T Power channel calibration for one operable RPS channel.

Required Materials SP-2601 D, Power Range Safety Channel and Delta T Power (procedures, equipment): Channel Calibration Rev 016-03 SP-2601 D-003 Rev 000-03 Surveillance Form with expected SM/US Authorization signatures and Tech Spec entry signed.

General

References:

JPM based on Bank JPM 115 Rev 2 Page 1 of 14

JPM Number: S-7 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator

Initialize into a 100% power IC.

Requirements:

RunIC long enough that CV4CAL from PPC is valid

Mis-adjust Nl Channels "B" 'C" and "D" the same amount on both Nl and delta-T power (within the allowed operability tolerance but outside the 0.1% tolerance state in steps 4.5.8.c and 4.5.8.h.

Trip RPS Channel "A" Trip Units 1,7,8, 11

Fail the Nl input to RPS Channel "A" to 0% power (Malfunction RP18A)

Lock potentiometers on Power Range Nl's all channels.

Initial Conditions:

The plant is in MODE 1, at approximately 100% and stable

RPS Channel "A" trip units have been tripped due to the failure of the linear power range instrument 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months ago.

Initiating Cues:

You are the BOP operator.

You are directed to perform calibration of the OPERABLE RPS channels in accordance with SP-2601 D, Power Range Safety Channel and Delta T Power Channel Calibration.

Page 2 of 14

JPM Number: S-7 Rev. 0 START TIME*

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. RPS Calibration With One Channel Examinee selects appropriate surveillance y Inoperable for> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months procedure step 4.5 for one channel SP2601D inoperable.

4.5 Cue: If necessary, cue that sections 4.1 and 4.2 have been completed and are satisfactory.

Comments:

2. NOTE: Attachment 5 may be used as an Examinee reads note and may or may not N aid in place keeping when multiple channel decide to use Attachment 5 for SP2601D checks are required. placekeeping.

NOTE Cue:

Comments:

3. ENSURE entry into TS LCO 3.3.1.1 has Examinee determines that TS entry has N been logged in the Shift Manager Log and been logged in the Shift Manager Log and SP2601D SP 2601 D-003. on form SP 2601 D-003.

4.5.1 Cue: Shift Manager log contains entry into TS LCO 3.3.1.1 Action Statement 2 Comments:

4. CAUTION: Failure to follow the prescribed Examinee reads CAUTION and N procedural sequence when one RPS determines that it IS applicable because SP2601D channel is inoperable and tripped, may RPS Channel "A" is tripped.

CAUTION result in a reactor trip.

Cue:

Page 3 of 14

JPM Number: S-7 Rev. 0 Comments:

5. RECORD OPERABLE RPS channels on Examinee writes "B" "C" and "D" on form N SP 2601 D-003 SP 2601 D-003 line 4.5.2.

SP2601D 4.5.2 Cue:

Comments:

6. NOTE: TS LCO 3.3.1.1 Table 3.3-1 Examinee reads NOTE and determines N ACTION 2, imposes a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limit unless that NOTE is satisfied because RPS SP2601D the inoperable channel is placed in the Channel "A" is in the tripped position.

NOTE tripped condition Cue:

Comments:

7. ENSURE the following trip unit modules for Examinee determines trip unit modules for N the inoperable RPS channel power trip unit RPS Channel "A" are removed and SP2601D are removed and DOCUMENT on SP documents this checking each trip unit on

4.5.3 2601D-003

form SP 2601 D-003 line 4.5.3.

High Power Trip ("1")

TMLP Trip ("7")

Turbine Trip ("8")

Local Power Density Trip ("11 ")

Cue: Fuses have been removed for RPS Channel A Trip Units 1, 7, 8, and 11.

Comments:_ - - - *- -

Page 4 of 14

JPM Number: S-7 Rev. 0

8. CAUTION: Failure to bypass OPERABLE Examinee reads and acknowledges N trip units prior to continuing with calibration caution statement.

SP2601D could result in a reactor trip.

CAUTION Cue:

Comments:

9. OBTAIN the necessary keys and BYPASS Examinee obtains the bypass keys for the y the following on the channel to be tested, given trip units, places them in the SP2601D INITIAL SP 2601 D-003: appropriate slot for the channel he/she 4.5.4

High Power Trip ("1") selects to test first and observes the yellow

TMLP Trip ("7") bypass lights are lit for each trip bypassed.

Turbine Trip ("8")

Local Power Density Trip ("11 ") Examinee initials the appropriate slots on form SP-2601 D-003 line 4.5.4.

Cue:

Comments:

10. PERFORM Independent Verification of trips Examinee requests a person to N listed in step 4.5.4 in bypass condition independently check that the required SP2601D (amber lights lit) and INITIAL modules are bypassed and to initial form 4.5.5 SP 26010-003. SP-2601 D-003 line 4.5.5.

Cue: Examiner should act as the Independent Verifier and initial the form.

Comments: ---*-----

Page 5 of 14

JPM Number: S-7 Rev. _ _0 __

11. CALCULATE Calorimetric power (in Examinee calculates Calorimetric power y percent) as follows and RECORD on SP using CV4CAL on the PPC and records it SP2601D 2601D-003: on SP2601 D-003 on line 4.5.6.

4.5.6

a. IF PPC is available, OBSERVE PPC Calorimetric power(%)=

point "CV4CAL" and CALCULATE 100 X CV4CAL Calorimetric power (in percent) as: 2700 MWTH Calorimetric power(%)= "CV4CAL" I 2, 700 MWTH x 100

b. !E PPC is not available, Refer To EN 21002, "Core Heat Balance,"

and PERFORM manual core heat balance and CALCULATE Calorimetric power (in percent) as:

Calorimetric power(%)= "Core Thermal Power" I 2, 700MWth x 100 where "Core Thermal Power =

Manual core heat balance Cue:

Comments: Examiner must determine CV4CAL from PPC to verify this step complete.

12. !E steady state equilibrium power level Examinee acknowledges step. N conditions change during the performance SP2601D of this section (greater than 1% of RATED 4.5.7 THERMAL POWER), prior to performing the remaining channel adjustments, Go To step 4.5.6 to obtain a new calorimetric value.

Cue:

Comments: Equilibrium power level conditions SHOULD NOT change during the performance of this JPM.

Page 6 of 14

JPM Number: S-7 Rev. 0

13. NOTE: Step 4.5.8 applies only to the RPS Examinee reads and acknowledges note. N '

channel in bypass.

SP2601D NOTE Cue:

Comments:

14. PERFORM the following for an OPERABLE For the selected channel, the examinee y RPS channel: places the METER INPUT switch to SP2601D a. PLACE "METER INPUT" switch to NUCLEAR PWR and records the DVM 4.5.8a-b "NUCLEAR PWR" and RECORD As reading for Percent Nuclear Power on form Found "Percent Nuclear Power" SP-2601 D-003 on line 4.5.8.a.

(DVM reading) on SP 2601 D-003.

b. !E DVM reading is within plus or Examinee determines that step b. is not minus 0.1% of plant calorimetric applicable because DVM reading is MORE recorded in step 4.5.6, Go To step than 0.1% of plant calorimetric calculated 4.5.8.d. in step 4.5.6.

Cue:

Comments: The DVM reading should be more than 0.1% of plant calorimetric calculated in ste_p 4.5.6.

15. Examinee determines that DVM reading is N

c. !E DVM reading is not within plus or not within 0.1% of plant calorimetric SP2601D minus 0.1% of plant calorimetric recorded in step 4.5.6 and reads the 4.5.8c recorded in step 4.5.6, PERFORM applicable NOTE.

NOTE the following:

NOTE:

1. Clockwise rotation raises DVM reading.

2. Counterclockwise rotation lowers DVM reading.

3. Gamma-Metrics power range monitor "NUCLEAR POWER CALIBRATE" potentiometer is located on the power range monitor drawer. -*------ -- -*---- -

Page 7 of 14

JPM Number: S-7 Rev. _ _0 __

Cue:

Comments:

16. PERFORM the following: For the selected operable channel to test, y the examinee performs the following:

SP2601D 1) MONITOR DVM reading and 4.5.8.c1-4 DISENGAGE locking device on

Monitors DVM reading while "NUCLEAR POWER CALIBRATE" disengaging the locking device on potentiometer. the NUCLEAR PWR CALIBRATE potentiometer.

2) Slowly ADJUST "NUCLEAR POWER CALIBRATE"

Adjusts potentiometer to obtain a potentiometer to obtain a DVM DVM value that is within .:t 0.1% of reading equal to the plant the value from Step #11.

calorimetric recorded in step 4.5.6.

Monitors DVM while re-engaging

3) MONITOR DVM reading and the locking device to ensure it ENGAGE locking device on doesn't change.

"NUCLEAR POWER CALIBRATE" potentiometer.

Records the new NUCLEAR PWR CALIBRATE potentiometer setting.

4) IF DVM indication changed while engaging locking device, REPEAT step 4.5.8.c.

Cue:

Comments: Causing a reactor trip during calibration constitutes a failure during this JPM.

17. RECORD As Left "Percent Nuclear Power" For the selected channel, the examinee N DVM reading on SP 2601 D-003. places the METER INPUT switch to SP2601D NUCLEAR PWR and records the DVM 4.5.8.d reading for Percent Nuclear Power on form SP-2601 D-003 on line 4.5.8.d.

Cue:

Comments:

Page 8 of 14

JPM Number: S-7 Rev. 0

18. COMPARE As Left "Percent Nuclear For the selected channel, the examinee N Power" DVM reading with the "Acceptance determines that the As Left "Percent SP2601D Criteria" on SP 2601 D-003 and Nuclear Power" DVM indication is within 4.5.8.e DOCUMENT results. .:!_0.1% of calorimetric power (%) in step 4.5.6 and marks the SAT box on form SP-2601D-003.

Cue:

Comments:

19. PLACE "METER INPUT" switch to "LH For the selected channel, the examinee N PWR." places the METER INPUT switch to bT I

SP2601D PWR and records the specified readings I 4.5.8.f-g RECORD the following on SP 2601 D-003: on form SP-2601 D-003 line 4.5.8.g I

As Found "bT PWR" (DVM) '

"NUCLEAR PWR -LH PWR (%)"

Cue:

Comments: - - -------------

Page 9 of 14

JPM Number: S-7 Rev. 0

20. IF "t.T PWR" (DVM) is not within plus or For the selected operable channel to test, y minus 0.1% of calorimetric recorded in step the examinee performs the following:

SP2601D 4.5.6 OR "NUCLEAR PWR -t.T PWR (%)"

4.5.8.h average indication is not 0.0% (-0.5% to +

Monitors DVM while disengaging 0.5%), PERFORM the following: the locking device on the t.T PWR CALIBRATE potentiometer on the

1) MONITOR "t.T PWR" indication selected channel.

(DVM) and DISENGAGE locking device on "t.T PWR CALIBRATE"

Adjusts the t.T PWR CALIBRATE potentiometer. potentiometer to obtain the t. T NOTE: PWR indication equal to the

1. Clockwise rotation raises DVM reading. calorimetric power in the percent

2. Counterclockwise rotation lowers DVM value.

reading.

Verifies by observing the

2) Slowly ADJUST "b.T PWR NUCLEAR PWR- t.T PWR (%)

CALIBRATE" potentiometer to meter that the deviation is obtain "b.T PWR" indication (DVM) approximately zero.

within plus or minus 0.1% of calorimetric recorded in step 4.5.6.

Monitors DVM while re-engaging the locking device to ensure it

3) CHECK average deviation on doesn't change.

"NUCLEAR PWR- t.T PWR (%)"is 0.0% (-0.5% to+ 0.5%).

4) MONITOR "t.T PWR" indication I

(DVM) and ENGAGE locking device on "t.T PWR CALIBRATE" I potentiometer. I I

5) IF DVM indication changed while engaging locking device, REPEAT step 4.5.8.h.

Cue:

Comments: Causing a reactor trip during calibration constitutes a failure during this JPM.

Page 10 of 14

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JPM Number: S-7 Rev. 0 VERIFICATION OF JPM COMPLETION

Title:

RPS Calibration with One Channel Inoperable for > 48 Hours Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes

- - No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 12 of 14

JPM Number: S-7 Rev. 0 EXAMINEE HANDOUT Initial Conditions:

The plant is in MODE 1, at approximately 100% and stable

RPS Channel "A" trip units have been tripped due to the failure of the linear power range instrument 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months ago.

Initiating Cues:

You are the BOP operator.

You are directed to perform calibration of the OPERABLE RPS channels in accordance with SP-2601 D, Power Range Safety Channel and Delta T Power Channel Calibration.

JOB PERFORMANCE MEASURE CONTROL ROOM I IN-PLANT JPM S-8

JPM Number: S-8 Rev. 0 JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: S-8 Task

Title:

Initiate Containment Purge Via Enclosure Building Filtration System System: Containment Purge Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes):

Task No.(s): NUTIMS 029-01-018 KIA No. 029.A1.02 KIA Rating 3.4, 3.4 Method of Testing:

Simulated Performance: Actual Performance: X Location:

Classroom:

Simulator:

- -X- - In-Plant:

Task Standards: Operate the containment purge system to place containment purge in service using EBFS Train A and the containment cleanup flow path and take proper manual action to ensure purge valve closure following faulted containment high radiation condition.

Required Materials OP-23148, Rev. 022-10 (procedures. equipment):

General

References:

OP-2314B, Rev. 022-10

ARP 2590E-135, (Alarm Window DA-24), Rev 001-04

ARP 2590H-009B (RM8123 Cntmt Particulate Hi), Rev 000-01

Dwgs 25203-26028 Shts 1 (B-11, C-2), 2 (D-1) and 5 (H-12)

JPM based on Bank JPM 33 (modified)

Page 1 of 11

JPM Number: S-8 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER** * *

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

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

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

Simulator

Initialize in any Mode 5 IC with E8FS not in operation.

Requirements:

Install fuses for AC-4/5/6/7 using CHR04.

Ensure "CTMT PURGE EXH DMPR, AC-57" is closed and place a red tag on hand switch at C-01.

Set R8VIS bistable on ESAS to maximum, such that RM-8123 does not cause R8VIS.

Use Sim Malf RM02C at 90% severity to drive RM-8123 to high alarm approximately 15 seconds after the examinee completes OP-23148 Step 4.1.21 (JPM Step 12)

Initial Conditions: 1

It is February 16 h

Outside air temperature is 33°F.

The plant is in MODE 5.

A plant cooldown is in progress for emergent welding work on a leaking reactor coolant loop drain valve.

Chemistry has sampled and analyzed Containment atmosphere.

Chemistry analysis of containment atmosphere sample indicates:

3

);;> 3x1 o- 1JCilcc noble gas

);;> 1x1 o- 5 1JCi/cc iodine and particulates with half-lives > 8 days

The sample results have been recorded in the SM log.

I&C has set the Containment atmosphere radiation monitor alarms and ESAS bistable trips to the Unit 1 stack high radiation alarm setpoint.

Containment Purge Exhaust Damper AC-57 has been red tagged closed.

Section 4.1 of OP-23148, Initiating Containment Purge Using E8FS Page 2 of 11

JPM Number: S-8 Rev. 0 and Containment Cleanup Flow Path, has been completed through Step 4.1.11.

EBFS filter fan run hours are NOT expected to exceed 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months during this evolution Initiating Cues: You are the BOP operator. You are directed to begin at Step 4.1.12 of OP-23148 to continue placing containment purge in service using EBFS Train A and the Containment Cleanup Flow Path.

Page 3 of 11

JPM Number: S-8 Rev. _ _ 0_

START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. ALIGN condenser air removal fan discharge Examinee opens E8-57 on C-06 and N from Millstone stack to Unit 2 stack, as observes red light only is lit and closes E8-OP-23148 follows (C-06): 56 and E8-55 on C-06 and observes each Step 4.1.12 a. OPEN E8-57, "COND AIR RMVL UNIT respective green light only is lit.

2 STACK."

b. ENSURE E8-55, "COND AIR RMVL MILLSTONE STACK," closed.

c. ENSURE E8-56, "COND AIR RMVL MILLSTONE STACK," closed.

Cue: I Comments: I

2. IF locking devices are installed AND fuse Examinee may state that they would have N blocks are removed, the blocking devices removed and the fuse OP-23148 blocks installed.

Step a. REMOVE the locking devices and 4.1.13.a INSTALL fuse blocks at the following locations (C01 R):

AC-4, "CTMT PURGE OUT8D ISOL,"

(F8-CFA-C01 R)

AC-5, "CTMT PURGE IN8D ISOL,"

(F8-DFJ-C01 R)

AC-6, "CTMT PURGE IN8D ISOL,"

(F8-DFR-C01 R)

AC-7, "CTMT PURGE OUT8D ISOL,"

(F8-CFH-C01 R)

Cue: The fuse blocks are installed and the blocking devices removed for AC-4, 5, 6, and 7 are installed.

Page 4 of 11

JPM Number: S-8 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (5/U)

Comments: Part of the simulator setup has the fuses installed and the examinee may note that fuses have already been installed. However they may send someone to verify that the fuses are installed.

3. ENSURE AC-57, "CTMT PURGE EXH Examinee notes that initial condition sheet N DMPR," is closed or red tagged closed. states that AC-57 is red tagged closed.

OP-23148 Step 4.1.14 Cue:

Comments: Examinee may point out that there is a red tag on AC-57 control switch.

4. OPEN AC-6, "CTMT IN8D ISOL DMPR." Examinee takes control switch for AC-6 to y the open position and notes red only light OP-23148 lit.

Step 4.1.15 Cue:

Comments:

5. OPEN AC-7, "CTMT OUT8D ISOL DMPR." Examinee takes control switch for AC-7 to y the open position and notes red only light OP-23148 lit.

Step 4.1.16 Cue:

Comments:

6. IF using "A" E8FS train, OPEN the Examinee takes the control switches for y following: E8-51 and E8-73 to the open position and OP-23148

E8-51, "E8FS HDR A ISOL" observes the red light lit for each valve. I Step 4.1.17

E8-73, "CTMT CLEANUP TO E8FS" Cue:

Comments:

Page 5 of 11

JPM Number: S-8 Rev.--=--0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

7. !E using "8" E8FS train, OPEN the Examinee notes that this step is Not N following: Applicable because only using Train "A" OP-23148

E8-41, "E8FS HDR B ISOL" E8FS.

Step 4.1.18

E8-72, "CTMT CLEANUP TO E8FS" Cue:

Comments:

8. OPEN the following (C-01 ): In order the examinee opens AC-1, AC-4 y

a. AC-1, "SPLY FAN." and AC-5 by placing the control switch to OP-23148 b. AC-4, "CTMT OUT8D ISOL DMPR." the open position and observes the red Step 4.1.19 c. AC-5, "CTMT IN8D ISOL DMPR." light lit on each of the valves Cue:

Comments:

9. NOTE: AC-3 switch is positioned to open, Examinee reads note and acknowledges N then to mid, to vent air from the actuator to that it applies to opening AC-3 in the next OP-23148 get the valve to move to a mid position. step.

NOTE Cue:

Comments:

1 0. PLACE AC-3, "E8 PURGE SUPPLY Examinee should note the placard on the y DMPR," in "OPEN," then to "MID (20,000 control board that AC-3 does not operate I OP-23148 CFM)" (C-01 ). when going from close to mid.

Step 4.1.20 I The examinee should take the control I switch for AC-3 to the open position and then to the mid position.

Cue: If the examinee asks a PEO to check the position of AC-3 and has not taken the control switch to the open position, state that AC-3 is closed. If examinee asks a PEO to check the position of AC-3 and the examinee has operated the control switch properly, report that AC-3 is in a mid-position. ------- -- ***-- ****------------

Page 6 of 11

JPM Number: S-8 Rev.

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Comments:

11 . F-23, "PURGE SPLY FAN," must not be Examinee reads the CAUTION. N started.

OP-23148 CAUTION Cue:

Comments: If during this JPM the examinee starts the purge supplyfan, F-23, it will constitute a failure of the JPM.

12. IF using the "A" E8FS train, PERFORM the Examinee starts F-25A by taking y following (C-01 ): handswitch "E8FS FAN A, F-25A" to OP-23148 a. START F-25A, "E8FS FAN A." "START" and observing its red light only lit Step 4.1.21 b. CHECK E8-52, "E8FS FAN A DIS and checking E8-52 open by observing its DMPR," open. red light only lit.

Cue:

ALTERNATE PATH BEGINS HERE Comments: About 15 seconds after the examinee has initiated the purge, RIT -8123A CTMT Particulate Radiation Monitor will go into high alarm. The examinee should recognize that the purge did not isolate on a reactor building ventilation isolation signal (R8VIS) on high radiation level. The examinee is expected to take action to secure purge- by manually closing valves per alarm response xocedures.

1 3. Refer To the following LCOs and Examinee informs unit supervisor of N I DETERMINE applicability: guidance to refer to tech specs.

ARP ... I 2590E-135 Step 1 Cue: Inform examinee that Unit Supervisor will refer to Tech Specs.

Comments: Examinee may decide to secure the containment purge by manually initiating R8VIS.

Page 7 of 11

JPM Number: S-8 Rev. _ _ 0_

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U) 1 4. OBSERVE which process radiation monitor Examinee goes behind main boards to rad N is alarming (RC-14). monitor panels and determines RM-8123 ARP is in high alarm.

2590E-135 Step 2 Cue:

Comments:

1 5. IF no "ALARM" OR "INSTRUMENT FAIL" Examinee determines step is not N lights lit, PERFORM the following (RC-14): applicable. RM-8123 is in high alarm.

ARP 2590E-135 Step 3 Cue:

Comments:

1 6. Refer To ARP 2590H, "Alarm Response for Examinee refers to ARP 2590H-009A or B N Control Room Radiation Monitor Panels," as appropriate for the high alarm on RM-ARP and PERFORM applicable corrective 8123. I 2590E-135 actions for alarming radiation monitor.

Step 4 I Cue: !

Comments: !

1 7. OBSERVE radiation monitor indication (RC- Examinee verifies RM-8123 in high alarm. N 14A, PPC, ESAS).

ARP 2590H-009NB Step 1 Cue:

Comments: --

Page 8 of 11

JPM Number: S-8 Rev. _ _ 0 _

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U) 1 8. COMPARE indication to setpoint indicated Examinee notes that this step is not N on "SETPOINT" sticker on module. applicable.

ARP 2590H-009A/B Step 2 Cue:

Comments:

1 9. CHECK PROCESS RADIATION, RR- Examinee checks trend data. N I 8123A/B for trend data (RC-14A).

ARP I 2590H-009A/B Step 3 Cue:

Comments:

20. IF high alarm or instrument failure has Examinee determines automatic actions y occurred, VERIFY all automatic functions did not occur and manually closes AC-6 ARP have taken place (C-01 ). and AC-7 to isolate containment purge.

2590H-009A/B Step 4 Cue:

Comments: If applicant decides to perform normal containment purge shutdown lAW OP-23148, then ask follow up questions to determine whether he/she recognized the failure of RBVIS.

Terminating Cue: The JPM is complete when applicant has secured the containment purge and the above step is complete.

STOP TIME:

Page 9 of 11

JPM Number: S-8 Rev. __a:___

VERIFICATION OF JPM COMPLETION

Title:

Initiate Containment Purge Via Enclosure Building Filtration System Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 10 ofll

JPM Number: S-8 Rev. __o __

EXAMINEE HANDOUT Initial Conditions:

It is February 16th

Outside air temperature is 33°F.

The plant is in MODE 5.

A plant cooldown is in progress for emergent welding work on a leaking reactor coolant loop drain valve.

Chemistry has sampled and analyzed Containment atmosphere.

Chemistry analysis of containment atmosphere sample indicates:

3x1 o- IJCi/cc noble gas 3

).-

).- 1x1 o- 1-.1Ci/cc iodine and particulates with half-lives > 8 days 5

The sample results have been recorded in the SM log.

I&C has set the Containment atmosphere radiation monitor alarms and ESAS bistable trips to the Unit 1 stack high radiation alarm setpoint.

Containment Purge Exhaust Damper AC-57 has been red tagged closed.

Section 4.1 of OP-23148, Initiating Containment Purge Using EBFS and Containment Cleanup Flow Path, has been completed through Step 4.1.11.

EBFS filter fan run hours are NOT expected to exceed 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months during this evolution Initiating Cues: You are the BOP operator. You are directed to begin at Step 4.1.12 of OP-23148 to continue placing containment purge in service using EBFS Train A and the Containment Cleanup Flow Path.

JOB PERFORMANCE MEASURE P-1

JPM Number: P-1 Rev. - - 0 -

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: P-1 Task

Title:

Appendix R Actions for a Fire in Fire Area R-1 System: Electrical Distribution I Appendix R Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 20 Task No.(s): NUTIMS #000-04-113 KIA No. APE-068-AA 1.21 KIA Rating 3.9, 4.1 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 transferred control from the Control Room to Fire Shutdown Panel C-10, and secured the A Diesel Generator using AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1.

Required Materials AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire (procedures, equipment): Area R-1, Rev. 010-02 General

References:

OP-23148, Rev. 022-10

ARP 2590E-135, (Alarm Window DA-24), Rev 001-04

ARP 2590H-009B (RM8123 Cntmt Particulate Hi), Rev 000-01

Dwgs 25203-26028 Shts 1 (B-11, C-2), 2 (D-1) and 5 (H-12)

JPM based on Bank JPM 33 (modified)

Page 1 of 10

JPM Number: P-1 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER** * *

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

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

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

Simulator

Not Applicable Requirements:

Initial Conditions:

A serious fire is in progress in the Control Room.

The reactor is tripped.

The Shift Manager has announced the evacuation of the Control Room.

Steps 1-7 of AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1 are complete.

Normal communications are available.

Initiating Cues: You have been directed by the Unit Supervisor to obtain the required keys and perform required local actions per AOP 2579A, Steps 8 thru 12.

Page 2 oflO

JPM Number: P-1 Rev.

- START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

1. NOTE Examinee reads and acknowledges that N Operating "#2 S/G AUX. FW F.C.V. 2-FW- when the handswitch for 2-FW-438 is AOP 438 (HS-52790)" in the following step taken to LOCAL, the valve will open.

2579A opens 2-FW-438.

Prior to Step 8 Cue:

Comments:

2. PLACE the following isolation switches in Examinee obtains the necessary key (Key y "LOCAL" (C-10): 164) in the SM key locker.

AOP 2579A Examinee proceeds to Upper 4160V Step 8 Switchgear Room and unlocks the Fire Shutdown Panel, C-10.

Cue:

Comments: Opening C-10 will bring in Annunciator 040 on Control Room Panel C-01.

3. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-10): C-1 0 in LOCAL.

AOP * "AUX. FW TUR8. STEAM INLET HS- I 2579A 41880" I Step 8 I (continued)

I Page 3 of 10

JPM Number: P-1 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Cue: If asked, inform examinee that the GREEN light illuminates- on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL.

Comments:

4. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-10): C-10 in LOCAL.

AOP * "#2 S/G AUX. FW F.C.V. 2-FW-438 2579A (HS-52790)"

Step 8 (continued)

Cue: If asked, inform examinee that the GREEN light illuminates, then both RED and GREEN are illuminated, and then the GREEN extinguishes - on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL.

Comments:

5. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-1 0): C-1 0 in LOCAL.

AOP 2579A

"TDAFP SPD CTL" HS-41920" Step 8 (continued)

I Cue: If asked, inform examinee that the WHITE lights illuminate- on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL. I Comments: I

6. PLACE the following isolation switches in Examinee places isolation switches on y I "LOCAL" (C-10): Panel C-1 0 in LOCAL.

I AOP * "CHARGING PUMP C P18C (HS-2579A 20050)" I Step 8 (continued) * "CHARGING PUMP 8 P188 (HS- I 20040)"

I Page 4 of 10

JPM Number: P-1 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Cue: If asked, inform examinee that the GREEN lights illuminate- on the adjacent handswitches associated with the components after their isolation switches are placed in LOCAL.

Comments:

7. PLACE the following isolation switches in Examinee places isolation switch on Panel y I

"LOCAL" (C-10): C-1 0 in LOCAL.

AOP 2579A

"CHARGING HEADER ISOL. 2-CH- I 429 (HS-25248)" I Step 8 I

(continued)

Cue: If asked, inform examinee that the RED light illuminates, then both RED and GREEN are illuminated, and then the RED extinguishes - on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL.

Comments:

8. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-10): C-1 0 in LOCAL.

AOP * "REGEN HX DISCHARGE ISOL. 2-2579A CH-089 and 2-R8-402 (HS-25258)"

Step 8 (continued)

Cue: If asked, inform examinee that the RED light illuminates- on the adjacent handswitch associated with these components after the isolation switch is placed in LOCAL.

Comments: HS-25258, is labeled different than the procedure: plant label is "LTON ISOL & LTON HX TCV CH-089 & R8-402".

9. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-10): C-10 in LOCAL.

AOP * "LOOP 1A CHARGING ISOL. 2-CH-2579A 519 (HS-25198)"

Step 8 (continued)

Page 5 of 10

JPM Number: P-1 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

Cue: If asked, inform examinee that the RED light illuminates, then both RED and GREEN are illuminated, and then the RED extinguishes - on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL.

Comments:

1 0. PLACE the following isolation switches in Examinee places isolation switch on Panel y "LOCAL" (C-10): C-10 in LOCAL.

AOP * "AUX SPRAY ISOL 2-CH-517 HS-2579A 2517B" Step 8 (continued)

Cue: If asked, inform examinee that the GREEN light illuminates- on the adjacent handswitch associated with the component after its isolation switch is placed in LOCAL.

Comments: Ensure C-1 0 is locked upon completion of this step. Also, notify the Control Room to regard all further alarms and return the key to the locker. Opening C-1 0 will bring in Annunciator D40 on Control Room Panel C-01.

11 . PLACE "#2 ATMOS. DUMP HIC-4224A" in Examinee places HIC-4224A in M and N AOP "M" and ENSURE that 2-MS-1908, #2 SG verifies output at zero.

2579A Atmospheric Dump, is closed (C-10).

Step 9 I Cue:

Comments: !

1 2. Refer To Attachment 2, "Breaker 10.10.1 The applicant continues on with Step 11 I Alignment in the DC Switchgear after being informed that another operator AOP Rooms," and PERFORM the specified has completed Attachment 2.

2579A actions.

Step 10 Cue Another operator has completed the Attachment 2 actions.

Comments: -

Page 6 of 10

JPM Number: P-1 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U) 1 3. ENSURE that BOTH of the following valves Examinee closes CH-089 by taking HS- y are closed (C-10): 2525A to close and observes that 2-CH-AOP 089 and 2-CH-517 are closed by 2579A

2-CH-089, Regenerative Heat observing green lights only lit.

Exchanger Discharge Isolation Step 11

2-CH-517, Auxiliary Spray Isolation Examinee reports to Control Room that AOP 2579A Steps 8, 9 and 11 are complete Cue: Green lights only lit for 2-CH-089 and 2-CH-517.

Comments:

1 4. CAUTION Examinee reads and acknowledges N Once DC power has been lost to DG A, caution. I AOP failure to promptly secure DG A could result 2579A in damage to the DG. I Prior to Step 12 Cue:

Comments:

- - - ~-

- - ~-

Page 7 of 10

JPM Number: P-1 Rev. 0 CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) (S/U)

15. ENSURE that DG A is secured by y performing the following (A DG Room): Examinee proceeds to the A Diesel AOP a. IF DG A is operating, PRESS the Generator room.

2579A "EMERGENCY STOP" mechanical Step 12 overspeed trip button (north side of Examinee marks Step 12.a. N/A because DG). A DG is not running.

b. ENSURE the following DG A fuel oil supply and air start valves are Examinee closes 2-F0-17, 2-DG-30A closed:

and 2-DG-308 by unlocking and taking

2-F0-17, "FUEL OIL HEADER their valve handles in the clockwise STOP TO "A" DIESEL direction to a hard-stop.

GENERATOR"

2-DG-30A, "DIG 12U AIR START Examinee informs the Unit Supervisor that HEADER A ISOLATION" the A Diesel Generator is secured.

2-DG-308, :D/G 12U AIR START HEADER 8 ISOLATION" Cue: The A Diesel Generator is NOT running.

2-F0-17, 2-DG-30A and 2-DG-308 are closed.

The Control Room acknowledges report that A DG is secured.

Comments:

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 8 of 10

JPM Number: P-1 Rev. 0 -

VERIFICATION OF JPM COMPLETION

Title:

Appendix R Actions for a Fire in Fire Area R-1 Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

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

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 9 of 10

JPM Number: P-1 Rev. 0 EXAMINEE HANDOUT Initial Conditions:

A serious fire is in progress in the Control Room.

The reactor is tripped.

The Shift Manager has announced the evacuation of the Control Room.

Steps 1-7 of AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1 are complete.

Normal communications are available.

Initiating Cues: You have been directed by the Unit Supervisor to obtain the required keys and perform required local actions per AOP 2579A, Steps 8 thru 12.

JOB PERFORMANCE MEASURE P-2

JPM Number: P-2 Rev. 0 -

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: P-2 Task

Title:

Local Manual Operation of the A Atmospheric Dump Valve System: Main Steam System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes): 15 Task No.(s): NUTIMS 035-01-029 KIA No. 039-A2.04 KIA Rating 3.4/3.7 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 taken local manual control of the A Atmospheric Dump Valve (ADV) and placed it to 25%

open per EOP 2541 Appendix 36, ADV Local Operation.

Required Materials EOP 2541, Appendix 36, ADV Local Operation, Rev. 000-01

{procedures. equipment):

General

References:

EOP 2525, Standard Post Trip Actions JPM based on Bank JPM 93 Page 1 of 10

JPM Number: P-2 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including Jogs. Make all written reports, oral reports, alarm acknowledgments, and Jog entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER* * * *

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

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

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

Simulator Not Applicable Requirements:

Initial Conditions:

A loss of Instrument Air has occurred in the plant.

The plant is tripped and the crew has entered EOP 2525 Standard Post Trip Actions.

The crew decided to use the A Atmospheric Dump Valve (ADV) to remove decay heat.

Initiating Cues:

You have been directed by the Unit Supervisor to take local manual control of the A ADV and open the valve to 25% using EOP Appendix 36, ADV Local Operation.

Page 2 of 10

JPM Number: P-2 Rev. 0 START TIME:

CRITICAL GRADE I STEP PERFORMANCE STANDARD (Y/N) (S/U) J

1. IF C-21 operation of the ADV is desired, Examinee marks step N/A. N I Refer To Attachment 36-C, "Remote I EOP2541- Operation of ADV atnC- 21 ". I App36 Step 1 Cue:

Comments:

2. CAUTION Examinee reads and acknowledges N Elevated ambient air temperatures in the caution.

EOP2541- East and West penetration rooms may App36 result in conditions that cause heat related Step 1 health concerns.

Cue:

Comments:

3. DETERMINE local ambient air Examinee enters East Penetration Room N temperatures for the applicable penetration and reads local thermometer on wall just EOP2541- rooms by reading local area thermometers. inside the door.

App36 Step 1 Cue: Using pen, indicate thermometer reading of- 98°F Comments:

Page 3 of 10

JPM Number: P-2 Rev. 0

4. NOTE Examinee reads and acknowledges note. N The following equipment may be required to EOP2541- perform the following step:

App36

Ice Vest may be obtained from the Step 1N Maintenance Tool Crib.

Cool Suits may be obtained from the HP Control Point.

Gloves are part of the PEO normal watch station equipment.

Cue:

Comments:

5. CHECK local ambient air temperatures less Examinee verifies temperature is below N than 120°F. 120°F and states no additional safety EOP2541- equipment needed.

App36 Step 1 Cue:

Comments:

6. IF local operation of the ADV is desired, Examinee refers to Attachment 36-A for N Refer To Attachment 36---A, Establishing Establishing Local ADV Control EOP2541- Local ADV Control.

App36 Step 1 Cue:

Comments:

7. ESTABLISH communications with the Examine states they would establish N Control Room. communications with the Control Room EOP2541- using either Gai-Troincs located on station App36 or other suitable communication device.

Step 1 Cue: Communication with the Control Room has been established.

Page 4 of 10

JPM Number: P-2 Rev. 0 Comments: I

8. ENSURE ADV manual isolation valve, MS- Examinee states they would verify 2-MS- N I

EOP2541- 3A is open. 3A is open by rotating the valve hand I App36 wheel in the clockwise direction, verifying I Step 1 movement then return it to its original I position or they may state that the valve I stem is fully raised.

Cue: ADV Manual Isolation valve, 2-MS-3A, hand wheel rotates in the clockwise direction or the valve stem is in the full out position.

Comments:

9. REMOVE the "VENT VALVE" assembly Examinee locates the VENT VALVE and y from the instrument rack located below the removes it by releasing the quick EOP2541- ADV. disconnect.

App36 Step 1 Cue:

Comments:

10. ENSURE the "VENT VALVE" assembly is Examinee verifies the whitey valve on the N closed. vent rig closed by rotating the hand wheel EOP2541- in the clockwise direction.

App36 Step 1 Cue: ADV Manual Isolation valve, 2-MS-3A, hand wheel is rotated in the clockwise direction. Valve is at a hard stop.

Comments:

11. NOTE Examinee reads and understands note. N EOP2541- Isolating instrument air to an ADV will result Examinee should recognize as part of the App36 in the valve failing to the closed position. initial conditions that the valve is already in Step 1 the closed position due to the loss of Instrument Air.

Cue:

Comments: If the examinee does not state that the valve is already failed closed,_guestion them as to the status of the valve.

Page 5 of 10

JPM Number: P-2 Rev. 0

12. CLOSE the instrument air isolation valve to Examinee locates the Instrument air y the ADV. isolation valve and rotates it in the EOP2541- clockwise direction to a hard stop.

App36 Step 1 Cue: Valve rotates clockwise to a hard stop.

Comments: Valve is located on the Containment wall behind the ADV.

13. REMOVE the vent cap from the quick Examinee states that they remove the y disconnect at the top of the ADV operator quick disconnect vent cap from the top of EOP2541- diaphragm. the ADV diaphragm.

App36 Step 11 Cue: Vent cap is removed Comments:

14. INSERT the VENT VALVE assembly into Examinee connects the VENT VALVE y the quick disconnect. assembly on the top of the operator EOP2541- diaphragm using the quick connect. I I

App36 I Step 1 I Cue:

Comments:

15. OPEN the vent valve assembly to ensure Examinee states that they would rotate the y air has been vented off the ADV operator. whitey valve on the VENT VALVE EOP2541- assembly in the counterclockwise direction App36 to a hard stop. Examinee states they may Step 1 hear some residual air bleed off.

Cue: Valve is rotated in the counterclockwise direction to a hard stop. A small amount of air bleed off is heard. Airflow has stopped.

Comments: - -- -- ------ *- -- *- * - - ---- *- - * - - -- - - - - - - -----------------

Page 6 of 10

JPM Number: P-2 Rev. 0

16. ENSURE that the ADV is closed. Examinee states that the valve is closed N by verifying the local valve position EOP2541- indicator and by evidence of no steam flow App36 noise.

Step 1 Cue: Acknowledge indications. Using pen, show valve position as closed. No steam flow noise is heard.

Comments:

17. REMOVE the hand wheel retaining device. Examinee removes restraining device. y AOP2556 Steps 4.20, 4.24 and 4.26 h-m Cue: Restraininq device has been removed.

Comments:

18. NOTE Examinee reads and acknowledges note. N ADV hand wheels are reverse operated.

AOP2556 Steps 4.20, I 4.24 and I I

4.26 h-m I Cue: I Comments:

19. POSITION the ADV as directed by the Examinee states they contact the control y Control Room. room and communicates to them that them AOP2556 they are ready to open the A ADV 25%

Steps 4.20, open.

4.24 and 4.26 h-m Examinee states that they need to rotate the valve hand wheel in the clockwise direction until the position indicator indicates 25%.

Cue: The Control Room acknowledges communication. Using a pen show valve position moving to the 25% open indication.

Comments:

Page 7 of 10

Rev.

JPM Number: P-2 - -

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 8 of 10

JPM Number: P-2 Rev. __0:......__

VERIFICATION OF JPM COMPLETION

Title:

Local Manual Operation of the A Atmospheric Dump Valve Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 9 of 10

JPM Number: P-2 Rev. 0 -

EXAMINEE HANDOUT Initial Conditions:

A loss of Instrument Air has occurred in the plant.

The plant is tripped and the crew has entered EOP 2525 Standard Post Trip Actions.

The crew decided to use the A Atmospheric Dump Valve (ADV) to remove decay heat.

Initiating Cues:

You have been directed by the Unit Supervisor to take local manual control of the A ADV and open the valve to 25% using EOP Appendix 36, ADV Local Operation.

JOB PERFORMANCE MEASURE P-3

JPM Number: P-3 Rev. -~0=----

JOB PERFORMANCE MEASURE WORKSHEET Facility: Millstone Unit 2 JPM Number: P-3 Task

Title:

Manual Boration to the Reactor Coolant System System: Chemical and Volume Control System Time Critical Task: Yes No X Alternate Path: Yes No X Validated Time (minutes):

Task No.(s): NUTIMS KIA No. 004-A2.14 KIA Rating 3.8/3.9 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 commenced a manual boric acid addition to the Reactor Coolant System from the Boric Acid Storage Tanks in accordance with AOP 2551, Shutdown from Outside the Control Room, Attachment 1, Manual Boration.

Required Materials AOP 2551, Shutdown from Outside the Control Room, Rev. 09-03

{procedures. equipment):

General

References:

Page 1 of7

JPM Number: P-3 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 job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including Jogs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.

* *

NOTES TO EXAMINER * * * *

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

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

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

Simulator Not Applicable Requirements: I Initial Conditions:

Plant is in Mode 3, approximately 25 minutes following a reactor trip due to the Control Room becoming uninhabitable (not due to a fire).

The Control Room has been evacuated.

The Unit Supervisor has entered AOP 2551, Shutdown from Outside the Control Room and completed steps 3.1 - 3.19.

The plant is being controlled at the Hot Shutdown Panel, C-21.

The Unit Supervisor and a Reactor Operator are stationed at C-21.

Communications are being maintained via portable radios.

Initiating Cues:

In preparation for a plant cooldown to Mode 5, the Unit Supervisor has directed you to perform a manual boration from the Boric Acid Storage Tanks (BASTs) to the reactor coolant system using AOP 2551, Shutdown from Outside the Control Room, Attachment 1, Manual Boration. Start at step 3.20 of AOP 2551, Shutdown from Outside the Control Room. All previous steps have been completed.

The examiner will act as the Unit Supervisor.

Page 2 of7

JPM Number: P-3 Rev. 0 START TIME:

CRITICAL GRADE STEP PERFORMANCE STANDARD (Y/N) {S/U)

1. NOTE Examinee reads note. N Berating the RCS should be considered if it AOP2551 is anticipated cooling the RCS down to a lower mode.

Cue:

Comments:

2. IF desired to borate the RCS, PERFORM Examinee proceeds to the 14'6" Auxiliary y the following: Building, locates and opens the following AOP2551 a. CONTACT Reactor Engineer for breakers:

Step 3.20 assistance in determining SDM and required boration.

B5151, "BORIC ACID STORAGE TANK B GRAVITY

b. OPEN the following supply breakers FEED ISOLATION, 2-CH-508" (14'6", Aux. Bldg.):

B5151, "BORIC ACID

B5149, "BORIC ACID STORAGE TANK B GRAVITY STORAGE TANK A GRAVITY FEED ISOLATION, 2-CH-508" FEED ISOLATION, 2-CH-509"

B5149, "BORIC ACID STORAGE TANK A GRAVITY

B5145, 2-CH-501, "VCT FEED ISOLATION, 2-CH-509" OUTLET HEADER TO

B5145, 2-CH-501, "VCT CHARGING PUMPS" OUTLET HEADER TO CHARGING PUMPS" Cue: Reactor Engineer acknowledges your request.

If the examinee inquires, the Unit Supervisors directs Boric Acid addition to commence without a known stop time.

Breakers are open.

Comments: -- -

Page 3 of7

JPM Number: P-3 Rev. 0

3. c. Refer to Attachment 1 "Manual Boration." Examinee turns to Attachment 1. N AOP2551 Step 3.20 continued Cue:

Comments:

4. ENSURE at least ONE charging pump is Examinee says that he/she would contact N AOP2551 operating (C-21 ). the operator at the Hot Shutdown Panel, Att1 C-21 and request charging pump status.

Step 1.1 Cue: Operator at C-21 reports that Charging Pump 'C' is running.

Comments: Examinee may verify Charging Pump C is running locally at the pump.

5. MONITOR BAST levels AND CHECK at Examinee goes to the BAST Area and y least ONE BAST level greater than 10% (C- observes that at least one BAST level is AOP2551 10 or BAST area). above 10%.

Att1 Step 1.2 Cue: The Unit Supervisor reports that access to C-1 0 is not available at this time.

Comments:

6. Manually OPEN the following: (-5'6", Aux Examinee goes to the -5'6", Aux Bldg. and y Bldg.): opens CH-508 and CH-509.

AOP2551 Att1 a. CH-508, " 'B' GRAVITY FEED" Step 1.3 b. CH-509, "'A' GRAVITY FEED" Cue: CH-508 and CH-509 are in the fully counter-clockwise position.

Comments:_ L__- - --- -- - - - - -

Page 4 of7

JPM Number: P-3 Rev. 0

7. NOTE Examinee reads note. N I VCT pressure prevents boric acid flow from I AOP2551 the BASTs if CH-501, "VCT OUTLET I Att1 HEADER TO CHARGING PUMPS," is I open.

Cue:

Comments:

8. Manually CLOSE CH-501, "VCT OUTLET Examinee goes to the degasifier room and y HEADER TO CHARGING PUMPS," and closes CH-501.

AOP2551 COMMENCE timing Boric Acid addition(-

Att1 25'6", degasifier room). Examinee reports to the Unit Supervisor Step 1.4 that he/she has started the Boric Acid addition and notes the time of start.

Cue: CH-501 is in the fully counter-clockwise position.

The Unit Supervisor acknowledges status Boric Acid addition.

Comments: CH-501 is located in the degasifier room. Examinee will need to notify RP and obtain a key to enter the room.

Terminating Cue: When the above step is achieved, the JPM is complete.

STOP TIME:

Page 5 of7

JPM Number: P-3 Rev. __0=---

VERIFICATION OF JPM COMPLETION

Title:

Manual Boration to the Reactor Coolant System Date Performed:

Examinee:

NRC Examiner:

Number of Attempts:

For examinee 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.

Time Critical Task? Yes

- - No X Validated Time (minutes):

Actual Time to Complete (minutes):

Overall Result of JPM: SAT UNSAT (circle one)

Question Documentation:

Examiner's signature and date:

Page 6 of7

JPM Number: P-3 Rev. 0 EXAMINEE HANDOUT Initial Conditions:

Plant is in Mode 2, approximately 25 minutes following a reactor trip due to the Control Room becoming uninhabitable (not due to a fire).

The Control Room has been evacuated.

The Unit Supervisor has entered AOP 2551, Shutdown from Outside the Control Room and completed steps 3.1 - 3.19.

The plant is being controlled at the Hot Shutdown Panel, C-21.

The Unit Supervisor and a Reactor Operator are stationed at C-21.

Communications are being maintained via portable radios.

Initiating Cues:

In preparation for a plant cooldown to Mode 5, the Unit Supervisor has directed you to perform a manual boration from the Boric Acid Storage Tanks (BASTs) to the reactor coolant system using AOP 2551, Shutdown from Outside the Control Room, Attachment 1, Manual Boration. Start at step 3.20 of AOP 2551, Shutdown from Outside the Control Room. All previous steps have been completed.

The examiner will act as the Unit Supervisor.

SIMULATOR SCENARIO #3 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 3 Op-Test No.: NRC 2014 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power IC, BOL, Equilibrium Xenon, 1105 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C, Channel "C" Wide Range Containment Pressure safety instrument is OOS. Winds are NE 54° at 40 mph.

Turnover: 100% power, SOL, equilibrium Xenon, 1105 ppm Boron, blend ratio: 4.32: 1.0, SGBD @

40gpm per Steam Generator, 24E is aligned to 24C. High winds reported on Long Island Sound.

Channel "C" Wide Range Containment Pressure (PI-8115) instrument is OOS. Entered TS 3.3.1.1 Action 2 for RPS Instrumentation and 3.3.2.1 Action 2 for ESAS Instrumentation 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

Prerequisites met for SP2606D 2-CS-4.1 B Stroke and Timing IST. Perform 1ST at the start of this shift.

Critical Tasks:

1. Manually Shutdown the reactor. The reactor must be manually tripped using the CEDM output breakers immediately (within 1 minute) when an automatic reactor trip fails and/or the manual push buttons do NOT work. (CT-1/SPTA-5)

2. The operator is required to trip all RCPS within 5 minutes of the loss of NPSH, following a Small Break LOCA (SBLOCA).

Event Malf. No. Event Event Description No. Type*

N (ATC, 1 BOP) Stroke time out of specification during Surveillance Procedure SP-RHHS-(0 min) 3022 1 26060 for stroke test of Containment Spray Valve CS-4.1 B.

TS (SRO)

RX03B RXHS- Pressurizer Pressure Transmitter Y fails high, BOTH spray valves I (ATC, 100-2_1, open.

2 SRO)

RXHS-(10 min) 100-2_3, During transient, Pressurizer Proportional Heater Group 2 breaker 02A2A5S5 TS (SRO) trips open. (EN-49779) 3 C (BOP, SW09A Service Water Pump "A" strainer high D/P (4psid and rising)

(30 min) SRO) 4 (40 min) FW39A High vibration on "A" SGFP (both HP/LP bearings >3mils, <5mils)

N (All)

Scenario 3 1 of 34

Appendix D Scenario Outline Form ES-D-1 R (SRO, 5 Rapid power reduction in preparation for "A" SGFP offline at -65%

ATC, (43 min) power BOP)

TU02A Turbine High Vibration results in manual scram (greater than 12 RP04A-D 6 mils sustained). Reactor Trip manual pushbuttons do not work and RD0202 M (All)

(60 min) Automatic Reactor trip disabled (ATWS). 8 CEAs fail to insert on thru 0209 RP27B reactor trip (ATWS). Emergency Boration required.

7 RC04, C (ATC) RX Head Vent Leak and RCS cold leg break Loop 1A (LOCA)

(61 min) RC03A

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Actual Section D.S.d)

1. Total malfunctions(_5-8)_ 6

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 2 Scenario 3 2 of34

NRC 2014 Scenario 3 Summary The crew will take the shift with the unit at 100% power and 24E aligned to 24C. The "C" Channel Containment Wide Range pressure instrument is out of service and the off-going crew entered Technical Specification Action statements for RPS and ESAS instrumentation 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the crew assuming the shift. The appropriate RPS and ESAS channels have been bypassed and I&C expects to return the instrument to operable within the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Event 1: The crew has been directed to perform Surveillance SP2606D, Section 4.1, 2-CS-4.1 B Stroke and Timing 1ST, Facility 2. Section 2.1 General Prerequisites satisfied for performing surveillance and initialed. During this 1ST, the valve stroke time will be out of specification. The SRO will have to make a Technical Specification entry for the out of specification stroke time.

Event 2: Once Technical Specifications are evaluated, Pressurizer Pressure Transmitter, PT-100Y, fails above actual pressure. Both spray valves open causing actual pressure to lower and backup heaters will trip. The crew will respond per AOP 2585 Immediate Actions and Annunciator Response Procedures (ARPs), 2509B-212 for Pressurizer Pressure Selected Channel deviation from setpoint Hi!Lo. This ARP directs that if heaters and spray are not operating properly, manually OPERATE pressurizer heaters and spray to establish desired RCS pressure and refer to Technical Specification LCO 3.4.4. Desired RCS pressure band lAW OP 2204 Load Changes, section for Operation at Steady State power is 2225-2300 psia.

The Proportional Heater group breaker trip requires a Technical Specification entry. (Reference similar event: Millstone Unit 2 EN-49779 Jan 2014). With only one group of pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Event 3: When pressurizer pressure is returned to its normal band, the Train "A" Salt Water Cooling Pump strainer will become clogged as a result of the high winds pushing seaweed into the intake structure.

Differential pressure across the service water strainers rises to 4 psid. The crew will take actions for SW Pump A Strainer Trouble ARP 2590E-028 for strainer D/P greater than or equal to 3 psid and service water strainer has not started. This will require starting the B Service Water pump on Facility 1 per OP2326A, Service Water System. They may also refer to AOP 2565, Loss of Service Water to more quickly switch to the swing Service Water pump. The SRO will refer to TSAS 3.7.4.1, Service Water System and TRM 7.1.21, Service Water System but no Technical Specification entry is required.

Event 4 and 5: After Service Water is restored, the "A" Steam Generator Feed Pump (SGFP) will have high vibrations requiring the crew to down power to approximately 60% and take the pump off line. They will enter AOP 2575, "Rapid Downpower" and use a reactivity plan for the downpower.

Event 6: During the downpower, the TURBINE VIBRATION HI annunciator alarms followed by the TURBINE VIBRATION HI HI annunciator. The crew will refer to ARP 2590E-174 and see that reactor trip criteria is met (greater than 12 mils sustained). The crew will attempt to manually trip the reactor. The manual reactor trip pushbuttons fail. Operators will have to open the CEDM output breakers to trip the reactor. On the reactor trip, eight CEAs fail to fully insert and the crew will commence emergency boration per EOP 2541 Standard Appendixes, Appendix 3A, Emergency Boration.

The crew will perform Emergency Operating Instruction EOP 2525, Standard Post Trip Actions Scenario 3 3 of34

NRC 2014 Scenario 3 Summary Event 7: During Step 2 of SPTAs (Vital Auxiliaries) a LOCA will occur. The crew should respond by diagnosing a Loss of Coolant Accident and entering EOP 2532 LOCA.

The scenario is terminated once the crew initiates plant depressurization using EOP 2532.

Scenario 3 4 of34

Simulator Setup Instructions INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

IDNum Description Delay Ramp Event Sev or Final Rei Time Time Time Value Value Order MALFUNCTIONS SW09A Reduced SW PP A STR CAP 2:00 100 3 FW39A Feed Pump A Turbine Vibration 3.3 4 TU02A TURB BRG HIGH VIB (HP) 10 5 RD0202- STUCK CEA # 2-9 RD0209 RP27B No RPS Auto Trip RP04A-4D Manual Reactor Trip PB-1A-4A Fail RC04 RX Head Vent Leak 100 RC03A RCS Cold Leg Loop 1A Break 150 RX03B CH Y PZR Pressure control transmitter _(PT-1 OOY)fails HIGH REMOTE FUNCTIONS C07-B33 EHS Monitor Panel Trouble OFF OVERRIDES 05A1A2S3 DIG HX B Bypass SW-231 B (digital CLOSE 4 input) 05A1A2S2 DIG HX A Bypass SW-231A (digital CLOSE 0 input)

RHHS- CTMT Spray Valve CS-4.1 B (DO G 1 3022 1 GREEN)

RXHS- PZR PROP HTR BKR GP 2 (DO NG 2 100-2 1 GREEN)

RXHS- PZR PROP HTR BKR GP 2(DO A 2 100-2 3 AMBER) 02A2A5S5 PZR PROP HTR BKR GP 2 (digital OFF 2 Input)

Scenario 3 5 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _1_

Event

Description:

1ST, CS-4.18 Stroke Test Surveillance SP-26060 Time I Position I Applicant's Actions or Behavior Examiner Note: The crew has been instructed to perform SP2606D. All prerequisites are met.

They have been provided a calibrated stop watch and marked up procedures The following steps are from SP 26060, 2-CS-4.1 B Valve Tests, Facility 2. Note: Remote position indication testing is NOT required at this time.

4.1 2-CS-4.1 B Stroke and Timing 1ST NOTE ATC Cycling 2-CS-4.1 B verifies the CS header in Containment filled. [Ref.

6.6]

Examiner Note: Remote position indication testing is not required.

4.1.2 IF valve does not stroke full open or full closed during testing, Go To Attachment 1.

4.1.3 OPEN CS-4.1 B, "CS HDR B ISOL," and MEASURE stroke time (C-01 ).

ATC 4.1.4 RECORD open stroke time on SP 2606D-004.

4.1.5 CLOSE CS-4.1 B, "CS HDR B ISOL," and MEASURE stroke time (C-01 ).

4.1.6 RECORD close stroke time on SP 2606D-004.

4.1. 7 COMPARE stroke time data to "Acceptable" and "Normal" limits on SP 2606D-004.

4.1.8 MARK SP 2606D-004, "Acceptable" and "Normal" limit "YES" or "NO," and INITIAL.

4.1.9 MARK SP 2606D-004, "Operational Readiness," "SAT" or "UNSAT," and ATC INITIAL.

4.1.1 0 IF valve stroke times are not within "Acceptable" limits, Go To Attachment 1.

Examiner Note: Applicant informs Unit Supervisor and goes to Attachment 1 because stroke time is not within acceptable limits.

Scenario 3 6 of34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _1_

Event

Description:

1ST, CS-4.1B Stroke Test Surveillance SP-26060 Time I Position I Applicant's Actions or Behavior Examiner Note: The following steps are from SP2606D Attachment 1.

1. CONSIDER component not OPERABLE.

2. lE in MODEs 1, 2, 3 (~1, 750 psia), LOG entry in TSAS 3.6.3.1 and TSAS 3.6.2.1a.

4. SUBMIT CR and RECORD CR number in applicable Form cover sheet.

5. NOTIFY the following:

1ST Coordinator

System Engineer Examiner Note: SRO logs into TSAS 3.6.3.1 and TSAS 3.6.2.1a LCO 3.6.3.1 Each containment isolation valve shall be OPERABLE. APPLICABILITY:

MODES 1, 2, 3 and 4. ACTION:

With one or more of the isolation valve(s) inoperable, either:

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or Isolate the affected penetration(s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of a deactivated SRO automatic valve(s) secured in the isolation position(s), or Isolate the affected penetration(s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of a closed manual valve(s) or blind flange(s); or Isolate the affected penetration that has only one containment isolation valve and a closed system within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange; or Be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

LCO 3.6.2.1 Two containment spray trains and two containment cooling trains, with each cooling train consisting of two containment air recirculation and cooling units, shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3*.

ACTION a: For one containment spray train inoperable, Restore the inoperable containment spray train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Scenario 3 7 of34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _1_

Event

Description:

1ST, CS-4.1 B Stroke Test Surveillance SP-26060 Time I Position I Applicant's Actions or Behavior Examiner Note: When Technical Specifications have been evaluated or at lead examiner's direction, go to Event 2, Pressurizer Pressure Transmitter Failure.

Scenario 3 8 of34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _2_

Event

Description:

Pressurizer Press Transmitter "Y" Fails High, Grp 2 Proportional Heater Failure Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 2, Pressurizer Pressure Transmitter Y Failure.

Indications Available:

25098-212 for Pressurizer Pressure Selected Channel DEVIATION HIILO D-37 on C-03

PRESSURIZER CH Y PRESS HI/LO, D-39 on C-03 Examiner Note: The following steps are from AOP 2585 Immediate Actions Section 10.0 Pressurizer Spray Valve Open. Steps in [] may be performed from memory without referencing a procedure.

[1 0.1] OBSERVE Pressurizer pressure safety channel indications to evaluate RCS pressure.

[1 0.2] IF Pressurizer pressure less than 2260 psig, manually CLOSE affected spray valve( s ):

HIC 100E, PZR SPRAY-1A

HIC 100F, PZR SPRAY-18

[1 0.3] CHECK affected Pressurizer Spray Valve(s) are closed:

ATC

HIC 100E, PZR SPRAY-1A

HIC100F,PZRSPRAY-1B

[1 0.4] START backup heaters as needed Examiner Note: Backup heaters cannot be started until operator shifts to Pressurizer Channel X.

SRO 10.5 Go to ARP 2590B-212 "PZR PRESSURE SELECTED CHANNEL DEVIATION HI/LO" (C-02/3, window D-37).

Examiner Note: The following steps are from ARP 25908-212 PZR PRESSURE SELECTED CHANNEL DEVIATION HI/LO, D-37 Note: If forcing pressurizer sprays, this is an expected alarm.

ATC 1. OBSERVE the following to evaluate RCS Pressure:

PRESS CNTL-X, PIC 100X

PRESS CNTL-Y, PIC-100Y ATC 2. IF alarm is determined not to be valid, SHIFT pressure control to the redundant channel (C-03).

Examiner Note: Operator shifts to Pressurizer Channel X Examiner Note: Step 3 is not applicable.

Scenario 3 9 of34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _2_

Event

Description:

Pressurizer Press Transmitter "Y" Fails High, Grp 2 Proportional Heater Failure Time I Position I Applicant's Actions or Behavior ATC 4. VERIFY proper operation of pressurizer heaters and spray valves (C-03).

IF heaters and spray are not operating properly, manually OPERATE pressurizer heaters and spray to establish desired RCS pressure, and Refer To TIS LCO 3.4.4.

Examiner Note: Operator may energize additional heaters to raise pressure.

Operator may or may not restore heaters and spray to automatic control using this step. By this point, the ATC operator should notice that Group 2 Pressurizer Proportional heaters are not energized.

Examiner Note: Desired RCS pressure band JAW OP 2204 Load Changes, section for Operation at Steady State power is 2225 - 2300 psia SRO 4.1 Refer to TIS LCO 3.4.4:

The pressurizer shall be OPERABLE with:

a. Pressurizer water level ~70%, and

b. At least two groups of pressurizer heaters each having a capacity of at least 130 kW.

APPLICABILITY: MODES 1, 2 and 3.

Examiner Note: SRO logs entry into TS 3.4.4 for one group of pressurizer proportional heaters not operable.

Examiner Note: Once pressurizer pressure is restored to normal band, or at lead examiner's direction, proceed to Event 3, Service Water Pump A strainer high D/P.

Scenario 3 10 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _3_

Event

Description:

Service Water Pump "A" Strainer High D/P Time I Position I A_pplicant's Actions or Behavior Simulator Operator: When directed, initiate Event 3, Service Water Pump A strainer high D/P.

Indications Available:

SW Pump A STNR TROUBLE on C-06/7 Examiner Note: SRO may direct BOP to start "B" Service Water Pump and secure "A" Service Water Pump from memory to stabilize the plant. SRO enters AOP 2565, Loss of Service Water Examiner Note: The following steps are from AOP 2565 Loss of Service Water Section 4.0 Loss of "A" SW Pump.

SRO/BOP 1E "A" service water pump tripped or lost, PEFORM the following:

a. PLACE Service Water Pump A switch in "PULL TO LOCK."

b. ENSURE SW-978, service water pump discharge cross-tie is closed.

c. ENSURE SW-97A, service water pump discharge cross-tie is open.

d. Start "B" service water pump.

e. CHECK alarm AA19, C06/7, "SERVICE WATER PUMP B SIAS/LNP START MANUALLY BLCOKED" lit.

f. Refer To OP 2328A, "Sodium Hypochlorite System," and STOP injection to "A" Service Water Pump CUE: If asked, PEO reports that the A Service Water Strainer D/P is pegged high and the Service Water Strainer is not rotating. It appears that seaweed is clogging the strainer. If directed to start the "A" strainer pump, PEO reports that pump failed to start.

CUE: If directed, PEO reports proper operation of "B" Service Water Pump.

CUE: When directed, report that Sodium Hypochlorite is secured to the "A" Service Water Pump.

Examiner Note: The following steps are from ARP 2590E-089 AA-19 for SW PUMP B SIAS/LNP START MANUALLY BLOCKED on C06/7.

Scenario 3 11 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: _3_

Event

Description:

Service Water Pump "A" Strainer High D/P Time I Position I Applicant's Actions or Behavior NOTE With "SIAS/LNP ACTUATION SIGNAL HS 6484A" in "BLOCK" position, the "B" Service Water Pump is considered not OPERABLE.

1. lE "B" SW pump is to remain in service as the OPERABLE pump, PERFORM BOP the following:

1.1 VERIFY it is operating on the same facility 24E is aligned to.

1.2 PLACE "SIAS/LNP ACTUATION SIGNAL HS 6484A," in NORMAL (A502)

Examiner Note: SW Pump "B" and 24E are aligned to Facility 1. BOP directs PEO to place HS 6484A in Normal which will clear this annunciator alarm.

CUE: AS PEO, respond to direction to place the SIAS/LNP ACTUATION SIGNAL HS 6484A on A502 in "NORMAL" position.

Simulator Operator: IF directed to vent the "B" SW Pump strainer, insert an override for the SW PUMP B STNR TROUBLE, CA-4 ON C-06/7. Delete override after 2 minutes.

When directed, insert Remote Function SWR31 in NORM, to place HS-6484A (on A502), SIAS/LNP Actuation Signal Hand Switch in the NORMAL position.

Examiner Note: Once SIAS/LNP actuation signal alarm is cleared, or at lead examiner's direction, proceed to Event 4, High Vibration of "A" SGFP.

Scenario 3 12 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position l Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 3, High Vibration of "A" SGFP.

Indications Available:

SGFP A Turbine Vibration (C-05, 04)

SGFP Vibration will be displayed on the PPC and UR4500 Examiner Note: The following steps are from ARP 25900-016, D-4 BOP 1. CHECK either of the following PPC Secondary System Menu displays:

Steam Generator Feed Pump (SGFP_01)

Main Turbine Bentley Nevada (BNTURB_AI)

2. lE both of the following criteria are met,

Vibration level on either HP bearing OR LP bearing is greater than 5 mils

Vibration level on both HP bearing AND LP bearing are greater than 3 mils THEN TRIP the reactor.

Examiner Note: Reactor trip is NOT REQUIRED.

3. IF vibration level on both HP bearing AND LP bearing are greater than 3 mils but less than 5 mils, Refer To AOP 2575, "Rapid Down Power," OR OP 2321, "Main Feedwater System," and REMOVE affected SGFP from service.

Examiner Note: Unit Supervisor should determine that HP and LP vibration levels (-4 mils) require a Rapid Downpower and removal of "A" SGFP from service.

Simulator Operator: If crew decides to trip the reactor, ensure that applicable post reactor trips malfunctions for Events 7 and 8 are inserted.

SRO Enters AOP 2575, Rapid Downpower.

Examiner Note: The following steps are from AOP 2575 Rapid Downpower, Section 3.0 Rapid Down power.

Scenario 3 13 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position I Applicant's Actions or Behavior SRO

PERFORM focus brief on the 3.1. following:

REACTOR TRIP CRITERIA

Parameters associated with automatic reactor or turbine trips are challenged

RCS T cold not within 1ooF of temperature program and efforts to regain control are unsuccessful RCS TEMPERATURE CONTROL

RCS T cold to be maintained within 10°F of Attachment 5, "Temperature vs. Power program" using Attachment 10, "Main Turbine Load Set Control."

To avoid uncontrolled cooldowns or power transients, sudden changes in RCS temperature or boron concentration should be avoided.

3.2 REQUEST SM/STA to 3.2. Refer To Attachment 8, "Required Notifications,"

and PERFORM notifications.

ATC 3.3 INITIATE forcing pressurizer sprays.

Examiner Note: Skill of Trade, no procedure required.

CAUTION In the case of a dropped CEA, rod motion is not used to initiate down power.

3.4 IF not downpowering due to a dropped rod, INSERT Group 7 CEAs1 0 2: 2 ATC steps to initiate downpower 3.5 Using the "Load Speed Control" switch, REDUCE turbine load to Maintain Tc BOP on program (+/-2 deg).

3.6 Refer To PPC or Reactor Engineering Curve and Data Book and OBTAIN SRO reactivity plan for the initial reactor power condition and desired load reduction.

Examiner Note: The crew should refer to Reactivity Plan RE-G-11 for downpower parameters.

Scenario 3 14 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position 1 Applicant's Actions or Behavior NOTE Attachment 11 "Approximate Load Demand vs. Reactor Power," can be used to correlate the desired power level to a turbine load demand setpoint.

3. 7 Refer To Attachment 10, "Main Turbine Load Set Control," REDUCE turbine BOP load and MAINTAIN Tc on program (+/-2 deg).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Attachment 10 Main Turbine Load Set Control:

CAUTION Operation of the "Load/Speed CONTROL" switch will change turbine load at 600%/hour, and cancel any previous load setpoint.

BOP NOTE Steps provided in this attachment are dependent on plant conditions and may be performed in any sequence, and repeated as necessary.

Scenario 3 15 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position i Applicant's Actions or Behavior

1. IF desired to commence or modify a turbine load ramp, PERFORM the following (HMI "Load" screen):

a. !E previous ramp has stopped, SELECT "Load Hold."

b. SELECT "Load Setpt" and ENTER desired value.

>BOP enters 45% (variable)

c. SELECT "Rate setpt" and ENTER desired value. (

>BOP enters 84%/hr

d. WHEN ready to commence load reduction, SELECT "Load Resume."

2. IF desired to adjust the "Load Ramp Rate," PERFORM any of the following:

SELECT "Rate setpt" and ENTER new value .

BOP

SELECT "5% I hour," OR "1 0% I hour," OR "20% I hour."

SELECT "Raise" or "Lower" (0.25% I hour change) .

a. !E Tavg and Tc are high off program, PERFORM the following:

a. SELECT "Load Hold" to stop ramp.

b. WHEN Tavg and Tc are trending back to program, SELECT "Load Resume."

b. !E Tavg and Tc are low off program, PERFORM the following:

a. JOG the "Load/Speed CONTROL" switch to "Lower."

b. WHEN Tavg and Tc are back on program, SELECT Load Setpt" and ENTER desired value.

c. !E desired, Go To Step 1 and RESUME turbine load ramp.

c. IF desired load has been reached SELECT "Load Hold."

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Section 3.0 Rapid Downpower.

Scenario 3 16 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position I Applicant's Actions or Behavior ATC 3.8 IF desired to borate from the RWST (preferred method)

PERFORM the following:

a. ENSURE at least one charging pump operating.

b. ENSURE CH-196, VCT makeup bypass, closed.

c. ENSURE CH-504, RWST to charging suction, open.

d. OPEN CH-192, RWST isolation.

e. CLOSE CH-501, VCT outlet isolation.

f. CHECK charging flow at desired rate.

g. Go To step 3.11 Examiner Note: Crew should borate from the RWST using 2 charging pumps.

SRO/ATC/ 3.11 During the downpower, Refer To Attachment 1,"Rapid Downpower BOP Parameters," and MAINTAIN parameters as specified throughout downpower:

Attachment 1 Rapid Downpower Parameters:

Condensate and heater drain flows and pressures: sufficient to maintain adequate SGFP suction pressure

FRV D/P: greater than 40 psid

Turbine load: responding to changes in load demand, with control valves operating together

Steam generator levels 55 to 70% .

MSR parameters tracking together

Turbine Generator MVARs: as specified by CONVEX

Reactor power: being monitored using delta T power indication

ASI: In accordance with reactivity plan or within 0.01 of ESI or per COLR.

CEA position: greater than PDIL

Tc: less than or equal to 549 deg

Pressurizer level: between 35 and 70%

Pressurizer pressure: between 2,225 and 2,300 psia _(DNB margin)

Scenario 3 17 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 4 5 Event

Description:

High Vibration of A" SGFP and Rapid Downpower Time I Position I Applicant's Actions or Behavior NOTE

1. Xenon rate of change should be considered when terminating boration.

SRO/ATC

2. During rapid downpower, the PPC calorimetric may be inaccurate due to SG level transients. The most accurate available indication of reactor power is RPS delta T power.

Examiner Note: Once power has dropped at least 5%, or at the lead examiner's direction, proceed to Event 6, Turbine High Vibration.

Scenario 3 18 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event Number 6, Turbine Vibration High.

Indications Available:

TURBINE VIBRATION HI, A-34 on C06/7

TURBINE VIBRATION HI-HI, B-34 on C06/7 Examiner Note: The following steps are from ARP 2590E-17, B34 for TURBINE VIBRATION HI-HI annunciator.

CAUTION If abnormal vibration is detected while the unit is on line, a rapid, safe BOP shutdown of the unit is required to prevent serious Turbine damage NOTE This alarm is expected during performance of SP 2561 N, "Main Control Valve BOP Operability Test," but should clear when control valve is re-opened.

1. Observe either of the following to determine which point is in alarm:

BOP

HMI "Vibration" screen

PPC Scenario 3 19 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior 2.J.E vibration level is great than 12 mils (sustained) AND reactor power is greater than 15%, PERFORM the following:

2.1 TRIP the Reactor and PERFORM EOP 2525, "Standard Post Trip Action."

BOP 2.2 MONITOR either of the following and Go To step 3.:

HMI "Post Trip" screen

PPC EXAMINER NOTE: Vibration is greater than 12 mils and less than 30 mils.

Step 3 is not applicable.

Examiner Note: An operator should attempt to trip the reactor using the manual pushbuttons. The reactor will not trip because the push buttons fail. An operator must open the CEDM output breakers to trip the reactor manually.

CRITICAL TASK: Manually Shutdown the reactor. The reactor must be manually tripped using the CEDM output breakers immediately (within 1 minute) when an automatic reactor trip fails and/or the manual push buttons do NOT work. (CT-1/SPTA-5)

Time that manual pushbuttons attempted: _ _ _ __

Time of reactor trip: _ _ _ __

Examiner Note: The following steps are from EOP 2525 Standard Post Trip Actions.

Determine Status of Reactivity Control

1. DETERMINE that Reactivity Control acceptance criteria are met by performing ALL of the following steps:

a. CHECK that reactor power is dropping.

ATC b. CHECK that SUR is negative.

c. CHECK that no more than one CEA is not fully inserted.

c.1 IF more than one CEA is not fully inserted, COMMENCE emergency boration. Refer to Appendix 3, Emergency Boration.

Examiner Note: The following steps are from EOP 2541 Standard Appendices, Appendix 3-A, Commencing Emergency Boration.

Scenario 3 20 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior

1. IF boric acid storage tanks are available, INTIATE emergency boration as follows:

a. ENSURE CH-512, VCT makeup valve stop is closed.

b. ENSURE CH-196, VCT makeup bypass is closed.

c. OPEN CH-514, boric acid isolation.

d. START BOTH boric acid pumps.

e. CLOSE BOTH boric acid recirc valves.

ATC f. OPEN BOTH boric acid gravity feed isolations:

CH-508

CH-509

g. CLOSE CH-501, VCT outlet isolation.

h. IF CH-500, letdown divert handswitch is in the "VCT" position, PLACE the valve to the "RWS" position.

i. ENSURE at least one charging pump is operation.

j. CHECK charging flow is greater than 40gpm.

Examiner Note: The following steps are from EOP 2525 Standard Post Trip Actions.

Determine Status of Maintenance of Vital Auxiliaries

2. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

BOP a. CHECK that the main turbine is tripped by BOTH of the following:

ALL main stop valves are closed.

Generator megawatts indicate zero.

b. !E 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

Scenario 3 21 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Determine Status of Maintenance of Vital Auxiliaries (continued)

2. c. CHECK that ALL Facility 1 and 2 electrical buses are energized:

6.9kV Electrical Buses 25A, 25B

4.16kV Non-Vital Electrical Buses 24A, 24B

4.16vV Vital Electrical Buses 24C, 24D

Vital DC Buses 201A, 201B, DV-10, DV-20 BOP

Vital AC Instrument Buses VA-10, VA-20

d. CHECK that BOTH facilities of service water are operating.

e. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

f. CHECK on facility of CRAC operating.

Determine Status of RCS Inventory Control

3. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

a. CHECK that BOTH of the following conditions exist:

Pressurizer level is 20 to 80%

Pressurizer level is trending to 35 to 70%

a.1. IF the Pressurizer Level Control System is not operating properly in ATC automatic, RESTORE and Maintain pressurizer level 35 to 70% by performing ANY of the following:

1) OPERATE the Pressurizer Level Control System

2) Manually Operate charging and letdown.

Examiner Note: ATC should isolate letdown and verify that all 3 Charging Pumps are running.

b. CHECK that RCS subcooling is greater than or equal to 30°F Scenario 3 22 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Determine Status of RCS Pressure Control

4. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of the following:

CHECK that pressurizer pressure is 1900 to 2350 psia.

CHECK that pressurizer pressure is trending to 225 to 2300 psia.

4.31E pressurizer pressure is less than 1714 psia, ENSURE ALL of the following:

ATC

SIAS, CIAS, EBFAS have actuated

ONE complete facility of CRACS is operating in recirc mode (C25).

Examiner Note: Crew may decide to manually initiate SIAS, CIAS, EBFAS because plant is approaching setpoints.

4.4 lE pressurizer pressure is less than 1714 psia AND SIAS has initiated, ENSURE that ONE RCP in each loop is stopped.

4.5 IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, STOP ALL RCPs.

CRITICAL TASK: The operator is required to trip all RCPS within 5 minutes of the loss of NPSH, following a Small Break LOCA (SBLOCA).

Time all RCPS secured: _ _ _ __

Pressurizer Pressure when all RCPS secured:

Determine Status of Core Heat Removal

5. DETERMINE that Core Heat Removal acceptance criteria are met by ATC performing ALL of the following:

a. CHECK that at least one RCP is operating.

b. CHECK that loop delta T is less than 1ooF

c. CHECK that Th subcooling is great than or equal to 30°F.

Scenario 3 23 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Determine Status of RCS Hea~ Removal

6. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

a. CHECK that BOTH steam generators pressure are 880 to 920 psia.

b. CHECK that RCS Tc is being maintained 530 to 535°F.

c. CHECK that at least one steam generator has BOTH of the following conditions met:

BOP

Level is 10 to 80%.

Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

d. CHECK that RCS subcooling is greater than or equal to 30°F.

d.1 RESTORE steam generator level 40 to 70% by performing ONE of the following:

FEED each unaffected steam generator greater than 300 gpm

FEED the least affected steam generator greater than 300 gpm Scenario 3 24 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Determine Status of Containment Isolation

7. DETERMINE that Containment Isolation acceptance criteria are met by ALL of the following:

a. CHECK that NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment

RM---7890, Personnel Access Area

RM---7891, Ctmt Refuel Floor Area

RM---8240, High Range

RM---8241, High Range

RM---8123 A and B, Ctmt Atmosphere

RM---8262 A and B, Ctmt Atmosphere Radiation Monitors Outside Containment ATC

RM---7894, Charging Pump Area

RM---7895, Primary Sample Sink

RM---7896, ---25ft 6 in Waste Process Area

RM---7897, ---45ft 6 in Waste Process Area

RM---8132A and B, Unit 2 Plant Stack

RM---8169, Millstone Stack WR

RM---8168, Unit 2 WR Stack

RM---6038, RBCCW

b. CHECK that NONE of the following steam plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors

RM---5099, Steam Jet Air Ejector

RM---4262, SG Slowdown

RM---4299A and B, Main Steam Line 1

RM---4299C, Main Steam Line 2

c. CHECK that containment pressure is less than 1.0psig.

Determine Status of Containment Temperature and Pressure Control

8. DETERMINE that Containment Temperature and Pressure Control acceptance ATC criteria are met by BOTH of the following steps:

a. CHECK that containment temperature is less than 120°F. (PPC or avg of Points 5 and 6)

b. CHECK that containment pressure is less than 1.0psig.

Scenario 3 25 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time J Position 1 Applicant's Actions or Behavior Perform Subsequent Actions of EOP 2525 SPTAs.

ATC/BOP Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

Diagnoses EOP 2532 Loss of Coolant Accident.

SRO Examiner Note: The following steps are from EOP 2532 Loss of Coolant Accident. Asterisked steps are "Continuously Applicable," and may be performed out of order after they have been accomplished once.

NOTE Harsh Containment values are designated with brackets []. These values should be used anytime CIAS has actuated on high containment pressure greater than 4.42 psig.

Confirm Diagnosis

1.CONFIRM diagnosis of a Loss of Coolant Accident by performing the following:

a. CHECK Safety Function Status Check Acceptance Criteria are satisfied.

b. OPEN the steam generator sample valves.

SRO c. DIRECT Chemistry to perform the following:

Sample both steam generators

Frisk the samples

Report frisk results

Analyze samples for boron and activity

d. WHEN Chemistry reports that samples have been taken, CLOSE the steam generator sample valves.

Classify the Event SRO *2. CLASSIFY the event. Refer To MP-26-EPI-FAP06, "Classification and PARs"

IF classification requires RCS sampling, Refer To Appendix 46, "Sampling for EAL Determination" and DIRECT Chemistry ~as required.

Implement Placekeeping SRO 2. PERFORM ALL of the following:

OPEN the placekeeper and ENTER the EOP entry time.

ENSURE the master alarm silence switch is in "NORMAL".

Scenario 3 26 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Check SIAS Actuation

4.1F pressurizer pressure is less than 1714 psia, PERFORM ALL of the following:

. a. ENSURE SIAS, CIAS and E8FAS have actuated. (C01)

b. ENSURE ONE complete facility of CRAGS is operating in the recirc mode:

(C25)

Facility 1

HV- 203A, Fan F- 21A exhaust damper is open.

Fan F- 21A, supply fan is running.

HV- 206A, Fan F- 31A exhaust damper is open.

Fan F- 31A, exhaust fan is running.

HV- 212A, Fan F- 32A exhaust damper is open.

Fan F- 32A, filter fan is running.

HV- 202, minimum fresh air damper is closed.

SRO

HV- 207, cable vault exhaust damper is closed.

HV- 208, exhaust air damper is closed.

Facility 2

HV- 2038, Fan F- 21 exhaust damper is open.

Fan F- 21 8, supply fan is running.

HV- 2068, Fan F- 318 exhaust damper is open.

Fan F- 318, exhaust fan is running.

HV- 2128, Fan F- 328 exhaust damper is open.

Fan F- 328, filter fan is running.

HV- 495, fresh air damper is closed.

HV- 496, exhaust air damper is closed.

HV- 497, cable vault exhaust damper is closed.

Scenario 3 27 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Optimize Safety Injection

5.1F SIAS has initiated, PERFORM the following:

a. CHECK at least one train of SIAS, CIAS, and EBFAS has properly actuated. (C01X)

b. CHECK that safety injection flow is adequate. Refer to Appendix 2, "Figures."

c. ENSURE ALL available charging pumps are operating.

d. ENSURE vital switchgear cooling is operating for each operating ECCS train as follows:

SRO Facility 1

Fan F- 51 is running.

Fan F-134 is running.

SW-178A, service water supply is open.

SW-178B, service water supply is open.

Facility 2

Fan F- 52 is running.

Fan F- 142 is running.

Fan F- 133 is running.

SW- 178C, service water supply is open.

RCP Trip Strategy

6.1E pressurizer pressure is less than 1714 psia AND SIAS has initiated, PERFORM the following:

a. ENSURE ONE RCP in each loop is stopped.

b. PLACE associated pressurizer spray valve controller RC- 1OOE or RC-SRO 1OOF in manual and CLOSE the valve.

c. IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, PERFORM the following:

1) STOP ALL RCPs.

2) PLACE TIC- 4165, steam dump TAVG controller, in manual and closed.

3) 3) PLACE pressurizer spray valve controllers RC- 1OOE and RC-1OOF in manual and CLOSE the valves.

Scenario 3 28 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Isolate the LOCA

d. PERFORM the following to isolate the leak:

a. IF pressurizer pressure is less than 2250 psia, CHECK the PORVs are closed.

b. ENSURE BOTH of the following letdown isolation valves are closed:

CH- 515

CH-516

c. ENSURE at least one facility of the following RCS sample line isolation valves are closed:

Facility 1 SRO

RC-45, RC combined sample isolation valve Facility 2

RC-001, RC hot leg isolation valve

RC-002, pressurizer surge sample isolation valve

RC-003, pressurizer steam sample isolation valve

d. CHECK no leakage in the RBCCW system by BOTH of the following:

CHECK RM- 6038, "RBCCW Radiation Monitor," is not alarming or trending to alarm.

CHECK RBCCW Surge Tank level not rising.

Scenario 3 29 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior Check LOCA NOT Outside of Containment

8. CHECK that the LOCA is not occurring outside of containment:

a. CHECK that NONE of the following Radiation Monitors Outside Containment have an unexplained alarm or indicate an unexplained rise in activity:

RM- 7894, Charging Pump Area

RM- 7895, Primary Sample Sink

RM- 7896,- 25ft 6 in Waste Process Area

RM- 7897,- 45ft 6 in Waste Process Area SRO

RM- 8169, Millstone Stack WR

RM- 8168, Unit 2 WR Stack

b. CHECK that ALL of the following annunciators are not in alarm:

"AUX BLDG SUMP LEVEL HI" (C06, AA-21)

"RBCCW RM SUMP LEVEL HI" (C06, AB-21)

"SI RM A SUMP LEVEL HI" (C06, CA- 21)

"SI RM B SUMP LEVEL HI" (C06, CB- 21)

"SI RM C SUMP LEVEL HI" (C06, DA- 21)

c. MONITOR Aerated Waste Tank levels for abnormal rise.

Place Hydrogen Analyzers in Service SRO

9. PLACE the hydrogen analyzers in service. Refer To Appendix 19, "Hydrogen Analyzer Operation."

Scenario 3 30 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior ENSURE CIAS

1 0. 1E ANY of the following exists:

Containment pressure is great than or equal to 4.42 psig

Radiation monitors inside containment are great than their alarm setpoint PERFORM the following:

a. ENSURE SIAS, CIAS, E8FAS and MSI have actuated. (C01)

b. CHECK that at least one train of SIAS, CIAS, E8FAS and MSI has properly actuated. (C01X).

c. ENSURE ONE complete facility of CRACs is operating in the recirc mode:

(C25)

Facility 1

HV- 203A, Fan F- 21A exhaust damper is open.

SRO

Fan F- 21A, supply fan is running.

HV- 206A, Fan F- 31A exhaust damper is open.

Fan F- 31A, exhaust fan is running.

HV- 212A, Fan F- 32A exhaust damper is open.

Fan F- 32A, filter fan is running.

HV- 202, minimum fresh air damper is closed.

HV- 207, cable vault exhaust damper is closed.

HV- 208, exhaust air damper is closed.

Facility 2

HV- 2038, Fan F- 218 exhaust damper is open.

Fan F- 21 8, supply fan is running.

HV- 2068, Fan F- 31 exhaust damper is open.

Fan F- 318, exhaust fan is running.

HV- 2128, Fan F- 328 exhaust damper is open.

Fan F- 328, filter fan is running.

HV- 495, fresh air damper is closed.

HV- 496, exhaust air damper is closed.

HV- 497, cable vault exhaust damper is closed.

Scenario 3 31 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time T Position I Applicant's Actions or Behavior ENSURE CIAS (continued}

d. ENSURE ALL available CAR fans are operating:

CAR fans operating in slow speed

CAR emergency outlet valves open:

RB- 28.3A SRO

RB- 28.38

RB- 28.3C

RB- 28.30

e. IF 24C or 240 is energized from offsite power, ENSURE no more than TWO CEDM cooling fans are operating.

f. START ALL available containment auxiliary circulation fans in low speed.

g. START ALL available post- incident recirculation fans.

Examiner Note: Steps 11, 12, 13 are not applicable.

Align Instrument Air SRO

14. CHECK instrument air pressure great than 90 psig and stable.

Align Condenser Air Removal to Unit 2 Stack

15.1E EBFAS has initiated AND the condenser is available, ALIGN the condenser air removal system to Unit 2 stack:

a. ENSURE condenser air removal fan, MF- 55A or MF- 55B is running.

b. IF condenser air removal fan MF- 55A is operating, ENSURE makeup damper, SRO EB- 171, is open.

c. OPEN EB- 57, condenser air removal to Unit 2 stack.

d. ENSURE AC- 11, Purge exhaust filter outlet damper is closed.

e. OPEN AC- 59, Outside air makeup damper.

f. START ONE main exhaust fan.

g. ENSURE HV- 118, Radwaste exhaust damper is closed.

h. START F- 20, Fuel handling area supply fan.

i. ENSURE HV- 173, Exhaust mod discharge damper is in "MOD" position.

j. PLACE AC- 59, Outside air makeur> damper to "MID" rJOSition.

Examiner Note: Step 16 is not applicable because the LOCA cannot be isolated.

Scenario 3 32 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 EventDescription: Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position I Applicant's Actions or Behavior NOTE

1. RCS cool down should be initiated within one hour after the event to conserve condensate inventory and comply with the Long Term cooling Analysis.

2. RCS cooldown rate greater than 40°F/hr should be maintained until the steam dump/bypass valves or atmospheric dump valves are full open.

3. The starting point for the RCS cooldown should be the Tc or CET SRO temperatures where RCS has stabilized.

4. Tc should be used for monitoring RCS cooldown if in forced or natural circulation. CETs should be used for all other cases.

NOTE Technical Specification cooldown rates should be observed during the cooldown. The cooldown rates are as follows:

1. RCS Tc greater than 220°F the cooldown rate is 100°F/hr.

2. RCS Tc less than or equal to 220°F the cooldown rate is 50°F/hr.

Perform Controlled Cooldown

17.1NITIATE a controlled cooldown using the steam dumps to establish shutdown SRO/BOP cooling entry conditions.

Examiner note: the BOP should initiate a controlled cooldown by opening the steam dump valves and establishing a 40-1 00°F/hr cool down.

Depressurize RCS to SOC Entry Conditions

18.1NITIATE a controlled depressurization of the RCS to less than or equal to 230 psia [190 psia] using ANY of the following:

Main or auxiliary pressurizer spray

IF HPSI throttle/stop criteria are met, DEPRESSURIZE the RCS using SRO/ATC ANY of the following:

Charging and letdown

HPSI flow Examiner Note: The ATC should depressurize the RCS as necessary using Auxiliary Spray Flow.

Scenario 3 33 of 34

Op-Test No.: NRC Scenario No.: _3_ Event No.: 6 7 Event

Description:

Turbine High Vibration, ATWS/Reactor Trip, 8 CEAs fail to insert, SPTAs, Emergency Boration, LOCA Time I Position 1 Applicant's Actions or Behavior Scenario Termination: The scenario may be terminated once a plant depressurization has been initiated or at the discretion of the Lead Examiner.

Scenario 3 34 of 34

SIMULATOR SCENARIO #4 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 4 Op-Test No.: NRC 2014 Examiners: Operators: SRO ATC BOP Initial Conditions: (IC 55) 100% Power, BOL, Equilibrium Xenon, 1065 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C. Turbine Driven Auxiliary Feedwater pump is OOS.

Turnover: 100% Power, BOL, Equilibrium Xenon, 1065 ppm Boron, blend ratio: 4.32: 1.0, SGBD @

40gpm per Steam Generator, 24E aligned to 24C, Turbine Driven Auxiliary Feedwater pump is OOS due to an oil issue.

Critical Tasks:

1. Manually trip the turbine or close MSIVs within 1 minute following a reactor trip and failure of automatic turbine trip.

2. Isolate AFW to the affected SG #2 within 30 minutes following the generation of MSIS during an ESDE.

3. Manually start "A" HPSI pump prior to reaching pressurizer low level alarm following a failure of "A" HPSI _pump to actuate and a degradation of the "C" HPSI pump.

Event No. Malf. Event Event Description No. Type*

1 I (ATC, Channel Y PZR Level transmitter, LT110Y (selected), fails low RX04B

(+10 min) SRO) (55%, 2 minute ramp).

C (BOP, 2 SRO) No. 1 Turbine control valve failure.(- 20MWe drop, 20% open TC06A

(+20 min) total, 1 min ramp)

N {ATC)

I (ATC, 3

RP09D SRO) Spurious RPS low flow trip Channel "D"

(+35 min)

TS (SRO)

C (BOP, 4 No. 1 Steam Generator tube leak (75 gpd and rising more than 15 SG01A SRO),

(+40 min) gpd/min - 0.12 gpm )

TS (SRO)

Scenario 4 1 of 30

Appendix D Scenario Outline Form ES-D-1 5

R (All) Rapid power reduction for Steam Generator Tube Leak

(+40 min) 6 M (ATC, No.1 SGTR exceeds charging pump capacity. Reactor trip SG02A

(+55 min) SRO) required. (200 gpm) 7 TC10H C (BOP) Turbine fails to trip on reactor trip

(+55 min) 8 C (BOP, Excessive Steam Demand Event inside containment on #2 Steam MS01B

(+57 min) SRO) Generator 9 ES031 C (ATC, "A" HPSI pump fails to start on SIAS. "C" HPSI pump is degraded

(+60 min) SI05C SRO) (50%)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Actual Section D.5.d}

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 3

4. Major transients ( 1-2_) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP conting_encies reguiring_ substantive actions _{0-21 1

7. Critical tasks (2-3) 3 Scenario 4 2 of30

NRC 2014 Scenario 4 Summary The crew will take the shift with the unit at 100% power and 24E aligned to 24C and the TDAFWP tagged out.

Event 1: Shortly after the crew takes the shift, Channel "Y" Pressurizer level transmitter will fail low causing Pressurizer level to rise. The crew will enter AOP 2585, Immediate Actions, take manual control of Pressurizer level and swap to Channel "X" level control.

Event 2: When Pressurizer level is restored to automatic control, a turbine control system failure causes Control Valve #1 to slowly throttle closed (20% open total). RCS temperature and pressure will slowly trend up and the crew will have to lower reactor power to match turbine load. The crew should respond using AOP 2584, Turbine Valve Failure.

Event 3: After Tc is restored in its band, a spurious RPS Low Flow trip occurs on Channel "D." The crew should enter applicable TSAS for the failed transmitter and place the channel in bypass in accordance with the ARP for RPS LOW FLOW TRIP CH D.

Events 4 and 5: A N-16 alarm will actuate on a small (0.12 gpm) Steam Generator Tube Leak (SGTL) on

1 Steam Generator. The crew should respond to the N-16 ALERT and N-16 HIGH annunciators on C06.

The crew should enter AOP 2569, Steam Generator Tube Leak and carry out applicable steps. The crew will go to the N-16 PPC screen and determine the tube leakage is> 75 gpd and rising> 15 gpd on #1 Steam Generator. The crew will conclude that a down power is required. The crew will perform a rapid down power per AOP 2575, using CEA insertion first and then boration from the RWST. Technical Specifications require the leakage be within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Cold Shutdown in the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Events 6, 7, 8 and 9: After the down power has commenced, the tube leak will increase to 200 gpm and the MAIN STM LINE HI RAD/INST FAIL annunciator will sound. The crew will verify that this is a valid alarm and trip the plant due to leakage greater than charging pump capacity. Upon the reactor trip, the turbine will fail to trip and the BOP operator will have to manually trip the turbine by either closing the MSIVs or pressing the turbine trip pushbuttons. An un-isolable Excessive Steam Demand Event (ESDE) inside containment occurs on #2 Steam Generator. When SIAS occurs, "A" HPSI pump fails to start and the "C" HPSI pump is degraded. The ATC must start the "A" HPSI pump manually.

The crew will complete EOP 2525; diagnose a Steam Generator Tube Rupture and ESDE and transition to EOP 2540, Functional Recovery as a result of diagnosing multiple events.

The scenario will be terminated when they determine that Cl-1 cannot be met and they cannot perform Step 2 of SUCCESS PATH: Cl-1: AUTOMATIC/MANUAL ISOLATION because they cannot isolate No.1 Steam Generator.

Scenario 4 3 of 30

Simulator Setup Instructions INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

IDNum Description Delay Ramp Event Sev or Final Rei Time Time Time Value Value Order MALFUNCTIONS RX04B Channel Y PZR Level Transmitter 2 min 55% 1 Failure TC06A No. 1 Turbine Control Valve Failure 1 min 20% 2 open RP09D RPS low flow trip Channel D 3 SG01A No. 1 Steam Generator Tube Leak 0.12 4 gpm SG02A No. 1 Steam Generator Tube Rupture 200 6 gpm TC10H Turbine tripfailure 7 MS01B ESDE inside containment 2 min 8 ES031 A HPSI fails to start automatically on SIAS SI05C C HPSI degraded flow 50% 9 REMOTE FUNCTIONS OVERRIDES Scenario 4 4 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _1_

Event

Description:

Channel Y PZR Level transmitter, L T-110Y (selected), fails low.

Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 1, Channel Y Pressurizer level transmitter fails low.

Indications Available:

Pressurizer CH Y LEVEL HI/LO (A-39 on C02-3)

Pressurizer level rising, letdown flow lowering. Both backup charging pumps start.

Examiner Note: Crew may respond using AOP 2585 Immediate Actions Section for Pressurizer Level Control Malfunction or the ARP for one of the corresponding alarms.

Examiner Note: The following steps are from AOP 25851mmediate Actions Section 9.0 Pressurizer Level Malfunction. [Steps] may be performed from memory.

[9.1] SHIFT "LTDN FLOW CNTL, HIC---110" to "MAN" (C-02).

[9.2] ADJUST "LTDN FLOW CNTL, HIC-110" to stabilize Pressurizer level (C-SRO/ATC 02).

9.3 Not applicable 9.4 IF affected Pressurizer Level control is channel PRESSURIZER CH Y, Go To ARP 25908-217, "PRESSURIZER CH Y LEVEL HI/LO" (C-02/3, window A-39).

Scenario 4 5 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _1_

Event

Description:

Channel Y PZR Level transmitter, LT-110Y (selected), fails low.

Time I Position I Applicant's Actions or Behavior Examiner Note: The following steps are from ARP 25908-217, A-39

1. OBSERVE Pressurizer level on all channels (C-03).

2. OBSERVE Pressurizer pressure on all channels (C-03).

3. N/A

4. N/A

5. OBSERVE TAVG/TREF recorder for deviation in TAVGITREF (C-04).

6. OBSERVE Foxboro 1/A control screen for Reactor Reg, or PPC status screen (screen "RRS_TP").

7. N/A

8. 1E indicated high or low level was caused by controller or transmitter malfunction (other than Reactor Regulating System inputs), PERFORM the following:

8.1 SHIFT "LTDN FLOW CNTL, HIC-110" to "MAN" (C-02).

8.2 ADJUST "LTDN CNTL, HIC-110" to stabilize Pressurizer level and Letdown flow (C-02).

8.3 SHIFT Pressurizer heater control "SEL SW" to channel "X."

SRO/ATC 8.4 As necessary, RESET the following Pressurizer heater breakers:

"PROP HTR GROUP 1"

"PROP HTR GROUP 2"

"BACKUP HTRS GROUP 1"

"BACKUP HTRS GROUP 2"

"BACKUP HTRS GROUP 3"

"BACKUP HTRS GROUP 4" 8.5 IF desired, COMMENCE forcing Pressurizer sprays.

8.6 SHIFT Pressurizer level control to channel "X" (C-03).

Examiner Note: Pressurizer heater breakers do not need to be reset for level failure at 55% level.

9. RESTORE Letdown to automatic as follows:

9.1 ADJUST bias to "0", using black thumbwheel.

9.2 SHIFT "LTDN FLOW CNTL, HIC-110" TO "AUTO."

9.3 ADJUST bias to restore Pressurizer level to setpoint Examiner Note: When automatic control of Pressurizer level is restored, or at the lead examiner's direction, proceed to Event 2, #1 Turbine Control Valve failure. (- 20MWe drop)

Scenario 4 6 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _2_

Event

Description:

No. 1 Turbine Control Valve fails closed.

Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 2, #1 Turbine Control Valve failure.

Indications Available:

Generator output lowering. RCS temperature rising, RCS pressure rising. Reactor Power lowering.

-20MWe drop in Generator output.

SRO Enter AOP 2584, Turbine Control Valve Failure.

Examiner Note: The following steps are from AOP 2584, Turbine Control Valve Failure. Steps with an

may be completed at any time.

3.0 Plant Stabilization SRO CAUTION Raising turbine load to address an actual reactor power transient is never an appropriate response. Lower reactor power with rods or boron in these cases.

3.1 * !E any of the following conditions are met, TRIP the reactor and Go To EOP 2525.

Parameters associated with automatic reactor or turbine trips are SRO challenged.

RCS Tc not within 1ooF of temperature program and efforts to regain control are unsuccessful.

Examiner Note: Reactor trip not required.

Scenario 4 7 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _2_

Event

Description:

No. 1 Turbine Control Valve fails closed.

Time I Position I Applicant's Actions or Behavior 3.2 Not applicable 3.3 1E turbine valve position is closed below pre-event position AND RCS temperature is increasing, PEFROM the following:

a. SELECT "Load Hold" (HMI).

b. REDUCE reqactor power using control rods or boron to stabilize Tc on ATC/BOP program.

c. 1E necessary, PLACE SGFP controls in MAN and RETURN SG level to pre-transient values (nominally 70%).

Examiner Note: ATC may insert Grp 7 CEAs several steps for temperature control. BOP will select LOAD HOLD on the Human Machine Interface (HMI).

3.4 *To maintain pressurizer pressure between 2250 to 2300 psi, PERFORM either of the following:

ATC

INITIATE forcing pressurizer sprays .

OPERATE pressurizer heaters and spray, as necessary.

4.0 Problem Determination NOTE

Closure of a single Intermediate Stop Valve (ISV) or Intercept Valve (IV) may cause feedwater heater level or turbine vibration issues. These conditions will be handled with respective ARP performance.

Complete Isolation of steam flow path to either LP Turbine will require a Turbine trip due to configuration uncertainties.

Complete Isolation of a steam flow path from either MSR will require a Turbine trip due to the potential for the MSR reliefs lifting and loss of hotwell inventory.

Scenario 4 8 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _2_

Event

Description:

No. 1 Turbine Control Valve fails closed.

Time I Position I Applicant's Actions or Behavior 4.1 CHECK all turbine Stop, Control Intercept and Intermediate Stop valves are in the correct position (HMI/PPC).

4.1.1 lE reactor power is greater than 15% AND any of the following conditions (HMI/PPC) exist, TRIP the reactor and Go To EOP 2525:

More than one HP turbine stop valve is CLOSED or CLOSING.

More than one HP turbine control valve is CLOSED or BOP CLOSING.

Complete isolation of steam flow paths to either LP turbine.

Complete isolation of steam flow paths from either MSR.

4.1.2 lE reactor power rise less than 15% AND any of the following conditions (HMI/PPC) exist, TRIP the turbine:

Examiner Note: Only one HP turbine control valve, is partially closed and Reactor Power is great than 15%. Contingency actions 4.1.1 and 4.1.2 are not applicable.

Examiner Note: When Tc and Pressurizer pressure are returned to normal operating bands, or at the lead examiner's direction, proceed to Event 3, Spurious RPS Low Flow Trip.

Scenario 4 9 of30

Op-Test No.: NRC Scenario No.: _4_ Event No.: _3_

Event

Description:

Spurious RPS low flow trip Channel "D" Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 3, Spurious RPS Low Flow trip Channel "D."

Indications:

RC LO FLOW TRIP CH D (DB-2 on C04)

Examiner Note: The following steps are from ARP 2590C-016 for DB-2, RC LO FLOW TRIP CH D.

1. IF reactor trips, Go To EOP 2525, "Standard Post Trip Actions" and PERFORM necessary corrective actions.

2. OBSERVE core and loop flow indication and running RCPs (C-03).

3. IF one or more RCPs are not providing full flow AND no automatic reactor trip has occurred, manually TRIP reactor and Go To EOP 2525, "Standard Post Trip Actions."

SRO/ATC

4. IF RCPs are operating properly AND alarm is due to instrument malfunction, PERFORM the following:

4.1 OBTAIN necessary key and PERFORM applicable actions to bypass channel "D" RCS flow bistable on RPS.

4.2 Refer To Technical Specifications LCO, 3.3.1.1, Table 3.3-1 and DETERMINE applicability.

4.3 SUBMIT Trouble Report to I&C Department.

SRO Refer To LCO, 3.3.1.1, Table 3.3-1:

Examiner Note: SRO enters Technical Specification 3.3.1.1 Action statement 2.

Examiner Note: When SRO has finished evaluating Technical Specifications, or at lead examiner's direction, proceed to Event 4, No. 1 Steam Generator Tube Leak (75 gpd and rising more than 15 gpd/min).

Scenario 4 10 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No. 1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 4, No. 1 Steam Generator tube leak (75 gpd and rising more than 15 gpd/min).

Indications:

S/G N16 monitor on PPC rising leakage for No.1 Steam Generator

N16 Alert Alarm (C-06/7 CB-19)

N16 High Alarm (C-06/7 CA-19)

SJAE Discharge RIT-5099 level rising Examiner Note: The following steps are from ARP 2590E-094, CB-19 N16 Alert.

1. OBSERVE radiation monitor indication (RC_14A, PPC N16 screen).

BOP

2. COMPARE with trends from RIT_ 4262, S/G blowdown gross activity and R1_5099, steam jet air ejector.

3. REQUEST Chemistry to perform SP 2833, Secondary Coolant Analysis for Primary to Secondary Leak Rate and Dose Equivalent Iodine Concentration" to aid in accomplishing the following:

3.1 DETERMINE the presence of primary to secondary leakage.

3.2 DETERMINE primary to secondary leak rate.

3.3 IDENTIFY the leaking Steam Generator.

4. lE primary to secondary leak is confirmed by chemistry analysis or independent radiation monitor indications, Refer To AOP 2569 Steam Generator Tube Leak and perform applicable actions.

CUE: Chemistry acknowledges request to perform secondary samples for a primary to secondary leak. Wait appropriate time and report back that frisk results indicate activity in No. 1 Steam Generator.

SRO Enters AOP 2569, Steam Generator Leak.

Examiner Note: The following steps are from AOP 2569 Steam Generator Tube Leak. Steps marked with an

are performed continuously or once specified conditions are met.

Scenario 4 11 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No. 1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior SRO 3.1

IF leakage exceeds capability of available charging pumps to maintain pressurizer level, PERFORM the following:

a. lE in MODE 1 or 2, PERFOM the following:

TRIP the reactor.

Go To EOP 2525, "Standard Post Trip Actions."

b. IF in MODE 2 or lower, PERFORM the following:

ENSURE SIAS is actuated.

Go To EOP 2541, Appendix 1, and "Diagnostic Flowchart."

3.2* IF the 'Main Steam Line Radiation Monitor High' alarm is annunciated AND is verified to be valid based on other changing RCS indications, PERFORM the following:

a. TRIP the reactor

b. Go To EOP 2525, "Standard Post Trip Actions."

Examiner Note: SGTL initiates at approximately 2 gpm or 2880 gpd.

Leakage will rise slowly over next few minutes. These steps are not a_m>licable at this time.

SRO/BOP 3.3* lEa SJAE OR SGBD Radiation Monitor alarm is received, ENSURE the following automatic actions occur:

MS-220A and MS-2208, blowdown isolation, close.

MS-15, blowdown tank discharge isolation, closes.

MS-135, blowdown quench tank discharge isolation, closes.

HV-4287 and HV-4288, SG blowdown sample discharge to secondary sample sink, close (secondary sample panel).

Slowdown values in PPC reset to "0."

Scenario 4 12 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No.1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior SRO 3.4* IF "N-16 HIGH," (C-06/7) radiation monitor alarm is annunciated AND is verified to be valid based on other indications, Refer To PPC "N16" screen to determine primary to secondary leak rate and PERFORM the following:

a. IF primary to secondary leak rate is greater than or equal to 75 gpd AND is increasing by greater than or equal to 15 gpd I 30 minutes, Refer To AOP 2575, "Rapid Downpower," LOWER reactor power to less than 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and be in Hot Standby within the following 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b. Refer To MP-26-EPI-FAP06, "Classification and PARs," and DETERMINE reportability requirements.

c. Refer To Technical Specification 3.4.6.2, "Reactor Coolant System Operational Leakage" and PERFORM applicable actions.

Examiner Note: Primary to secondary leak rate is~ 75 gpd AND increasing by~ 15 gpd/30minutes. A rapid power reduction is required by this AOP.

Scenario 4 13 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No. 1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior SRO Examiner Note: The following is from Technical Specification 3.4.6.2, Reactor Coolant System Operational Leakage:

Reactor Coolant System Operational LEAKAGE shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE,

c. 75 GPD primary to secondary LEAKAGE through any one steam generator, and

d. 10 GPM IDENTIFIED LEAKAGE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With any RCS operational LEAKAGE not within limits for reasons other than PRESSURE BOUNDARY LEAKAGE or primary to secondary LEAKAGE, reduce LEAKAGE to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

b. With ACTION and associated completion time of ACTION a. not met, or PRESSURE BOUNDARY LEAKAGE exists, or primary to secondary LEAKAGE not within limits, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in COLD SHUTDOWN within Examiner Note: SRO quantifies SGTL leak rate in excess of Technical Specification LCO and enters TSAS 3.4.6.2 c for primary to secondary leakage.

SRO Enter AOP 2575, Rapid Downpower.

Examiner Note: The following steps are from AOP 2575 Rapid Downpower.

Scenario 4 14 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No. 1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior ALL 3.1 PERFORM focus brief on the following:

REACTOR TRIP CRITERIA

Parameters associated with automatic reactor or turbine trips are challenged

RCS T cold not within 1OoF of temperature program and efforts to regain control are unsuccessful RCS TEMPERATURE CONTROL

RCS T cold to be maintained within 10°F of Attachment 5, "Temperature vs Power program" using Attachment 10, "Main Turbine Load Set Control."

To avoid uncontrolled cooldowns or power transients, sudden changes in RCS temperature or boron concentration should be avoided.

SRO 3.2 REQUEST SM/STA to Refer to Attachment 8, "Required Notifications," and PERFORM notifications.

ATC 3.3 INITIATE forcing pressurizer sprays.

ATC 3.4 IF not downpowering due to a dropped rod, INSERT Group 7 CEAs 10.:!:: 2 steps to initiate downpower.

BOP 3.5 Using the "Load Speed Control" switch, REDUCE turbine load to maintain Tc on program(+/- 2 deg).

SRO 3.6 Refer to PPC or Reactor Engineering Curve and Data Book and OBTAIN reactivity plan for the initial reactor power condition and desired load reduction.

Examiner Note: Reactivity Plan RE-G-14 NOTE Attachment 11 "Approximate Load Demand vs. Reactor Power," can SRO/BOP be used to correlate the desired power level to a turbine load demand setpoint.

Scenario 4 15 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No. 1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior BOP 3.7 Refer To Attachment 10, "Main Turbine Load Set Control," REDUCE turbine load and MAINTAIN Tc on program (+/-2 deg).

Examiner Note: The following steps are from AOP 2575 Rapid Downpower Attachment 10 Main Turbine Load Set Control:

1. IF desired to commence or modify a turbine load ramp, PERFORM the following (HMI "Load" screen):

a. IF previous ramp has stopped, SELECT "Load Hold."

b. SELECT "Load Setpt" and ENTER desired value.

>BOP enters 15%

c. SELECT "Rate setpt" and ENTER desired value.

>BOP enters 84%/hr

d. WHEN ready to commence load reduction, SELECT "Load Resume."

2. IF desired to adjust the "Load Ramp Rate," PERFORM any of the following:

.* SELECT "Rate setpt" and ENTER new value .

SELECT "5% I hour," OR "10% I hour," OR "20% I hour."

SELECT "Raise" or "Lower" (0.25% I hour change) .

3. IF Tavg and Tc are high off program, PERFORM the following:

a. SELECT "Load Hold" to stop ramp.

b. WHEN Tavg and Tc are trending back to program, SELECT "Load Resume."

4. IF Tavg and Tc are low off program, PERFORM the following:

a. JOG the "Load/Speed CONTROL" switch to "Lower."

b. WHEN Tavg and Tc are back on program, SELECT Load Setpt" and ENTER desired value.

c. IF desired, Go To Step 1 and RESUME turbine load ramp.

5. IF desired load has been reached SELECT "Load Hold."

Scenario 4 16 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 4 5 Event

Description:

No.1 Steam Generator SGTL (75 gpd and rising more than 15 gpd/min) and Rapid Power Reduction Time I Position I Applicant's Actions or Behavior ATC 3.8 !E desired to borate from the RWST (preferred method) PERFORM the following:

a. ENSURE at least one charging pump operating.

b. ENSURE CH-196, VCT makeup bypass, closed.

c. ENSURE CH-504, RWST to charging suction, open.

d. OPEN CH-192, RWST isolation.

e. CLOSE CH-501, VCT outlet isolation.

f. CHECK charging flow at desired rate.

g. Go To step 3.11.

Examiner Note: Crew should borate from the RWST.

ALL 3.11 During the down power, Refer To Attachment 1, "Rapid Down power Parameters," and MAINTAIN parameters as specified throughout downpower.

Examiner Note: Attachment 1 Rapid Downpower Parameters:

Condensate and heater drain flows and pressures: sufficient to maintain adequate SGFP suction pressure.

FRV D/P: greater than 40 psid

Turbine load: responding to changes in load demand, with control valves operating together

Steam generator levels 55 to 70%.

MSR parameters tracking together

Turbine Generator MVARs: as specified by CONVEX

Reactor power: being monitored using IT power indication

ASI: In accordance with reactivity plan or within 0.01 of ESI or per COLR.

CEA position: greater than POlL

Tc: less than or equal to 549°F

Pressurizer level: between 35 and 70%

Pressurizer pressure: between 2,225 and 2,300 psia (DNB margin)

Examiner Note: When reactor power has been lowered approximately 5% or at lead examiner's direction, proceed to Event No. 6, Steam Generator Tube Rupture on No. 1 Steam Generator.

Scenario 4 17 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6. 7. 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 6, SGTR on No. 1 Steam Generator.

Indications:

Steam Line Radiation Monitor Alarm (C-01, A30)

N16 Alarm (C-06 CA-19)

N16 Alert (C-06 CB-19)

PROCESS RAD MON HI/HI FAIL (C-06, DA-24)

Backup charging pumps start, Letdown lowers

Pressurizer Level Lowering ALL Trip the Reactor based on leakage exceeding charging pump capability to maintain pressurizer level or Main Steam Line Radiation Monitor High Alarm validated with RCS indications. Go To EOP 2525 Standard Post Trip Actions.

Examiner Note: SRO directs step 3.1* or 3.2* of AOP 2569 Steam Generator Tube Leak. Crew may perform step 3.3*.

SRO Enters EOP 2525 Standard Post Trip Actions Examiner Note: Turbine fails to trip on reactor trip. An ESDE occurs two minutes after reactor trip.

The "A" HPSI pump fails to start on SIAS and the "C" HPSI pump has degraded flow.

CRITICAL TASK: Manually trip the turbine or close MSIVs within 1 minute following a reactor trip and failure of automatic turbine trip.)

Time of reactor trip: _ _ _ __

Time of turbine trip: _ _ _ __

CRITICAL TASK: Isolate AFW to the affected SG #2 within 30 minutes following the generation of MSIS during an ESDE.

To isolate AFW to No.2 Steam Generator (ESDE generator) with Auto AFW signal IN, the BOP must take both Auto Aux Feedwater Override Switches to and take AFW FCV controller HIC-5279A to manual and dial it closed.

Time ofMSI: - - - - -

Time AFW isolated to No. 2 Steam Generator:

Scenario 4 18 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6. 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior Examiner Note: The following steps are from EOP 2525 Standard Post Trip Actions.

Determine Status of Reactivity Control

1. DETERMINE that Reactivity Control acceptance criteria are met by performing ALL of the following steps:

ATC

a. CHECK that reactor power is dropping.

b. CHECK that SUR is negative.

c. CHECK that no more than one CEA is not fully inserted.

Determine Status of Maintenance of Vital Auxiliaries

2. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

a. CHECK that the main turbine is tripped by BOTH of the following:

ALL main stop valves are closed.

Generator megawatts indicate zero.

a.1 PERFORM ANY of the following:

1) Manually TRIP the main turbine.

2) CLOSE the MSIVs.

Examiner Note: Operator should manually TRIP the main turbine.

BOP

b. !E 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

c. CHECK that ALL Facility 1 and 2 electrical buses are energized:

6.9kV Electrical Buses 25A, 25B

4. 16kV Non-Vital Electrical Buses 24A, 24B

4.16vV Vital Electrical Buses 24C, 24D

Vital DC Buses 201A, 201B, DV-10, DV-20

Vital AC Instrument Buses VA-10, VA-20

d. CHECK that BOTH facilities of service water are operating.

e. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

f. CHECK on facility of CRAC operating.

Scenario 4 19 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7. 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Ap_plicant's Actions or Behavior Determine Status of RCS Inventory Control

3. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

a. CHECK that BOTH of the following conditions exist:

Pressurizer level is 20 to 80%

Pressurizer level is trending to 35 to 70%

ATC a.1 IF the Pressurizer Level Control System is not operating properly in automatic, RESTORE and MAINTAIN pressurizer level 35 to 70% by performing ANY of the following:

1) OPERATE the Pressurizer Level Control System.

2) Manually OPERATE charging and letdown.

Examiner Note: Operator may isolate letdown.

b. CHECK that RCS subcooling is greater than or equal to 30°F Scenario 4 20 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6 7 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior Determine Status of RCS Pressure Control

4. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of the following:

CHECK that pressurizer pressure is 1900 to 2350 psia.

CHECK that pressurizer pressure is trending to 2225 to 2300 psia.

4.3 IF pressurizer pressure is less than 1714 psia, ENSURE ALL of the following:

SIAS has actuated. (C01)

Examiner Note: Crew may manually initiate SIAS based on pressurizer pressure approaching setpoint of 1714 psia and secure 2 RCPs.

CIAS has actuated. (C01)

E8FAS has actuated. (C01)

ONE complete facility of CRAGS is operating in recirc mode. (C25)

Facility 1

HV-203A, Fan F-21A exhaust damper is open.

Fan F-21A, supply fan is running.

HV-206A, Fan F-31A exhaust damper is open.

Fan F---31A, exhaust fan is running.

HV-212A, Fan F-32A exhaust damper is open.

ATC

Fan F-32A, filter fan is running.

HV-202, minimum fresh air damper is closed.

HV-207, cable vault exhaust damper is closed.

HV-208, exhaust air damper is closed.

Facility 2

HV-2038, Fan F-21 8 exhaust damper is open

Fan F-21 8, supply fan is running.

HV-2068, Fan F-31 8 exhaust damper is open.

Fan F-31 8, exhaust fan is running.

HV-2128, Fan F-328 exhaust damper is open.

Fan F-328, filter fan is running.

HV-495, fresh air damper is closed.

HV-496, exhaust air damper is closed.

HV-497, cable vault exhaust damper is closed.

4.4 !E pressurizer pressure is less than 1714 psia AND SIAS ha initiated, ENSURE that ONE RCP in each loop is stopped.

4.5 !E pressurizer pressure lowers to less than the minimum RCP NPSH limit, STOP ALL RCPs.

Scenario 4 21 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior CRITICAL TASK: Manually start "A" HPSI pump prior to reaching pressurizer low level alarm following a failure of "A" HPSI pump to actuate and a degradation of the "C" HPSI pump.

Time that "A" HPSI pump manually started_ _ _ __

Pressurizer Level when "A" HPSI pump started: _ _ _ __

Determine Status of Core Heat Removal

5. DETERMINE that Core Heat Removal acceptance criteria are met by ATC performing ALL of the following:

a. CHECK that at least one RCP is operating.

b. CHECK that loop delta T is less than 1oo

c. CHECK that Th subcooling is greater than or equal to 30°F.

Determine Status of RCS Heat Removal

6. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

a. CHECK that BOTH steam generators pressure are 880 to 920 psia.

a.2 !E ANY steam generator pressure is less than 880 psia, PERFORM the following:

1) ENSURE that the steam dumps are closed.

2) ENSURE that the ADV is closed.

3) CHECK that the main steam safety valves are closed.

BOP a.3 IF ANY steam generator pressure is less than 800 psia AND lowering, PERFORM the following:

1) CLOSE BOTH MSIVS.

2) !E ANY MSIV failed to close, PLACE Bottle-Up Panel isolation switches for the open MSIV to "ISOL":

Examiner Note: a3.2 Not Applicable

3) ENSURE BOTH MSIV bypass valves are closed.

a.4 IF ANY steam generator pressure is less than 572 psia, ENSURE that MSI has actuated. (C01)

Examiner Note: MSI is expected. See Critical Task for isolating AFW to No. 2 Steam Generator.

Scenario 4 22 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position 1 Applicant's Actions or Behavior Determine Status of RCS Heat Removal (continued) 6.

b. CHECK that RCS Tc is being maintained 530 to 535°F.

Examiner Note: Expected Tc < 530°F contingency action b.2.3 is applicable b.2. !E RCS Tc is less than 530°F, PERFORM the following:

BOP 3) OPERATE the steam dumps or ADVs to stabilize RCS Tc.

c. CHECK that at least one steam generator has BOTH of the following conditions met:

Level is 10 to 80% .

Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

d. CHECK that RCS subcooling is greater than or equal to 30°F.

Scenario 4 23 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position J Applicant's Actions or Behavior Determine Status of Containment Isolation

7. DETERMINE that Containment Isolation acceptance criteria are met by ALL of the following:

a. CHECK that NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment

RM-7890, Personnel Access Area

RM-7891, Ctmt Refuel Floor Area

RM-8240, High Range

RM-8241, High Range

RM-8123 A and B, Ctmt Atmosphere

RM-8262 A and B, Ctmt Atmosphere Radiation Monitors Outside Containment ATC

RM-7894, Charging Pump Area

RM-7895, Primary Sample Sink

RM-7896, -25ft 6 in Waste Process Area

RM-7897, -45ft 6 in Waste Process Area

RM-8132A and B, Unit 2 Plant Stack

RM-8169, Millstone Stack WR

RM-8168, Unit 2 WR Stack

RM-6038, RBCCW

b. CHECK that NONE of the following steam plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors

RM-5099, Steam Jet Air Ejector

RM-4262, SG Slowdown

RM-4299A and B, Main Steam Line 1

RM-4299C, Main Steam Line 2 Scenario 4 24 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6. 7. 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position J Applicant's Actions or Behavior Examiner Note: Radiation Monitors in alarm: RM-5099, Steam Jet Air Ejector, RM-4262, SG Slowdown, RM-4299A and B, Main Steam Line 1.

The following contingency actions are applicable:

b.1 IF feed is available to BOTH steam generators, THROTTLE feed to the steam generator with the highest radiation readings to maintain level 40-45% by performing ANY of the following:

ATC/BOP Examiner Note: ATC/BOP should perform this for No.1 Steam Generator:

a. OPERATE associated main feed reg bypass valve, FW-41A or FW-418.

b. IF AFAS has actuated, PERFORM the following:

PLACE the auxiliary feed "OVERRIDE/MAN/START/RESET" handswitches in "PULL TO LOCK".

OPERATE the associated aux feed reg valve, FW-43A or FW-438.

Determine Status of Containment Isolation continued ATC 7.

c. CHECK that containment pressure is less than 1.0psig.

Determine Status of Containment Temperature and Pressure Control

8. DETERMINE that Containment Temperature and Pressure Control acceptance criteria are met by BOTH of the following steps:

a. CHECK that containment temperature is less than 120°F. (PPC or avg of Points 5 and 6)

ATC b. CHECK that containment pressure is less than 1.0psig.

8.1 ENSURE at least two CAR fans operating on the facility with an operating train of RBCCW.

8.3 PERFORM the following:

a. PLACE ALL available containment aux eire fans in low speed.

b. START ALL available containment post incident recirc fans.

Perform Subsequent Actions of EOP 2525 SPTAs.

ATC/BOP Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

Scenario 4 25 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior Enters EOP 2540 Functional Recovery due multiple events in progress (SGTR SRO and ESDE).

Examiner Note: The following steps are from EOP 2540 Functional Recovery. Steps marked with an

can be pulled forward or performed when conditions are met.

1. CLASSIFY the event. Refer To MP EPI- FAP06, "Classification and PARs" SRO

IF classification requires RCS sampling, Refer To Appendix 46, "Sampling for EAL Determination" and DIRECT Chemistry as required.

2. PERFORM ALL of the following:

SRO

OPEN the Safety Function Tracking Page and ENTER the EOP entry time.

ENSURE the master alarm silence switch is in "NORMAL."

3. * !E pressurizer pressure is less than 1714 psia AND SIAS has initiated, PERFORM the following:

a. ENSURE ONE RCP in each loop is stopped.

b. PLACE associated pressurizer spray valve controller RC-100E or RC-1OOF in manual and CLOSE the valve.

ATC c. IF pressurizer pressure lowers to less than the minimum RCP NPSH limit, PERFORM the following:

1) STOP ALL RCPS.

2) PLACE TIC-4165, steam dump T AVG controller, in manual and closed.

3) PLACE pressurizer spray valve controllers RC-100E and RC-100F in manual and CLOSE the valves.

Scenario 4 26 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior

4. SAMPLE steam generators that are available for RCS heat removal as follows:

a. OPEN appropriate steam generator sample valves:

MS-191A Examiner Note: Steam Generator 1 is available for RCS heat removal. Steam Generator 2 is not available due to ESDE.

BOP b. DIRECT Chemistry to perform ALL of the following:

Sample ANY steam generator that is available for RCS Heat Removal

Frisk the samples

Report frisk results

Analyze samples for boron and activity.

c. WHEN Chemistry reports that samples have been taken, CLOSE the steam generator sample valves.

CUE: When directed to sample Steam Generators, respond 20 minutes later that samples have been taken. Report that frisk results show indication of activity in No. 1 Steam Generator.

5. PLACE the hydrogen analyzers in service. Refer To Appendix 19, ATC/BOP "Hydrogen Analyzer Operation."

NOTE If the Safety Function Status Checklist is not satisfied for the selected SRO success path, the US may commence the operator actions for safety functions which are not met based on Safety Function hierarchy. The remaining Safety Functions should be prioritized as time permits.

6.* IDENTIFY success paths to be used to satisfy each safety function using BOTH of the following:

SRO

Resource Assessment Trees

Safety Function Tracking Page Scenario 4 27 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior 7.* PRIORITZE safety functions to be addressed first based on ALL of the following:

a. Safety functions which do not meet the Safety Function Status Checklist SRO for the selected success path.

b. Safety functions for which the equipment to support the success path is not operating.

c. Safety functions for which success path three has been selected.

d. Safety functions for which success path two has been selected.

e. e. Safety functions for which success _Q_ath one has been selected.

Safety Function Path Met? Priority RC-1 CEA Insertion Yes 5 DC-1 DC Power Yes 6 AC-1 RSST Yes 7 IC-2 CVCS only if Lpzr Yes 3

>20% if not then IC2 PC-1 Subcooled Yes 8 HR-2 Sl operating Yes 4 SRO Cl-1 Automatic/Manual No 1 CTPC-3 CARs (Normal) Yes 2 Examiner Note: The success paths and order of priority are based on the conditions seen during the scenario validation. A different path and priorities may be applicable due to the timing of operator mitigating actions.

Identifies Cl-1 as the first priority and enters EOP 2540E, Functional Recovery SRO of Containment Isolation.

Scenario 4 28 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6. 7. 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time I Position I Applicant's Actions or Behavior Examiner Note: The following steps are from EOP 2540E Functional Recovery of Containment Isolation.

1.* Not applicable because already performed.

2.*1F a SGTR is indicated by ANY of the following:

Steam generator activities

Main steam piping radiation levels

Steam generator level change when not feeding

Steam generator blowdown activity

Steam generator mismatch in level with essentially the same feed and steaming rate for both steam generators

Feed flow mismatch between steam generators

Steam flow versus feed flow mismatch in a steam generator prior to the trip

Steam flow to feed flow mismatch in a SG prior to the trip IDENTIFY and ISOLATE the most affected SG. Refer To Appendix 12, "SGTR Response."

Scenario Termination: When the crew has established safety function recovery priorities, implemented Cl-1 and determined that they CANNOT isolate No.1 Steam Generator (SGTR) or at the lead examiner's the scenario may be terminated.

Follow-up question if necessary:

1. Given the plant condition at the end of the scenario, how would you procedurally cooldown to Mode 5?

Answer: HR-2 Step 15 and EOP 2541 Appendix 11.

Examiner Note: The following steps are from Appendix 11, ESDE Response.

Examiner Note: The following is guidance from OP 2260 EOP User Guide for stabilizing CET temperatures using the least affect SG ADV; If the ESDE progresses to SG dry out conditions, when CET temperatures begin to rise, the operator is required to stabilize CET temperatures using the least affected SG ADV. CET temperatures must be closely monitored and actions taken to minimize any large temperature change (CET temperature may be affected by the establishment of natural circulation and feedwater flow rate).

A general rule of thumb that can be used is to adjust the ADV automatic setpoint for the least affected SG to the saturation pressure for the CETs (this can be obtained using the Steam Tables or the value displayed on SPDS).

Scenario 4 29 of 30

Op-Test No.: NRC Scenario No.: _4_ Event No.: 6, 7, 8 and 9 Event

Description:

SGTR No. 1 SG, Reactor Trip, Turbine Fails to trip, ESDE on No. 2 SG , A HPSI pump fails to start on SIAS, C HPSI pump is degraded.

Time l Position I Applicant's Actions or Behavior Examiner Note: The following steps are from EOP 25400 Functional Recovery of Heat Removal.

Examiner Note: The following guidance from OP 2260 EOP User Guide:

If there is a conflict between isolating a SG (e.g., due to indications of SGTR or ESDE) and maintaining adequate heat removal via at least one SG, then maintain RCS heat removal via the least affected SG has precedence. At least one SG should always be available for heat removal, if at all possible. [Isolation of both SGs and going to OTC is a last resort option.]

Scenario 4 30 of 30

SIMULATOR SCENARIO #2 Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 2 Op-Test No.: NRC 2014 Examiners: Operators: SRO ATC BOP Initial Conditions: IC 56, 74%, "B" Motor Driven AFW Pump OOS, "B" Diesel Generator OOS, AlB Condensate Pumps running, AJC Charging Pumps running. 24E aligned to 24C.

Turnover: Power has been less than 85% for one day to support "C" condensate pump maintenance; Crew has been instructed to raise power to 100%. Post maintenance testing of the "B" Diesel Generator is scheduled for this shift. "B" Diesel Generator is OOS. 24E is aligned to 24C. Condensate Pumps A and B running. C condensate pump is in standby and ready for testing. A and C Charging pumps running and forcing_psessurizer SQra_y_s in _pJe_paration for up power.

Critical Tasks:

1. CT-1 (SPTA-5): Manually shut down the Reactor: The plant must be manually tripped prior to reaching the Automatic Auxiliary Feedwater initiation set point of 27% in either S/G.

2. Prior to emptying either Steam Generator, operator action is required to establish AFW flow to Steam Generators. (Source EOP User Guide).

Event No. Malf. No. Event Event Description Type*

1 R (ATC, Raise power to 100%.

(0 min) SRO) 2 TS (SRO)

CVR36 "C" Charging Pump Trip (20 min) C (ATC) 3 C (BOP, RX11B Failure of No. 1 SG Steam Flow Transmitter (low)

(30 min) SRO) 4 RC06D, TS(SRO)

PORV RC-404 leakage.

(35 min) ORs C (ATC) 5 FW03B "B" Condensate pump trips, "C" condensate pump is either auto or

(+45 min) FW03C manually started and then trips off line 1 minute later.

RP28D, SGFP trip due to loss of suction. Reactor fails to automatically trip.

6 RP28E M (All) Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D

(+45 min)

ED02 to Auto Transfer on Reactor Trip (Loss of Normal Power).

7 Mechanical failure of Diesel Generator 12U output breaker-EG08A C (BOP)

(+46 min) prevents closure of breaker.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 1 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time .r Position I Applicant's Actions or Behavior Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 2 NRC 2014, Scenario 2 Summary:

The crew will take the shift with the unit at 74% power and the crew has been instructed to raise reactor power to 100%. A and C Charging pumps are running and forcing pressurizer sprays in preparation for up power. B Charging pump is aligned to Facility 1 (24E is aligned to 24C). Condensate Pumps: A running, B running. C secured because of maintenance. C condensate pump is ready for testing and in standby.

Event 1: The crew takes the shift and raises power approximately 5%. The crew may or may not get to the point of starting C condensate pump and could continue scenario with 2 condensate pumps running. If they attempt to start C condensate pump, it start but a will then trip offline during Event 5 instead of tripping after it is started.

Event 2: The "C" Charging Pump trips. The CHARGING PUMP C TRIP annunciator will alarm and the crew will take ARP actions to lower letdown flow and align B Charging pump to Facility 2. They may start the B charging pump to continue the power change. Two Charging pumps were running initially for the up power.

The SRO will address TS for charging pump operability.

Event 3: The alternate steam flow transmitter for No. 1 Steam Generator will fail low. The crew will respond per AOP 2585 Immediate Actions.

Event 4: When feed control has been returned to auto, PORV RC-404 starts to leak by. Quench Tank level will slowly rise and PORV Discharge Temperature will rise. The crew will respond to the QUENCH TANK HI TEMPERATURE alarm and take ARP steps to close the PORV block valve. The SRO will address TS for PORV operability.

Event 5: After the leaking PORV has been isolated and technical specifications evaluated, the "B" Condensate pump trips and "C" Condensate pump trips approximately 1 minute after being started (manually or automatically). This causes Steam Generator Feed Pump suction pressure to lower. The crew will manually trip the reactor because of the loss of feed flow. If the crew does not trip the reactor, the reactor will NOT trip automatically as the Low Steam Generator Level auto reactor trip is defeated.

Event 6 and 7: On the reactor trip, there is a failure of 4.16kV Buses 24C and 24D to auto transfer (Loss of Normal Power) and loss of offsite power from Grid for Unit 2. The "A" Diesel Generator (DG) breaker fails to 2 of34

Op-T est No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time J Position I Applicant's Actions or Behavior closure due to a mechanical failure after the diesel starts. The "B" Diesel Generator is out of service. The crew will transition to EOP 2530, Station Blackout. Maintenance responds that "B" DG will be available within two hours.

The crew will work to power 24E from Unit 3 NSST. The scenario is terminated when) one vital4.16kV bus is energized from Unit 3.

INPUT

SUMMARY

Either INPUT or VERIFY the following functions:

ID Num Description Delay Ramp Event Sev or Final Rei*

Time Time Time Value Value Order MALFUNCTIONS ED02 Loss of RSST RP28D Rx Trip Fail (SG#1 Lo Level)

RP28E Rx Trip Fail (SG#2 Lo Level)

EG08A DG 12 Output Brkr 15G-12U-2 Fail RX11B MS Flow XMTR (FT-4243B) Fail 3.456E

+6 lbm/hr RC06B PORV (RC-404) Fail 0.3 RC06D PORV (RC-404) Leakage 0.08 FW03B Condensate PP P-2B Trip FW03C Condensate PP P-2C Trip 1 min REMOTE FUNCTIONS CO?- EHC Monitor Panel Trouble OFF B33 CVR36 Charging Pump C Sue VLV 2CH322 CLOSE OVERRIDES C02- PORV RC-404 Open OFF D11 RCHS- PORV RC 404 PZR Relief (DO RED) NRED 1404B-2 3 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time I Position I Applicant's Actions or Behavior Examiner Note: The crew has been instructed to brief the up power prior to taking the watch. The up power is performed in accordance with OP 2204 and the reactivity plan.

Method: Dilution to the Charging Pump suction and CEAs Rate: 10%/hr Examiner Note: Dilution is performed using OP2304C Section 4.2 Diluting Directly to Charging Pump Suction. The following steps are from OP2304C Section 4.2 4.2.3 ENSURE the following:

At least one RCP operating (C-03)

At least one charging pump running (C-02)

Available volume in clean Liquid Radwaste System is adequate for letdown flow (C-63)

"MAKEUP MODE SEL" in "DILUTE" (C-04)

PMW pump running (indicating lights on C-02)

"PRI MAKEUP WTR FLOW CONTROLLER FC-210X" "AM" is lit (C-04)

ATC 4.2.4 IF RCS boron concentration will be changed a specific amount, Refer To OP 2208, "Reactivity Calculations," or PPC.

4.2.5 DETERMINE quantity of PMW needed to reach desired condition.

4.2.6 ENSURE the following are closed:

CH:.512, "MAKEUP VLV STOP," (C-04)

CH-196, "VCT MAKEUP BYPASS," (C-02)

CH-192, "RWST ISOL," (C-02) 4 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time I Position I Applicant's Actions or Behavior 4.2.7 IF required, ADJUST automatic setpoint of "PRI MAKEUP WTR FLOW CONTROLLER FC---210X" as follows (C-04):

a. OBSERVE charging flow on Fl-212, "CHG HDR FLOW" (C-02/3) or F212 (PPC).

b. RECORD charging flow:

c. ENSURE "AM" is lit.

d. PRESS "SEL" button until cursor appears above setpoint (left hand bar graph).

e. Using "UP arrow" and "DOWN arrow" buttons, ADJUST setpoint to less than or equal to the charging flow rate recorded in step 4.2. 7b.

4.2.8 IF desired, Refer to Attachment 4 as required and RESET "PRI MAKEUP ATC WTR FLOW CONTROLLER FC-210X" to 0 total gallons (C-04).

4.2.9 SET "PRI MAKEUP WATER FQIS---210X" to desired quantity (C-04).

4.2.10 ENSURE CH-504,"RWST TO CHG SUCT," is open (C-02).

NOTE: When CH-196, "VCT MAKEUP BYPASS" is opened, the "M" part of the "AM" light will extinguish, indicating the controller is activated.

4.2.11 OPEN CH-196, "VCT MAKEUP BYPASS," (C-02).

4.2.12 MONITOR VCT level and pressure as indicated on the following: (C-02 or PPC).

"VCT PRES, Pl-225"

"VCT LVL, Ll-226" 5 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time I Position J Applicant's Actions or Behavior 4.2.13 IF desired, ADJUST automatic setpoint of "PRI MAKEUP WTR FLOW CONTROLLER FC-210X" as follows (C-04):

a. OBSERVE charging flow on Fl---212, "CHG HDR FLOW" (C-02/3) or F212 (PPC).

b. RECORD charging flow:

c. PRESS "SEL" button until cursor appears above setpoint (left hand bar graph).

d. Using "UP arrow" and "DOWN arrow" buttons, ADJUST setpoint to less than or equal to the charging flow rate recorded in step 4.2. ?b.

ATC Examiner Note: The following step is NOT APPLICABLE unless the crew decides to secure the dilution at a later point in the scenario:

4.2.14 !E desired to stop dilution before determined quantity of PMW has been injected, PERFORM the following:

a. CLOSE CH-196, "VCT MAKEUP BYPASS," (C-02).

b. ENSURE "PRI MAKEUP WTR FLOW CONTROLLER FC-210X" indicates 0 gpm (C-04).

c. !E desired to recommence dilution, Go To step 4.2.11.

d. !E not desired to recommence dilution, RESET "PRI MAKEUP WATER, FQIS-210X" to Ogallons (C-04).

6 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _1_

Event

Description:

Raise Power to 100%

Time I Position I Applicant's Actions or Behavior Examiner Note: The turbine load ramp can be performed using OP 2204 Att 15 Turbine Generator Adjustments or OP 2203 Attachment 5 {same). The following steps are from OP 2305 Attachment 15:

NOTE Selecting the "Load Setpt" "Rais~" and "Lower" buttons changes the Load Setpoint in 0.1% increments. To eliminate response time delay when using these buttons, the Load Ramp Setpoint is normally set to 600%1hr.

4.0 !E desired to use Load Set controls to obtain required turbine load adjustment, PERFORM the following: (HMI "Load" screen).

4.1 NIA 4.2 PERFORM one of the following, to adjust "Load Setpoint (%)"to desired value:

SELECT "Load Setpt" and ENTER desired value

SELECT "Raise" or "Lower" (0. 1% change) 4.3 PERFORM any of the following to adjust "Load Ramp Setpoint (%1hr)" to desired value:

BOP

SELECT "Rate Setpt" and ENTER desired value

SELECT "Raise" or "Lower" (0.25%1hr change)

SELECT "5% I hour," "10% I hour" or "20% I hour" 4.4 WHEN ready to commence turbine load ramp, SELECT "Load Resume."

4.5 REPEAT steps as necessary to adjust turbine load or ramp rate.

4.6 WHEN desired load is reached, SELECT "Load Hold."

5.0 NIA

6. MONITOR the following plant parameters to check control valve response is in the direction expected:

Turbine control valve positions

Turbine 1st stage pressure

Main generator output (MWe)

Steam Generator pressure

Tcold

Thermal power Examiner Note: When reactor power is 5% higher than initial power or at the lead examiner's direction, proceed to Event #2, Trip of "C" Charging Pump.

7 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _2_

Event

Description:

"A" Charging Pump Trip Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event #2, "C" Charging Pump trip.

Indications Available:

CHARGING PUMP C TRIP JB-14 on C-02/31.

Examiner Note: The following steps are from ARP 25908-054, B-14 Examiner Note: Crew secure should dilution in progress from Event #1 using Step 4.2.14 of OP2304C and using the Load Hold button on the turbine HMI.

CAUTION ATC Prior to starting a standby pump, consider if pump trip was caused by gas binding. ["INPO SOER 97-1, Potential Loss of High Pressure Injection And Charging Capability From Gas Intrusion."]

1. Place "CH PP C," charging pump hand switch in "PULL TO LOCK" (C-02).

2. N/A because gas intrusion is not indicated.

3. N/A because letdown should not isolate on high temperature.

ATC 4. IF only "C" charging pump was operating and letdown is not isolated, START another charging pump.

5. 1E more than one charging pump was operating, ADJUST "LTDN FLOW CNTL, HIC-110," bias to balance charging and letdown flows and restore pressurizer level to program (C-02).

CUE: If asked to determine investigate and determine the status of "C" Charging Pump, report back that pump is hot to the touch.

8 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _2_

Event

Description:

"A" Charging Pump Trip Time J Position I Applicant's Actions or Behavior

6. Refer ToTS 3.5.2 and TRM 3.1.2.3, 3.1.2.4, 7.1.1 and DETERMINE applicability LCO 3.5.2 Two ECCS subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3*

With pressurizer pressure ~ 1750 psia.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Examiner Note: Because there is no Charging Pump on Train B (24E aligned SRO to 24C and "B" Charging Pump is in Pull-To-Lock), SRO should enter TS 3.5.2 Action statement "a:"

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Examiner Note:

TRM 3.1.2.3 not applicable.

SRO should enter TRM 3.1.2.4: With only one charging pump FUNCTIONAL, manage the risk impact in accordance with the requirement of 10 CFR 50.65(a) (4). SRO should enter TRM 7.1.1 TR Item A on Table 7.1.1-1 for Charging Pump "A."

SRO/ATC 7. IF necessary, Refer To OP 2304E, "Charging Pumps" and ALIGN "B" charging pump, to Facility 2.

CUE: If directed to align Charging Pump "B" to Facility 2, acknowledge request and align it. Report back to Control Room.

8. On the running charging pump(s), VERIFY charging pump suction stabilizer heater indicator switch (amber color) is lit.

ATC 9. IF valve misalignment is suspected, Refer To OP 2304C-002, "Boric Acid Valve Lineup" and ENSURE proper valve alignment.

10. MONITOR performance of operating charging pumpl_sl CUE: If directed, PEO reports that charging pump suction stabilizer heater indicator switch (amber color) is lit. Operating charging pumps running as expected.

9 of34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _3_

Event

Description:

Failure of No. 1 Steam Generator Steam Flow Transmitter (low)

Time I Position J Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 3, Failure of No. 1 Steam Generator Steam Flow Transmitter {low).

Indications Available:

PPC alarm No. 1 SG Steam Flow

Steam flow and feed flow mismatch on No. 1 SG Flow Yokojawa

No. 1 SG FRV closing, No. 1 SG level lowering

SG LEVEL SETPOINT DEVIATION HIILO {D-16 on C-05) {may or may not get this alarm depending on crew response time)

SRO Enter AOP 2585, Immediate Actions Examiner Note: The following steps are from AOP 2585, Immediate Actions Section 4.0 Abnormal Steam Generator Level. Step in [] are expected to be performed from memory.

[4.1] PLACE both SGFPs in manual:

PRESS "A" SGFP "CONTROL" "MANUAL" pushbutton and ENSURE "MANUAL" pushbutton, lit.

PRESS "B" SGFP "CONTROL" "MANUAL" pushbutton and ENSURE "MANUAL" pushbutton, lit.

[4.2] SHIFT affected SG Feedwater Flow Control to MANUAL (C-05):

No.1 SG BOP

"REG VLV, LIC-5268," controller in manual (red light lit)

[4.3] RESTORE SGFP speeds to normal value (100% Power: 4400 to 4600 rpm).

Examiner Note: Speeds should be lower because plant is less than 100%

power.

[4.4] STABILIZE affected SG level (Steam Flow and Feed Flow matched).

Examiner Note: Steam Generator Level normal range 60-75%

10 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _3_

Event

Description:

Failure of No. 1 Steam Generator Steam Flow Transmitter (low)

Time I Position I Applicant's Actions or Behavior 4.5 Go To ARP 2590D-064, "SG LEVEL SETPOINT DEVIATION HI/LO" (C-05, SRO/BOP window D-16).

Examiner Note: The following steps are from ARP 25900-064, D-16.

CORRECTIVE ACTIONS

1. DETERMINE which SG has the level deviation (C-05).

2. IF necessary, Refer To OP 2385, "Feedwater Control System Operation" and PLACE feedwater control system in manual control to restore SG level to setpoint (C-05).

BOP 3. OBSERVE PPC S/G transient display to determine if level, steam flow, or feed flow transmitter failure has caused the deviation.

4. OBSERVE the affected side green transmitter lights to determine if level, steam flow, or feed flow transmitter failure has caused the deviation (C-05).

Examiner Note: Applicant observes that No. 1 SG Flow Transmitter failed low as indicated by PPC.

CAUTION BOP SG level is auctioneered low, therefore, when selecting "MAIN" or "ALT" level transmitter, caution must be observed. Selecting "HIGH" could cause a plant trip.

11 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.: _3_

Event

Description:

Failure of No. 1 Steam Generator Steam Flow Transmitter (low)

Time I Position I Applicant's Actions or Behavior

5. !E transmitter failure has occurred, (indicated by its green LED not lit), or suspected. TURN associated transmitter control switch from "BOTH" position to position for transmitter that is not failed or suspected ("MAIN" or "ALT") (C05).

6. !E necessary, PLACE SGFP(s) speed control in "MANUAL," and ESTABLISH FRV differential pressure between 40 to 150 psid (C05).

7. DETERMINE cause of abnormal SG level and CORRECT.

8. !E deviation is due to a failed feedwater flow instrument, Refer To EN 21002, "Core Heat Balance," and PERFORM actions to deselect affected transmitter input to calorimetric program (cause false indicated BOP calorimetric).

9. IF desired, Refer To OP 2385, "Feedwater Control System Operation" and PLACE Feedwater Control System in "Automatic."

Examiner Note: The ALTERNATE Transmitter failed low but green LED is still lit. BOP should transfer No. 1 SG transmitter control switch from BOTH to MAIN and then place Feedwater Control System in Automatic using OP 2385. Step 6 was performed during immediate actions and Step 8 does not apply.

12 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _3_

Event

Description:

Failure of No. 1 Steam Generator Steam Flow Transmitter (low)

Time I Position .I Applicant's Actions or Behavior Examiner Note: The following steps are from OP 2385 Feedwater Control System Section 4.3, Operation of No. 1 FW Control System During Normal Operation 4.3.4 !E desired to place No. 1 FRV controllers in automatic control, PEFORM the following:

a. ENUSRE the following:

1). No. 1 FRV cantril is in "Master Manual" control 2). S/G Level is at deisred setpoint

b. CHECK the followoing:

1). "REG VLV, LIC-5268," controller in "AUTO" (green light lit) 2). "BYPASS LIC-5215," controller in "AUTO" (green light lit)

BOP

c. ENSURE the following:

1). "MSTR, LIC-:-5272," controller level setpoint equal to actual SG level by adjusting tumbwheel on "MSTR, LIC-5272," as necessary

2) Feed flow and steam flow are matched

d. PRESS "MSTR, LIC-5272," controller "A" button and ENSURE green light, lit.

e. IF steamflow great than 15% (900,0001bm/hr), CHECK yellow light below "M" button on "MSTR, LIC-5272," controller, lit (3 element control).

f. N/A

h. As necessary, ADJUST "MSTR-LIC-5272," controller level setpoint and MAINTAIN No. 1 SG level within desired operating band with No.1 FRV.

Examiner Note: When Feedwater Control System has been restored to automatic control, or at the lead examiner's direction, proceed to Event 4, PORV RC-404 leakage.

13 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _4_

Event

Description:

PORV RC-404 Leakage Time I Position I Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 4, PORV RC-4041eakage.

Indications:

Quench Tank level will slowly rise

PORV Discharge Temperature will rise

PRESSURIZER RELIEF VALVES DIS TEMP HI{ C-42 on C-02/3).

QUENCH TANK TEMP HI {C-36 on C-02/3)

Examiner Note: The following steps are form ARP 25908-231 for PRESSURIZER RELIEF VALVES DIS TEMP HI alarm C-42.

NOTE: Excessive PORV pilot valve leakage,(> 0.75% per hour rise in QT level) could result in spurious opening of a PORV. In this condition, a PORV should be considered inoperable and NOT capable of being manually cycled.

SRO/ATC

1. Closely MONITOR Quench Tank parameters.

2. IF alarm condition is reached on quench tank, Refer To OP 2301A, "PDT and Quench Tank Operation."

3. Refer To Technical Specifications LCOs, 3.4.3 and 3.4.6.2.

4. DETERMINE leaking PORV/safety valve as follows:

4.1 MONITOR the following:

Tl-106, "A PORV VLV DIS TEMP" (C-03)

Tl-114, "B PORV VLV DIS TEMP" (C-03) 4.2 MONITOR the following:

SRO/ATC

Tl-107, "A SAFETY VLV DIS TEMP" (C-03)

Tl-108, "B SAFETY VLV DIS TEMP" (C-03) 4.3 CHECK the following closed:

RC-402, "PORV" (C-03)

RC-404, "PORV" (C-03) 14 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _4_

Event

Description:

PORV RC-404 Leakage Time I Position I Applicant's Actions or Behavior 4.41F leaking PORV is identified, PERFORM one of the following:

4.4.1 IF leakage rate is acceptable, AND it is desired to leave the PORV un-isolated to monitor for lowering leak rate following an outage, Refer To OP---AA---101, "Operational Decision Making," and DOCUMENT the basis for continued operation within the acceptable limits of leakage.

4.4.2 IF leakage rate is not acceptable, OR it is desired to isolate the PORV, PERFORM the following:

a. VERIFY RCS pressure less than or equal to 2,250 psia (C-03).

NOTE: Re-opening the block valve after an extended closure time may cause the SRO/ATC associated PORV to briefly "pop" or "burp" as indicated by a brief loss of closed indicating light, a sharp drop and recovery of RCS pressure, and an increase in tailpipe temperature.

b. CLOSE applicable PORV block valve (C---03).

"I SOL VLV, RC-405" for "PORV, RC---404"

c. Refer To MP-13-PRA-FAP01.1, "Performing (a)(4) Risk Reviews," and PERFORM risk review.

Examiner Note: RCS pressure should be less than or equal to 2250 psia and ATC should close PORV block valve RC-405.

Examiner Note: The following steps are form ARP 25908-207 for Quench Tank Temp HI alarm. These ARP steps also direct closing the block valve and some steps may be redundant to the ARP steps for the Pressurizer Relief Valve Discharge tem_peratur high ARP above.

CORRECTIVE ACTIONS

1. CHECK temperature of PORV or pressurizer safety valve discharge lines to QT (C-03).

SRO/ATC

2. CHECK AVMS and DETERMINE if safety valve is leaking (RC05E).

3. Refer To Technical Specifications LCOs, 3.4.3 and 3.4.6.2, for applicability.

15 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.: _4_

Event

Description:

PORV RC-404 Leakage Time .I Position l Applicant's Actions or Behavior NOTE

1. If safety valve leakage is causing QT high temperature, the plant must be brought to cold shutdown for valve repair.

SRO/ATC

2. Excessive PORV pilot valve leakage, > 0. 75% level rise in an hour in the quench tank, could result in spurious opening of a PORV.

4. IF pressurizer safety valve leakage is causing high temperature, NOTIFY SM or US.

5. DETERMINE which PORV/safety valve is leaking as follows:

5.1 MONITOR the following:

"PORV DIS TEMP, Tl-106" (C-03)

"PORV DIS TEMP, Tl-114" (C-03) 5.2 MONITOR the following:

ATC * "A SAFETY VLV DIS TEMP," Tl-107 (C-03)

"B SAFETY VLV DIS TEMP," Tl-108 (C-03) 5.3 CHECK the following indicate closed:

"PORV, RC-402" (C-03)

"PORV, RC-404" (C-03)

Examiner Note: PORV Discharge Temperature Tl-114 indicates higher than Tl-106 and rising. No changes to A and B Safety Valve Discharge Temperatures. PORV RC-404 indicates open/intermediate on C-03.

6. !E leaking PORV is identified, VERIFY RCS pressure is less than or equal to 2,250 psia and CLOSE applicable PORV block valve (C-03):

ATC * "ISOL VLV, RC-405," for "PORV, RC-404" Examiner Note: RCS pressure should be less than or equal to 2250 psia and ATC should close PORV block valve RC-405.

16 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.: _4_

Event

Description:

PORV RC-404 Leakage Time I Position I Applicant's Actions or Behavior Review Technical Specifications:

LCO 3.4.3: Both power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one or both PORVs inoperable and capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s)*; otherwise, SRO be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one PORV inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Examiner Note: PORV-404 is capable of being manually cycled. SRO enters TSAS "a."

Examiner Note: When the PORV block valve is closed and the SRO has finished evaluating Technical Specifications, or at lead examiner's direction, proceed to Event 5, "8" Condensate Pump Trip.

17 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: _5_

Event

Description:

"B" Cond Pump Trip, "C" Cond Pump fails to start. Loss of SGFP suction pressure Time J Position J Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 5,"B" Condensate pump trip.

Indications:

CONDENSATE PUMP B DIS PRES LO (C-11 on C-05)

SGFP A SUCTION FLOW LO (C-1 on C-05)

SGFP B SUCTION FLOW LO (C-2 on C-05)

SGFP AlB Suction Press Lo (PPC alarms)

SGFP A TURBINE TRIP (A-4 on C-05)

SGFP B TURBINE TRIP (A-5 on C-05)

Examiner Note: The following steps are from ARP 2590B-043 for Condensate Pump "B" Discharge Pressure Low annunciator.

AUTOMATIC FUNCTIONS

1. Standby pump starts automatically at 400 psig Examiner Note: "C" Condensate Pump is in standby.

CORRECTIVE ACTIONS

1. CHECK condensate pump status lights to determine if pump has tripped.

3.1 !E pump has tripped, (amber light on), CHECK standby pump SRO/BOP running OR START standby pump as required to maintain discharge header pressure great than 460 psig.

4. IF discharge header pressure is less than 460 psig, START additional pump(s) to raise pressure.

5. !E additional condensate pumps are not available, REDUCE loads as necessary, to maintain Condensate System pressure.

Examiner Note: Applicant may use ARP for SGFP B TURBINE TRIP, RPS PRE TRIP, or SRO may direct tripping reactor without referencing the ARP.

18 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time l Position I Applicant's Actions or Behavior The following steps are from ARP 2590C-049 for RPS PRE TRIP (At 54%

Steam Generator Level).

SRO/BOP lE conditions are degrading to the point where an automatic reactor trip would be expected, prior to the actuation of automatic trip, manually TRIP reactor and Go To EOP 2525, "Standard Post Trip Actions."

CRITICAL TASK: Manually shut down the Reactor: The plant must be manually tripped prior to reaching the Automatic Auxiliary Feedwater initiation set point of 27% in either S/G.

Steam Generator Level at Reactor Trip: _ _ _ __

Time of Reactor T r i p : - - - - - -

Examiner Note: The following steps are from EOP 2525 Standard Post Trip Actions.

Determine Status of Reactivity Control

1. DETERMINE that Reactivity Control acceptance criteria are met by performing ALL of the following steps:

ATC a. CHECK that reactor power is dropping.

b. CHECK that SUR is negative.

c. CHECK that no more than one CEA is not fully inserted.

a. c.1 IF more than one CEA is not fully inserted, COMMENCE emergency boration. Refer to Appendix 3, Emergency Boration.

19 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior Determine Status of Maintenance of Vital Auxiliaries

2. DETERMINE that Maintenance of Vital Auxiliaries acceptance criteria are met by performing ALL of the following steps:

a. CHECK that the main turbine is tripped by BOTH of the following:

ALL main stop valves are closed.

Generator megawatts indicate zero.

b. !E 15G-2XI-4, motor operated disconnect, is closed, CHECK that the main Generator output breakers 8T and 9T are open.

c. CHECK that ALL Facility 1 and 2 electrical buses are energized:

6.9kV Electrical Buses 25A, 25B

4.16kV Non-Vital Electrical Buses 24A, 24B

4. 16vV Vital Electrical Buses 24C, 24D

Vital DC Buses 201A, 201B, DV-10, DV-20

Vital AC Instrument Buses VA-1 0, VA-20 Examiner Note: All buses de-energized with the exception of Vital DC and AC.

c.1 !E bus 24C or 24D is not energized PERFORM ALL of the following:

1) !E containment pressure is greater than or equal to 20 psig, PLACE the associated RBCCW pump in "PULL TO LOCK".

2) ENSURE that the associated diesel generator has started.

3) ENSURE the associated bus vital to non-vital tie breaker is open.

4) ENSURE that the associated diesel generator output breaker is closed.

5) JE the diesel generator output breaker cannot be closed, STOP the associated Diesel Generator.

20 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior

2. Status of Maintenance of Vital Auxiliaries continued:

c. CHECK that BOTH facilities of RBCCW are operating with service water cooling.

e.1 !E a service water pump is not running, PLACE the associated RBCCW pump in "PULL TO LOCK".

e.2 !E a RBCCW pump is not running AND ALL of the following conditions are met:

Associated service water pump is running .

BOP

Containment pressure is less than 20 psig .

RBCCW pump is electrically aligned .

START the associated RBCCW pump.

e.3 IF RBCCW cooling is lost to an RCP, STOP RCPs that are no longer being supplied with RBCCW.

Examiner Note: Operator should place the "A" and "B" RBCCW pumps in PULL TO LOCK. RCPs are automatically secured due to the Loss of Normal Power.

d. CHECK on facility of CRAG operating.

Determine Status of RCS Inventory Control

3. DETERMINE that RCS Inventory Control acceptance criteria are met by performing ALL of the following:

a. CHECK that BOTH of the following conditions exist:

Pressurizer level is 20 to 80%

Pressurizer level is trending to 35 to 70%

ATC a.1 IF the Pressurizer Level Control System is not operating properly in automatic, RESTORE and MAINTAIN pressurizer level 35 to 70% by performing ANY of the following:

1) OPERATE the Pressurizer Level Control System.

2) Manually OPERATE charging and letdown.

b. CHECK that RCS subcooling is greater than or equal to 30°F 21 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior Determine Status of RCS Pressure Control

4. DETERMINE RCS Pressure Control acceptance criteria are met by BOTH of ATC the following:

CHECK that pressurizer pressure is 1900 to 2350 psia.

CHECK that pressurizer pressure is trending to 2225 to 2300 psia.

Determine Status of Core Heat Removal

5. DETERMINE that Core Heat Removal acceptance criteria are met by performing ALL of the following:

a. CHECK that at least one RCP is operating.

ATC 5.1 PLACE TIC-4165, steam dump T AVG controller, in manual and closed.

Examiner Note: No RCPs are running due to the Loss of Normal Power.

b. CHECK that loop delta T is less than 1OoF

c. CHECK that Th subcooling is greater than or equal to 30°F.

Determine Status of RCS Heat Removal

6. DETERMINE that RCS Heat Removal acceptance criteria are met by ALL of the following conditions:

a. CHECK that BOTH steam generators pressure are 880 to 920 psia.

b. CHECK that RCS Tc is being maintained 530 to 535°F.

c. CHECK that at least one steam generator has BOTH of the following conditions met:

BOP

Level is 10 to 80%.

Main feedwater or TWO auxiliary feedwater pumps are operating to restore level 40 to 70%.

c.1 RESTORE level to 40 to 70% in at least one steam generator using ANY of the following:

TDAFW Pump. Refer To Appendix 6, "TDAFW Pump Normal Startup."

d. CHECK that RCS subcooling is greater than or equal to 30°F.

22 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior Determine Status of Containment Isolation

7. DETERMINE that Containment Isolation acceptance criteria are met by ALL of the following:

a. CHECK that NONE of the following primary plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Radiation Monitors Inside Containment

RM-7890, Personnel Access Area

RM-7891, Ctmt Refuel Floor Area

RM-8240, High Range

RM-8241, High Range

RM-8123 A and B, Ctmt Atmosphere

RM-8262 A and B, Ctmt Atmosphere Radiation Monitors Outside Containment ATC

RM-7894, Charging Pump Area

RM-7895, Primary Sample Sink

RM-7896, -25ft 6 in Waste Process Area

RM-7897, -45ft 6 in Waste Process Area

RM-8132A and B, Unit 2 Plant Stack

RM-8169, Millstone Stack WR

RM-8168, Unit 2 WR Stack

RM-6038, RBCCW

b. CHECK that NONE of the following steam plant radiation monitors have an unexplained alarm or indicate an unexplained rise in activity:

Steam Plant Radiation Monitors

RM-5099, Steam Jet Air Ejector

RM-4262, SG Slowdown

RM-4299A and B, Main Steam Line 1

RM-4299C, Main Steam Line 2

c. CHECK that containment pressure is less than 1.0 psig.

Determine Status of Containment Temperature and Pressure Control

8. DETERMINE that Containment Temperature and Pressure Control acceptance criteria are met by BOTH of the following steps:

ATC

a. CHECK that containment temperature is less than 120°F. (PPC or avg of Points 5 and 6)

b. CHECK that containment pressure is less than 1.0psig.

23 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior Perform Subsequent Steps (9-17) of EOP 2525 SPTAs.

ATC/BOP Examiner Note: EOP 2525 SPT A Steps 9-17 are attached to guide.

18 . .!.E no contingency actions were performed in the Immediate Actions AND ALL safety function acceptance criteria are met, PERFORM ONE of the following:

Go To EOP 2526, "Reactor Trip Recovery."

DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

Examiner Note: Step 18 is N/A.

SRO

19. IF ANY contingency action was performed in the Immediate Actions OR ANY safety function acceptance criteria are not met, PERFORM the following:

a. DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

b. Go To the appropriate EOP.

Examiner Note: The Unit Supervisor refers to EOP 2541 Appendix 1, Diagnostic Flowchart to diagnose the event.

Enters EOP 2530 Station Blackout.

SRO Examiner Note: The following steps are from EOP 2530 Station Blackout. Asterisked steps, within the ORP or selected FRPs being implemented, may be brought forward to restore or preserve a Safety Function. Asterisked steps are "Continuously Applicable," and may be performed out of order after they have been accomplished once.

1. CONFIRM diagnosis of a Station Blackout by checking that Safety Function Status Check Acceptance Criteria are satisfied.

SRO Examiner Note: SRO checks EOP 2530-001 SBO Safety Function Status Checks and confirms that all Safety Criteria are satisfied.

2. CLASSIFY the event. Refer To MP-26-EPI-FAP06, "Classification and PARs" SRO

IF classification requires RCS sampling, Refer To Appendix 46, "Sampling for EAL Determination" and DIRECT Chemistry as required.

e. PERFORM ALL of the following:

SRO

OPEN the placekeeper and ENTER the EOP entry time.

ENSURE the master alarm silence switch is in "NORMAL".

24 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior

4. ALIGN instrument air by performing ANY of the following:

a. ALIGN instrument air from Unit 3 by performing the following:

1) CHECK that Unit 3 is available to supply air.

2) ENSURE SA- 10.1, station air to instrument air cross- tie is open.

3) DIRECT a PEO to perform the following:

ENSURE SA- 26, SA- 11.1 outlet bypass is open.

OPEN SA- 12, SA- 11.1 inlet bypass.

OPEN SAS- 379, bypass valve for SAS- EFV- 20

OPEN SAS- 6, station air cross tie to Unit 3

Slowly OPEN 3- SAS- V900, service air cross- tie to Unit 2.

b.JE instrument air is not available, ENSURE backup air is aligned as necessary.

Refer To Appendix 40, "Aligning Backup Instrument Air."

Examiner Note: Unit 3 is available to supply instrument air.

CUE: For Unit 3 to provide Instrument Air to Unit 2.

5. MAINTAIN secondary plant inventory by performing ALL of the following:

a. SECURE steaming to the condenser by performing the following:

1) CLOSE BOTH MSIVs.

2) ENSURE BOTH MSIV bypass valves are closed.

3) OPEN AR- 17, condenser vacuum breaker.

4) CLOSE BOTH main steam leg low point drains:

MS- 265B

MS- 266B

b. CLOSE MS- 220A, blowdown isolation valve.

c. CLOSE MS- 220A, blowdown isolation valve.

d. CLOSE BOTH steam generator sample valves:

MS-191A

MS-191B 25 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior

6. MINIMIZE RCS leakage by performing ALL of the following:

a. ENSURE BOTH of the following letdown isolation valves are closed:

CH- 515

CH- 516

b. CLOSE CH-506, RCP controlled bleedoff isolation.

c. DIRECT chemistry to ensure at least one facility of RCS sample line isolation valves are closed:

Facility 1

RC- 45, RC combined sample isolation valve Facility 2

RC- 001, RC hot leg isolation valve

RC- 002, pressurizer surge sample isolation valve

RC- 003, pressurizer steam sample isolation valve CUE: For chemistry to sample.

7. ENSURE RCS TC is being maintained less than 535° F by ANY of the following:

Operation of the ADVs from the Control Room.

Local operation of the ADVs. Refer To Appendix 36, "ADV Local Operation."

Examiner Note: ADVs should be operated from the Control Room.

NOTE Normal lighting may be lost to the TDAFP Room. Emergency lighting is available, but portable lighting may be necessary in order to perform some portions of Appendix 7.

26 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior

8. ENSURE at least one steam generator meets ANY of the following conditions:

Steam generator level is 40 to 70%

Steam generator level is being restored by ANY of the following:

TDAFW Pump. Refer To Appendix 6, "TDAFW Pump Normal Startup."

TDAFW Pump. Refer To Appendix 7, "TDAFW Pump Abnormal Startup."

Examiner Note: Step 1 of Appendix 6, TDAFW Pump Normal Startup states:

IF a SBO event has occurred OR DC Bus 201 B is not energized, Go To Appendix 7, "TDAFW Pump Abnormal Startup."

CUE: For PEO direction of TDAFWP local startup. Add practical time to report back that TDAFWP is running and feeding both Steam Generators (This affects CT below).

CRITICAL TASK: Prior to emptying either SG, operator actions are required to establish AFW flow to SGs.

Steam Generator Level when AFW established:

Steam Generator 1 Level: - - - - -

Steam Generator 2 Level:

9. ENSURE adequate RCS heat removal by performing the following:

a. PLACE TIC-4165, steam dump TAVG controller, in "MANUAL" and closed.

b. CHECK natural circulation flow in at least one loop by ALL of the following:

Loop~ Tis less than 55°F.

Thot and Tcold are constant or dropping.

CET subcooling is greater than or equal to 30° F.

Thot and CET temperature ~Tis less than 10°F.

1 0. CHECK DC buses 201A and 201 Bare energized.

11. IF 24C or 24D is not expected to be restored within 30 minutes of event initiation, ALIGN supplemental cooling for vital equipment. Refer To Appendix 14, "Supplemental Cooling on Loss of Ventilation.

CUE: PEO acknowledges direction to perform Appendix 14 Supplemental Cooling on Loss of Ventilation steps.

27 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time l Position .I Applicant's Actions or Behavior

12. IF either vital battery charger is not expected to be restored within one hour of event initiation, REDUCE loads on the associated vital battery bus. Refer To Appendix 28, "DC Load Reduction."

Examiner Note: The SRO may or may not direct this step to be performed at this time.

13. ENSURE that all supply breakers on the deenergized 4.16 kV and 6.9 kV buses are open. Refer To Appendix 39, "Opening Supply Breakers on Deenergized Electrical Buses."

14. IF power has been lost to a vital DC electrical bus, AND resources permit, ALIGN power to electrical buses as desired. Refer To Appendix 29, "Restoring DC And Vital Instrument AC Buses."

15. ENERGIZE at least one vital 4.16 kV bus. Refer To Appendix 23, "Restoring Electrical Power."

Examiner Note: The following steps are from Appendix 23, Restoring Electrical Power, Attachment 23-N Energizing 4.16 kV Bus 24E From Unit 3.

NOTE The following may indicate a fault on 4.16 kV Bus 24E:

BOP

Annunciator "4KV BUS 24E/34B TIE BKR A505 TRIP" lit (A-9, C08)

Annunciator "4KV BUS 24C/E TIE BKR A305 TRIP" lit (B-10, C08)

Annunciator "4KV BUS 24D/E TIE BKR A408 TRIP" lit (D-10, C08)

1. CHECK that no fault indications are present for 4.16 kV Bus 24E.

2. ENSURE 4.16 kV Bus 24E "SPLY VOLTS" voltage is indicated.

BOP

3. ENSURE ALL of the following load breakers on 4.16 kV Bus 24E are open:

A502, "SERVICE WTR PUMP B"

A503, "HPSI PUMP B"

A504, "RBCCW PUMP B" 28 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.: 6 7 Event

Description:

SGFPs trip, Manual reactor trip required, Failure of 4.16KV Buses 24C and 24D to Auto Transfer on reactor trip, Diesel Generator 12U breaker mechanical failure resulting in Station Blackout Time I Position I Applicant's Actions or Behavior

4. ENSURE ALL of the following breakers are open:

A305, "24C/24E TIE BKR, 24C-2T-2" BOP

A408, "24D/24E TIE BKR, 24D-2T-2"

5. REQUEST permission from Unit Shift Manager or Unit Supervisor to energize Unit 2 4.16 kV Bus 24E from Unit 3 4.16 kV Bus 34A/34B.

NOTE Due to the "Dead Bus" state of 4.16 kV Bus 24E, the synchroscope will not BOP move.

6. PLACE "SYN SEL SW, 34B-24E-2 (A505)" to "ON" and CHECK "INCOMING" voltage indicated.

7. CLOSE A505, "24E/34B TIE BKR, 34B-24E-2".

8. CHECK voltage indicated on "RUNNING" voltmeter.

BOP

9. PLACE "SYN SEL SW, 34B-24E-2 (A505)" to "OFF".

10. Refer To Attachment 23-U, "3 MVA Electrical Limit on Bus 34A/34B," and ENSURE that 3 MVA is not exceeded as loads are restored to service.

Examiner Note: Attachment 23-U is in the back of this guide for reference.

11. At the direction of the US, REALIGN as necessary for the applicable facility and PLACE the following pumps in service:

Service Water Pump B

HPSI Pump B

RBCCW Pump B BOP

12. IF desired to restore power to 4.16 kV Bus 24C from 4.16 kV Bus 24E, Refer To Attachment 23-D, "Energizing 4.16 kV Bus 24C From 4.16 kV Bus 24E."

13. IF desired to restore power to 4.16 kV Bus 24D from 4.16 kV Bus 24E, Refer To Attachment 23-G, "Energizing 4.16 kV Bus 24D From 4.16 kV Bus 24E."

Examiner Note: The crew may decide to restore power to EITHER 24C or 240.

Follow-up question: What are priorities following restoration of power to Bus 24E?

Scenario Termination: When crew has restored power to Vital4.16kV bus 24E, or at the lead examiner's direction, the scenario is complete.

29 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.:

Event

Description:

EOP 2525 SPTA Subsequent Actions Time I Position J Applicant's Actions or Behavior Examiner Note: The following steps are from EOP 2525 Standard Post Trip Actions, Subsequent Actions.

9. IF charging pumps are taking suction from the VCT, CHECK VCT level is 72 to 86%.

10. CHECK Main Condenser is available, as indicated by ALL of the following:

At least one MSIV open

Condenser vacuum better than15 inches HG-ABS (0 to 15 inches)

At least one condensate pump operating

At least one Circ Water pump operating 10.1 IF Main Condenser is not available, PERFORM the following:

CLOSE BOTH MSIVs .

ENSURE BOTH MSIV bypass valves are closed .

OPEN AR---17, condenser vacuum breaker.

11. OPEN HD-1 06, subcooling valve.

12. ENSURE BOTH heater drain pumps are stopped.

30 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.:

Event

Description:

EOP 2525 SPTA Subsequent Actions Time I Position I Ap_pJicant's Actions or Behavior 13.1E MFW is supplying feed to the steam generators, PERFORM the following:

a. ENSURE that only ONE main feedwater pump is running.

b. ENSURE that BOTH main feed block valves are closed:

FW-42A

FW-428

c. ADJUST the running main feedwater pump pressure to 50 to 150 psi greater than SG pressure.

d. ENSURE that BOTH main feed reg bypass valves are throttled to control SG level:

FW-41A

FW-418

e. 1E Main Feedwater Pump A is secured, CLOSE the following:

1) FW-38A, main feedwater pump discharge valve

2) FW-36A, main feedwater pump mini flow recirc valve

f. 1E Main Feedwater Pump 8 is secured, CLOSE the following:

1) FW-388, main feedwater pump discharge valve

2) FW-368, main feedwater pump mini flow recirc valve Examiner Note: Main Feedwater Pump A and B are secured.

14.JE MFW is not supplying feed to the SGs, CLOSE BOTH main feedwater pump mini flow recirc valves:

FW-36A

FW-368 Examiner Note: Main Feedwater is not supply feed to the Steam Generators.

15. IF AFAS has actuated AND at least one steam generator is being restored to between 40 and 70%, PERFORM the following:

a. PLACE auxiliary feed OVERRIDE/MAN/START/RESET" handswitches in "PULL TO LOCK".

b. IF auxiliary feed is supplying steam generator makeup, manually CONTROL auxiliary feed flow rate.

Examiner Note: AFAS has actuated.

31 of 34

Op-T est No.: NRC Scenario No.: _2_ Event No.:

Event

Description:

EOP 2525 SPTA Subsequent Actions Time I Position I Applicant's Actions or Behavior

16. IF 25A or 258 is energized, ALIGN condensate pumps as follows:

a. ENSURE that ONE pump is running.

b. ENSURE that ONE pump is in "AUTO".

c. ENSURE that ONE pump is in "PULL TO LOCK".

Examiner Note: Buses 25A and 258 are de-energized.

17. CHECK instrument air pressure greater than 90 psig and stable.

18. IF no contingency actions were performed in the Immediate Actions AND ALL safety function acceptance criteria are met, PERFORM ONE of the following:

Go To EOP 2526, "Reactor Trip Recovery."

DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

19. IF ANY contingency action was performed in the Immediate Actions OR ANY safety function acceptance criteria are not met, PERFORM the following:

a. DIAGNOSE the event. Refer To Appendix 1, "Diagnostic Flowchart."

b. Go To the appropriate EOP.

32 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.:

Event

Description:

Appendix 23, Attachment 23-U: 3 MVA Electrical Limit on Buses 34N34B Time l Position J Applicant's Actions or Behavior

~Iillstoue Vnit .2 EOP 15-tl. Appt>ndLx :!,'\ Rt>v, 000-0l Restoring Electrical Power Pagt- 7-+ of 83 Attachment 13- l" 3 :\I\:\ Elect tical Limit on Bm. 3-lA 34B Pagt- l of.:!

. t::N*

-lHO ~

-lC>SO ~

~ I"KO"K-OPERA:TJ:;G ~

-10~0

.'\%{!

"'-~ .--\RE-\

.

3900 I OPER-\TI."'G I AREA

~

I I 3&-W ~

.n;n ~

3";2(1 ~

~

366D

.'600

.;JO 4~0 HO 4-li:l -150 460 ro

\'\1PS 3 MYA Electrical Limit on Bus 3-4A3-IB

!'OTE 1: R.ofer to tab!., on : fot app.h<able Sour<:<> and Lt=t SOTE 2: Obtain arnpo from Level of Use I Continuous 33 of 34

Op-Test No.: NRC Scenario No.: _2_ Event No.:

Event

Description:

Appendix 23, Attachment 23-U: 3 MVA Electrical Limit on Buses 34A/34B Time I Position I Applicant's Actions or Behavior

\ttachment 13- r 3 ~f\:\ Electrical Limit on Bus 3-lA 3-lB Page 2 of2 sorRcE LDfiT SOt'1KE LDfiT RSST 3 ~f\:--\ ~SST 3M\':\

34 of 34

ML15007A437

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4.5.3 2601D-003

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