Text

Job Performance Measure, 2011-02-Final Operating Test
	ML110660642
Person / Time
Site:	Callaway
Issue date:	02/04/2011
From:	Clyde Osterholtz; Operations Branch IV
To:	; Ameren Corp, Union Electric Co
References
	50-483/11-002
	Download: ML110660642 (252)
	v • d • e

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A1, Rev. 1 KSA NO: GEN2.1.25 COMPLETION TIME: 20 min KSA RATING: 3.9 JOB TITLE: RO REVISION: 2011 DUTY: ADMINISTRATIVE TASK TITLE: Ability to interpret reference materials, such as graphs, curves, tables, etc.:

Determine Hydrogen Recombiner Power Settings The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTN-GS-00001 Rev 15, Containment Hydrogen Control System OOA-GS-00001, Rev 1, Reference Power Settings TOOLS/EQUIPMENT: Copies of above listed reference procedures Student Handout Calculator FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A1 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was operating at 100% power when it experienced a Loss of Coolant Accident. The Control Room crew is currently in E-1, LOSS OF REACTOR OR SECONDARY COOLANT, at the step to check Containnment Hydrogen Concentration. Hydrogen Concentration is reported to be at 0.7%.

Another Operator has completed some initial steps to place the Hydrogen Recombiners in service in accordance with OTN-GS-00001, CONTAINMENT HYDROGEN CONTROL SYSTEM. Steps 5.5.1 through 5.5.10 are complete.

Initiating Cues: The Control Room Supervisor directs you to continue in OTN-GS-00001, CONTAINMENT HYDROGEN CONTROL SYSTEM, and determine the appropriate Hydrogen Recombiner power setting for Recombiner 1A and Recombiner 1B by performing Step 5.5.11.

NOTE: Do NOT use a Most conservative approach. Perform your determination as accurately as you can.

Task Standard: Upon completion of this JPM, the Operator will have determined that:

Recombiner 1A Required Power = 61.3824 to 62.2656 KW, and Recombiner 1B Required Power = 63.245 to 64.155 KW.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: A1 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OBTAIN A VERIFIED OPERATOR OBTAINED COPIES WORKING COPY OF OTN- OF OTN-GS-00001 AND OOA-GS- Comments:

GS-00001 AND OOA-GS- 00001.

00001.

S U

2. RECORD EXISTING OPERATOR RECORDS FOUR CONTAINMENT CONTAINMENT PRESSURES AS Comments:

PRESSURE (POST-LOCA) PROVIDED ON STUDENT HANDOUT.

STEP 5.5.11.a S U

3. CALCULATE OPERATOR CALCULATES CONTAINMENT ABSOLUTE CONTAINMENT ABSOLUTE Comments:

PRESSURE AS FOLLOWS: PRESSURE = (14.7 + 9.0) = 23.7 psia 14.7 + Average of GNPI934 thru GNPI0937 = ______psia STEP 5.5.11.b S U

4. USING GN-TR-63, CTMT OPERATOR RECORDS PRE-LOCA TEMP RECORDER, CONTAINMENT TEMPERATURE = Comments:

DETERMINE THE PRE- 90°F, AS PROVIDED ON STUDENT LOCA CONTAINMENT HANDOUT.

TEMPERATURE.

__________°F.

STEP 5.5.11.c

CRITICAL STEP PAGE 2 of 3

JPM NO: A1 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

5. USING ATTACHMENT 1 OPERATOR USES OTN-GS-00001 PRESSURE FACTOR (CP) ATT 1 TO DETERMINE CP = 1.4 Comments:

VS POST-LOCA BASED ON POST-LOCA CTMT CONTAINMENT PRESS AND PRE-LOCA CTMT PRESSURE, DETERMINE TEMP PROVIDED IN THE THE PRESSURE FACTOR. STUDENT HANDOUT.

CP = __________ (May accept CP = 1.39 - 1.41)

STEP 5.5.11.d S U

6. USING OOA-GS-00001, OPERATOR USES OOA-GS-00001 REFERENCE POWER TO DETERMINE: Comments:

SETTINGS, OBTAIN THE MOST RECENT RECOMBINER 1A REFERENCE REFERENCE POWER FOR POWER = 44.16 KW THE RECOMBINER BEING PLACED IN SERVICE. RECOMBINER 1B REFERENCE POWER = 45.5 KW Reference Power = ____KW STEP 5.5.11.e S U

7. MULTIPLY THE VALUES OPERATOR DETERMINES:

FROM STEPS 5.5.11.d and Comments:

5.5.11.e TO DETERMINE RECOMBINER 1A REQUIRED REQUIRED ETHR POWER. POWER = 61.824 KW CP X Reference Power = (May accept 61.3824 to 62.2656)

_____ KW RECOMBINER 1B REQUIRED POWER = 63.7 KW STEP 5.5.11.f (May accept 63.245 to 64.155)

S U

8. THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Comments:

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was operating at 100% power when it experienced a Loss of Coolant Accident. The Control Room crew is currently in E-1, LOSS OF REACTOR OR SECONDARY COOLANT, at the step to check Containnment Hydrogen Concentration. Hydrogen Concentration is reported to be at 0.7%.

Another Operator has completed some initial steps to place the Hydrogen Recombiners in service in accordance with OTN-GS-00001, CONTAINMENT HYDROGEN CONTROL SYSTEM. Steps 5.5.1 through 5.5.10 are complete.

Initiating Cues: The Control Room Supervisor directs you to continue in OTN-GS-00001, CONTAINMENT HYDROGEN CONTROL SYSTEM, and determine the appropriate Hydrogen Recombiner power setting for Recombiner 1A and Recombiner 1B by performing Step 5.5.11.

NOTE: Do NOT use a Most conservative approach. Perform your determination as accurately as you can.

Plant Parameters:

Containment Pressures

GNPI0934, CTMT ATMS PEN 99 PRESS IND = 8.5 PSIG

GNPI0935, CTMT ATMS PEN 101 PRESS IND = 9.2 PSIG

GNPI0936, CTMT ATMS PEN 103 PRESS IND = 8.8 PSIG

GNPI0937, CTMT ATMS PEN 104 PRESS IND = 9.5 PSIG Pre-LOCA Containment Temperature

GN-TR-63, CTMT TEMP RECORDER = 90°F

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A2 Rev 1 KSA NO: GEN2.1.37 COMPLETION TIME: 15 MINUTES KSA RATING: 4.3/4.6 JOB TITLE: RO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: KNOWLEDGE OF PROCEDURES, GUIDELINES, OR LIMITATIONS ASSOCIATED WITH REACTIVITY MANAGEMENT The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

PLANT CURVE BOOK TOOLS/EQUIPMENT: Copy of Curve Book FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A2 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant is operating at 100% power. Core Burnup is 250 EFPD.

Boron Concentration is 1010 PPM. Boron Concentration in both Boric Acid Tanks (BAT) is 7000 PPM.

It has been determined that the plant must be shut down to Mode 5 to replace the impeller in PEN01B, Containment Spray Pump B.

Initiating Cues: You are an extra RO on shift. The Shift Manager has assigned you the task of determining how many gallons of Boric Acid must be added to the RCS to place the plant in Mode 5.

Task Standard: Upon completion of this JPM, the Operator will have determined that 3446 +/- 344 gallons (3102-3790) of Boric Acid will be needed to place the plant in Mode 5.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: A2 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OBTAIN A VERIFIED OPERATOR OBTAINED COPY WORKING COPY OF THE OF PLANT CURVE BOOK Comments:

PLANT CURVE BOOK S U

2. DETERMINE REQUIRED OPERATOR DETERMINED BORON CONCENTRATION REQUIRED BORON Comments:

FOR MODE 5 IS 1300 PPM CONCENTRATION FOR MODE FROM CURVE BOOK 5 IS 1300 PPM FROM CURVE TABLE 1-8, SHUTDOWN BOOK TABLE 1-8, SHUTDOWN MARGIN DATA MARGIN DATA S U 3.* DETERMINE AMOUNT OF OPERATOR DETERMINED BORIC ACID REQUIRED TO 5354 +/-535 GALLONS (4819- Comments:

PLACE THE PLANT IN 5889) OF BORIC ACID IS MODE 5 REQUIRED TO PLACE THE PLANT IN MODE 5 FROM CURVE BOOK FIG 7-3:

VB=(-M/8.33)ln(7000-Cf/7000-Ci)

VB=(-578,451/8.33) X ln(7000-1300/7000-1010)

VB=3446 GALLONS +/-344 VB=3102 - 3790 GALLONS

CRITICAL STEP PAGE 2 of 3

JPM NO: A2 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

4. RECORD STOP TIME ON PAGE 1 Comments:

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant is operating at 100% power. Core Burnup is 250 EFPD.

Boron Concentration is 1010 PPM. Boron Concentration in both Boric Acid Tanks (BAT) is 7000 PPM.

It has been determined that the plant must be shut down to Mode 5 to replace the impeller in PEN01B, Containment Spray Pump B.

Initiating Cues: You are an extra RO on shift. The Shift Manager has assigned you the task of determining how many gallons of Boric Acid must be added to the RCS to place the plant in Mode 5.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A3 Rev 1 KSA NO: GEN2.2.12 COMPLETION TIME: 15 MINUTES KSA RATING: 3.7/4.1 JOB TITLE: RO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: KNOWLEDGE OF SURVEILLANCE PROCEDURES The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OSP-EN-P001B, TRAIN B CONTAINMENT SPRAY PUMP INSERVICE TEST, REVISION 35 TOOLS/EQUIPMENT: Copy of OSP-EN-P001B Copy of Attachment 4 filled in with field data.

FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A3 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The comprehensive pump test is being performed for PEN01B, Containment Spray Pump B, in accordance with OSP-EN-P001B, TRAIN B CONTAINMENT SPRAY PUMP INSERVICE TEST. Field data for the surveillance has been recorded on Attachment 4, TRAIN B CONTAINMENT SPRAY PUMP COMPREHENSIVE TEST DATA SHEET.

Group B pump testing is not being performed for this surveillance.

Initiating Cues: You are an extra RO on shift. The Shift Manager (SM) has given you Attachment 4 to complete the calculations and determine if the Acceptance Criteria has been satisfied in accordance with OSP-EN-P001B.

Give your results to the SM when complete.

Task Standard: Upon completeion of this JPM, the poperator will have completed filling in the calculations on Attachment 4 and determined that the Acceptance Criteria for EN-P001B are satisfied.

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: A3 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OBTAIN A VERIFIED OPERATOR OBTAINED WORKING COPY OF OSP- PROCEDURE COPY Comments:

EN-P001B, TRAIN B CONTAINMENT SPRAY CUE: PROVIDE PUMP INSERVICE TEST OPERATOR WITH COPY OF ATTACHMENT 4 FILLED IN WITH FIELD DATA S U 2.* CALCULATE ENFO0001 OPERATOR CALCULATES DIFFERENTIAL PRESSURE ENFO0001 DIFFERENTIAL Comments:

AND RECORD ON PRESSURE AND ATTACHMENT4 RECORDS ON ATTACHMENT 4 STEP 6.1.23.e.4 DIFFERENTIAL PRESSURE CALCULATED TO BE 197.9 PSID S U 3.* USING EQUATION ON OPERATOR CONVERTS ATTACHMENT 4, ENFE0030 DIFFERENTIAL Comments:

CONVERT ENFE0030 PRESSURE INTO GPM DIFFERENTIAL PRESSURE FLOW AND RECORDS ON INTO GPM FLOW AND ATTACHMENT 4 RECORD ON ATTACHMENT 4 ENFO0030 FLOW CALCULATED TO BE 307.2 Step 6.1.23.e.6 GPM

CRITICAL STEP PAGE 2 of 4

JPM NO: A3 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U 4.* USING EQUATION ON OPERATOR CONVERTS ATTACHMENT 4, ENFE0030 INCHES OF Comments:

CONVERT ENFE0030 WATER COLUMN INCHES OF WATER DIFFERENTIAL (H) INTO COLUMN DIFFERENTIAL GPM FLOW AND (H) INTO GPM FLOW AND RECORDS ON RECORD ON ATTACHMENT 4 ATTACHMENT 4 ENFE0030 FLOW Step 6.1.23.e.7 CALCULATED TO BE 2854.3 GPM S U 5.* CALCULATE PUMP TOTAL OPERATOR CALCULATES FLOW BY ADDING RECIRC PUMP TOTAL FLOW BY Comments:

LINE FLOW AND ADDING RECIRC LINE ENFO0001 FLOW AND FLOW AND ENFO0001 RECORD ON FLOW AND RECORDS ON ATTACHMENT 4 ATTACHMENT 4 Step 6.1.23.e.8 PUMP TOTAL FLOW CALCULATED TO BE 3161.5 GPM S U 6.* CALCULATE PUMP OPERATOR CALCULATES DIFFERENTIAL PRESSURE PUMP DIFFERENTIAL Comments:

AND RECORD ON PRESSURE AND ATTACHMENT 4 RECORDS ON ATTACHMENT 4 Step 6.1.23.e.8 PUMP DIFFERENTIAL PRESSURE CALCULATED TO BE 203.6 PSID

CRITICAL STEP PAGE 3 of 4

JPM NO: A3 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U 7.* DETERMINE IF OPERATOR DETERMINES SURVEILLANCE RESULTS THAT ACCEPTANCE Comments:

FROM ATTACHMENT 4 CRITERIA IS MET MEET ACCEPTANCE CRITERIA Step 3.1: GROUP B PUMP TESTING NOT APPLICABLE FOR THIS SURVEILLANCE (GIVEN IN INITIAL CONDITIONS)

Step 3.2: ROOM COOLER AUTOMATICALLY STARTED WHEN PUMP WAS STARTED Step 3.3: PUMP TEST DATA IS NOT WITHIN THE REQUIRED ACTION RANGE S U

8. RECORD STOP TIME ON PAGE 1 Comments:

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The comprehensive pump test is being performed for PEN01B, Containment Spray Pump B, in accordance with OSP-EN-P001B, TRAIN B CONTAINMENT SPRAY PUMP INSERVICE TEST. Field data for the surveillance has been recorded on Attachment 4, TRAIN B CONTAINMENT SPRAY PUMP COMPREHENSIVE TEST DATA SHEET.

Group B pump testing is not being performed for this surveillance.

Initiating Cues: You are an extra RO on shift. The Shift Manager (SM) has given you Attachment 4 to complete the calculations and determine if the Acceptance Criteria has been satisfied in accordance with OSP-EN-P001B.

Give your results to the SM when complete.

Attachment 4 Train B Containment Spray Pump Comprehensive Test Data Sheet Sheet 1 of 1 Person (s) Performing (print) Initial/ PIN Date Started: TODAY Date Completed: TODAY Step 6.17 PEN01B start time: TODAY Step 6.19 SGL13B, AUX BLD CSP B RM CLR, started as required? (circle one) YES / NO Required Action Actual Alert Step Parameter Normal Range Range Baseline Value Range Low High ENFO00001 Press at 6.1.23.e.2 236.1 N/A N/A N/A N/A 200 ENV0108 (psig)

ENFO00001 Press at 6.1.23.e.3 38.2 N/A N/A N/A N/A 37.5 BNV0027 (psig)

Differential Pressure 6.1.23.e.4 ______ N/A N/A N/A 162.5 across ENFO0001 (psid)

Recirc Line Inches Of Water Column 6.1.23.e.5 549.8 N/A N/A N/A N/A 550 Differential at ENFE0030 (INWC) 6.1.23.e6 ENFO0001 Flow (gpm) ______ N/A N/A N/A N/A 278.4 Recirc Line Flow at 6.1.23.e.7 ______ N/A N/A N/A N/A 2854.8 ENFE0030 (gpm) 6.1.23.e.8 Total Pump Flow (gpm) ______ 3130 to 3190 N/A N/A N/A 3133.2 Disch Press Test Gauge 6.1.23.e.9 237.2 N/A N/A N/A N/A 238 at ENV0034 (psig)

Suct Press Test Gauge at 6.1.23.e.10 33.6 N/A N/A N/A N/A 31 ENV0033 (psig)

Pump Differential 186.3 to 6.1.23.e.11 ______ 192.5 to 213.2 < 186.3 > 213.2 207 Pressure (psid) < 192.5 Flow gpm = (21.84) (Differential Press across ENFO0001 psid)

Flow gpm = (121.73) (h INWC)

Step 7.4.2 Calculated Pump Spin-up Time: N/A ( 5 sec)

M & TE Data: ID Numbers GA2013 GAP2041OP Cal Due Dates: 3-15-11 4-5-11 Comments: _____________________________________________________________________________

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A4 Rev 1 KSA NO: GEN2.3.4 COMPLETION TIME: 15 MINUTES KSA RATING: 3.2/3.7 JOB TITLE: RO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE RADIOLOGICAL REQUIREMENTS FOR HRA ENTRY The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

NONE TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A4 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: An extensive tagout containing a large number of tags is required to be hung in an area posted as a High Radiation Area (HRA).

The General Area Dose Rate in the HRA is 30 mR/hr.

The first valve on the tagout (a valve which has to be manually closed) is located in a 360 mR/hr field. It is estimated that 5 minutes will be required to close this valve based on previous performance history.

The remainder of the the items on the tagout are located in the General Area Dose Rate.

Radiation Protection (RP) has placed a Dose limit of 50 mR on this task.

Initiating Cues: You have been assigned the task to determine the MAXIMUM time that can be spent hanging the remaining tags in the General Area without exceeding the Dose limit for this task.

Task Standard: Upon completion of this JPM, the Operator will have determined that the MAXIMUM time that can be spent hanging tags in the General Area is 40 MINUTES.

START TIME:

STOP TIME:

PAGE 1 of 2

JPM NO: A4 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. DETERMINE THE TOTAL OPERATOR CALCULATES DOSE RECEIVED CLOSING TOTAL DOSE FOR CLOSING Comments:

THE VALVE AND HANGING THIS VALVE AND HANGING WPA IN THE 360 mR/hr WPA IS 30 Mr FIELD 360 mR/hr X 5 MIN = 30 mR 60 MIN/HR S U

2. DETERMINE THE OPERATOR DETERMINES AVAILABLE DOSE FOR AVAILABLE DOSE FOR Comments:

HANGING TAGS IN THE HANGING TAGS IN THE GENERAL AREA GENERAL AREA IS 20 mR 50 mR - 30 mR = 20 mR S U 3*. DETERMINE MAXIMUM OPERATOR DETERMINES TIME TO HANG MAXIMUM TIME TO HANG Comments:

REMAINDER OF TAGS REMAINDER OF TAGS IS 40 MINUTES 20 mRr / 30 mR/hr X 60 min/hr

= 40 MINUTES S U

4. THIS JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 2

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: An extensive tagout containing a large number of tags is required to be hung in an area posted as a High Radiation Area (HRA).

The General Area Dose Rate in the HRA is 30 mR/hr.

The first valve on the tagout (a valve which has to be manually closed) is located in a 360 mR/hr field. It is estimated that 5 minutes will be required to close this valve based on previous performance history.

The remainder of the the items on the tagout are located in the General Area Dose Rate.

Radiation Protection (RP) has placed a Dose limit of 50 mR on this task.

Initiating Cues: You have been assigned the task to determine the MAXIMUM time that can be spent hanging the remaining tags in the General Area without exceeding the Dose limit for this task.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A5 Rev 1 KSA NO: 2.1.25 COMPLETION TIME: 15 minutes KSA RATING: 3.9 / 4.2 JOB TITLE: SROI / SROU REVISION: 2011 DUTY: ADMINISTRATIVE TASK TITLE: Determine Time to Boil for a Loss of Shutdown Cooling The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTO-EJ-00003, Loss of RHR While Operating at Reduced Inventory or Mid-Loop Conditions, Rev. 003 OOA-BB-00003, Refuel Level Indications TOOLS/EQUIPMENT:

FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A5 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant operated for 4 days following a refueling outage. An FME concern was identified during Control Rod Testing and the Plant has been returned to Mode 6.

The Plant has now been shutdown for 5 days

The present RCS temperature is 140 degrees F

The RCS has been drained down to 62.5 inches indicated on BBL153A and BBL153B

The Plant Computer is unavailable Initiating Cues: The Shift Manager has requested you to determine the time to boil given a Loss of RHR and the following:

1. Using present plant conditions.

2. Three (3) days from now based on the following conditions:

RCS level will be reduced to 14.5 inches on BBL153A and BBL153B

RCS temperature will be lowered to 100 degrees F Task Standard: Condition 1, Time to Boil is determined to be 14 minutes (accept 13 to 15 minutes)

Condition 2, Time to Boil is determined to be 21 minutes (accept 20 to 22 minutes)

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: A5 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. Obtain a copy of drawing Provide operator with procedure OOA-BB-00003, Refuel OTO-EJ-00003. Comments:

Level Indications and a copy of OTO-EJ-00003, Loss of RHR while Operating at Reduced Inventory or Mid-Loop.

S U

2. Determine using OOA-BB- Operator determined condition 1 is 00003 that Condition 1 is Reduced Inventory due to being Comments:

REDUCED INVENTORY and less than 64 Condition 2 is MID-LOOP.

and condition 2 is Mid-Loop due to being at 14.5 S U

3. Determine using OTO-EJ- Operator determined:

00003, Step 4, that Comments:

Figure 2 is used for condition 1, Figure 2 is used for condition 1 Reduced Inventory (Hot Core)

AND Figure 1 is used for condition 2, Mid-Loop (Hot Core)

Figure 1 is used for condition 2

CRITICAL STEP PAGE 2 of 3

JPM NO: A5 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

4. Determine time to boil for Operator determines using Figure 2 condition 1 is 14 minutes time to boil for condition 1 is 13 - Comments:

15 minutes AND Figure 1 time to boil for condition 2 Condition 2 is 21 minutes. is 20 to 22 minutes S U

5. THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 Comments:

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant operated for 4 days following a refueling outage. An FME concern was identified during Control Rod Testing and the Plant has been returned to Mode 6.

The Plant has now been shutdown for 5 days

The present RCS temperature is 140 degrees F

The RCS has been drained down to 62.5 inches indicated on BBL153A and BBL153B

The Plant Computer is unavailable Initiating Cues: The Shift Manager has requested you to determine the time to boil given a Loss of RHR and the following:

1. Using present plant conditions.

2. Three (3) days from now based on the following conditions:

RCS level will be reduced to 14.5 inches on BBL153A and BBL153B

RCS temperature will be lowered to 100 degrees F

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A6 Rev 1 KSA NO: GEN2.1.5 COMPLETION TIME: 15 MINUTES KSA RATING: 3.9 JOB TITLE: SRO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE SHIFT STAFFING (FATIGUE RULE)

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

APA-ZZ-00905, Limitiations of Callaway Plant Staff Working Hours TOOLS/EQUIPMENT: Copy of Procedure, Copies of 5 workers work schedules FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A6 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant is operating at 100% power.

Due to illnesses on the crew you are required to call in an additional Senior Reactor Operator (SRO) to maintain minimum crew staffing on DAY shift.

You have been given a package of 5 potential candidates schedules to fill the th SRO position for the 29 .

Initiating Cues: Choose which Senior Reactor Operators are eligible to work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months DAY shift th on the 29 based on their NOT exceeding the limits of the Fatigue Rule or Callaway Work hour limitations.

The shift cycle for determining days off is 4 weeks, starting the 3rd of the month provided and DOES NOT REPEAT.

(No waivers or exceptions are allowed, per a recent Management directive.)

Assume all hours on sheets provided are the hours that were or will actually be worked.

Inform the Shift Manager (Examiner) of the eligible individuals.

Task Standard: The candidate chooses only two Senior Reactor Operators that meet the criteria.

G. Green and T. Davis Williams ineligible due to not having off 10 days in the 4 week period.

Johnson ineligible due exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period.

Smith ineligible due to not having off 10 days in 4 weeks, not having a 34 hr break in 9 days, and exceeding 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months worked in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: A6 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OBTAIN A VERIFIED Candidate obtained a copy of WORKING COPY OF APA- APA-ZZ-00905 and reviews the Comments:

ZZ-00905, LIMITATIONS OF working hour limitations.

CALLAWAY PLANT STAFF WORKING HOURS S U

2. REVIEW THE HOURS OF After reviewing the shift THE SIX OPERATORS schedules, the candidate Comments:

GIVEN AS POTENTIAL compared the time worked to the CANDIDATES TO TAKE time allowed under working hour THE TWELVE HOUR SHIFT limitiations.

S U 3.* CHOOSE OPERATORS Two (2) candidates are chosen THAT WILL BE to be eligible to take a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Comments:

CONTACTED TO FILL THE watch without exceeding VACANT 12 HOUR SHIFT overtime limitations.

POSITION.

G. Green and T. Davis were chosen.

S U

4. RECORD STOP TIME ON PG 1 Comments:

CRITICAL STEP PAGE 2 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant is operating at 100% power.

Due to illnesses on the crew you are required to call in an additional Senior Reactor Operator (SRO) to maintain minimum crew staffing on DAY shift.

You have been given a package of 5 potential candidates schedules to fill the SRO position for the 29th.

Initiating Cues: Choose which Senior Reactor Operators are eligible to work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months DAY shift th on the 29 based on their NOT exceeding the limits of the Fatigue Rule or Callaway Work hour limitations.

The shift cycle for determining days off is 4 weeks, starting the 3rd of the month provided and DOES NOT REPEAT.

(No waivers or exceptions are allowed, per a recent Management directive.)

Assume all hours on sheets provided are the hours that were or will actually be worked.

Inform the Shift Manager (Examiner) of the eligible individuals.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A7 Rev 1 KSA NO: GEN2.2.42 COMPLETION TIME: 15 MINUTES KSA RATING: 3.9/4.6 JOB TITLE: SRO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: ABILITY TO RECOGNIZE SYSTEM PARAMETERS THAT ARE ENTRY-LEVEL CONDITIONS FOR TECHNICAL SPECIFICATIONS The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OSP-NB-00001, CLASS 1E ELECTRICAL SOURCE VERIFICATION, REVISION 35 OTA-RK-00016, ANNUNCIATOR RESPONSE PROCEDURE MCB PANEL RK016, ADDENDUM 25C TECHNICAL SPECIFICATIONS TOOLS/EQUIPMENT: Copy of OSP-NB-00001 Completed copy of Attachment 1, Train A Status, and Attachment 2, Train B Status, from OSP-NB-00001.

FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A7 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway is at 100% Power. The Reactor Operator has just completed the weekly Surveillance for Train A and Train B electrical lineups and completed Attachments 1 and 2 from OSP-NB-00001, CLASS 1E ELECTRICAL SOURCE VERIFICATION.

Initiating Cues: You are an extra SRO on shift. The Shift Manager (SM) has given you Attachments 1 and 2 to review. Inform the SM when your review is complete and include any Actions required that need to be taken.

Write down required Actions, if any, on your cue sheet and return to the Examiner.

Task Standard: Upon completion of this JPM, the Operator will have determined that NK01 is INOPERABLE and that it must be restored to OPERABLE STATUS within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: A7 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OPERATOR PROVIDED OPERATOR REVIEWS COPIES OF ATTACHMENTS PROVIDED Comments:

ATTACHMENTS 1 AND 2 TO DETERMINE COMPLETENESS AND REQUIRED ACTIONS, IF ANY S U

2. OPERATOR REVIEWS OPERATOR REVIEWS OTA 25C FOR REQUIRED OTA 25C FOR REQUIRED Comments:

ACTIONS ACTIONS OPERATOR MAY GO DIRECTLY TO TECH SPECS TO REVIEW OPERABILITY REQUIREMENTS FOR DC BUSSES S U

3. DISPATCH AN OPERATOR OPERATOR DETERMINES TO NK01 TO DETERMINE NO LOCAL ALARM IS IN Comments:

WHICH LOCAL ALARM HAS FROM NOTE STATING IF OCCURRED COMPUTER POINT NKE0001 IS IN ALARM THERE WILL BE NO LOCAL Step 3.1 ALARMS IF ASKED THERE ARE NO LOCAL ALARMS

CRITICAL STEP PAGE 2 of 4

JPM NO: A7 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

4. REFER TO OTA-NK-00001, OPERATOR RECOGNIZES 125 VDC CLASS IE PANEL THERE ARE NO LOCAL Comments:

NK01 ALARMS-FROM STEP 3.1 Step 3.2 S U

5. IF CHARGER IS LOST, OPERATOR RECOGNIZES REFER TO OTO-NK-00001, CHARGER IS NOT LOST Comments:

FAILURE OF NK BATTERY CHARGER CHARGER VOLTAGE IS PROVIDED ON Step 3.3 COMPLETED ATTACHMENT S U

6. IF NK01 BUS VOLTAGE OPERATOR RECOGNIZES INDICATES ZERO VOLTS, BUS VOLTAGE IS NOT Comments:

REFER TO OTO-NK-00002, ZERO DUE TO NOT LOSS OF VITAL 125 VDC HAVING ANY LOCAL BUS ALARMS Step 3.4 S U

7. IF ONLY COMPUTER OPERATOR DETERMINES POINT NKE0001 IS IN BUS VOLTAGE IS LOW Comments:

ALARM, CHECK FROM INFORMATION ON INSERVICE CHARGER COMPLETED (NK21/NK25) VOLTAGE ATTACHMENT 1 Step 3.5 S U

8. REFER TO THE OPERATOR REFERS TO FOLLOWING TECHNICAL APPLICABLE TECH Comments:

SPECIFICATIONS: SPECS-TS 3.8.4 FOR T/S LCO 3.8.4 GIVEN CONDITIONS T/S LCO 3.8.5 T/S LCO 3.8.6 Step 3.6

CRITICAL STEP PAGE 3 of 4

JPM NO: A7 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U 9*. OPERATOR REVIEWS T/S OPERATOR DETERMINES LCO FOR OPERABILITY THAT DC SOURCES ARE Comments:

REQUIREMENTS FOR DC INOPERABLE AND THAT SOURCES OPERABILITY MUST BE RESTORED WITHIN 2 HOURS TWO (2) HOUR TIME LIMIT TO RESTORE OPERABILITY COULD ALSO BE DETERMINED FROM A REVIEW OF T/S LCO 3.8.4, Condition A OR LCO 3.8.9, Condition C S U

10. OPERATOR INFORMS SM THAT THE PLANT IS IN A 2 Comments:

HOUR TECH SPEC TO RESTORE BUS NK01 TO OPERABLE STATUS RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway is at 100% Power. The Reactor Operator has just completed the weekly Surveillance for Train A and Train B electrical lineups and completed Attachments 1 and 2 from OSP-NB-00001, CLASS 1E ELECTRICAL SOURCE VERIFICATION.

Initiating Cues: You are an extra SRO on shift. The Shift Manager (SM) has given you Attachments 1 and 2 to review. Inform the SM when your review is complete and include any Actions required that need to be taken.

Write down required Actions, if any, on your cue sheet and return to the Examiner.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A8 Rev 1 KSA NO: GEN2.3.4 COMPLETION TIME: 15 MINUTES KSA RATING: 3.2/3.7 JOB TITLE: SRO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE REPORTABILITY REQUIREMENTS FOR OVEREXPOSURE The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

APA-ZZ-00520, REPORTING REQUIREMENTS AND RESPONSIBILITIES REVISION 34 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A8 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in MODE 6. Refueling activities are in progress. An Operations Technician (OT) was sent inside the Incore Instrument Tunnel to hang WPA.

Due to an Incore Instrument Thimble being retracted, the OT received an overexposure of 30 REM Total Effective Dose Equivalent (TEDE).

Initiating Cues: Your are the Control Room Supervisor. You are directed to determine the following items:

1. Is this overexposure REPORTABLE

2. If YES, WHO is the primary recipient of the report

3. If YES, WHAT is the time limit for the first report due RECORD your answers on your CUE sheet and return it to the examiner when complete.

Task Standard: Upon completion of the task, the Candidate will have determined the following:

1. The overexposure IS REPORTABLE

2. The primary recipient is the NRC OPERATIONS CENTER

3. The time limit for the report is ONE HOUR START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: A8 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE OPERATOR REVIEWS WITH MATERIAL AND INITIAL CONDITIONS AND Comments:

ALLOW TIME FOR REVIEW INITIATING CUES OF WORK TO BE PERFORMED S U

2. CANDIDATE SHOULD OPERATOR REVIEWS REFER TO APA-ZZ-00520, APA-ZZ-00520 Comments:

REPORTING REQUIREMENTS AND ATTACHMENT 1, STEP RESPONSIBILITIES 3.h.1)a), AND ATTACHMENT 2, ITEM 40, CONTAIN THE REPORTING CRITERIA FOR THIS EVENT S U 3*. CANDIDATE SHOULD OPERATOR DETERMINES DETERMINE WHETHER THE OVEREXPOSURE IS Comments:

THE OVEREXPOSURE IS REPORTABLE REPORTABLE S U 4*. CANDIDATE SHOULD OPERATOR DETERMINES DETERMINE WHO IS THE THE NRC OPERATIONS Comments:

PRIMARY RECIPIENT OF CENTER IS THE PRIMARY THE REPORT RECIPIENT OF THE REPORT NRC ENS LINE (RED PHONE) IS ALSO AN ACCEPTABLE ANSWER

CRITICAL STEP PAGE 2 of 3

JPM NO: A8 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U 5*. CANDIDATE SHOULD OPERATOR DETERMINES DETERMINE THE TIME THE TIME LIMIT FOR THE Comments:

LIMIT FOR THE REPORT REPORT IS ONE HOUR S U

6. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in MODE 6. Refueling activities are in progress. An Operations Technician (OT) was sent inside the Incore Instrument Tunnel to hang WPA.

Due to an Incore Instrument Thimble being retracted, the OT received an overexposure of 30 REM Total Effective Dose Equivalent (TEDE).

Initiating Cues: Your are the Control Room Supervisor. You are directed to determine the following items:

1. Is this overexposure REPORTABLE

2. If YES, WHO is the primary recipient of the report

3. If YES, WHAT is the time limit for the first report due RECORD your answers on your CUE sheet and return it to the examiner when complete.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: A9 Rev 1 KSA NO: GEN2.4.44 COMPLETION TIME: 15 MINUTES KSA RATING: 4.1 JOB TITLE: SRO REVISION: 2010 DUTY: ADMINISTRATIVE TASK TITLE: MAKE PROTECTIVE ACTION RECOMMENDATION DURING A GENERAL EMERGENCY (TIME CRITICAL)

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

EIP-ZZ-00102, Emergency Implementing Actions EIP-ZZ-00211, Field Monitoring EIP-ZZ-00212, Protective Action Recommendations CA2843, PAR Flowchart TOOLS/EQUIPMENT: Copy of Procedures and Form CA2843 FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: A9 Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

This JPM is TIME CRITICAL from the moment you acknowledge understanding of the Initiating Conditions and Initiating Cues.

Initial Conditions: THIS IS A DRILL NOTIFICATION Callaway Plant has been shutdown following a Reactor Trip due to indications of failed fuel and a Large Beak LOCA.

A minipurge was in progress when the LOCA occurred, and the minipurge Containment Outlet Isolation Valves could not be closed. Because of this, an on-going release to the atmosphere is occurring from the Containment. Attempts to control the release have failed and it is not known when the release will be terminated.

The Control Room Communicator arrived and made the correct Emergency Announcement using Attachment 1, of EIP-ZZ-00102 (provided).

Containment radiation on GT RE-59 and GT RE-60 indicate 9.5 Rem/hr.

Core Exit Thermocouples are reading approximately 950 °F.

There are no indications of travel conditions that would present an extreme hazard during any recommended evacuation. Wind speed is 5 mph heading from 270°.

The Dose Assessment Technician has informed you there is a RELEASE ABOVE NORMAL OPERATING LIMITS with dose readings at the site boundary of 0.2 rem TEDE and 0.5 CDE Thyroid.

Initiating Cues: Make the Initial Protective Action Recommendation (PAR) based on the above conditions.

Fill out the following forms to document the PAR and submit them to the Control Room Communicator (Examiner):

1) EIP-ZZ-00102, Att. 4, Control Room Offsite Notification Form, (only items required for an accurate notification are BOLDED and RED on Form provided)

2) CA2843, PAR Flowchart Task Standard: Once the Operator states understanding of Initiating Conditions and Initiating Cues, EIP-ZZ-00102, Att 4 and CA2843 are filled out correctly in accordance with exam key provided within 15 minutes.

START TIME: STOP TIME:

PAGE 1 of 3

JPM NO: A9 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

1. OBTAIN COPIES OF EIP- Candidate obtained copies of the ZZ-00102, EMERGENCY various required procedures and Comments:

IMPLEMENTING ACTIONS, forms.

EIP-ZZ00211, FIELD MONITORING, EIP-ZZ-00212, PROTECTIVE ACTION RECOMMENDATIONS, AND FORM CA 2843, PAR FLOWCHART OPERATOR MAY USE THE EIP PROCEDURES TO ASSIST FILLING OUT THE APPLICABLE EMERGENCY FORMS S U 2*. FILL OUT EIP-ZZ-00102, Operator filled out EIP-ZZ-00102, Att 4 WITH INFORMATION Att. 4 with critical information as Comments:

GIVEN IN THE CUE AS is circled on the KEY WELL AS FROM Att 1 (provided)

S U 3.* PLACEKEEP AND FILL OUT Operator placekept on the flow FORM CA2843 chart and filled in information per Comments:

the key.

Marked an E for Evacuation in Sectors/Segments as seen on the KEY OR otherwise clearly annotated Filled in pertinent information at top of Form CA2843 as seen on KEY.

CRITICAL STEP PAGE 2 of 3

JPM NO: A9 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE S U

4. RECORD STOP TIME ON PG 1 Comments:

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

This JPM is TIME CRITICAL from the moment you acknowledge understanding of the Initiating Conditions and Initiating Cues.

Initial Conditions: THIS IS A DRILL NOTIFICATION Callaway Plant has been shutdown following a Reactor Trip due to indications of failed fuel and a Large Beak LOCA.

A minipurge was in progress when the LOCA occurred, and the minipurge Containment Outlet Isolation Valves could not be closed. Because of this, an on-going release to the atmosphere is occurring from the Containment. Attempts to control the release have failed and it is not known when the release will be terminated.

The Control Room Communicator arrived and made the correct Emergency Announcement using Attachment 1, of EIP-ZZ-00102 (provided).

Containment radiation on GT RE-59 and GT RE-60 indicate 9.5 Rem/hr.

Core Exit Thermocouples are reading approximately 950 °F.

There are no indications of travel conditions that would present an extreme hazard during any recommended evacuation. Wind speed is 5 mph heading from 270°.

The Dose Assessment Technician has informed you there is a RELEASE ABOVE NORMAL OPERATING LIMITS with dose readings at the site boundary of 0.2 rem TEDE and 0.5 CDE Thyroid.

Initiating Cues: Make the Initial Protective Action Recommendation (PAR) based on the above conditions.

Fill out the following forms to document the PAR and submit them to the Control Room Communicator (Examiner):

1) EIP-ZZ-00102, Att. 4, Control Room Offsite Notification Form, (only items required for an accurate notification are BOLDED and RED on Form provided)

2) CA2843, PAR Flowchart

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: Sim A, Rev 1 KSA NO: 001A2.14 JOB TITLE: RO/ SROI/ SROU KSA RATING: 3.7 / 3.9 DUTY: CONTROL ROD DRIVE SYSTEM TASK TITLE: PERFORM CONTROL ROD PARTIAL MOVEMENT COMPLETION TIME: 20 MINUTES The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OSP-SF-00002, CONTROL ROD PARTIAL MOVEMENT, R021 OTO-SF-00001, ROD CONTROL MALFUNCTIONS, R015 TOOLS/EQUIPMENT:

FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: Sim A, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in MODE 1, 100% STEADY STATE POWER. There are no special Physics Tests in progress, no Boron Concentration changes being made or planned, and Control Rods are in a normal configuration.

Initiating Cues: The Control Room Supervisor (CRS) has directed you to perform Control Rod Partial Movement for Control Bank D, Per OSP-SF-00002, Section 6.3, Control Banks Partially Withdrawn. Section 6.2 for Control Banks A, B and C has been completed and the CRS has the paperwork.

Notes: IC-11 or any Mode 1 IC ENSURE ALL FULLY WITHDRAWN ROD BANKS ARE AT 228 STEPS.

Insert Malfunction (SF) SF003a, Value = In, Conditional = X03I115I eq true Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL RESPOND TO A CONTINUOUS ROD MOTION EVENT AND TRIP THE REACTOR IN ACCORDANCE WITH OTO-SF-00001, ROD CONTROL MALFUNCTION START TIME:

STOP TIME:

PAGE 1 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR WORKING COPY OPERATOR WITH OBTAINED Comments:

OF OSP-SF-00002, PROCEDURE COPY PROCEDURE COPY CONTROL ROD PARTIAL MOVEMENT S U

2. REVIEW THE ALL PRECAUTIONS OPERATOR PRECAUTIONS AND AND LIMITATIONS REVIEWED THE Comments:

LIMITATIONS OF ARE SATISFIED PRECAUTIONS AND OSP-SF-00002 LIMITATIONS STEP 4.0 S U

3. REVIEW ALL PREREQUISITES OPERATOR PREREQUISITES ARE SATISFIED REVIEWS THE Comments:

OF OSP-SF-00002 PREREQUISITES IF ASKED:

Key #149 and replacement bulbs will be provided as necessary STEP 5.0

CRITICAL STEP PAGE 2 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. NOTE: OPERATOR READS NOTE Comments:

A CABINET WITHOUT ANY GROUP SELECT LIGHT ILLUMINATED MAY INDICATE A BAD LIGHT BULB OR A BLOWN MULTIPLEXER FUSE.

MOVING RODS WITHOUT THE CORRECT GROUP SELECT LIGHT ILLUMINATED COULD RESULT IN DROPPED OR MISPOSITIONED RODS.

PRIOR TO STEP 6.3 S U

5. LIST THE CONTROL OPERATOR BANKS THAT ARE UNDERSTOOD THAT Comments:

PARTIALLY ATTACHMENT 3 WITHDRAWN ON WILL BE USED AND ATTACHMENT 3. FILLS OUT THE TOP OF THE PAGE STEP 6.3.1 S U

6. PLACE SE HS-9, OPERATOR ROD BANK SWITCHED SE HS-9 Comments:

AUTO/MAN SEL, IN TO THE CBD THE CONTROL POSITION AND BANK TO BE INITIALED TESTED AND ATTACHMENT 3 INITIAL ATTACHMENT 3 STEP 6.3.2

CRITICAL STEP PAGE 3 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. AT POWER GROUP SELECT OPERATOR CABINETS, LIGHT B IS ON AT CONTACTED OT TO Comments:

ENSURE THE POWER CABINETS ENSURE GROUP PROPER LIGHTS 1BD AND 2BD SELECT LIGHT B IS ARE ON FOR THE ON AT POWER SELECTED BANK CABINETS 1BD AND AND INITIAL 2BD AND INITIALED ATTACHMENT 3 ATTACHMENT 3 STEP 6.3.3 S U

8. RECORD THE Note: AT 100% OPERATOR CONTROL BANK POWER THE STEP RECORDED Comments:

STEP COUNTER COUNTERS FOR APPROPRIATE POSITION FOR THE CONTROL BANK D CONTROL BANK D SELECTED BANK WILL INDICATE 215 STEP COUNTER ON ATTACHMENT 3 STEPS POSITION ON ATTACHMENT 3 STEP 6.3.4 S U

9. If the Selected Bank THE ROD BANK OPERATOR will be Inserted SELECTED WILL CONTINUED in Comments BELOW THE LIMITS NOT BE INSERTED PROCEDURE AT shown on Figure 2, BELOW THE ROD STEP 6.3.6 Rod Bank Insertion INSERTION LIMITS Limit vs. Rated Thermal Power- four loop operation, of the Callaway Core Operating Limits Report, PERFORM the following while monitoring Reactor Power.

STEP 6.3.5

CRITICAL STEP PAGE 4 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. While monitoring Note: At 100% power Group D Control Bank Reactor Power and Control Bank D rods Rods were withdrawn Comments:

DRPI, PERFORM the will be withdrawn to to 12 steps higher than following: 227 steps initial conditions.

WITHDRAW the selected bank at least 12 steps from initial position of Step 6.3.4 or to all rods out condition, whichever comes first STEP 6.3.6a S U

11. While monitoring Note: Ensure the The correct position Reactor Power and Operator records the for the Group D Comments:

DRPI, PERFORM the position correctly in Control Bank Step following: Attachment 3 Counter was recorded in Attachment 3 RECORD DRPI and CONTROL BANK STEP COUNTER positions for the selected bank on Attachment 3 STEP 6.3.6b

CRITICAL STEP PAGE 5 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

12 While monitoring Note: Control Bank D Operator commenced Reactor Power and will be returned to 215 rod insertion to return Comments:

DRPI, PERFORM the steps if at 100% rods to their original following: position INSERT the selected bank at least 12 steps as indicated by the step counters and digital rod position STEP 6.3.6c S U

13. Rods continue to Alternate Path Operator determined INSERT after Manual that an uncontrolled Comments:

Control is completed rod insertion occurred and performs Immediate Actions of OTO-SF-00001, Rod Control Malfunction OTO-SF-00001 S U

14. Check Both of the Operator determined Following Are Met that NO Rods have Comments For Indication of dropped, but that rods Multiple Rod Drops were still inserting THIS STEP NOT MET Go To Step 3 OTO-SF-00001 STEP 1

CRITICAL STEP PAGE 6 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

15. CHECK Main Turbine Operator determined Runback or Load that NO Main Turbine Comments:

Reject - IN Runback or Load PROGRESS Reject is Progress THIS STEP NOT MET Go To Step 5 OTO-SF-00001 STEP 3 S U

16. PLACE Rod Control Operator Selected in MANUAL MANUAL on Comments:

Handswitch SE HS-9 SE HS-9 OTO-SF-00001 STEP 5

CRITICAL STEP PAGE 7 of 8

JPM NO: Sim A, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

17. CHECK Control Acknowledge as the Reactor was Tripped Rods Motion - CRS that the Reactor by the Operator Comments:

STOPPED is Tripped THIS STEP NOT MET Other Operators will perform the steps of

Manually Trip the E-0 Reactor

Go To E-0, Reactor Trip Or Safety ________________

Injection The JPM is Complete Record Stop Time on OTO-SF-00001 Page 1 STEP 6

CRITICAL STEP PAGE 8 of 8

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in MODE 1, 100% STEADY STATE POWER. There are no special Physics Tests in progress, no Boron Concentration changes being made or planned, and Control Rods are in a normal configuration.

Initiating Cues: The Control Room Supervisor (CRS) has directed you to perform Control Rod Partial Movement for Control Bank D, Per OSP-SF-00002, Section 6.3, Control Banks Partially Withdrawn. Section 6.2 for Control Banks A, B and C has been completed and the CRS has the paperwork.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: SIM B, Rev 1 KSA NO: 006A1.13 JOB TITLE: RO / SROI / SROU KSA RATING: 3.5 / 3.7 DUTY: Inventory Control /Safety Injection Accumulators TASK TITLE: Lowering Accumulator Level COMPLETION TIME: 20 Minutes The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

Evaluators Signature: Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab X Plant Classroom Method of Performance: Simulated Performed X

References:

OTN-EP-00001, Accumulator Safety Injection System, R025 Addendum 1, SI Accumulator Level Control, R004 Tools/Equipment:

FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: Sim B, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1.

Safety Injection Accumulator A level is 84%.

The Safety Injection System and RWST are in a normal lineup IAW OTN-EM-00001 and OTN-BN-00001.

Initiating Cues: The Control Room Supervisor has directed you to lower Safety Injection Accumulator A level to 78% by draining it to the RWST, per OTN-EP-00001 Addendum 1, Section 5.7.

Notes: Use any MODE 1 IC. To raise SI Accumulator A level:

Set Parameter TEP01ATAZTCPLL To 10.9 Set Remote BNV0004TASTEM To 100 Set Remote EMV0120TASTEM To 0 Task Standard: Upon completion of this JPM, the operator will have lowered SI Accumulator A level to 78% +/- 3%.

Start Time:

Stop Time:

Page 1 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN VERIFIED PROVIDE OPERATOR WORKING COPY OF OPERATOR WITH OBTAINED COMMENTS:

OTN-EP-00001, PROCEDURE COPY PROCEDURE COPY ADDENDUM 1 S U

2. REVIEW ALL PRECAUTIONS OPERATOR PRECAUTIONS AND AND LIMITATIONS REVIEWED COMMENTS:

LIMITATIONS ARE SATISFIED PRECAUTIONS AND LIMITATIONS SECTION 3 S U

3. REVIEW ALL PREREQUISITES OPERATOR PREREQUISITES ARE SATISFIED REVIEWED COMMENTS:

PREREQUISITES SECTION 4.0

Critical Step Page 2 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. CAUTION: OPERATOR READ BECAUSE CAUTION COMMENTS:

CHANGING ACCUMULATOR LEVEL CAUSES A CORRESPONDING CHANGE IN ACCUMULATOR PRESSURE, ACCUMULATOR PRESSURE NEEDS TO BE CLOSELY MONITORED WHEN ADJUSTING LEVEL.

S U

5. ENSURE THE THE SAFETY OPERATOR SAFETY INJECTION INJECTION SYSTEM ENSURED THE COMMENTS:

SYSTEM AND AND RWST ARE IN A SAFETY INJECTION RWST ARE IN A NORMAL LINEUP IN SYSTEM AND RWST NORMAL LINEUP IN ACCORDANCE WITH ARE IN A NORMAL ACCORDANCE BOTH OF THE LINEUP WITH BOTH OF THE FOLLOWING:

FOLLOWING:

OTN-EM-00001 OTN-EM-00001 AND OTN-BN-00001 OTN-BN-00001 (GIVEN IN INITIAL STEP 5.7.1 CONDITIONS)

Critical Step Page 3 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. ENSURE RCS RCS PRESSURE IS OPERATOR PRESSURE IS 2235 PSIG ENSURED RCS COMMENTS:

SUFFICIENT TO PRESSURE IS PREVENT OPENING SUFFICIENT TO OF THE PREVENT OPENING ACCUMULATOR OF THE OUTLET CHECK ACCUMULATOR VALVES OUTLET CHECK VALVES STEP 5.7.2 S U

7. AT RL018, THE RED LIGHT IS OPERATOR PERFORM THE ILLUMINATED AND ENSURED COMMENTS:

FOLLOWING: THE GREEN LIGHT EPHV8808A ENSURE IS EXTINGUISHED EPHV8808B EPHV8808A ON: EPHV8808C EPHV8808B EPHV8808 EPHV8808C EP HIS-8808A ARE OPEN EPHV8808D EP HIS-8808B ARE OPEN EP HIS-8808C AND EP HIS-8808D STEP 5.7.3

Critical Step Page 4 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

8. AS DIRECTED BY THE RWST IS OPERATOR THE SM/CRS, AVAILABLE AND ENSURED EITHER COMMENTS:

ENSURE EITHER HAS SUFFICIENT THE RWST OR A OF THE AVAILABLE VOLUME RHUT IS AVAILABLE FOLLOWING IS TO RECEIVE THE AND HAS AVAILABLE AND WATER FROM THE SUFFICIENT HAS SUFFICIENT ACCUMULATOR AVAILABLE VOLUME AVAILABLE TO RECEIVE THE VOLUME TO WATER FROM THE RECEIVE THE ACCUMULATOR WATER FROM THE ACCUMULATOR:

THE RWST A RHUT STEP 5.7.4 S U

9. NOTE: NORMAL THE ACCUMULATOR OPERATOR READ LINEUP IS WILL BE DRAINED NOTE COMMENTS:

DRAINING TO THE TO THE RWST RWST (GIVEN IN INITIATING CUES)

Critical Step Page 5 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. CAUTION: CARE OPERATOR READ MUST BE USED CAUTION COMMENTS:

WHEN PERFORMING STEP 5.7.5.a OR 5.7.5.b TO ENSURE THAT THE CORRECT VALVES ARE PROPERLY ALIGNED.

S U

11. AS DIRECTED BY THE CRS DIRECTS OPERATOR THE SM/CRS, YOU TO ALIGN THE PROCEEDED TO COMMENTS:

ALIGN THE SIS SIS TEST LINE STEP 5.7.5.a TEST LINE DISCHARGE TO THE DISCHARGE TO RWST EITHER THE RWST OR THE RECYCLE HOLDUP TANK (GIVEN IN INITIAL CONDITIONS)

STEP 5.7.5

Critical Step Page 6 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

12. TO ALIGN TO THE OT REPORTS OPERATOR RWST, PERFORM BNV0004 IS OPEN DIRECTED OT TO COMMENTS:

THE FOLLOWING: OPEN BNV0004 OPEN BNV0004, RWST SI SYS TEST LINE ISO STEP 5.7.5.a.1 S U

13. TO ALIGN TO THE OT REPORTS OPERATOR RWST, PERFORM EMV0120 IS CLOSED DIRECTED OT TO COMMENTS:

THE FOLLOWING: CLOSE EMV0120 CLOSE EMV0120, SI THEN PROCEEDED SYS TEST LINE ISO TO TO RHT STEP 5.7.6 STEP 5.7.5.a.2

Critical Step Page 7 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

14. AT RL017, THE RED LIGHT IS OPERATOR OPENED PERFORM THE ILLUMINATED AND EMHV8964 USING COMMENTS:

FOLLOWING: THE GREEN LIGHT EM HIS-8964 IS EXTINGUISHED USING EM HIS- ON EM HIS-8964 8964, SI SYS TEST LINE OUTER CTMT ISO VLV, OPEN EMHV8964 STEP 5.7.6.a S U

15. AT RL017, THE RED LIGHT IS OPERATOR OPENED PERFORM THE ILLUMINATED AND EMHV8871 USING COMMENTS:

FOLLOWING: THE GREEN LIGHT EM HIS-8871 IS EXTINGUISHED USING EM HIS- ON EM HIS-8871 8871, SI SYS TEST LINE INNER CTMT ISO VLV, OPEN EMHV8871 STEP 5.7.6.b

Critical Step Page 8 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. AT RL018, OPEN THE RED LIGHT IS OPERATOR OPENED THE APPROPRIATE ILLUMINATED AND EPHV8877A USING COMMENTS:

ACCUMULATOR THE GREEN LIGHT EP HIS-8877A TANK TEST LINE IS EXTINGUISHED ISOLATION VALVE ON EM HIS-8877A AND MARK THE ONE OPENED:

USING EP HIS-8877A, ACC TANK A UPSTREAM TEST VLV, OPEN EPHV8877A STEP 5.7.7 S U

17. WHEN THE ACCUMULATOR A OPERATOR CLOSED DESIRED VOLUME LEVEL IS 78% EPHV8877A USING COMMENTS:

IS REACHED, AS EP HIS-8877A WHEN DETERMINED BY THE GREEN LIGHT ACCUMULATOR A THE SM/CRS, IS ILLUMINATED AND LEVEL REACHED CLOSE THE THE RED LIGHT IS 78% +/- 3%

APPROPRIATE EXTINGUISHED ON ACCUMULATOR EM HIS-8877A TANK TEST LINE ISO VALVE AT RL018 AND MARK THE ONE CLOSED STEP 5.7.8

Critical Step Page 9 of 11

JPM NO: Sim B, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

18. AT RL017, THE GREEN LIGHT OPERATOR CLOSED PERFORM THE IS ILLUMINATED AND EMHV8964 USING COMMENTS:

FOLLOWING: THE RED LIGHT IS EM HIS-8964 EXTINGUISHED ON USING EM HIS- EM HIS-8964 8964, SI SYS TEST LINE OUTER CTMT ISO VLV, CLOSE EMHV8964 STEP 5.7.9.a S U

19. AT RL017, THE GREEN LIGHT OPERATOR CLOSED PERFORM THE IS ILLUMINATED AND EMHV8871 USING COMMENTS:

FOLLOWING: THE RED LIGHT IS EM HIS-8871 EXTINGUISHED ON USING EM HIS- EM HIS-8871 8871, SI SYS TEST LINE INNER CTMT ISO VLV, CLOSE EMHV8871 THE JPM IS COMPLETE RECORD STOP TIME STEP 5.7.9.b ON PAGE 1

Critical Step Page 10 of 11

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1.

Safety Injection Accumulator A level is 84%.

The Safety Injection System and RWST are in a normal lineup IAW OTN-EM-00001 and OTN-BN-00001.

Initiating Cues: The Control Room Supervisor has directed you to lower Safety Injection Accumulator A level to 78% by draining it to the RWST, per OTN-EP-00001 Addendum 1, Section 5.7.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: SIM C, Rev 1 KSA NO: 003 A1.01 JOB TITLE: RO/SRO-I KSA RATING: 2.9/2.9 DUTY: Reactor Coolant Pumps TASK TITLE: Start B Reactor Coolant Pump; Trip on High Vibration COMPLETION TIME: 15 minutes The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTN-BB-00003 Rev 21, Reactor Coolant Pumps OTO-BB-00002 Rev 26, RCP Off-Normal OTA-RK-00022 Add. 70A, Reactor Coolant Pump Vibration Danger TOOLS/EQUIPMENT: None FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: Sim C, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 3 at 557 deg F and 2235 psig. B Reactor Coolant Pump had been secured for maintenance on #1 seal leakoff isolation valve, BBHV8141B. CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling Coils per OTN-EG-00001.

There are no personnel in Containment at this time.

Initiating Cues: Tags have been cleared on BBHV8141B and signed off.

The Control Room Supervisor has directed you to start B RCP per OTN-BB-00003, Section 5.2.

Inform the Control Room Supervisor when the B RCP has been started and the lift oil pump is secured.

Simulator Setup:

Reset to IC-9, Mode 3 Operations and STOP the B RCP, Plant stabilizes Close BB HIS-8141B and BB-HIS8351B Put System BB10 (RCPs) on Screen #1 Insert Remote Function (BG) BGV0199ASTEM set to 100 Adjust BG HC-182 to establish 8-13 gpm Seal Injection Flow to RCP B Insert malfunction (BB) CRCPV1_2, Value = 10, Ramp = 1 min, Delay = 15 sec, conditional = x21i116r eq TRUE Insert malfunction (BB) CRCPV2_2, Value = 30, Ramp = 1 min, Delay = 15 sec, conditional = x21i116r eq TRUE ENSURE VIBRATION LEVELS POSTED ON EASEL Task Standard: Upon completion of this JPM, the operator will have tripped B RCP due to high vibration.

START TIME:

STOP TIME:

PAGE 1 of 14

JPM NO: Sim C, Rev 1 RCP Vibration Data All green OK LEDs illuminated solid RCP B Shaft Vibration 30 mils RCP B Frame Vibration 10 mils RCP B Shaft Vibration Rising 5 mils/hr RCP B Frame Vibration Rising 1 mil/hr All other RCP Shaft Vibrations are 8.0 mils All other RCP Frame Vibrations are 1.0 mil PAGE 2 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR WORKING COPY OPERATOR WITH OBTAINED Comments:

OF OTN-BB-00003, PROCEDURE COPY PROCEDURE COPY REACTOR COOLANT PUMPS S U

2. REVIEW THE ALL PRECAUTIONS OPERATOR PRECAUTIONS AND AND LIMITATIONS REVIEWED THE Comments:

LIMITATIONS OF ARE SATISFIED PRECAUTIONS AND OTN-BB-00003 LIMITATIONS SECTION 3 S U

3. REVIEW THE ALL PREREQUISITES OPERATOR PREREQUISITES ARE SATISFIED REVIEWED THE Comments:

OF OTN-BB-00003 PREREQUISITES SECTION 4

CRITICAL STEP PAGE 3 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. IF ANY COLD LEG ALL COLD LEG OPERATOR TEMPERATURE IS TEMPERATURES CHECKED COLD Comments:

LESS THAN 275°F, ARE 557°F LEG ENSURE T/S LCO TEMPERATURES >

3.4.6 IS MET 275°F STEP 5.2.1 S U

5. INITIATE SEAL WHEN THE OPERATOR OPENED WATER INJECTION OPERATOR BBHV8351B Comments:

FLOW TO 'A' RCP DEPRESSES OPEN ON BB HIS-8351B, USING THE VALVE OPENS BB HIS-8351B, RCP B SEAL WTR INJ VLV, ENSURE BBHV8351B IS OPEN STEP 5.2.2.a S U

6. USING WHEN THE OPERATOR OPENED BB HIS-8141B, RCP OPERATOR BB HIS-8141B Comments:

B SEAL WTR DEPRESSES OPEN RETURN VLV, ON BB HIS-8141B, ENSURE THE VALVE OPENS BBHV8141B IS OPEN STEP 5.2.2.b

CRITICAL STEP PAGE 4 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. ENSURE DIFF PRESSURE OPERATOR DIFFERENTIAL ACROSS BGV0199 IS ENSURED Comments:

PRESSURE 200 PSID DIFFERENTIAL ACROSS BGV0199, PRESSURE ACROSS RCP B SEAL WTR BGV0199 IS INJ THROT VLV, < 1700 PSID DOES NOT EXCEED 1700 PSID STEP 5.2.2.c S U

8. ENSURE SEAL SEAL INJECTION OPERATOR INJECTION TO RCP FLOW TO RCP B IS ENSURED SEAL Comments:

B IS 8 TO 13 GPM 8 - 9 GPM ON BG FR- INJECTION FLOW TO 156 RCP B IS 8 TO 13 GPM STEP 5.2.2.d S U

9. IF REQUIRED, ALL RCPs SHOW A OPERATOR ADJUST BGV0199, FLOW OF 8 TO 9 DETERMINED THAT Comments:

RCP B SEAL WTR GPM ON THE BLUE NO ADJUSTMENT IS INJ THROT VLV, PEN FOR BG FR-157, REQUIRED USING OSP-BG- 156, 155, AND 154 00005, SETTING THROTTLE POSITION OF RCP SEAL INJECTION VALVES STEP 5.2.2.e

CRITICAL STEP PAGE 5 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. IF STARTING THE RCS TEMPERATURE OPERATOR LAST IDLE RCP, IS 557°F ENSURED RCS Comments:

ENSURE RCS TEMPERATURE IS TEMPERATURE IS GREATER THAN GREATER THAN 140°F 140°F STEP 5.2.3 S U 11.ENSURE THE ANNUNCIATORS OPERATOR FOLLOWING 42C, 71A, 73A, 74D, ENSURED Comments:

ANNUNCIATORS ARE 71C, AND 71E ARE ANNUNCIATORS CLEAR: CLEAR 42C, 71A, 73A, 74D, 71C, AND 71E ARE 42C, VCT PRESS HI/LO CLEAR 71A, RCP #1 SEAL DP LO 73A, RCP #2 SEAL FLOW HI 74D, RCP OIL RSVR LEV HI LO 71C, RCP B THRM BAR CCW FLOW 71E, RCP B STNDPIPE LEV LO STEP 5.2.4

CRITICAL STEP PAGE 6 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

12. ENSURE THE RCP MOTOR OPERATOR FOLLOWING: BEARING RTD ENSURED RCP Comments:

TEMPERATURES MOTOR BEARING RCP MOTOR ALL INDICATE LESS RTD BEARING RTD THAN 190°F TEMPERATURES TEMPERATURES ARE ALL LESS THAN ARE ALL LESS 190°F THAN 190°F STEP 5.2.5 S U

13. ENSURE THE RCP #1 SEAL DIFF OPERATOR FOLLOWING: PRESSURE ENSURED RCP #1 Comments:

GREATER THAN 200 SEAL DIFF RCP #1 SEAL DIFF PSID PRESSURE IS PRESSURE GREATER THAN 200 GREATER THAN PSID 200 PSID STEP 5.2.5 S U

14. ENSURE THE RCP #1 SEAL BACK OPERATOR FOLLOWING: PRESSURE IS ENSURED RCP #1 Comments:

GREATER THAN SEAL BACK RCP #1 SEAL BACK 15 PSIG VCT PRESSURE IS PRESSURE PRESSURE GREATER THAN GREATER THAN 15 PSIG VCT 15 PSIG VCT PRESSURE PRESSURE STEP 5.2.5

CRITICAL STEP PAGE 7 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

15. AT RL022 USING BG FR-156 USING BG FR-156 RECORDER INDICATES 3 GPM #1 THE OPERATOR Comments:

BG FR-156, SEAL LEAKOFF ENSURED RCP B #1 ENSURE RCP B #1 FLOW SEAL LEAKOFF IS SEAL LEAKOFF IS WITHIN THE WITHIN THE NORMAL NORMAL OPERATING RANGE OPERATING PER ATTACHMENT 3 RANGE PER ATTACHMENT 3 STEP 5.2.6 S U

16. IF SEAL LEAKOFF BG FR-156 USING BG FR-156 FLOW IS GREATER INDICATES 3 GPM #1 THE OPERATOR Comments:

THAN THE NORMAL SEAL LEAKOFF ENSURED RCP B #1 OPERATING FLOW SEAL LEAKOFF IS RANGES THEN WITHIN THE ENGINEERING NORMAL SHOULD OPERATING RANGE CONTACTED PER ATTACHMENT 3 BEFORE THE RCP IS STARTED STEP 5.2.7 S U

17. IF SEAL LEAKOFF LEAKOFF FLOW IS OPERATOR FLOW DOES NOT NORMAL PROCEEDED TO Comments:

EXCEED THE STEP 5.2.9 MINIMUM OPERATING FLOW PERFORM THE FOLLOWING STEPS. IF LEAKOFF FLOW IS NORMAL PROCEED TO STEP 5.2.9 STEP 5.2.8

CRITICAL STEP PAGE 8 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

18. USING BB PK-455C, RCP B SPRAY VALVE OPERATOR PZR SPRAY LOOP 2 IS CLOSED ENSURED RCP B Comments:

CTRL, CLOSE RCP SPRAY VALVE IS B SPRAY VALVE CLOSED STEP 5.2.9 S U

19. START RCP B AS NO PERSONNEL OPERATOR FOLLOWS: ARE IN DETERMINED THAT Comments:

CONTAINMENT NO PERSONNEL IF PERSONNEL ARE ARE IN IN CTMT, DISPATCH (GIVEN IN INITIAL CONTAINMENT (CTMT COORD, RP CONDITIONS)

OR EO) TO THE CTMT AND WARN PERSONNEL LOCATED NEAR RCP B IT IS ABOUT TO START STEP 5.2.10.a S U

20 USING BB HIS-42, AFTER OPERATING OPERATOR RCP B LIFT PUMP, BB HIS-42, RCP B OIL STARTED RCP B OIL Comments:

START RCP B OIL LIFT PUMP IS LIFT PUMP LIFT PUMP RUNNING STEP 5.2.10.b

CRITICAL STEP PAGE 9 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

21. ENSURE THE OIL TWO MINUTES HAVE OPERATOR LIFT PUMP RUNS ELAPSED ENSURED THE OIL Comments:

FOR AT LEAST LIFT PUMP HAS RUN TWO (2) MINUTES FOR AT LEAST TWO MINUTES PRIOR TO STARTING THE RCP STEP 5.2.10.c S U

22. IF IN SOLID PLANT THERE IS A BUBBLE OPERATOR OPERATIONS, IN THE DETERMINED THE Comments:

PLACE BG PK-131 PRESSURIZER PLANT IS NOT IN IN MANUAL AND SOLID PLANT CONTROL OPERATIONS AND PRESSURE PROCEEDS TO BETWEEN 325 - STEP 5.1.11 425 psig STEP 5.2.10.d S U

23. ANNOUNCE OPERATOR MADE STARTING PLANT Comments:

REACTOR ANNOUNCEMENT COOLANT PUMP 'B' STARTING REACTOR COOLANT PUMP B STEP 5.2.11

CRITICAL STEP PAGE 10 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

24. WAIT 10-15 AFTER OPERATING OPERATOR SECONDS, THEN BB HIS-38, THE RED STARTED RCP B Comments:

USE BB HIS-38, LIGHT IS ON AND RCP B, AND START GREEN LIGHT IS RCP B OFF STEP 5.2.13 S U

25. AFTER RCP B STARTING CURRENT OPERATOR STARTS MONITOR PEGS FOR 20 MONITORED RCP B Comments:

THE FOLLOWING SECONDS AFTER STARTING CURRENT PARAMETERS: PUMP STARTS AND THEN LOWERS TO RCP STARTING 250 AMPS CURRENT, AMMETERS PEGS RCP LOOP FLOW, FOR 15 TO 20 SLOWLY OPERATOR SECONDS INCREASES AS MONITORED RCP PUMP SPEED LOOP FLOW RCP RUNNNG INCREASES CURRENT, 351 AMPS MAX RCP LOOP FLOW, SLOWLY INCREASES AS PUMP SPEED INCREASES STEP 5.2.12

CRITICAL STEP PAGE 11 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

26. ACKNOWLEDGE ANNUNCIATORS 70A OPERATOR ANNUNCIATORS AND 70B LIGHT. DETERMINED THAT Comments:

ANNUNCIATORS 70A 70A AND 70B (RCP VIB DANGER)

AND 70B (RCP VIB/SYS ALERT) ARE LIT, AND ACKNOWLEDGES THEM. BOTH ARE UNEXPECTED.

S U

27. GO TO OPERATOR ANNUNCIATOR RETRIEVED OTA Comments:

RESPONSE FOR 70A and 70B.

PROCEDURE 70A/B S U

28. GO TO OTO-BB- OTO 70A DIRECTED 00002, RCP OFF- OPERATOR GO TO Comments:

NORMAL OTO-BB-00002, RCP OFF-NORMAL STEP 3.1 S U

29. CHECK ALL RCPs - ALL RCPs RUNNING OPERATOR RUNNING VERIFIED ALL RCPs Comments:

ARE RUNNING STEP 1

CRITICAL STEP PAGE 12 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

30. GO TO ONE OF THE OPERATOR WENT FOLLOWING TO OTO-BB-00002 Comments:

ATTACHMENTS, AS ATT. A APPLICABLE:

ATTACHMENT A, RCP HIGH VIBRATION STEP 2 S U

31. NOTE: RCP OPERATOR READS VIBRATION NOTE AND Comments:

SHOULD BE PROCEEDED TO MONITORED AT RP312, BB YI-471 RP312, BB YI-471 (BACK PANEL EASEL)

ATTACHMENT A S U

32. CHECK RCP FRAME VIBRATION = OPERATOR READ VIBRATION LEVEL: 10 MILS VIBRATIONS ON THE Comments:

FRAME AND SHAFT, ALL RCPs SHAFT VIBRATION = ACKNOWLEDGES VIBRATION ON THE 30 MILS THEY ARE GREATER FRAME - LESS THAN THE LIMIT.

THAN 5 MILS ALL RCPs VIBRATION ON THE SHAFT - LESS THAN 20 MILS STEP A1

CRITICAL STEP PAGE 13 of 14

JPM NO: Sim C, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

33. PERFORM ONE OF REACTOR POWER IS OPERATOR WENT THE FOLLOWING: LESS THAN 48% TO OTO-BB-00002 Comments:

IF REACTOR ATTACHMENT E.

POWER IS LESS THAN 48% (P-8 EXTINGUISHED),

THEN GO TO ATTACHMENT E, RCP TRIP LESS THAN 48%

STEP A1 RNO S U

34. TRIP THE AFTER OPERATING OPERATOR PLACED AFFECTED RCP BB HIS-38, THE RED RCP B CONTROL Comments:

LIGHT IS OFF AND SWITCH IN STOP GREEN LIGHT IS ON STEP E1 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 14 of 14

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 3 at 557 deg F and 2235 psig. B Reactor Coolant Pump had been secured for maintenance on #1 seal leakoff isolation valve, BBHV8141B. CCW is in operation and is supplying cooling water to the Thermal Barrier Cooling Coils per OTN-EG-00001.

There are no personnel in Containment at this time.

Initiating Cues: Tags have been cleared on BBHV8141B and signed off.

The Control Room Supervisor has directed you to start B RCP per OTN-BB-00003, Section 5.2.

Inform the Control Room Supervisor when the B RCP has been started and the lift oil pump is secured.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: Sim D - CR, Rev 1 KSA NO: 059A4.11 JOB TITLE: RO / SROI KSA RATING: 3.1 / 3.3 DUTY: MAIN FEEDWATER TASK TITLE: FWIS Bypass Operation COMPLETION TIME: 10 MINUTES The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM X SIMULATOR/LAB PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

EOP Addendum 29, FWIS BYPASS OPERATION, Rev. 02 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: Sim D - CR, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was in Mode 1 when an earthquake occurred causing a Reactor Trip and Loss of all Auxiliary Feedwater Pumps.

The crew has transitioned to FR-H.1, Response to Loss of Secondary Heat Sink, and is now Trying to Establish Main Feedwater Flow to at least One Steam Generator.

Initiating Cues: The Control Room Supervisor now directs you to BYPASS the FWIS for all of the FWIVs using EOP Addendum 29, FWIS Bypass Operation.

Task Standard: Upon completion of this JPM, the operator will have completed all steps of EOP Addendum 29 and informed the CRS. This will be Simulated at the Control Room Backpanels.

START TIME:

STOP TIME:

PAGE 1 of 6

JPM NO: Sim D - CR, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Obtain a Verified Provide operator with Operator obtained Working Copy of procedure copy. procedure copy Comments:

EOP Addendum 29, FWIS BYPASS Provide following OPERATION Cue once Cabinet is located:

Remove procedure copy from procedure holder on door for visibility. DO NOT open Cabinet Door.

S U

2. CAUTION: This Operator reviewed the procedure causes the CAUTION Comments:

FWIV(s) that are in bypass to be (should circle and INOPERABLE. slash the word CAUTION)

CAUTION prior to Step 1

CRITICAL STEP PAGE 2 of 6

JPM NO: Sim D - CR, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. NOTES: Operator reviewed the NOTES Comments:

This procedure is entered from FR-H.1, (should circle and Response To Loss Of slash the word Secondary Heat Sink, NOTES)

Step 5.d, when FWIV can NOT be opened.

To open a FWIV, the toggle switches on both MSFIS Cabinets SA075A and SA075B must be selected to FWIS BYPASS NOTE prior to Step 1

CRITICAL STEP PAGE 3 of 6

JPM NO: Sim D - CR, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. BYPASS The FWIS: All FWIV toggle switches on both Comments:

On Emergency SA075A and SA075B Override Panel at have been moved to MSFIS Cabinet the FWIS BYPASS SA075A, Place FWIV position toggle switch(es) for desired FWIV(s) to FWIS BYPASS As each toggle position: switch is Simulated to be operated - CUE o AE-FV-39 (SG A) the candidate that the toggle switch is o AE-FV-40 (SG B) moved to the down position o AE FV-41 (SG C)

(down is the FWIS o AE FV-42 (SG D) position)

On Emergency Override Panel at MSFIS Cabinet SA075B, Place FWIV toggle switch(es) for desired FWIV(s) to FWIS BYPASS position:

o AE-FV-39 (SG A) o AE-FV-40 (SG B) o AE FV-41 (SG C) o AE FV-42 (SG D)

Step 1

CRITICAL STEP PAGE 4 of 6

JPM NO: Sim D - CR, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

5. RESET the FWIV Note to examiner: Operator PRESSED FAST CLOSE Ensure the candidate Only the OP (open) Comments:

Output: is on the bottom button for each section of the panel, individual FWIV on

On A7 Test Panel at since the top section is both MSFIS Cabinets MSFIS Cabinet MSIVs and not FWIVs SA075A, PRESS OP (open) button for FWIV(s) placed in FWIS BYPASS in Step 1:

As each switch is o AE-FV-39 (SG A) Simulated to be PRESSED - CUE the o AE-FV-40 (SG B) candidate that the OP button has been o AE FV-41 (SG C) depressed for each o AE FV-42 (SG D) FWIV

On A7 Test Panel at MSFIS Cabinet SA075B, PRESS OP (open) button for FWIV(s) placed in FWIS BYPASS in Step 1:

o AE-FV-39 (SG A) o AE-FV-40 (SG B) o AE FV-41 (SG C) o AE FV-42 (SG D)

Step 2

CRITICAL STEP PAGE 5 of 6

JPM NO: Sim D - CR, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. NOTIFY SS/CRS of The CRS Operator Notified CRS FWIS Bypass Status acknowledges the of FWIS Bypass Comments:

FWIS is BYPASSED Status and completion of EOP Addendum 29 Step 3 The JPM is Complete Record Stop Time on Page 1

CRITICAL STEP PAGE 6 of 6

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was in Mode 1 when an earthquake occurred causing a Reactor Trip and Loss of all Auxiliary Feedwater Pumps.

The crew has transitioned to FR-H.1, Response to Loss of Secondary Heat Sink, and is now Trying to Establish Main Feedwater Flow to at least One Steam Generator.

Initiating Cues: The Control Room Supervisor now directs you to BYPASS the FWIS for all of the FWIVs using EOP Addendum 29, FWIS Bypass Operation.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: SIM E, Rev 1 KSA NO: 026 A4.01 JOB TITLE: RO / SROI/ SROU KSA RATING: 4.5 / 4.3 DUTY: Containment Integrity / Containment Spray TASK TITLE: Align Containment Spray for Recirculation COMPLETION TIME: 10 min The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

ES-1.3, Transfer to Cold Leg Recirculation, Rev 010 TOOLS/EQUIPMENT:

FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: Sim E Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A Large Break LOCA has occurred inside Containment. The Crew has completed the actions of ES-1.3, Transfer to Cold Leg Recirculation, through Step 5.

RWST Level has decreased to less than 12%.

Initiating Cues: You are directed to complete the actions of ES-1.3, Transfer to Cold Leg Recirculation, Step 6.

Notes: 1. Initilize using any Mode 1 - 3 IC. (IC-9 preferred)

2. Open the power supply breaker to BN HV-3, Containment Spray Insert Remote Function (NG) NG02ABF1, Value = OPEN Insert Override Light (BN) HWX17O100R, Value = TRUE Override BN HV-3 related lights on the B ESF Status Panel Override Crywolf Alarms (SA) SA066Y_A10A, Value = Fail Off Override Crywolf Alarms (SA) SA066Y_A11A, Value = Fail Off Override Crywolf Alarms (SA) SA066Y_B10A, Value = Fail Off

3. Insert a large break LOCA inside containment at a break size to initiate CSAS.

Insert Malfunction (BB) BB001_D, Value = 75,0000 Perform actions of ERGs through step 5 of ES 1.3. Freeze simulator /make temporary IC with RWST level at 12% AND Annunciator 47B, RWST Lev LoLo 2 Insert Plant Parameter (BN) TBN01TAZTLIL, Adjust the value until < 12%

Task Standard: Train A Containment Spray Pump is RUNNING in the RECIRCULATING LINEUP. Train B Containment Spray Pump is stopped and EN HIS-7 (BN HV-3),

Containment Recirc Sump to Contaiment Spray Pump is CLOSED.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: Sim E, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR WORKING COPY OPERATOR WITH OBTAINED Comments:

OF ES-1.3, PROCEDURE COPY PROCEDURE COPY TRANSFER TO COLD LEG RECIRCULATION.

S U

2. VERIFY SIMULATOR OPERATOR CONTAINMENT INDICATION VERIFIED BOTH Comments:

SPRAY PUMPS ARE CONTAINMENT RUNNING. SPRAY PUMPS ARE RUNNING.

EN HIS-3

EN-HIS-9 Step 6.a S U 3 VERIFY RWST RWST LEVEL OPERATOR LEVEL IS LESS INDICATORS CHECKED RWST Comments THAN 12%. AND/OR LEVEL IS <12%.

ANNUNCIATOR 47B, RWST LEVEL LOLO 2 is lit.

Step 6.b

CRITICAL STEP PAGE 2 of 5

JPM NO: Sim E, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. RESET CSAS SIMULATOR OPERATOR RESET INDICATION OF CSAS USING SB HS- Comments

SB HS-51 CSAS RESET. 51 AND SB HS-54.

SB HS-54 Step 6.c S U

5 OPEN SIMULATOR OPERATOR OPENED CONTAINMENT SPRAY INDICATION OF EN EN HIS-1 AND EN Comments PUMP SUCTION HIS-1 AND EN HIS-7 HIS-7.

VALVES HV-1 AND HV-7 OPEN Step 6.d S U

6. MONITOR SIMULATOR OPERATOR CONTAINMENT INDICATION OF VERIFIED Comments SPRAY PUMP CONTAINMENT CONTAINMENT DISCHARGE FLOW SPRAY PUMP SPRAY PUMP DISCHARGE FLOW. FLOWS USING FT-5 AND FT-11.

Step 6.e

CRITICAL STEP PAGE 3 of 5

JPM NO: Sim E, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. CLOSE RWST TO BN HIS-3 WILL NOT OPERATOR CLOSED CONTAINMENT CLOSE BN HIS-4 AND Comments SPRAY PUMP ELECTRICALLY. ATTEMPTED TO VALVES BN HIS-4 CLOSE BN HIS-3.

AND BN HIS-3. (Alternate Path)

Step 6.e S U

8. STOP SIMULATOR EN-HIS-9 (BN HV-3),

CONTAINMENT INDICATION OF IN STOP OR PULL- Comments SPRAY PUMP B, CONTAINMENT TO-LOCK.

EN HIS-9 (BN HV-3) SPRAY PUMP B STOPPED.

Step 6.e RNO 1)

S U

9. CLOSE RECIRC SIMULATOR EN HIS-7 (BN HV-3)

SUMP TO INDICATION OF EN- IS CLOSED AND EN Comments CONTAINMENT HIS-7 CLOSED HIS-9 (BN HV-3)

SPRAY PUMP CONTAINMENT VALVE EN-HIS-7 SPRAY PUMP B (BN HV-3) NOT RESTARTED.

Step 6.e RNO 2)

CRITICAL STEP PAGE 4 of 5

JPM NO: Sim E, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. START IF ASKED ABOUT OPERATOR CONTAINMENT STARTING PUMPS, VERIFIED Comments SPRAY PUMPS AS PROVIDE NECESSARY NECESSARY FOLLOWING CUE: CONTAINMENT SPRAY PUMPS ARE CRS DIRECTS YOU RUNNING TO MAINTAIN CURRENT PLANT CONDITIONS Step 6.f S U

11. JPM IS COMPLETE RECORD STOP TIME ON PAGE 1. Comments

CRITICAL STEP PAGE 5 of 5

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A Large Break LOCA has occurred inside Containment. The Crew has completed the actions of ES-1.3, Transfer to Cold Leg Recirculation, through Step 5.

RWST Level has decreased to less than 12%.

Initiating Cues: You are directed to complete the actions of ES-1.3, Transfer to Cold Leg Recirculation, Step 6.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim F, Rev 1 KSA No: 055 EA1.02 Job

Title:

RO / SROI KSA Rating: 4.3 / 4.4 Duty: Safety Related Elec. Gen. & Dist.

Task

Title:

Manually Start Diesel Generators Completion Time: 10 minutes The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

Evaluator Signature: Date:

Task Performer:

Location of Performance:

Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X

References:

ECA-0.0, Loss of All AC Power, Rev. 12 Tools / Equipment: None FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: Sim F, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant was in Mode 3 at Normal Operating Pressure and Temperature when an improper switching order caused a loss of both NB buses.

The crew has completed ECA-0.0, Loss of All AC Power up to and including Step 4.

Initiating Cues: The Control Room Supervisor directs you to continue in the procedure by performing all applicable sections of Step 5 of ECA-0.0.

Inform the CRS when you have completed Step 5.

SETUP:

Using any IC with rods withdrawn while keeping the Simulator in FREEZE

1) Insert Remote Function (KJ) DGBLOCK_1, Value = Defeat

2) Insert Remote Function (KJ) DGBLOCK_2, Value = Defeat

3) Insert Remote Function (EF) JLOASBI8_11, Value = Inhibit

4) Insert Remote Function (MD) N3PCB3B, Value = Open

5) Insert Remote Function (PA) LOAPA201, Value = Trip

6) GO TO RUN Task Standard: Upon completion of this JPM, the operator will have manually started the A and B DGs, re-energized NB01 and NB02, then Manually Start ESW Pump A.

Start Time: __________

Stop Time: __________

PAGE 1 of 5

JPM NO: Sim F, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Obtain a copy of Provide operator with Operator obtained ECA-0.0 procedure copy procedure copy and Comments:

went to Step 5 of the procedure S U

2. TRY To Restore Operator observed Power to Any AC that neither DG A nor Comments:

Emergency Bus DG B is running Energize AC emergency bus with diesel generator:

Check Both DGs Running - NO Step 5.a.1)

S U

3. Manually START Alternate Path Operator Started Both DG(s) DG(s) by depressing Comments:

start Pushbuttons:

KJ HS-8A KJ HS-108A Step 5.a RNO 1)

CRITICAL STEP PAGE 2 of 5

JPM NO: Sim F, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. ENERGIZE AC Operator observed emergency bus with that both NB Buses Comments:

diesel generator are energized CHECK AC emergency buses -

AT LEAST ONE ENERGIZED

NB01 - YES

NB02 - YES Step 5.a 2)

S U

5. CHECK AC Operator determined emergency buses - at Least ONE NB BUS Comments:

AT LEAST ONE is Energized ENERGIZED NB01 - YES OR NB02 - YES Step 5.b

CRITICAL STEP PAGE 3 of 5

JPM NO: Sim F, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. CHECK ESW Alternate Path Operator verified:

associated with Comments:

energized AC A ESW Pump IS emergency bus(es) - NOT running RUNNING B ESW Pump IS EF HIS-55A NOT running RUNNING EF HIS-56A RUNNING Step 5.c S U

7. PERFORM the Operator verified:

following: Comments:

ESW to UHS valve are ENSURE ESW To OPEN UHS valves are OPEN

EF HIS-37 Step 5.c RNO c.1)

S U

8. PERFORM the Operator started ESW following: Pump A using: Comments START ESW EF HIS-55A Pump(s) as necessary Step 5.c RNO c.2)

CRITICAL STEP PAGE 4 of 5

JPM NO: Sim F, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. PERFORM the Operator verified that following: both DGs are now Comments running with IF any DG is running appropriate cooling with NO cooling water water THEN STOP affected DG(s) Continued to next step Step 5.c RNO c.3)

S U 10.Return To procedure Acknowledge as the Operator Completed and step in effect and CRS that Step 5 of Step 5 of ECA-0,0 and Comments:

IMPLEMENT ECA-0.0 is complete reports to CRS actions Functional Restoration that were necessary.

Procedures as necessary The JPM is Complete Step 5.d Record Stop Time on Page 1

CRITICAL STEP PAGE 5 of 5

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant was in Mode 3 at Normal Operating Pressure and Temperature when an improper switching order caused a loss of both NB buses.

The crew has completed ECA-0.0, Loss of All AC Power up to and including Step 4.

Initiating Cues: The Control Room Supervisor directs you to continue in the procedure by performing all applicable sections of Step 5 of ECA-0.0.

Inform the CRS when you have completed Step 5.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: Sim G, Rev 2 KSA NO: 073 A4.03 JOB TITLE: RO / SROI KSA RATING: 3.1/3.2 DUTY: Instrumentation / Process Radiation Monitoring System TASK TITLE: Radiation Monitors Source Check COMPLETION TIME: 15 Mins The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OSP-SP-00001, Radiation Monitors Source Check, Rev 13 OTA-SP-RM011, Radiation Monitor Control Panel RM-11, Rev 36 OOA-SP-00002, Process Monitor Tech Spec/ FSAR Actions, Rev 17 FSAR Section 16 TOOLS/EQUIPMENT: Copy of OSP-SP-00001, Radiation Monitors Source Check FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: Sim G, Rev 2 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1 at 100% power.

Initiating Cues: Perform OSP-SP-00001, Radiation Monitors Source Check.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Inform the Candidate to disregard conditions in other areas of the Simulator and focus solely on RM-11, in the Initial Conditions stated by the JPM.

Task Standard: The operator will have successfully source checked one (1) Radiation Monitor and responded to the failure of a source check of a second.

This JPM can be run on any Mode 1 Initial Condition.

START TIME:

STOP TIME:

PAGE 1 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Review Precautions Precautions and and Limitations of Limitations reviewed Comments:

OSP-SP-00001 by the Operator Section 4.0 S U 2.Note: Source checks If asked, cue the Note was read by the are performed on operator to perform Operator Comments:

RM-11 computer the radition monitor console with a source checks in the display and printer order listed in the message. procedure Monitors may be checked in any order as long as steps specific to performing a source check are performed in order.

Note prior to Step 6.1

CRITICAL STEP PAGE 2 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. NOTE: After one Note was read by the minute the source Operator Comments:

check test will end, the CHECK SOURCE indicating lights will go off, and the status display will clear the channel CHECK SOURCE ENERGIZED.

The test is SAT unless the status display indicates channel CHECK SOURCE TEST FAILED. In addition to status display indication, failure of the test will be indicated by a printer message ALM CHECK SOURCE TEST FAILED.

Note prior to Step 6.1.1 S U 4*. SELECT BM-RE-52, BM-RE-52 (526) On RM-11 panel:

Channel 526 Steam Comments:

Generator Blowdown 526 typed Discharge Channel for display on RM-11 SELECT Pushed White box around BML526 observed Step 6.1.1.a

CRITICAL STEP PAGE 3 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 5*. PRESS the STATUS BM-RE-52 (526) Status Function Key -

key to display PRESSED Comments:

channel status Status Display displayed on RM-11 Step 6.1.1. b S U 6*. Press the CHECK BM-RE-52 (526) CHECK SOURCE key SOURCE key and pressed Comments:

check the indicating lights are ON Indicating lights lit CHECK the RM-11 CHECK SOURCE status display ENERGIZED indicated indicates channel CHECK SOURCE ENERGIZED CHECK the printer message is CHECK CHECK SOURCE SOURCE ENERGIZED printed ENERGIZED on printer Step 6.1.1 c, d, e

CRITICAL STEP PAGE 4 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 7*. Upon test sequence BM-RE-52 (526) Operator observed completion, CIRCLE that after one minute Comments:

SAT or UNSAT on the CHECK SOURCE Attachment 1 Indicating lights will go off, and the Status If UNSAT Refer to Display will clear the OTA-SP-RM-11, CHECK SOURCE Radiation monitor ENERGIZED - the Control Panel RM-11 Normal Operating Condition Box is lit SAT circled on BM-Step 6.1.1.f and g RE-52 on Att. 1 S U

8. Select Grid 1 to Operator selected display channel Grid 1 Comments:

status

CRITICAL STEP PAGE 5 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. NOTE: After one Note was read by the minute the source Operator Comments:

check test will end, the CHECK SOURCE indicating lights will go off, and the status display will clear the channel CHECK SOURCE ENERGIZED.

The test is SAT unless the status display indicates channel CHECK SOURCE TEST FAILED. In addition to status display indication, failure of the test will be indicated by a printer message ALM CHECK SOURCE TEST FAILED.

Note prior to Step 6.2.1 S U 10*. SELECT GT-RE-21B, GT-RE-21B (214) On RM-11 panel:

Channel 214 Unit Comments:

Vent Lo Range, for 214 typed display on RM-11 SELECT Pushed White box around GTG214 observed Step 6.2.1.a

CRITICAL STEP PAGE 6 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 11*. PRESS the STATUS GT-RE-21B (214) Status Function Key -

key to display PRESSED Comments:

channel status Status Display displayed on RM-11 Step 6.2.1.b S U 12*. Press the CHECK GT RE-21B (214) CHECK SOURCE key SOURCE key and pressed Comments:

check the indicating lights are ON. Indicating lights lit NOTE: The Simulator cannot CHECK the RM-11 CHECK SOURCE simulate these status display CUE - After 30 secs ENERGIZED indicated conditions.

indicates channel CHECK SOURCE Status Display Screen indicates Therefore, the ENERGIZED Channel Check examiner will need Source TEST Failed to impress upon the (DARK BLUE operator that these ALARM) are the conditions that exist, and NOT those shown on the Status Display CHECK the printer Printer Message message is CHECK CHECK SOURCE reads: ALM CHECK ENERGIZED printed SOURCE SOURCE TEST ENERGIZED on printer FAILED Step 6.2.1 c, d, e

CRITICAL STEP PAGE 7 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 13*. Upon test sequence ALTERNATE PATH Operator recognized completion, CIRCLE that the source check Comments:

SAT or UNSAT on for Channel 214 Unit Attachment 1 Vent Lo Range has failed.

If UNSAT Refer to OTA-SP-RM-11, UNSAT circled on GT-Radiation Monitor RE-21B for Channel Control Panel RM-11 214 on Att. 1 Operator will Operator determined address OTA-SP- the need to Refer to RM011, Radiation OTA-SP-RM011, Monitor Control Radiation Monitor Panel RM-11, which Control Panel RM-11 is located next to Step 6.2.1.f and g RM11 panel S U

14. Operator recognizes Operator referred to failed check source OTA-SP-RM011 and Comments:

and refers to OTA- used Attachment 31 SP-RM011 for actions to respond to the failed check source

CRITICAL STEP PAGE 8 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 15.Operator Actions- Operator recognized from Attachment 31: failed check source Comments:

REPEAT the channel Check source has and refers to OTA-SP-check source. been repeated and RM011, using fails the second time. Attachment 31 for If check source fails a actions to be taken.

second time, PERFORM the following:

ATT 31, Steps 3.a/b S U 16*. DECLARE applicable EXAMINER NOTE: Operator recognized monitor inoperable that GT-RE-21B Lo Comments:

Operator will Range, has failed its COMPLY with the address OOA-SP- Source Check and that following per OOA- 00002, Process OOA-SP-00002, SP-00002, Process Monitor Tech Process Monitor Tech Monitor Tech Spec/FSAR Actions, Spec/FSAR Actions, Spec/FSAR for the which is located next must be addressed affected monitor to RM11 panel Tech Spec FSAR 16.0 CHAPTER ATT 31, Steps 3.b.1/2

CRITICAL STEP PAGE 9 of 10

JPM NO: Sim G, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 17*. Referring to posted Note to Examiner: Operator recognized OOA-SP-00002 for JPM is complete that FSAR 16.11.2.4 Comments:

GT-RE-21 (Gas) once candidate Table 16.11-5 Item 1a, Tech Spec/ FSAR identifies applicable and 16.3.3.4, Table Actions FSAR sections. 16.3-7 item 3 needs to be addressed.

OOA-SP-00002, Page 1 This JPM is complete

CRITICAL STEP PAGE 10 of 10

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1 at 100% power.

Initiating Cues: Perform OSP-SP-00001, Radiation Monitors Source Check.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: Sim H, Rev 2 KSA NO: 029K4.03 JOB TITLE: RO Only KSA RATING: 3.2 / 3.5 DUTY: CONTAINMENT PURGE TASK TITLE: REINITIATE CTMT PURGE FOLLOWING CPIS COMPLETION TIME: 15 MINUTES The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTN-GT-00001, CONTAINMENT PURGE SYSTEM, REV 26 TOOLS/EQUIPMENT: Copy of OTN-GT-00001 with Section 5.1 completed.

FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: Sim H, Rev 2 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 3. A containment mini-purge was in progress to reduce noble gas concentrations prior to a containment entry.

Thirty minutes ago, a CPIS occurred due to an instrument spike on GT RE-22, CTMT PURGE EXH GAS DETECTOR.

The cause of the spike on GT RE-22 has been determined and corrected.

Control Building HVAC has been realigned.

Initiating Cues: You have been directed to REINTIATE containment mini-purge per OTN-GT-00001, Section 5.6.

Inform the Control Room Supervisor when the containment mini-purge supply dampers are open and supply fan is running.

Notes: Use any Mode 3 IC Manually initiate a CPIS (Both Trains)

Ensure procedure copy is marked up with completed steps Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL HAVE REINITIATED CONTAINMENT MINI-PURGE EHAUST FLOW PATH.

START TIME:

STOP TIME:

PAGE 1 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR WORKING COPY OF OPERATOR WITH OBTAINED Comments:

OTN-GT-00001 PROCEDURE COPY PROCEDURE COPY S U

2. REVIEW ALL PRECAUTIONS OPERATOR PRECAUTIONS AND AND LIMITATIONS REVIEWED Comments:

LIMITATIONS ARE SATISFIED PRECAUTIONS AND LIMITATIONS SECTION 3 S U

3. REVIEW OUTSIDE OPERATOR PREREQUISITES TEMPERATURE IS REVIEWED Comments:

EXPECTED TO PREREQUISITES REMAIN GREATER THAN 50°F CHECKLIST 1, 2 AND 3 ARE COMPLETE SECTION 4 PAGE 2 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. AS A NORMAL SM AUTHORIZES OPERATOR READ OPERATIONAL RELEASE TO BE AND UNDERSTOOD Comments:

PRACTICE, A RECOMMENCED CAUTION CONTAINMENT USING THE CONCERNING PURGE SHOULD PREVIOUS RELEASE STOPPING AND NOT BE STOPPED PERMIT STARTING RELEASE AND RESTARTED PERMIT W/O TERMINATING THE GASEOUS RW RELEASE PERMIT.

HOWEVER, UNDER SPECIAL CONDITIONS AND AT SM DISCRETION, A CONTAINMENT PURGE MAY BE STOPPED AND RESTARTED W/O TERMINATING THE PERMIT.

CAUTION BEFORE SECTION 5.6 S U

5. ENSURE TIME 30 MINUTES HAVE OPERATOR SHOULD BETWEEN ELAPSED SINCE THE ENSURE LESS THAN Comments:

STOPPING AND PURGE WAS TWO HOURS SINCE RESTARTING STOPPED (GIVEN IN PURGE WAS PURGE WILL NOT INITIAL STOPPED EXCEED TWO CONDITIONS)

HOURS STEP 5.6.1 PAGE 3 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. REQUEST THE COUNT ROOM OPERATOR RAD/CHEM TECHNICIAN HAS CONTACTED COUNT Comments:

TECHNICIAN ENSURED ROOM TECHNICIAN (COUNT ROOM) SETPOINTS TO ENSURE ENSURE CORRECT PER THE SETPOINTS ARE ALARM/TRIP RELEASE PERMIT CORRECT SETPOINTS FOR THE FOLLOWING ARE CORRECT PER GASEOUS RADWASTE RELEASE PERMIT:

GTRE0021B GTRE0022 GTRE0033 STEP 5.6.2 S U

7. IF READINGS ON NO READINGS ON OPERATOR ANY OF THE ANY OF THE ENSURED NO Comments:

MONITORS IN STEP MONITORS IN STEP READINGS ON ANY 5.6.2 ARE GREATER 5.6.2 ARE GREATER OF THE MONITORS THAN HI-HI ALARM THAN HI-HI ALARM IN STEP 5.6.2 ARE SETPOINT, SETPOINT GREATER THAN HI-REQUEST HI ALARM SETPOINT RAD/CHEM TECHNICIAN (COUNT ROOM)

PERFORM THE FOLLOWING:

CLOSE THE PERMIT RESAMPLE CTMT GENERATE A NEW PERMIT STEP 5.6.3 PAGE 4 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

8. IF ANY BISTABLE BISTABLE TRIP OPERATOR TRIP LIGHTS ARE LIGHTS ARE AS ENSURED ALL Comments:

LIT ON SA036D OR INDICATED ON BISTABLE TRIP SA036E, PERFORM SA036D AND SA036E LIGHTS RESET ON THE FOLLOWING: SA036D AND SA036E RECORD WHICH TRIP LIGHTS LIT IN RO DAILY LOG DEPRESS AFFECTED TRIP LIGHTS TO RESET STEP 5.6.4 S U

9. IF CONTROL ROOM CONTAINMENT OPERATOR VENT ISOLATION PURGE ISOLATION PRESSED RESET ON Comments:

OR CONTAINMENT IS ACTUATED ON SA HS-11 PURGE ISOLATION SA066X ARE ACTUATED ON SA066X, OBTAIN CRS GRANTS SM/CRS PERMISSION TO PERMISSION AND RESET CPIS ON PRESS SA066X APPLICABLE RESET:

SA HS-9, CRVIS A SA HS-11, CPIS A STEP 5.6.5 PAGE 5 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. IF CONTROL ROOM CONTAINMENT OPERATOR VENT ISOLATION PURGE ISOLATION PRESSED RESET ON Comments:

OR CONTAINMENT IS ACTUATED ON SA HS-15 PURGE ISOLATION SA066Y ARE ACTUATED ON SA066Y, OBTAIN SM/CRS CRS GRANTS PERMISSION AND PERMISSION TO PRESS RESET CPIS ON APPLICABLE SA066Y RESET:

SA HS-13, CRVIS B SA HS-15, CPIS B STEP 5.6.6 S U

11. IF CPIS OR CRVIS CPIS LIGHTS ARE OPERATOR RESET LIGHTS ARE LIT ON LIT ON ESFAS ESFAS STATUS Comments:

ESFAS STATUS STATUS PANELS PANEL LIGHTS PANELS, RESET USING SA HS-23 USING THE AND SA HS-24 FOLLOWING:

SA HS-23, SA066X SA HS-24, SA066Y STEP 5.6.7 PAGE 6 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

12. ENSURE THE ANNUNCIATORS 59D OPERATOR FOLLOWING AND 63A, ARE ENSURED Comments:

ANNUNCIATORS CLEAR ANNUNCIATORS 59D ARE CLEAR: AND 63A ARE CLEAR 59D, CPIS 63A, CRVIS STEP 5.6.8 S U

13. REALIGN CONTROL THE CONTROL THE OPERATOR BUILDING HVAC, AS BUILDING HVAC CONTINUED Comments:

REQUIRED, PER SYSTEM HAS BEEN PROCEDURE WITH OTN-GK-00001, REALIGNED STEP 5.6.10 CONTROL BUILDING HVAC (GIVEN IN INITIAL SYSTEM CONDITIONS)

STEP 5.6.9 S U

14. REINITIATE OPERATOR ACTIVITY, AS CONTINUED Comments:

APPLICABLE: PROCEDURE WITH SECTION 5.2 MINI-PURGE PER SECTION 5.2 STEP 5.6.10 PAGE 7 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

15. ENSURE SECTION SECTION 5.1 OF OPERATOR 5.1 HAS BEED THIS PROCEDURE ENSURED SECTION Comments:

PERFORMED HAS BEEN 5.1 HAS BEEN PERFORMED AND PERFORMED DOES NOT NEED TO BE RE-PERFORMED (COPY PROVIDED STEP 5.2.1 SHOULD HAVE SECTION 5.1 COMPLETED)

S U

16. ENSURE SHUTDOWN PURGE OPERATOR SHUTDOWN SYSTEM IS NOT IN ENSURED Comments:

PURGE SYSTEM IS SERVICE SHUTDOWN PURGE NOT IN SERVICE SYSTEM IS NOT IN SERVICE STEP 5.2.2 S U

17. MONITOR THE SDRE0041 (R0041H) OPERATOR FOLLOWING SDRE0042 (R0042H) MONITORED: Comments:

INSTRUMENTATION GT PDI-40 (GTD0040)

SDRE0041 (R0041H)

SDRE0041 (R0041H) ARE ALL STABLE. SDRE0042 (R0042H)

SDRE0042 (R0042H) GT PDI-40 (GTD0040)

GT PDI-40 (GTD0040)

STEP 5.2.3 PAGE 8 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

18. RECORD INFORM THE OPERATOR CONTAINMENT OPERATOR: RECORDED Comments:

PRESSURE, AS CONTAINMENT READ ON CONTAINMENT PRESSURE ON GTPDI0040 OR PRESSURE HAS GASEOUS GTD0040, ON BEEN RECORDED RADWASTE GASEOUS RELEASE PERMIT RADWASTE RELEASE PERMIT.

STEP 5.2.4 S U

19. IF IN MODES 1-4, GTRT2 AND GTRT33 OPERATOR GOES OR PREPARING TO ARE IN OPERATE TO BACK PANELS Comments:

ENTER MODE 4 WITH AND FINDS ESFAS FROM MODE 5, CONTAINMENT PANELS SA036D and ENSURE THE PURGE IN SA036E AND FOLLOWING ARE IN PROGRESS DO NOT ENSURED:

OPERATE WITH BYPASS COVERS CONTAINMENT IN PLACE OVER THE GTRT22 AND PURGE IN SWITCHES GTRT33 ARE IN PROGRESS DO OPERATE WITH NOT BYPASS COVERS OVER THE COVERS IN PLACE SWITCHES OVER THE SWITCHES:

GTRT22 GTRT33 STEP 5.2.5 PAGE 9 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

20. IF IN MODES THE PLANT IS IN OPERATOR GOES 5 OR 6 AND NOT MODE 3 TO STEP 5.2.7 Comments:

PREPARING FOR ENTRY INTO MODE 4, ENSURE THE FOLLOWING ARE IN BYPASS:

GTRT22 GTRT33 STEP 5.2.6 S U

21. USING GT HIS-20, CTMT MINI-PURGE OPERATOR CTMT MINI PURGE EXH FAN INDICATES STARTED CGT02 Comments:

EXH FAN & RUN AND DAMPER DAMPER, INDICATES OPEN START CGT02 STEP 5.2.7 S U

22. USING GT HIS-11, GT HIS-11 OPERATOR OPENED CTMT MINI PURGE INDICATES OPEN GTHZ0011 Comments:

EXH INNER CTMT ISO, OPEN GTHZ0011 STEP 5.2.8 PAGE 10 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

23. USING GT HIS-12, GT HIS-12 OPERATOR OPENED CTMT MINI PURGE INDICATES OPEN GTHZ0012 Comments:

EXH OUTER CTMT ISO, OPEN GTHZ0012 STEP 5.2.9 S U

24. USING GT HIS-28, GT HIS-28 OPERATOR OPENED CTMT PURGE EXH INDICATES OPEN GTHZ0028 Comments:

DAMPER, OPEN GTHZ0028 STEP 5.2.10 S U

25. USING GT HIS-29, GT HIS-29 OPERATOR OPENED CTMT PURGE EXH INDICATES OPEN GTHZ0029 Comments:

DAMPER, OPEN GTHZ0029 STEP 5.2.11 PAGE 11 of 12

JPM NO: Sim H, Rev 2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

26. RECORD DATE AND DATE AND TIME OPERATOR TIME DAMPERS HAVE BEEN RECORDED DATE Comments:

WERE OPENED ON RECORDED AND TIME DAMPERS GASEOUS WERE OPENED ON RADWASTE GASEOUS RELEASE PERMIT RADWASTE RELEASE PERMIT STEP 5.2.12 S U

27. ANOTHER OPERATOR WILL Comments:

COMPLETE THE REMAINING STEPS TO COMPLETE THE MINI-PURGE REINITIATION JPM COMPLETE RECORD STOP TIME ON PAGE 1.

PAGE 12 of 12

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 3. A containment mini-purge was in progress to reduce noble gas concentrations prior to a containment entry.

Thirty minutes ago, a CPIS occurred due to an instrument spike on GT RE-22, CTMT PURGE EXH GAS DETECTOR.

The cause of the spike on GT RE-22 has been determined and corrected.

Control Building HVAC has been realigned.

Initiating Cues: You have been directed to REINTIATE containment mini-purge per OTN-GT-00001, Section 5.6.

Inform the Control Room Supervisor when the containment mini-purge supply dampers are open and supply fan is running.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: In-Plant I, Rev. 1 KSA No: 061K4.07 Job

Title:

RO/ SROI KSA Rating: 3.1 / 3.3 Duty: Auxiliary Feedwater System (AL)

Task

Title:

Reset TDAFP Mechanical Overspeed Trip Completion Time: 15 minutes The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

Evaluator Signature: Date:

Task Performer:

Location of Performance:

Control Room Simulator / Lab Plant X Classroom Method of Performance: Simulated X Performed

References:

OTN-AL-00001, Addendum 01, Turbine Driven Auxiliary Feedwater Pump Trip/Throttle Valve Trip Check and Reset, R002 Tools / Equipment: Personal Protective (Safety) Equipment FACILITY REPRESENTATIVE: // // DATE:

CHIEF EXAMINER: // // DATE:

JPM NO: In Plant I, Rev. 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1.

Operations is performing the mechanical trip verification portion of OSP-AL-P0002, Turbine Driven Aux Feedwater Pump Inservice Test - Group B.

Initiating Cues: The Control Room Supervisor directs you to reset the mechanical overspeed trip per OTN-AL-00001, Addendum 01, Turbine Driven Auxiliary Feedwater Pump Trip/Throttle Valve Trip Check and Reset.

Notes: All operator actions are to be simulated in the plant.

Task Standard: Upon completion of this JPM, the operator will have:

1) identified the location of the Turbine Driven Auxiliary Feedwater Pump (TDAFP) Trip Throttle Valve and

2) demonstrated the ability to reset the TDAFP mechanical overspeed trip using the Trip Throttle Valve mockup NOTE TO EXAMINER: The candidate will be required to show the examiner:

1) where the Trip/Throttle valve is located in the plant and

2) how to RESET the Trip/Throttle valve on the Mockup provided.

Start Time:

Stop Time:

1

JPM NO: In-Plant I, Rev. 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Go to the Turbine Show me where the Operator went to the Driven Aux Feed Turbine Driven Turbine Driven Comments:

Pump Room and Auxiliary Feedwater Auxiliary Feedwater identify location of Pump Trip/Throttle Pump Room and FCHV0312 Valve is located identified the Trip/Throttle Valve location to the examiner (IN PLANT) Once shown, inform the Operator the JPM will be continued at the Trip Throttle Valve Mockup S U

2. Obtain a verified Provide operator Operator obtained working copy of with procedure copy procedure copy Comments:

OTN-AL-00001, Addendum 01 (AT MOCKUP)

S U

3. Review the Operator reviewed the Purpose and Scope Purpose and Scope Comments:

(AT MOCKUP)

Sections 1.0 and 2.0 2

JPM NO: In-Plant I, Rev. 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. Two operators are A second operator is Operator read note required to reset the standing by to assist and understood Comments:

mechanical you another Operator is overspeed trip, one standing by to assist operator standing Plant South of the turbine and one operator standing next to FCHV0312.

See Figure 3.

(AT MOCKUP)

Note prior to Step 3.2.1 S U

5. MOVE linkage The linkage has been Operator towards FCHV0312, moved towards demonstrated the Comments:

AFP TURB MECH FCHV0312 and the ability to move linkage TRIP/THROT HV, and Tappet Nut has been towards FCHV0312 PUSH down on pushed down to verify and push down on Tappet Nut to verify it it is completely seated Tappet Nut to verify it is completely seated is completely seated (AT MOCKUP)

Step 3.2.1.a/b

Critical Step 3

JPM NO: In-Plant I, Rev. 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. Slowly RELEASE FCHV0312 linkage Operator FCHV0312 linkage has been released and demonstrated the Comments:

so Head Lever rests Head Lever is resting ability to slowly release against the flat side against the flat side of FCHV0312 linkage so of Tappet Nut Tappet Nut Head Lever rests against the flat side of Tappet Nut (AT MOCKUP)

Step 3.2.1.c S U

7. ENSURE vertical There is vertical face- Operator face-to-face contact to-face contact demonstrated the Comments:

between Tappet Nut between Tappet Nut ability to ensure and Head Lever per and Head Lever per vertical face-to-face Figure 2 Figure 2 contact between Tappet Nut and Head Lever per Figure 2 (AT MOCKUP)

Step 3.2.2 S U

8. CHECK The Control Room Operator FCZL0312DA, TDAFP Operator reports that demonstrated the Comments:

MECHANICAL FCZL0312DA is lit ability to check OVERSPEED RESET FCZL0312DA is lit by INDICATOR LIGHT, on contacting the Control RL005 is lit Room for verification (AT MOCKUP)

Step 3.2.3

Critical Step 4

JPM NO: In-Plant I, Rev. 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. The JPM is Complete Comments:

Record Stop Time on Page 1

Critical Step 5

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Callaway Plant is in Mode 1.

Operations is performing the mechanical trip verification portion of OSP-AL-P0002, Turbine Driven Aux Feedwater Pump Inservice Test - Group B.

Initiating Cues: The Control Room Supervisor directs you to reset the mechanical overspeed trip per OTN-AL-00001, Addendum 01, Turbine Driven Auxiliary Feedwater Pump Trip/Throttle Valve Trip Check and Reset.

Notes: All operator actions are to be simulated in the plant.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: In Plant J, Rev 1 (RCA) KSA NO: 068AK3.18 JOB TITLE: URO/ SROI/ SROU KSA RATING: 4.2 / 4.5 DUTY: EMERGENCY ACTIONS TASK TITLE: EVACUATION OF CONTROL ROOM - BOP COMPLETION TIME: 15 MINUTES The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

OTO-ZZ-00001, CONTROL ROOM INACCESSIBILITY, ATT B, REV 33 TOOLS/EQUIPMENT: PPE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: In Plant J, Rev 1 (RCA)

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was at 100% power when the Shift Manager directed a Control Room evacuation due to a fire. The reactor was tripped and the MSIVs were closed. You are the Balance of Plant Operator and have completed the actions outside of the RCA.

Initiating Cues: You have been directed to continue the actions of OTO-ZZ-00001, Attachment B, starting with Step B13.

ALL EQUIPMENT MANIPULATIONS ARE TO BE SIMULATED.

Task Standard: UPON COMPLETION OF THIS JPM, SG ATMOSPHERIC STEAM DUMPS A AND C, EGHV0061, AND BGHV8105 WILL BE CLOSED.

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: In-Plant J, Rev 1 (RCA)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR WORKING COPY OF OPERATOR WITH OBTAINED Comments:

OTO-ZZ-00001, PROCEDURE COPY PROCEDURE COPY CONTROL ROOM INACCESSIBILITY, ATTACHMENT B S U

2. ENTER THE RCA OPERATOR AND PROCEED TO ENTERED THE RCA Comments:

THE MSIV VALVE AND PROCEEDED ROOM (AREA 5) TO THE MSIV VALVE ROOM (AREA 5)

STEP B13.

S U

3. CLOSE ABPV0001, ABV0733 IS IN THE OPERATOR SG A ATMS STEAM FULL CLOCKWISE DEMONSTRATED Comments:

DUMP BY POSITION ABILITY TO CLOSE PERFORMING THE ABV0733 AND OPEN FOLLOWING: ABV0734 IS IN THE ABV0734 FULL COUNTER-CLOSE MAN AIR/N2 CLOCKWISE ISO FOR MS LOOP POSITION 1 ABPV0001:

IF ASKED AFTER ABV0733 VALVE OPERATION, THERE IS NO NOISE OPEN MAN AIR HEARD AT SPLY DRN VLV FOR ABPV0001; VALVE MS LOOP 1 POSITION IS AS ABPV0001: INDICATED ABV0734 STEP B14.

CRITICAL STEP PAGE 2 of 4

JPM NO: In-Plant J, Rev 1 (RCA)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. CLOSE ABPV0003, ABV0737 IS IN THE OPERATOR SG C ATMS STEAM FULL CLOCKWISE DEMONSTRATED Comments:

DUMP BY POSITION ABILITY TO CLOSE PERFORMING THE ABV0737 AND OPEN FOLLOWING: ABV0738 IS IN THE ABV0738 FULL COUNTER-CLOSE MAN AIR/N2 CLOCKWISE ISO FOR MS LOOP POSITION 3 ABPV0003:

IF ASKED AFTER ABV0737 VALVE OPERATION, THERE IS NO NOISE OPEN MAN AIR HEARD AT SPLY DRN VLV FOR ABPV0003; VALVE MS LOOP 3 POSITION IS AS ABPV0003: INDICATED ABV0738 STEP B15.

S U

5. PROCEED TO OPERATOR NORTH PIPING PEN PROCEEDED TO Comments:

ROOM NORTH PIPING PEN (AB 2000 RM 1323) ROOM STEP B16.

CRITICAL STEP PAGE 3 of 4

JPM NO: In-Plant J, Rev 1 (RCA)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. LOCALLY CLOSE EGHV0061 POSITION OPERATOR CCW FROM RCP INDICATION IS IN DEMONSTRATED Comments:

THRM BAR OUTER CLOSED POSITION ABILITY TO CLOSE CTMT ISO: (PEN 76) EGHV0061 EGHV0061 STEP B17.

S U

7. LOCALLY CLOSE BGHV8105 POSITION OPERATOR CVCS CHARGING INDICATION IS IN DEMONSTRATED Comments:

HDR TO REGEN HX CLOSED POSITION ABILITY TO CLOSE OUTER CTMT ISO BGHV8105 VLV: (PEN 80)

BGHV8105 STEP B18.

S U

9. NOTIFY SM AT THE SM OPERATOR ASP THAT BOP ACKNOWLEDGES DEMONSTRATED Comments:

VALVE AND THE ABILITY TO BREAKER ANOTHER NOTIFY SM AT THE ALIGNMENTS OPERATOR WILL ASP THAT BOP NECESSARY TO COMPLETE THE VALVE AND START THE REMAINING STEPS BREAKER FOLLOWING ARE OF OTO-ZZ-00001, ALIGNMENTS COMPLETE: ATTACHMENT B NECESSARY TO START THE CCW PUMP B FOLLOWING ARE CCW PUMP D COMPLETE:

STEP B19. CCW PUMP B CCW PUMP D S U

10. JPM COMPLETE RECORD STOP TIME ON PAGE 1 Comments:

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Callaway Plant was at 100% power when the Shift Manager directed a Control Room evacuation due to a fire. The reactor was tripped and the MSIVs were closed. You are the Balance of Plant Operator and have completed the actions outside of the RCA.

Initiating Cues: You have been directed to continue the actions of OTO-ZZ-00001, Attachment B, starting with Step B13.

ALL EQUIPMENT MANIPULATIONS ARE TO BE SIMULATED.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: In-Plant K, Rev 1 KSA NO: 062A2.10 JOB TITLE: URO/SRO KSA RATING: 3.0 / 3.3 DUTY: SAFETY RELATED ELEC GEN & DIST TASK TITLE: SWITCH FROM SWING CHARGER NK25 TO NORMAL CHARGER NK21 COMPLETION TIME: 30 minutes The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

OTN-NK-00001 ADD 01, 125 VDC BUS NK01 AND DIST SYSTEM, R002 OTA-NK-00001, ANNUNCIATOR RESPONSE PROCEDURE 125 VDC CLASS 1E PANEL NK01, R005 TOOLS/EQUIPMENT: PPE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: In-Plant K, Rev 1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant is in Mode 5 following a refueling outage.

Swing Charger NK25 is supplying DC Bus NK01 while Normal Charger NK21 is out of service for scheduled maintenance.

NK77 is currently being supplied from NG0109.

Initiating Cues: Maintenance is complete on Normal Charger NK21. You have been directed to switch distribution switchboard NK01 from Swing Charger NK25 to Normal Charger NK21 per OTN-NK-00001, Addendum 1. Inform the Control Room Supervisor when NK01 is being supplied by NK21.

Notes: ALL OPERATOR ACTIONS ARE TO BE SIMULATED.

Task Standard: UPON COMPLETION OF THIS JPM, BATTERY CHARGER NK25 WILL BE BACK IN SERVICE TO DISTRIBUTION SWITCHBOARD NK01, DUE TO CHARGER NK21 OUTPUT BREAKER TRIPPING OPEN.

START TIME:

STOP TIME:

PAGE 1 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A VERIFIED PROVIDE OPERATOR OPERATOR WORKING COPY OF WITH PROCEDURE OBTAINED Comments:

OTN-NK-00001, PROCEDURE COPY ADDENDUM 01 S U

2. REVIEW ALL PRECAUTIONS OPERATOR PRECAUTIONS AND AND LIMITATIONS REVIEWED THE Comments:

LIMITATIONS ARE SATISFIED PRECAUTIONS AND LIMITATIONS SECTION 3 S U

3. REVIEW THE THERE ARE NO OPERATOR PREREQUISITES PREREQUISITES DETERMINED THAT Comments:

THERE ARE NO PREREQUISITES SECTION 4

CRITICAL STEP PAGE 2 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. OBTAIN THE YOU HAVE OPERATOR TRAIN A POSSESSION OF KEY DEMONSTRATED Comments:

KEYSWITCH #137 THE ABILITY TO (KEY #137) FROM OBTAIN KEY #137 THE CONTROL ROOM STEP 5.2.1 S U

5. NOTE: ONE KEY OPERATOR READ FITS ALL THE TRAIN NOTE Comments:

A KEYSWITCHES.

THE HANDSWITCHES AND KEYSWITCHES SPRING RETURN TO NEUTRAL. SWITCH POSITION IS VERIFIED BY INDICATING LIGHTS.

S U

6. RECORD CHARGER METER INDICATES OPERATOR CURRENT AT NK25, 40 AMPS RECORDED Comments:

SWING BATTERY CHARGER CURRENT CHARGER FOR 125 AT NK25 INDICATED VDC GROUPS 1 AND AS 40 AMPS 3, (CB2000).

___________ AMPS STEP 5.2.2

CRITICAL STEP PAGE 3 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. PERFORM THE BREAKER NG0103, OPERATOR CLOSED FOLLOWING TO POSITION IS AS NG0103 Comments:

ENERGIZE NK21, INDICATED 125 VDC VITAL BATT (CLOSED)

CHG #1:

CLOSE NG0103, FDR BKR TO NK21 125 VDC VITAL BATTERY CHARGER.

STEP 5.2.3.a S U

8. AT NK21: THE EQUALIZE OPERATOR ENSURED TIMER SETTING IS THE EQUALIZE Comments:

ENSURE THE AS INDICATED TIMER IS SET TO EQUALIZE TIMER IS (ZERO) ZERO SET TO ZERO STEP 5.2.3.b.1 S U

9. AT NK21: THE OPERATOR ENSURED FLOAT/EQUALIZE THE Comments:

ENSURE THE SWITCH IS AS FLOAT/EQUALIZE FLOAT/EQUALIZE INDICATED (FLOAT) SWITCH IS SELECTED SWITCH IS TO FLOAT SELECTED TO FLOAT STEP 5.2.3.b.2

CRITICAL STEP PAGE 4 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. AT NK21: CB2 POSITION IS AS OPERATOR CLOSED INDICATED (UP CB2 Comments:

CLOSE CB2, DC POSITION)

POWER STEP 5.2.3.b.3 S U

11. AT NK21: CB1 POSITION IS AS OPERATOR CLOSED INDICATED (UP CB1 Comments:

CLOSE CB1, AC POSITION)

POWER STEP 5.2.3.b.4 S U

12. AT NK21: 5 MINUTES HAS OPERATOR WAITED ELAPSED 5 MINUTES AND Comments:

AFTER 5 MINUTES, READ NK21 FLOAT CHECK NK21 FLOAT NK21 FLOAT VOLTAGE GIVEN AS VOLTAGE IS 134 TO VOLTAGE 135 VDC 136 VDC INDICATES 135 VDC STEP 5.2.3.b.5

CRITICAL STEP PAGE 5 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. AT NK21: NK21 FLOAT OPERATOR VOLTAGE DETERMINED NO Comments:

IF VOLTAGE INDICATES 135 VDC ADJUSTMENT IS ADJUSTMENT IS NECESSARY AND NECESSARY, PROCEEDED TO NOTIFY THE STEP 5.2.3.b.7 SYSTEM ENGINEER VIA SM/CRS STEP 5.2.3.b.6 S U

14. AT NK21: NO VOLTAGE OPERATOR ADJUSTMENT WAS DETERMINED NO Comments:

WHEN VOLTAGE NECESSARY. ADJUSTMENT WAS ADJUSTMENT HAS NECESSARY AND BEEN PERFORMED, PROCEEDED TO CHECK NK21 FLOAT STEP 5.2.4 VOLTAGE IS 134 TO 136 VDC STEP 5.2.3.b.7 S U

15. NOTE:IF BATTERY OPERATOR READS NK11 IS NOT NOTE Comments:

CONNECTED TO BUS NK01, NK01 WILL BE MOMENTARILY DEENERGIZED DURING THE TRANSFER

CRITICAL STEP PAGE 6 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. CHECK BATTERY NK0109 POSITION IS OPERATOR NK11 IS AS INDICATED (OFF) CHECKED NK0109 Comments:

CONNECTED TO OFF BUS NK01 AS FOLLOWS:

ENSURE NK0109, TO RESISTIVE LOAD FOR DISCH TEST OF BATT NK11, IS OFF STEP 5.2.4 S U

17. CHECK BATTERY NK0101 POSITION IS OPERATOR NK11 IS AS INDICATED (ON) CHECKED NK0101 ON Comments:

CONNECTED TO BUS NK01 AS FOLLOWS:

ENSURE NK0101, ALT FDR BKR TO NK01 FROM NK11 FULS, IS ON STEP 5.2.4 S U

18. NOTE:THE OPERATOR READS FOLLOWING STEP NOTE Comments:

DISCONNECTS NK25 AND LEAVES IT IN THE NORMAL STANDBY LINEUP.

CRITICAL STEP PAGE 7 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. AT NK71, DC NKHS0011 IS IN THE OPERATOR PLACED TRANSFER SWITCH NK21 POSITION NKHS0011 TO THE Comments:

NK21/NK25 TO NK21 POSITION NK01(CB 2016): ALT PATH:

PLACE NKHS0011, ON NK01 POINT TO HANDSWITCH TO ANNUNCIATOR 4B CONTROL NK71 AND STATE TRANSFER SWITCH, ANNUNCIATOR TO NK21 JUST ALARMED IF ASKED, NK01 VOLTAGE = 125VDC.

IF ASKED, NK11 BATT CURRENT = 45 AMPS STEP 5.2.5.a S U

20. OBTAIN A COPY OF ANNUNCIATOR OPERATOR OTA-NK-00001 Add RESPONSE OBTAINED Comments:

4B, CHARGER DC PROCEDURE SHOULD ANNUNCIATOR BREAKER OPEN BE ON STATION. RESPONSE PROCEDURE.

PROVIDE COPY OF OTA-NK-00001

CRITICAL STEP PAGE 8 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

21. ON THE IN-SERVICE NK21 CB2 IS MID- OPERATOR CHECKS CHARGER, CHECK POSITION NK21 CB2 CLOSED Comments:

THE FOLLOWING AND DISCOVERED IT CLOSED: IF OPERATOR ASKS, IS OPEN.

NK25 CB2 IS CLOSED.

NK21 CB2, BATTERY CHARGER NK21 DC OUTPUT CIRCUIT BREAKER STEP 3.1 S U

22. IF REQUIRED, IF OPERATOR ASKS OPERATOR NOTIFIED PLACE THE FOR DIRECTION, CR OF LOSS OF Comments:

ALTERNATE ASK WHAT ACTION CHARGER BATTERY CHARGER YOU WOULD IN SERVICE PER RECOMMEND TO OPERATOR OTN-NK-00001, TAKE RECOMMENDED CLASS 1E 125 VDC PLACING SWING ELECTRICAL CHARGER BACK IN SYSTEM. SERVICE STEP 3.2 S U

23. REFER TO OTN-NK- OPERATOR REFERS 00001 Add 1, Sect 5.1, TO OTN-NK-00001 Comments:

SWITCHING DIST ADD 1.

SWBD NK01 FROM NORMAL CHARGER NK21 TO SWING CHARGER NK25

CRITICAL STEP PAGE 9 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

24. OBTAIN THE TRAIN OPERATOR OPERATOR A KEYSWITCH ALREADY HAS KEY RECOGNIZES HE IS Comments:

(#137) FROM THE #137 ALREADY IN CONTROL ROOM POSSESSION OF KEY

137 STEP 5.1.1 S U

25. ENSURE THAT ANOTHER AFTER RECEIVING NK25, SWING OPERATOR HAS CUE, OPERATOR Comments:

BATTERY CHARGER PERFORMED STEP CONTINUED WITH FOR 125 VDC 5.1.2 STEP 5.1.3 GROUPS 1 AND 3, IS AVAILABLE FOR SERVICE PER THE FOLLOWING:

STEP 5.1.2 S U

26. IF NK25 IS DE- N/A: NK25 IS OPERATOR ENERGIZED, ENERGIZED RECOGNIZED THAT Comments:

PERFORM THE THE PREVIOUS STEP FOLLOWING VERIFIED NK25 WAS ENERGIZED STEP 5.1.3

CRITICAL STEP PAGE 10 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

27. NOTE: IF BATT OPERATOR READS NK11 IS NOT NOTE Comments:

CONNECTED TO BUS NK01, NK01 WILL BE MOMENTARILY DE-ENERGIZED DURING THE TRANSFER.

S U

28. ENSURE BATTERY NK0109 POSITION IS OPERATOR NK11 IS AS INDICATED (OFF) CHECKED NK0109 Comments:

CONNECTED TO OFF BUS NK01 BY CHECKING THE FOLLOWING:

ENSURE NK0109, TO RESISTIVE LOAD FOR DISCH TEST OF BATT NK11, IS OFF STEP 5.1.4 S U

29. ENSURE BATTERY NK0101 POSITION IS OPERATOR NK11 IS AS INDICATED (ON) CHECKED NK0101 IS Comments:

CONNECTED TO ON BUS NK01 BY CHECKING THE FOLLOWING:

ENSURE NK0101, ALT FDR BKR TO NK01 FROM NK11 FULS, IS ON STEP 5.1.4

CRITICAL STEP PAGE 11 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

30. RECORD CHARGER NK21 CHARGER OPERATOR CURRENT AT NK21, CURRENT = 0 AMPS CHECKED NK21 Comments:

125 VDC VITAL CURRENT AND BATT CHG #1 OPERATOR MAY RECORDED IT (CB2016): RECOGNIZE THAT WITH NK21 NOT

___________ AMPS SUPPLYING NK01, BATT CURRENT BETTER MEETS THE INTENTION OF THIS STEP.

STEP 5.1.5 IF ASKED, NK11 BATT CURRENT = 45 AMPS S U

31. AT NK71, DC NK25 ENERGIZED OPERATOR TRANSFER SWITCH LIGHT ON. CHECKED WHITE Comments:

NK21/NK25 TO NK25 ENERGIZED NK01(CB 2016): LIGHT ON.

CHECK THE WHITE NK25 ENERGIZED LIGHT ON STEP 5.1.6.a S U

32. AT NK71, DC NK03 TIED TO NK23 OPERATOR TRANSFER SWITCH LIGHT ON. CHECKED NK03 TIED Comments:

NK21/NK25 TO TO NK23 LIGHT ON.

NK01(CB 2016):

CHECK THE NK03 TIED TO NK23 LIGHT ON STEP 5.1.6.b

CRITICAL STEP PAGE 12 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

33. AT NK71, DC NK25 ALIGNED TO OPERATOR TRANSFER SWITCH NK01 LIGHT ON CHECKED NK25 Comments:

NK21/NK25 TO ALIGNED TO NK01 NK01(CB 2016): LIGHT ON.

CHECK THE NK25 ALIGNED TO NK01 LIGHT ON STEP 5.1.6.c S U

34. AT NK71, DC NKHS0011 OPERATOR PLACED TRANSFER SWITCH HANDSWITCH IS ON NKHS0011 Comments:

NK21/NK25 TO NK25 HANDSWITCH TO NK01(CB 2016): NK25 POSITION PLACE NKHS0011, HANDSWITCH TO CONTROL NK71 TRANSFER SWITCH, TO NK25 STEP 5.1.6.d S U

35. AT NK71, DC NK01 TIED TO NK25 OPERATOR TRANSFER SWITCH LIGHT ON CHECKED NK01 TIED Comments:

NK21/NK25 TO TO NK25 LIGHT ON NK01(CB 2016):

CHECK THE NK01 TIED TO NK25 LIGHT ON STEP 5.1.6.e

CRITICAL STEP PAGE 13 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

36. AT NK01,CHECK ANNUNCIATOR 5B, OPERATOR ANNUNCIATOR 5B, SWING CHGR IN CHECKED Comments:

SWING CHGR IN USE, IS ON ANNUNCIATOR 5B, USE, IS ON SWING CHGR IN USE, IS ON STEP 5.1.7 S U

37. AT RL016,CHECK ANNUNCIATOR 20F, OPERATOR ANNUNCIATOR 20F, SWING CHGR NK25 CONTACTED THE Comments:

SWING CHGR NK25 IN SERVICE, IS ON CONTROL ROOM TO IN SERVICE, IS ON VERIFY ANNUNCIATOR 20F, SWING CHGR NK25 IN SERVICE, IS ON STEP 5.1.8 S U

38. CHECK THE NK01 NK01 BUS VOLTAGE OPERATOR BUS VOLTAGE IS IS 137 VDC ON THE CHECKED THE NK01 Comments:

BETWEEN 131 AND LOCAL AND BUS VOLTAGE IS 140 VDC ON BOTH CONTROL ROOM BETWEEN 131 AND THE LOCAL AND METERS 140 VDC ON BOTH CONTROL ROOM THE LOCAL AND VOLTMETERS CONTROL ROOM VOLTMETERS STEP 5.1.9

CRITICAL STEP PAGE 14 of 15

JPM NO: In-Plant K, Rev 1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

39. IF NK21 IS TO BE DE- ANOTHER OPERATOR ENERGIZED, OPERATOR WILL CONTINUED WITH Comments:

PERFORM THE COMPLETE THE PROCEDURE AT STEP FOLLOWING: REMAINDER OF 5.1.10 THE OTN STEP 5.1.10 THE JPM IS COMPLETE.

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 15 of 15

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant is in Mode 5 following a refueling outage.

Swing Charger NK25 is supplying DC Bus NK01 while Normal Charger NK21 is out of service for scheduled maintenance.

NK77 is currently being supplied from NG0109.

Initiating Cues: Maintenance is complete on Normal Charger NK21. You have been directed to switch distribution switchboard NK01 from Swing Charger NK25 to Normal Charger NK21 per OTN-NK-00001, Addendum 1. Inform the Control Room Supervisor when NK01 is being supplied by NK21.

Notes: ALL OPERATOR ACTIONS ARE TO BE SIMULATED.

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 1 rev. 2 Op Test No.: 2011301 Examiners: Operators:

Initial Conditions:

100% Power, steady state, Middle of Core Life Turnover: Turnover: The Turbine Driven Auxiliary Feed pump has been out of service for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Work is scheduled to complete next shift. Lower letdown flow to 75 gpm for ALARA concerns due to maintenance planning walkdown near letdown line.

Event Malf. No. Event Event No. Type* Description 1 N/A SRO (N) Lower letdown flow to 75 gpm RO (N) 2 BGLT0149 RO (I)

VCT Level Channel BG LT-149 fails high TVSP SRO (I) 15 min 3 AELT0539 SRO (I) (TS) SG C Controlling Level Channel fails low (Tech Spec) 25 min BOP(I) 4 ACPT0505 SRO (I) (TS) Turbine Impulse Pressure Channel PT-505 Fails Low (Tech Spec) 35 min TVSP RO (I)

BOP(I) 5 EAD05 SRO (C) Loss of Main Condenser Vacuum at a rate requiring rapid controlled shutdown (provide cues as necessary for downpower) 45 min RO (C)

BOP (C) 6 AB003 SRO (M) Large Steam Line Rupture in Turbine Building with B MSIV failing open. (MSIV FAILURE PRELOADED) 60 min LOASAS RO (M) 9XX_2 & 6 BOP(M) 7 JLOASBI8_2 SRO (C) Failure of AL HIS-22A, MD AFP B, to automatically start (Integral to scenario) (PRELOADED)

N/A BOP (C)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3

Scenario Event Description NRC Scenario 1 rev. 2 Callaway 2011 NRC Scenario #1 The plant is operating at 100%, steady state power. The Turbine Driven Auxiliary Feedpump is tagged out for maintenance and will not be returned until next shift. During Turnover the crew is informed they will need to lower letdown flow for ALARA concerns. Once the crew takes the watch efforts should be made to reduce the amount of letdown flow to 75 gpm in accordance with OTN-BG-00001, Add 4, Operation of CVCS Letdown.

Once Letdown has been lowered, VCT Level Transmitter BG LT-149 fails High, causing the VCT Inlet, BG HV 0112A to Divert to the RHUT. The crew will enter OTO-BG-00004, VCT Level Channel Failures, and place Letdown Divert to VCT position. VCT Level will have to be controlled manually. No Tech Specs apply.

Once VCT Level addressed, Steam Generator C Controlling Channel, AE LI-553 fails low.

The crew recognizes the failure and selects to an operable channel in accordance with OTO-AE-00002, Steam Generator Water Level Control Malfunctions. Tech Specs 3.3.1 and 3.3.2 apply.

After Tech Specs have been addressed by the SRO, AB PT-505 fails low. The crew should respond per OTO-AC-00003, Turbine Impulse Pressure Channel Failure, place rod control in Manual and Select HP Turbine First Stage Pressure Selector to Operable. Tech Spec 3.3.1 applies.

Once Tech Specs have been addressed and maintenance contacted to repair the failed channels, a Main Condenser Vacuum Leak occurs. The crew observes the degrading vacuum on the Main Control Board and enters OTO-AD-00001, Loss of Condenser Vacuum. The crew sees that vacuum is degrading at a slow continuous rate and starts to reduce turbine load.

Once Turbine Load has been reduced to approximately 1000 MWe, a steam line break develops in the Turbine Building which will be seen by the crew as RCS pressure and temperature rapidly lower. The crew will Manually trip the reactor based on these plant conditions. The crew should enter E-0, Reactor Trip or Safety Injection.

The B Main Steamline Isolation Valve fails to close in response to the Low Steam Line Pressure. The crew should make efforts to manually isolate the Main Steamlines and complete the isolation of SG B in accordance with E-2, Faulted S/G Isolation, but the B SG cannot be isolated.

The A MDAFP starts normally, but the B MDAFP must be started manually due to malfunction inserted during the setup. The crew will then restore adequate feed to the intact Steam Generators The scenario will end when the crew gets to the final step of E-2 and starts to transition to ES-1.1, SI Termination

Scenario Event Description NRC Scenario 1 rev. 2 Critical Tasks:

Event #3 CT - SG level channel failed low - Select away prior to reactor trip Event #6 CT - Isolate Auxiliary Feedwater Flow supply to SG B before a transition out of E-2 Event #7 CT - Start the MDAFP B to establish AFW flow rate greater than 355,000 lbm/hr to the intact SGs before transition out of E-0.

References OTN-BG-00001, Add 4 OTO-AE-00002 OTO-AC-00003 OTO-AD-00001 OTO-BG-00004 E-0 E-2 ES-1.1

Scenario Event Description NRC Scenario 1 rev. 2 Scenario Setup Guide:

Establish the initial conditions of IC-161, MOL 100% power:

RCS boron concentration 960 ppm

CCP A 976 ppm minus 5 days

CCP B 986 ppm minus 15 days

Rod Control Bank D 215 steps, Other banks 228 steps ENSURE AE LS-539C is selected to L539 for Control ENSURE AC PS-505Z is selected to P505 for Control

=======SCENARIO PRELOADS / SETUP ITEMS==========

Remove from Service and then place Tags on Turbine Driven Auxiliary Feedwater Pump

Run Lesson AL01TD.lsn B Main Steam Line Isolation Failure to CLOSE in AUTO or MANUAL

Insert Remote Function (SA) LOASAS9XX_2

Insert Remote Function (SA) LOASAS9XX_6

Insert Remote Function (AB) ABHV0017_AuxM, Value = Connected Motor Driven Aux Feed Pump B fails to start in Auto

Insert Remote Function (AL) JLOASBI8_2, Value = inhibit

======= EVENT 2 ============================

VCT Level Channel BG LT-149 fails High

Insert Malfunction (BG) BGLT0149TVSP, Value = 1.0

======= EVENT 3 ============================

SG C Controlling Level Channel, AELT539, fails to 0% over 15 sec

Insert Malfunction (AE) AELT0539, Value = 0, ramp = 15 secs

=======EVENT 4 =============================

HP Turbine First Pressure Channel PT-505 fails Low over 15 secs

Insert Malfunction (AC) ACPT0505TVSP, value = 0, ramp = 15 secs

=======EVENT 5 ==============================

Loss of Condenser Vacuum requiring Rapid Plant Shutdown

Insert Malfunction (AD) EAD05, value = 75

=======EVENT 6 PRELOADED====================

Large Steam Line Rupture in Turbine Building with B MSIV failing OPEN

Insert Malfunction (AB) AB003, Value = 5000000, ramp = 60 secs

B MSIV failure - SEE PRELOADS ABOVE

=======EVENT 7 PRELOADED===============

Failure of Motor Driven Aux Feed Pump to Start Automatically SEE PRELOADS ABOVE

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev.2 Event # 1 Page 5 of 27 Event

Description:

Lower Letdown flow to 75 GPM Time Position Applicants Actions or Behavior Booth Operator Instructions

When contacted, respond as Chemistry. Acknowledge that letdown will be lowered to 75 GPM.

OTN-BG-00001 Add 4, Operation of CVCS Letdown T=0 CRS (Step 5.7.1) Inform Chemistry letdown is being changed (Step 5.7.2) Place BG PK-131, LTDN HX OUTLET PRESS RO CTRL, in MANUAL and SET Output to control pressure on BG PI-131, LTDN HX OUTLET PRESS, at 400 psig.

(Step 5.7.3) Close valves below as required to obtain 75 GPM letdown flow rate:

RO

BG HIS-8149AA, LTDN Orifice A Vlv (Step 5.7.4) Monitor BG PI-131and Manually control BG PK-RO 131, LTDN HX OUTLET PRESS CTRL, to control Letdown system pressure at approximately 350 psig.

(Step 5.7.5) When flow and pressure have stabilized, ENSURE RO BG PI-131 is reading 350 psig, then PLACE BG PK-131 in AUTO (Step 5.7.6) MONITOR BG TI-130, LTDN HX OUTLET TEMP, and SLOWLY adjust potentiometer on BG TK-130, LTDN HX RO OUTLET TEMP CTRL, (3.0 to 4.3 turns) to control Letdown Hx Disch Temp at 95°F to 115°F Note: Desired charging flow rate should match letdown flow rate plus total RCP Seal leakoff flow rate.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev.2 Event # 1 Page 6 of 27 Event

Description:

Lower Letdown flow to 75 GPM Time Position Applicants Actions or Behavior (Step 5.7.7) LOWER Charging flow to desired flow rate using RO the NCP controller

ADJUST BG FK-124, NCP DISCH FLOW CTRL (Step 5.7.8) If NCP is in service, WHEN NCP flow is less than RO 100 gpm, OPEN BGHV8109 using BG HIS-8109, NCP RECIRC HV (Step 5.7.9) ADJUST BG HC-182, CHG HDR BACK PRESS RO CTRL, to maintain seal injection flow of approximately 8 gpm per pump as indicated on BG FR-154 thru BG FR-157 (Step 5.7.10) PLACE in MANUAL and ADJUST BB LK-459, RO PZR LEV MASTER CTRL, to obtain desired setpoint:

For 87 gpm charging flow, setpoint is 41 to 45%

(Step 5.7.11) IF NCP is in service, PLACE BG FK-121, CCP RO DISCH FLOW CTRL, in MANUAL and ADJUST to 25%

demand.

(Step 5.7.12) WHEN pressurizer level is being maintained at program level, PLACE the following in AUTO as required:

RO

BG FK-124, NCP DISCH FLOW CTRL

BG LK-459, PZR LEV MASTER CTRL At the Discretion of the Lead Examiner Move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev.2 Event # 2 Page 7 of 27 Event

Description:

VCT Level Transmitter BG LT-149 fails High Time Position Applicants Actions or Behavior Booth Operator Instructions

T = 15 minutes or at the discretion of the Lead Examiner

VCT Level Channel BG LT-149 fails High o Insert Malfunction (BG) BGLT0149TVSP, Value = 1.0

When contacted as the Primary Operations Technician, report that Local indication at BGLT149 indicates 100%

When contacted, respond as I&C. Acknowledge the request to investigate the instrument/channel failure.

When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:

T= 15 ANN 42B, VCT LEV HILO ANN 42D, VCT DIVERT TO RHT OTO-BG-00004, VCT Level Channel Failures CRS Implement OTO-BG-00004, VCT Level Channel Failures (Step 1) Identify Failed VCT Level Channel RO

BG LT-149 (BGL0149)

(Step 2) Check Failed VCT Level Channel Identified As - BG LI-CRS/RO 112 OR BG LI-185 - NO RNO - GO TO STEP 14

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev.2 Event # 2 Page 8 of 27 Event

Description:

VCT Level Transmitter BG LT-149 fails High Time Position Applicants Actions or Behavior (Step 14) Check VCT Level Channel Failed - LOW - NO

REL0112A

BG LI-149 (local)

CRS/RO RNO - Perform the following:

Place Letdown Divert to VCT & RHT to VCT position

Initiate actions to repair the failed component

GO TO Step 16 (Step 16) MAINTAIN VCT level as necessary by cycling BG HIS-112A and initiating manual makeup per OTN-BG-00002, Reactor RO Makeup Control And Boron Thermal Regeneration System (Step 17) Perform Notifications per ODP-ZZ-00001 Add 13, Shift CRS Manager Communications At the Discretion of the Lead Examiner Move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 3 Page 9 of 27 Event

Description:

SG C Controlling Level Channel fails low (Tech Spec)

Time Position Applicants Actions or Behavior Booth Operator Instructions

T = 10 minutes or at the discretion of the Lead Examiner

SG C Controlling Level Channel, AELT539, fails to 0% over 15 sec o Insert Malfunction (AE) AELT0539, Value = 0, ramp = 15 sec

When contacted, respond as I&C. Acknowledge the request to investigate the instrument/channel failure.

When contacted, respond as EDO. Acknowledge entry into the OTO and Tech Spec entry Indications Available:

T= 25 ANN 110C, SG C LEV DEV ANN 110D, SG C FLOW MISMATCH OTO-AE-00002, Steam Generator Water Level Control Malfunctions Implement OTO-AE-00002, Steam Generator Water Level Control CRS Malfunctions (Step 1) Check SG Feedwater Flow Instrument Indications -

BOP Normal BOP (Step 2) Check SG Steam Flow Instrument Indications - Normal (Step 3) Check SG Level Instrument Indications - Normal - NO

SG C - AE LI-539 BOP RNO - Select SG Level Channel Selector to an operable channel:

SG C - AE LS-539C Critical CREW SG level channel failed low - Select away prior to reactor trip Task (Step 4) Check SG Pressure Instrument Indications - NORMAL BOP

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 3 Page 10 of 27 Event

Description:

SG C Controlling Level Channel fails low (Tech Spec)

Time Position Applicants Actions or Behavior (Step 5) Check Steam Generator NR Level RO Trending to and/or between 45% to 55%

CRS (Step 6) Review Attachment A, Effects of Instrument Failure (Step 7) Review Applicable Tech Specs in Attachment F

3.3.1, Table 3.3.1-1, Items 14.a and 14.b, Condition E, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to trip CRS

3.3.2, Table 3.3.2-1, Item 5.c and 5.e, Condition I and Condition D, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to trip

3.3.2, Table 3.3.2-1, Item 6.d, Condition D, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to trip (Step 8) Perform Notifications per ODP-ZZ-00001 Add 13, Shift CRS Manager Communications At the Discretion of the Lead Examiner Move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 4 Page 11 of 27 Event

Description:

Turbine Impulse Pressure Channel PT-505 Fails Low (Tech Spec)

Time Position Applicants Actions or Behavior Booth Operator Instructions

HP Turbine First Pressure Channel PT-505 fails Low over 15 secs o Insert Malfunction (AC) ACPT0505TVSP, value = 0, ramp = 15 secs

When contacted, respond as I&C. Acknowledge the request to investigate the instrument/channel failure.

When contacted as EDO. Acknowledge entry into the OTO and Tech Spec entry.

Indications Available:

T= 35 SC0066W WINDOWS LIT (NO AUDIBLE ALARM)

ANN 65E, TREF/ TAUCT LO OTO-AC-00003, Turbine Impulse Pressure Channel Failure Implement OTO-AC-00003, Turbine Impulse Pressure Channel CRS failure RO (Step 1) Place Rod Control in Manual using SE HS-9 (Step 2) Check HP Turbine First Stage Pressure Indicator -

BOP FAILED

AC PI-505 (Step 3) SELECT HP Turbine First Stage Pressure to Operable BOP Channel

AC PS-505Z (Step 4) CHECK RCS Tavg within 1.5 °F of Tref RO If not - restore using rods/ turbine load/ adjust Boron (Step 5) Check Rod Control - IN AUTO CRS/RO RNO - When RCS Tavg/Tref are equal AND CRS Concurs, place Rod control in AUTO

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 4 Page 12 of 27 Event

Description:

Turbine Impulse Pressure Channel PT-505 Fails Low (Tech Spec)

Time Position Applicants Actions or Behavior Note: The crew may restore rods to previous level at this time (Step 6) Place Steam Dump Bypass Interlock Switches to OFF/RESET BOP

AB HS-63

AB HS-64 (Step 7) CHECK the Following Permissives in the Correct State within one hour of the Channel Failure BOP

P-7 (Lit)

P-13 (Lit)

(Step 8) Review Applicable Tech Specs. Refer to Att. C CRS

3.3.1, Table 3.3.1-1Item 18.f, Cond T - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (Step 9) Review Att A Effects of Turbine Impulse Press Inst CRS Failure At the Discretion of the Lead Examiner Move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 5 Page 13 of 27 Event

Description:

Loss of Condenser Vacuum Requiring Rapid Load Reduction Time Position Applicants Actions or Behavior Booth Operator Instructions

Insert Malfunction(AD) EAD05, Value = 75

When contacted, respond as Operations Tech to investigate the cause of the Loss of Vacuum.

Indications Available:

T=45 Automatic Starting of Standby Condenser Vacuum Pump Rising Main Condenser Backpressure Unexplained lowering in Main Turbine Load OTO-AD-00001, Loss of Condenser Vacuum CRS Implement OTO-AD-00001, Loss of Condenser Vacuum (Step 1) Check Main Condenser Backpressure - LESS THAN BOP 7.5 inches HGA - YES Note: Attachment A, Diagnostic Actions, contains actions which may be performed for slow moving events.

(Step 2) Refer to Attachment A, Diagnostic Actions, As Time BOP permits to Perform Actions (Step 3) Check Main Condenser Backpressure - Deteriorating BOP or Stable RO (Step 4) Place Rod Control in AUTO (Step 5) Manage Reactivity CREW Perform a Reactivity Management Brief (Step 6) Reduce Turbine Load at Less than or Equal 5% per CREW min using:

%/ Min Loading Rate OR Load Limit Potentiometer

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 1 rev. 2 Event # 5 Page 14 of 27 Event

Description:

Loss of Condenser Vacuum Requiring Rapid Load Reduction Time Position Applicants Actions or Behavior (Step 7) BORATE from the BAST by performing any of the following:

RO

BORATE using OTN-BG-00002 Attachment 8 OTN-BG- (Attachment 8) Borate Mode of RMCS Operation

00002,

1. Place BG HS-26 , RCS M/U CTRL, in STOP Att. 8

2. Place BG HS-25, RCS M/U CTRL SEL, in BOR

3. RESET BG FY-110B, BA Counter, to 000

4. ENSURE BG-FY-110B is set to deliver the desired amount of boron

5. Place BG HS-26, RCS M/U CTRL, in RUN RO

6. When the desired amount of borated water has been added, PLACE BG HS-26, RCS M/U CTRL, in STOP.

7. If required, PERFORM the following:

a. Place BG HS-25, RCS M/U CTRL SEL, in AUTO

b. Place BG HS-26, RCS M/U CTRL, in RUN At the Discretion of the Lead Examiner Move to Event #6

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 15 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior Booth Operator Instructions When directed by Lead Examiner Initiate the Large Steamline Break in the Turbine Building Insert Malfunction(AB) AB003, Value = 5000000, ramp = 1 min The following PRELOADS WILL are activated B Main Steam Line Isolation Failure to CLOSE in AUTO or MANUAL

Insert Remote Function (SA) LOASAS9XX_2

Insert Remote Function (SA) LOASAS9XX_6

Insert Remote Function (AB) ABHV0017_AuxM, Value = Connected Motor Driven Aux Feed Pump B fails to start in Auto

Insert Remote Function (AL) JLOASBI8_2, Value = inhibit When contacted, respond as EDO to acknowledge plant trip.

Indications Available:

T=60 STEAM FLOW FEED FLOW MISMATCH RISING REACTOR POWER AND LOWERING TAVG Observes Indications of Steam Line Break and Trips Reactor CREW RCS Temperature Lowering RCS Pressure Lowering E-0, Reactor Trip or Safety Injection CRS Implement E-0, Reactor Trip or Safety Injection NOTE Steps 1 through 4 are immediate actions E-0 (Step 1) Check Reactor Trip Rod Bottom Lights - All Lit RO Reactor Trip and Bypass Breakers - Open Neutron Flux - Lowering (Step 2) Check Turbine Trip BOP Turbine Stop Valves - Closed

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 16 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior (Step 3) Check Power to AC Emergency Buses BOP At Least One Emergency Bus - Energized Both Emergency Buses - Energized (Step 4) Check SI Status Actuated or Required Manually Actuate SI (If not actuated)

RO Check both Trains of SI Actuated LOCA Sequencer ANN 30A - Lit LOCA Sequencer ANN 31A - Lit SB069 SI Actuate Red Light - Lit Solid (Step 5) Perform Attachment A, Automatic Action Verification, RO/BOP while continuing with this procedure E-0 Att A RO/BOP (Step A1) Check Charging Pumps - Both CCPs running RO/BOP (Step A2) Check SI and RHR Pumps - All running RO/BOP (Step A3) Check ECCS Flow - BIH flow indicated RO/BOP (Step A4) CHECK ESW Pumps - BOTH RUNNING

EF HIS-55A

EF HIS-56A RO/BOP (Step A5) CHECK CCW Alignment:

CCW Pumps - ONE RUNNING IN EACH TRAIN

Red Train:

EG HIS-21 or EG HIS-23

Yellow Train:

EG HIS-22 or EG HIS-24

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 17 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior

CCW Service Loop Supply and Return valves for one operating CCW pump - OPEN

EG ZL-15 AND EG ZL-53 OR

EG ZL-16 AND EG ZL-54

OPEN CCSW To RHR HX valves:

EG HIS-101

EG HIS-102

CLOSE Spent Fuel Pool HX CCW Outlet Valves:

EG HIS-101

EG HIS-102

CLOSE Spent Fuel Pool HX CCW Outlet Valves:

EC HIS-11

EC HIS-12

STOP Spent Fuel Pool Cooling Pump(s):

EC HIS-27

EC HIS-28

RECORD The Time Spent Fuel Pool Cooling Pump Secured

MONITOR Time Since CCW Flow Isolated to SFP HX LESS THAN 4 HOURS (Step A6) CHECK Containment Cooler Fans - RUNNING IN RO/BOP SLOW SPEED

GN HIS-9

GN HIS-17

GN HIS-5

GN HIS-13

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 18 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior (Step A7) CHECK Containment Hydrogen Mixing Fans -

RO/BOP RUNNING IN SLOW SPEED

GN HIS-2

GN HIS-4

GN HIS-1

GN HIS-3 RO/BOP (Step A8) CHECK If Containment Spray should Be Actuated:

CHECK the following:

Containment pressure - GREATER THAN 27 PSIG OR

GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR

Annunciator 59A CSAS LIT OR

Annunciator 59B CISB - LIT

Containment Spray Pumps -

EN HIS-3

EN HIS-9

ESFAS status panels CSAS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

ESFAS status panels CISB sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

ESFAS status panels CISB sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 19 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior

STOP all RCPs RO/BOP (Step A9) CHECK If Main Steamlines Should Be Isolated:

CHECK for any of the following:

Containment pressure - GREATER THAN 17 PSIG OR

GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR

Steamline pressure - LESS THAN 615 PSIG OR

AB PR-514 or AB PR-535 indicates steamline pressure

- HAS BEEN LESS THAN 615 PSIG

CHECK MSIVs and Bypass valves - CLOSED (Step A10) CHECK ECCS Valves - PROPER EMERGENCY RO/BOP ALIGNMENT

ESFAS status panels SIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A11) CHECK Containment Isolation Phase A:

ESFAS status panels CISA sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A12) CHECK SG Blowdown Isolation:

ESFAS status panels SGBSIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 20 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior (Step A13) CHECK Both Trains of Control Room Ventilation RO/BOP Isolation:

ESFAS status panels CRVIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A14) CHECK Containment Purge Isolation:

ESFAS status panels CPIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A15) NOTIFY CRS of the following:

Unanticipated Manual actions taken.

Failed Equipment status

Attachment A, Automatic Action Verification, completed.

E-0, REACTOR TRIP OR SAFETY INJECTION E-0 (Step 6) Check Generator Output Breakers - Open BOP (Step 7) Check Feedwater Isolation Main Feedwater Pumps - Tripped BOP Main Feedwater Reg Valves - Closed Main Feedwater Reg Bypass Valves - Closed Feedwater Isolation Valves - Closed (Step 8) Check AFW Pumps BOP MD AFW Pumps - Both Running - NO TD AFW Pump - Tagged out / Not Available

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 21 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior Critical Start the MDAFP B to establish AFW flow rate greater Task CREW than 355,000 lbm/hr to the intact SGs before transition out of E-0.

(Step 9) Check AFW Valves - Proper Alignment BOP MD AFP Flow Control Valves - Throttled (AFW may be isolated to SG B per foldout page)

BOP (Step 10) Check Total AFW Flow > 355,000 lbm/hr (Step 11) Check PZR PORVs and Spray Valves PZR PORVs - Closed PZR PORVs - Both in AUTO RO PORV Block Valves - Both Open Normal PZR Spray Valves - Closed (Step 12) Check if RCPs should be Stopped RCPs - Any Running ECCS Pumps - At least One Running RO RCS Pressure - Less than 1425 psig YES - Stop all RCPs RNO - Go To Step 13 (Step 13) Check RCS Temperatures RO RCPs Running - Tavg 557 Deg F No RCPs Running - Tcold 557 Deg F (Step 14) Check if any SG is Faulted Any SG pressure lowering uncontrollably RO/BOP Any SG completely depressurized Go To E-2, Faulted SG Isolation

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 22 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior E-2, FAULTED STEAM GENERATOR ISOLATION E-2 Initiate CSF Monitoring CAUTION At least one SG must be maintained available for RCS cooldown CAUTION Any faulted SG or secondary break should remain isolated during subsequent recovery unless needed for RCS cooldown BOP/RO (Step 1) CHECK MSIVs and Bypass Valves - CLOSED (Step 2) CHECK If Any SG Secondary Pressure Boundary Is BOP/RO Intact:

CHECK pressures in all SGs - ANY STABLE OR RISING BOP/RO (Step 3) Identify Faulted Steam Generator:

Check Pressures in all SGs:

ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED BOP/RO (Step 4) ISOLATE Faulted SG(s):

ISOLATE AFW flow to faulted SG(s):

CLOSE associated MD AFP Flow Control Valve(s)

AL HK-8A (SG A)

AL HK-10A (SG B)

AL HK-12A (SG C)

AL HK-6A (SG D)

CHECK ASD from faulted SG(s) - CLOSED

AB PIC-1A (SG A)

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 23 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior E-2

AB PIC-2A (SG B)

AB PIC-3A (SG C)

AB PIC-4A (SG D)

Locally CLOSE TDAFP Steam Supply from Main Steam Loop BOP Manual Isolation valve from faulted SG

ABV0085 (SG B) - ALREADY CLOSED / TDAFP WPA BOP/RO CHECK Main Feedwater valves to faulted SG(s) CLOSED

Main Feedwater Reg Valve:

AE ZL-510 (SG A)

AE ZL-520 (SG B)

AE ZL-530 (SG C)

AE ZL-540 (SG D)

Main Feedwater Reg Bypass valve:

AE ZL-550 (SG A)

AE ZL-560 (SG B)

AE ZL-570 (SG C)

AE ZL-580 (SG D)

Feedwater Isolation Valve:

AE HIS-39(SG A)

AE HIS-40 (SG B)

AE HIS-41 (SG C)

AE HIS-42 (SG D)

CHECK SG Blowdown Containment Isolation Valve from faulted SG(s) - CLOSED

BM HIS-1A (SG A)

BM HIS-2A (SG B)

BM HIS-3A (SG C)

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 24 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior

BM HIS-4A (SG D)

CLOSE Steamline Low Point Drain valve from faulted SG(s):

AB HIS-9 (SG A)

AB HIS-8 (SG B)

AB HIS-7 (SG C)

AB HIS-10 (SG D)

Critical Isolate Auxiliary Feedwater Flow supply to SG B before a CREW Task transition out of E-2 (Step 5) CHECK CST To AFP Suction Header Pressure -

BOP/RO GREATER THAN 2.75 PSIG NOTE Subsequent actions should NOT be delayed while awaiting SG sampling. Sampling of the SGs is repeated in E-1, Loss of Reactor or Secondary Coolant.

BOP (Step 6) CHECK Secondary Radiation:

PERFORM the following:

PERFORM EOP Addendum 11, Restoring SG Sampling After SI Actuation EOP (Step 1) Reset SI If Necessary ADD 11 BOP/RO

SB HS-42A

SB HS-43A (Step 2) Restore Instrument Air If Necessary BOP/ RO

Check if ESW to Air Compressor Valves OPEN - YES

Start Air Compressor(s)

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 25 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior EOP (Step 3) Open CCW to Radwaste Supply/Return Valves ADD 11 BOP/RO

EG HS-69

EG HS-70 (Step 4) Sample SG(s) as Necessary OPEN SG Upper or Lower Sample Inner Containment Isolation Valves

SG A: BM HIS-19 (upper) / BM HIS-35 (lower)

SG B: BM HIS-20 (upper) / BM HIS-36 (lower)

SG C: BM HIS-21 (upper) / BM HIS-37 (lower)

SG D: BM HIS-22 (upper) / BM HIS-38 (lower)

BOP/RO OPEN SG Sample Outer Containment Isolation Valve(s):

BM HIS-65 (SG A)

BM HIS-66 (SG B)

BM HIS-67 (SG C)

BM HIS 68 (SG D)

Direct Chemistry to obtain sample(s) one SG at time as necessary (Step 5) CHECK if all required SG samples - OBTAINED - NO BOP/RO RNO - When all SG samples are obtained, Then perform steps 6 and 7. Continue with procedure and step in effect.

E-2 (Step 6 continued)

BOP

DIRECT Chemistry to periodically sample all SGs for activity

DIRECT Radiation Protection to survey steamlines in Auxiliary Building Area 5 as necessary.

CHECK unisolated secondary radiation monitors:

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 26 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior

SG Sample radiation:

SJL 026

SG ASD radiation:

AB RIC-111 (SG A)

AB RIC-112 (SG B)

AB RIC-113 (SG C)

AB RIC-114 (SG D)

Turbine Driven Auxiliary Feedwater Pump Exhaust radiation:

FC RIC-385

Secondary radiation - NORMAL RO (Step 7) Check if ECCS Flow Should Be reduced:

RCS Subcooling - Greater Than 30oF.

Secondary Heat Sink:

NR Level in at least One SG > 7%

OR

Total Feedflow to intact SGs > 355,000 lbm/hr.

RCS Pressure - Stable or Rising.

Pzr Level > 9%.

CAUTION If offsite power is lost after SI reset, manual actions may be required to restart safeguards equipment RO (Step 8) Reset SI

SB HS-42A and SB HS43A RO (Step 9) Stop all but one CCP:

BG HIS-1A OR BG HIS 2A CRS Go to ES-1.1, SI Termination, Step 3.

Appendix D Operator Action Form ES-D-2 Op Test No: 2011301 Scenario # 1 rev. 2 Event # 6, 7 Page 27 of 27 Event

Description:

Steamline Break, MSIV fails to close, MDAFP B start failure Time Position Applicants Actions or Behavior ES-1.1, SI Termination ES-1.1 RO (Step 3) Reset CIS-A and CIS-B BOP (Step 4) Establish Instrument Air to Containment RO (Step 5) Check RCS Pressure - Stable or Rising (Step 6) Isolate Boron Injection Header CCP - Suction aligned to RWST Reset CCP Recirc Valves (BG HS-8110 and 8111)

RO Check CCP Recirc Valves Open (BG HIS-8110 & 8111)

Close BIH Inlet Valves (EM HIS-8803A and 8803B)

Close BIH Outlet Valves (EM HIS-8801A and 8801B)

Once the crew enters ES-1.1 or at the Lead Examiners discretion, the scenario is complete. - Freeze the Simulator

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 3 rev.2 Op-Test No.: 2011301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Power, steady state, Middle of Core Life Turnover: B RHR Pump is out of Service for a breaker inspection. The B RHR Pump should be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This is the A Train Protected week. The crew is directed to maintain the current power level.

Event Malf. No. Event Event No. Type* Description 1 BBLT0459 SRO (I) Pressurizer Level Channel fails Low (Tech Spec)

RO (I) 2 BGLCV RO (C) Letdown cannot be restored, establish Excess Letdown 0459 SRO (C) 3 SEN0042 SRO (I) Power Range Excore instrument N42 Fails Low (Tech Spec)

(25 min) BOP (I) 4 Quakey09 SRO (M) Earthquake / Loss of Off Site Power and Trip of Emergency Diesel (50 min) RO (M) Generator B (IPE/PRA). (Trip of DG B PRELOADED)

NE02 BOP (M) 5 SF006 SRO (C) Reactor Auto Trip Failure (PRELOADED)

(N/A) RO (C) 6 JINHBFC SRO (C) TDAFW Pump Auto Start Failure (PRELOADED)

(N/A) BOP (C) 7 NE01 SRO (M) DGA Failure / Loss of all AC (N/A) RO (M)

BOP (M)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 3

4. Major transients (1-2) 2

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3

Scenario Event Description NRC Scenario 3 rev. 2 Callaway 2011 NRC Scenario #3 The plant is stable at 100%. RHR Pump B was taken Out of Service for a breaker inspection and should be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The crew is requested to maintain power at 100%.

Pressurizer Level Channel BB LT-459 fails low, causing a loss of CVCS Letdown. The crew should respond per OTO-BG-00001, Pressurizer Level Control Malfunction, and refer to Technical Specification 3.3.1. When letdown restoration is attempted, BG LCV-0459 will not open. The crew will place excess letdown in service per OTN-BG-00001, Add 4, Operation of CVCS Letdown as a Normal Evolution.

Once Excess Letdown is in Service, Power Range Excore Nuclear Instrument N42 fails Low. The crew enters OTO-SE-00001, Nuclear Instrument Malfunction and takes action to Bypass the failed channel at the NI Back Panel. The BOP Operator will take these actions due to the RO monitoring Excess Letdown. Tech Spec 3.3.1 will be referenced due to the failed channel.

A major earthquake causes a loss of off-site power. The reactor fails to automatically trip. The crew must manually trip the reactor. Once the reactor trips the B Emergency Diesel Generator will trip, leaving the crew with only one emergency bus. The crew should respond to the reactor trip per E-0, Reactor Trip or Safety Injection. A Safety Injection also actuates.

The Turbine Driven Auxiliary Feed Pump (TDAFP) fails to automatically start. The crew must manually start the TDAFP.

At the completion of Step 10 in E-0, Reactor Trip or Safety Injection the 'A' Diesel Generator will be tripped causing a Loss of All AC Power. The crew will transition to ECA-0.0, Loss of All AC Power.

The scenario is complete when the crew initiates ECA-0.0 step 16, Depressurize Intact SGs to 260 PSIG OR at the discretion of the Chief Examiner.

Scenario Event Description NRC Scenario 3 rev. 2 Critical Tasks:

Event #5 CT - Manually Trip the reactor from the control room following failure to Auto trip.

Event #6 CT - Establish a > 355,000 lbm/hr Auxiliary Feedwater flow rate to the Steam Generators before SG level of < 10% Wide Range (dryout) occurs.

Event #7 CT - Establish a cooldown of the RCS at less than 100 °F/hr prior to RCP seal damage occurring.

References OTG-ZZ-00004 OTO-BG-00001 OTN-BG-00001, Addendum 4 OTN-BB-00005 OTO-SE-00001 E-0 ES-0.1 ECA-0.0

Scenario Event Description NRC Scenario 3 rev. 2 Simulator Set Up Establish the initial conditions of IC-161, MOL 100%:

Rod Control Bank D 215 steps, Other banks 228 steps

RCS boron concentration 960 ppm

CCP A 976 ppm minus 5 days

CCP B 986 ppm minus 15 days

Place tag on EJ HIS-2, and place in Pull to Lock

RHR Pump B inoperable, TS 3.5.2.A, 72 Hours, OOS at 0500, this date

Ensure PZR Level channel 459 is selected for control on BOTH BB LS-459D and BB LS-459E

======SCENARIO SETUP ITEMS===========

RHR Pump B Out of Service Run Lesson pej01b.lsn Reactor fails to trip Automatically, but can be tripped manually (Event #5)

Insert Malfunction (SF) SF006, Value = Auto Mode Insert Malfunction (NE) NE02, value = True, with conditional = jcrftr eq true Turbine Driven AFW Pump Auto Start Failure (Event #6)

Insert Remote Function (AL) JINHBFC, Value = Inhibit

========EVENT 1 =========================

Pressurizer Level Channel 459 fails low and BG LCV-459 cannot be opened Insert Malfunction (BB) BBLT0459_1, Value = 0 Letdown Control Valve BG LCV Fails closed Insert Malfunction (BG) BGLCV0459, Value = True

========EVENT 3 ==========================

Power Range Excore Nuclear Instrument N42 fails Low Insert Malfunction (SE) SEN0042, Value = 0

========EVENT 4 ==========================

Earth quake causes a Loss of Offsite power and trip of NB02 Run Lesson Quakey09.lsn Insert Malfunction (NE) NE02, Value = True on Reactor Trip - PRELOADED

========EVENT 5 PRELOADED================

Reactor Trip Auto Failure - PRELOADED

========EVENT 6 PRELOADED=================

Turbine Driven Auxiliary Feed Pump Auto start Failure - PRELOADED

========EVENT 7 ============================

DG A Failure / Loss of All AC Insert Malfunction (NE) NE01, Value = True

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 1 Page 5 of 21 Event

Description:

Pressurizer Level Instrument fails low Time Position Applicants Actions or Behavior Booth Operator Instructions:

Insert Malfunction (BB) BBLT0459_1, Value = 0

Insert Malfunction (BG) BGLCV0459, Value = True

When contacted, respond as I&C to investigate and repair the failed channel

When contacted, respond as EDO. Acknowledge the failed channel.

Indications Available:

T=0 min Annunciator 32B, PZR 17% HTRS OFF LTDN ISO Annunciator 39E, LTDN HX DISCH FLOW HILO OTO-BG-00001, Pressurizer Level Control Malfunction CRS Implement OTO-BG-00001, Pzr Level Control Malfunction Notes: Charging pumps that show signs of cavitation should be stopped and standby pumps should not be started without investigating The CCPs should not be run at less than 60 gpm total flow at anytime or less than 130 gpm total for greater than 30 minutes.

(Step 1) Check Charging Pumps - At least ONE Running-YES RO NCP is Running (BG HIS-3)

Note: Letdown isolates and Pressurizer control heaters will deenergize if the controlling level channel fails low.

(Step 2) Check for failed Pressurizer Level Indicator - YES RO

BB LI-459A (Step 3) TRANSFER Pressurizer Level Control Selector to RO Remove Failed Channel From Control

BB LS-459D

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 1 Page 6 of 21 Event

Description:

Pressurizer Level Instrument fails low Time Position Applicants Actions or Behavior (Step 4) CHECK Letdown- IN SERVICE - RNO 4a - 4c -

Perform the Following:

Slowly close BG HC-182

Throttle BG FK-124 for 8-13gpm seal injection RO

Ensure BG HC-182 is full closed

Ensure BG HIS-8152 and 8160 are open

Ensure BG HIS-459 and 460 are open o BG HIS-459 will NOT Open (Step 4) CHECK Letdown- IN SERVICE - NO RNO 4d - If letdown can NOT be established, THEN perform the following while attempting to restore normal letdown:

Ensure Orifice Isolation Valves(s) closed o BG HIS-8149AA, BA, and CA RO

Adjust seal injection to minimum required for RCP seal cooling to stabilize pressurizer level as necessary.

Establish excess letdown per OTN-BG-00001, Chemical and Volume Control System

Ensure BG HC-182 is full closed (Step 5) CHECK Pressurizer Heater Control Group C - ON RO

BB HIS-50 (Step 6) CHECK Pressurizer Level at or trending to program RO/BOP Level - NO (Step 7) CHECK Operable Pressurizer Level Channel - USED RO/BOP FOR RECORDER

BB LS-459E

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 1 Page 7 of 21 Event

Description:

Pressurizer Level Instrument fails low Time Position Applicants Actions or Behavior (Step 8) Review Applicable Tech Specs TS 3.3.1, Table 3.3.1-1, Item 9 CRS Condition M, M.1 Place channel in trip - 72 hrs

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 2 Page 8 of 21 Event

Description:

Letdown Isolation fails closed, place Excess Letdown In Service Time Position Applicants Actions or Behavior Booth Operator Instructions:

When contacted, respond as RP and Chemistry to acknowledge that Excess Letdown will be placed in Service.

When contacted, respond as Radwaste to support placing Excess Letdown in Service.

OTN-BG-00001, ADD 4, Operation of CVCS Letdown OTN-BG-(Step 5.2.1 & 5.2.2) Inform RP and Chemistry that Excess 00001, CRS ADD 4 Letdown is being placed in Service (Step 5.2.3) ENSURE Pressurizer Backup Heaters are in RO Manual Heater Operation per OTN-BB-00005, Pressurizer Pressure Control (Step 5.2.4) NOTIFY Radwaste Excess Letdown will be CRS directed to RCDT for approximately two (2) minutes to flush piping.

(Step 5.2.5 & 5.2.6) REQUEST Radwaste Operator place CRS RCDT in recirculation per RTN-HB-00100, Reactor Coolant Drain Tank Operation and maintain RCDT Level 22 -25%

(Step 5.2.7) Ensure Excess Letdown Heat Exchanger is supplied with CCW as indicated on either:

RO

EG FI-128, CCW TO RCS FLOW

EG FI-128, CCW TO RCS FLOW (Step 5.2.8) Ensure BG HIC-123, Excess LDHX Outlet Flow RO Ctrl, is CLOSED Perform the following to equalize boron concentration in 5.2.9 Excess Letdown header and RCS:

(Step 5.2.9.a and b.) ENSURE Radwaste Operator is ready to receive CRS Excess Letdown flow with sufficient volume in the RCDT.

OTN-BG-(Step 5.2.9.c) PLACE BG HIS-8143, Excess LDHX to RCDT/Seal 00001, RO ADD 4 Water HX, in RCDT.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 2 Page 9 of 21 Event

Description:

Letdown Isolation fails closed, place Excess Letdown In Service Time Position Applicants Actions or Behavior (Step 5.2.9.d) Open Either set of Reactor Coolant to Excess Letdown Hx valves with applicable control switches.

RO

Train A: BG HIS-8153A and BG HIS 8154A

Train B: BG HIS-8153B and BG HIS 8154B Note: Excess Letdown temperature should remain less than 175°F Caution: Initially opening BG HC-123 further than 20% in the following step could result in a sudden RCS pressure drop and subsequent adjustments to greater than 45% could result in temperature control problems.

(Step 5.2.9.e) Slowly Turn BG HC-123, Excess LDHX Outlet RO Flow Ctrl, to 20% Open to establish excess letdown flow.

(Step 5.2.9.f) Ensure BG TI-122, Excess LTDN HX Outlet RO Temp, does not exceed 175°F (Step 5.2.9.g) ENSURE Radwaste Operator maintains RCDT RO pressure less than 75 psig by controlling level BOP (Step 5.2.9.h) ENSURE RCP Seal Leak-Off is 1 to 5 gpm (Step 5.2.9.i) ENSURE RCP seal water leak-off flow is BOP acceptable per RCP Seal Leak-Off curve in OTN-BB-00003 (Step 5.2.10) After approximately two (2) minutes, DIRECT RO Excess Letdown flow to VCT as follows:

(Step 5.2.10.a) SLOWLY Turn BG HC-123, Excess LTDN HX RO Outlet Flow CTRL, to CLOSED to secure Excess Letdown flow.

RO (Step 5.2.10.b) ENSURE BG HC-123 is CLOSED (Step 5.2.10.c) Select VCT on BG HIS-8143, Excess LTDN HX CRS to RCDT/Seal WTR HX.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 2 Page 10 of 21 Event

Description:

Letdown Isolation fails closed, place Excess Letdown In Service Time Position Applicants Actions or Behavior (Step 5.2.10.d) ENSURE OPEN either set of RCS to Excess letdown RO

Train A: BG HIS-8153A and BG HIS 8154A

Train B: BG HIS-8153B and BG HIS 8154B (Step 5.2.11) NOTIFY Radwaste Excess Letdown flow is RO directed to the VCT (Step 5.2.12) Request Radwaste to secure recirculation of the RO RCDT per RTN-HB-00100, RCDT Operations.

(Step 5.2.13) Ensure Excess Letdown Temp does not exceed RO 175° on BG TI-122 BOP (Step 5.2.14) ENSURE RCP Seal Leak-Off is 1 to 5 gpm (Step 5.2.15) ENSURE RCP seal water leak-off flow is BOP acceptable per RCP Seal Leak-Off curve in OTN-BB-00003 (Step 5.2.16) UNLOCK and OPEN BG8482, CVCS VCT Seal RO Water IN ISO.

SIM OPS When contacted OPEN BG8482 Insert Remote Function (BG) BG8482TASTEM, Value = 100 (Step 5.2.17) UNLOCK and CLOSE BG8484, CVCS Seal RO Water Hx Out Dnstrm ISO.

SIM OPS When contacted CLOSE BG8484 Insert Remote Function (BG) BG8484TASTEM, Value = 0 (Steps 5.2.18 & 5.2.19) Log Valves in the Locked Component RO Deviation List of ODP-ZZ-00004, Locked Component Control

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 2 Page 11 of 21 Event

Description:

Letdown Isolation fails closed, place Excess Letdown In Service Time Position Applicants Actions or Behavior RO (Step 5.2.20) Restore Pressurizer Backup Heaters to AUTO (Step 5.2.21) NOTIFY RP Excess Letdown is in service and its RO flowpath.

At the Discretion of the Lead Examiner Move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 3 Page 12 of 21 Event

Description:

Power Range Channel Fails Low Time Position Applicants Actions or Behavior Booth Operator Instructions:

Power Range Channel Fails Low

Insert Malfunction (SE) SEN0042, Value=0

Respond as the WWM and/ or EDO if contacted about the failed instrument

Respond as I&C if contacted about the failed instrument Indications Available:

78 A PR CHANNEL DEV 78 B PR UPPER DETECTOR FLUX DEV 78 C PR LOWER DETECTOR FLUX DEV 82 A PR OVER PWR ROD STOP OTO-SE-00001, Nuclear Instrument Malfunction T= 25 min CRS Implement OTO-SE-00001, Nuclear Instrument Malfunction (Step 1) Check Power Range Nuclear Instruments - NORMAL RNO

a. Ensure Rod Control in MANUAL RO/BOP b. If any MFW Reg Bypass Valve is being used, place in MANUAL and Control SG Levels - NO

c. GO to Attachment A, Power Range Instrument Malfunction Att. A CRS/BO (Step A1) Stop Any Main Turbine Load Changes P

(Step A2) Maintain RCS Tavg within 1.5°F of Tref Using RO Manual Control Rods (Step A3) Check the following permissives in the correct state BOP

P-7, P-8, P-9, P-10 (Step A4) SELECT an Operable Channel on NIS Recorder RO

SE NR-45

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 3 Page 13 of 21 Event

Description:

Power Range Channel Fails Low Time Position Applicants Actions or Behavior (Step A5) BYPASS the malfunctioning Power Range Channel by selecting the Affected Channel at the NI Backpanels

a. On the Detector Current Comparator drawer

PLACE Upper Section switch to failed channel

PLACE Lower Section switch to failed channel\

CRS/

PLACE Rod Stop Bypass switch to failed channel BOP

Place Power Mismatch Byp switch to failed channel

b. On the Comparator and Rate drawer, PLACE Comparator Channel Defeat switch to the failed channel

c. Ensure the following Annunciators are extinguished:

78A, 78B, 78C, 82A (Step A6) Check Rod Control - IN AUTO RNO CRS/RO When RCS Tavg/Tref are equal AND rods werer in AUTO prior to the event, THEN PLACE Rod Control in AUTO (Step A7) CHECK any Steam Generator Level Being -

BOP Controlled by the MFW Reg Valve Bypass Valves - NO CRS/RO (Step A8) Check Reactor Power - GREATER Than 10%

(Step A9) Trip the Protective Bistable for the Failed Channel BOP Per Attachment D

Remove Control Power Fuses for the Failed channel RO (Step A10) Check Reactor Power Greater than 75% - YES (Step A11) Verify QPTR Every 12 Hours Per OSP-SE-0003, CRS/RO Quadrant Power Tilt Ratio

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev.2 Event # 3 Page 14 of 21 Event

Description:

Power Range Channel Fails Low Time Position Applicants Actions or Behavior (Step A12) Record Any of the Following in the Control Room Log:

CRS/BO

Permissives are in the correct state P

Any fuses that have been pulled (Step A13) Place Inoperable Power Range Channel in the CRS EOSL (Step A14) Review Applicable Tech Specs TS 3.3.1, Table 3.3.1-1, Item 2.a Condition D, Trip w/i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TS 3.3.1, Table 3.3.1-1, Item 2.b Condition V, Trip w/i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TS 3.3.1, Table 3.3.1-1, Item 3 Condition E, Trip w/i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CRS TS 3.3.1, Table 3.3.1-1, Item 6 Condition E, Trip w/i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TS 3.3.1, Table 3.3.1-1, Item 18. b,c,d,e, Condition S and T, verify interlock in correct state for existing conditions in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CRS (Step A15) Direct I& C to Repair Failed Channel At the Discretion of the Lead Examiner Move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 4, 5, and 6 Page 15 of 21 Event

Description:

Earthquake/ Loss of Offsite Power/ NB02 Trip/ ATWS / TDAFP fails to start Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed by the Lead Examiner enter EVENT #4, Quakey 09.lsn

Respond as the EDO and Power System Supervisor if contacted about the Loss of Offsite Power. Inform the crew that due to a fault on the grid, offsite power will not be available for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

IF contacted, respond as secondary operator and investigate the TDAFP not starting and after 5 minutes report no obvious problems with the TDAFP.

Indications Available:

T=50 86 A LO FLOW & P8 RX TRIP 98 A R SPCTRM SSE EXCEED E-0, Reactor Trip or Safety Injection CRS Implement E-0, Reactor Trip or Safety Injection (Steps 1-4 are immediate action steps)

Critical Manually Trip the reactor from the control room following CREW Task failure to Auto trip.

E-0 (Step 1) Check Reactor Trip Rod Bottom Lights - NO Reactor Trip and Bypass Breakers - NO RO Neutron Flux - Lowering RNO - MANUALLY TRIP REACTOR - Reactor Trips (Step 2) Check Turbine Trip BOP Turbine Stop Valves - Closed (Step 3) Check Power to AC Emergency Buses At least One Emergency Bus - Energized BOP Both Emergency Buses - Energized - NO RNO - Try to restore power to deenergized AC emergency bus Attempt to start B DG - Cannot be started

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 4, 5, and 6 Page 16 of 21 Event

Description:

Earthquake/ Loss of Offsite Power/ NB02 Trip/ ATWS / TDAFP fails to start Time Position Applicants Actions or Behavior (Step 4) Check SI Status Actuated - YES Manually Actuate SI (If not actuated)

Check both Trains of SI Actuated - NO RO LOCA Sequencer ANN 30A - Lit LOCA Sequencer ANN 31A - Lit - NO SB069 SI Actuate Red Light - Lit Solid RNO - SI Train B not actuated due to loss of power to NB02, and cannot be actuated.

(Step 5) Perform Attachment A, Automatic Action Verification, RO/BOP while continuing with this procedure E-0 Att A (Step A1) Check Charging Pumps - Both CCPs running RO/BOP Only CCP A Running due to Loss of Power to NB01 (Step A2) Check SI and RHR Pumps - All running RO/BOP A Train Only (Step A3) Check ECCS Flow - BIH flow indicated RO/BOP A Train Only (Step A4) CHECK ESW Pumps - BOTH RUNNING RO/BOP A Train Only (Step A5) CHECK CCW Alignment:

RO/BOP A Train Only (Step A6) CHECK Containment Cooler Fans - RUNNING IN RO/BOP SLOW SPEED A Train Only

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 4, 5, and 6 Page 17 of 21 Event

Description:

Earthquake/ Loss of Offsite Power/ NB02 Trip/ ATWS / TDAFP fails to start Time Position Applicants Actions or Behavior (Step A7) CHECK Containment Hydrogen Mixing Fans -

RO/BOP RUNNING IN SLOW SPEED A Train Only E-0 Att A (Step A8) CHECK If Containment Spray should Be Actuated:

RO/BOP NO RO/BOP (Step A9) CHECK If Main Steamlines Should Be Isolated (Step A10) CHECK ECCS Valves - PROPER EMERGENCY RO/BOP ALIGNMENT A Train Only RO/BOP (Step A11) CHECK Containment Isolation Phase A RO/BOP (Step A12) CHECK SG Blowdown Isolation (Step A13) CHECK Both Trains of Control Room Ventilation RO/BOP Isolation RO/BOP (Step A14) CHECK Containment Purge Isolation (Step A15) NOTIFY CRS of the following:

Unanticipated Manual actions taken.

RO/BOP

Failed Equipment status

Attachment A, Automatic Action Verification, completed E-0, REACTOR TRIP OR SAFETY INJECTION E-0 BOP (Step 6) Check Generator Output Breakers - Open

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 4, 5, and 6 Page 18 of 21 Event

Description:

Earthquake/ Loss of Offsite Power/ NB02 Trip/ ATWS / TDAFP fails to start Time Position Applicants Actions or Behavior E-0 (Step 7) Check Feedwater Isolation Main Feedwater Pumps - Tripped BOP Main Feedwater Reg Valves - Closed Main Feedwater Reg Bypass Valves - Closed Feedwater Isolation Valves - Closed Critical Establish a > 355,000 lbm/hr Auxiliary Feedwater flow rate Task CREW to the Steam Generators before SG level of < 10% Wide Range (dryout) occurs.

(Step 8) Check AFW Pumps BOP MD AFW Pumps - Both Running - NO TD AFW Pump - NOT RUNNING - MUST BE STARTED (Step 9) Check AFW Valves - Proper Alignment BOP MD AFP Flow Control Valves - Throttled BOP (Step 10) Check Total AFW Flow > 355,000 lbm/hr At Step 10 of E-0 or at the Discretion of the Lead Examiner Move to Event #7.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 7 Page 19 of 21 Event

Description:

Loss of All AC Time Position Applicants Actions or Behavior SIM SIM Simulator Operator: Enter Loss of the A DG (NE01)

ECA-0.0, Loss of All AC Power ECA-0.0 CRS Implements ECA-0.0 Loss of All AC Power (Step 1) Check Reactor Trip RO Reactor Trip and Bypass Breakers - NO Neutron Flux - Lowering (Step 2) Check Turbine Trip BOP All Turbine Stop valves - CLOSED (Step 3) Check if RCS is Isolated

PZR PORVs -CLOSED RO

Letdown Isolation valves - CLOSED

RCS to Excess Letdown HX valves - CLOSED

Reactor Head Vent valves - CLOSED BOP (Step 4) Check AFW Flow - Greater than 355,000 LBM/HR (Step 5) Try to restore Power to Any AC Emergency Bus

Both DGs Tripped and Loss of Offsite Power

Check AC emergency Buses - AT LEAST ONE ENERGIZED - NO BOP

RNO - OPEN Control Room Cabinet doors using EOP Add 20, Control Room Cabinet Door List (this will require a CUE from instructor informing Another operator will perform EOP Add 20)

RNO - GO TO Step 6

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 7 Page 20 of 21 Event

Description:

Loss of All AC Time Position Applicants Actions or Behavior ECA-0.0 (Step 6) Place the Following Equipment Switches in Pull-to-Lock:

CCPs

SI Pumps

RHR Pumps RO

Containment Spray Pumps

CCW Pumps

Containment Cooler Fans

Motor Driven AFW Pumps

Control Room AC Unit

Class 1E Electrical Equipment Room AC (Step 7) RESTORE AC Power CRS/BOP

All sources to restore power from offsite or Emergency Diesels are not available (Step 8) Locally Isolate RCP Seals using EOP Add 22, Local RO RCP Seal Isolation SIM Run Lesson RCP Seal Isolation.lsn SIM (Step 9) Check if CST is Isolated from HOTWELL

Place Hotwell Level Controllers in MANUAL and Zero BOP OUTPUT

Locally Close CST Makeup To Hotwell Isolation SIM SIM Insert Remote Function (AP) APV012TASTEM, Value =0 Step 10) Check SG Status

MSIVs and Bypass Valves - CLOSED

Main Feedwater Reg Valves- CLOSED BOP

Main Feedwater Reg Bypass Valves - CLOSED

Feedwater Isolation Valves - CLOSED

SG Blowdown Isolation Valves - CLOSED

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 3 rev. 2 Event # 7 Page 21 of 21 Event

Description:

Loss of All AC Time Position Applicants Actions or Behavior ECA-0.0 (Step 11) Check if Any SG is Faulted - NO BOP

GO To Step 12 BOP (Step 12) Check if SG Tubes are Intact - YES (Step 13) Check Intact SG Levels

Narrow range levels - > 7%

BOP

Control AFW flow to maintain narrow levels between 7% and 52%

SIM OP (Step 14) Check DC Bus Loads

Voltages and amps normal on all DC buses Resp RO

Engineering Consulted

Locally Check Security DG - RUNNING (Step 15) Check CST to AFP Suction Header Pressure -

BOP GREATER than 2.75 PSIG YES Critical Establish a cooldown of the RCS at less than 100 °F/hr CREW Task prior to RCP seal damage occurring.

(Step 16) Depressurize Intact SGs to 260 PSIG

Check SG narrow range levels > 7% in at least 1 SG

Dump Steam using SG ASDs in MANUAL to maintain cooldown rate in RCS Cold legs < 100 °F/HR BOP

Check RCS Cold leg temperatures > 275 °F

Check SG pressures < 260 PSIG

Manually Control SG ASDs to maintain SG pressures at 260 PSIG Once the crew has commenced a Cooldown or at the Discretion of the Lead Examiner - Terminate Scenario

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 4 rev 3 Op-Test No.: 2011301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Power, steady state, Middle of Core Life Turnover: The plant has been at the current power level for two (2) months. The crew has been requested to reduce Reactor Power to 90% to remove the A Condensate Pump from service due to problems with the suction strainer.

Event Malf. Event Event No. No. Type* Description 1 SRO (N) Reduce Power to 90% to remove Condensate Pump A from 10 min N/A RO (R) service BOP (N) 2 ABPT05 SRO (I) SG D Controlling Pressure Channel Fails Low (Tech Spec)

(20 min) 45 BOP (I) 3 BBPCV SRO (C) Pressurizer Spray Valve Drifts Open (20 min) 0455B_1 RO (C) 4 ABPV SRO (C) Atmospheric Steam Dump A Fails Open (Tech Spec)

(30 min) 0001_1 BOP (C) 5 SRO (M) Small Break LOCA Requiring Reactor Trip (Tech Spec)

BB (40 min) RO/BOP 002_A (M) 6 SRO (C) Large Break LOCA of 10000 gpm following Reactor Trip, requiring BB (50 min) RO (C) Safety Injection 002_A BOP (C) 7 SRO (I) Safety Injection fails to actuate Automatically, so Manual initiation (N/A) JINHBSI RO (I) required and then B Train LOCA Sequencer Fails to actuate BOP (I) components (PRELOADED)

NF039B 8 SRO (C) Upon receipt of SI Signal, EJ HV8811B loses power and A RHR NG02B (N/A) RO (C) Pump Trips (Integral to Loss of Emergency Recirc Capability)

EF2 (PRELOADED)

PEJ01A

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 4

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3

Scenario Event Description NRC Scenario 4 rev. 2 Callaway 2011 NRC Scenario #4 The plant has been at the current power level for two (2) months. The crew is directed to lower Reactor Power to 90% to remove Condensate Pump A from service.

After a power reduction has been observed, SG D controlling pressure channel fails low. The crew enters OTO-AE-00002, Steam Generator Water Level Control Malfunctions, and selects an operable steam flow channel. Tech Spec 3.3.2 is applicable.

After the plant has been stabilized, a single Pressurizer Spray Valve fails/drifts open. This causes pressurizer pressure to lower. The crew should enter OTO-BB-00006, Pressurizer Pressure Control Malfunction, to manually operate the pressurizer spray loop controller affected.

Tech Spec 3.4.1 many be entered to address RCS DNB conditions.

AB PV-0001, Atmospheric Steam Dump A fails open. The crew will enter OTO-AB-00001, Steam Dump Malfunction. The crew will be able to close the failed steam dump from the Control Room. Tech Spec 3.7.4 should be reviewed for the failed valve.

After Maintenance has been contacted to repair AB PV-0001, a small break LOCA of approximately 80 gpm initiates. The crew enters OTO-BB-00003, Excessive RCS Leakage, and maximizes charging to offset the leakage. The crew should determine that the leak rate is greater than 50 gpm and initiate a reactor trip. The CRS should determine that leakage is in excess of allowed per Tech Spec 3.4.13, RCS operational Leakage.

The crew enters E-0, Reactor Trip or Safety Injection. When the reactor is tripped the leak continues to increase to 10,000 gpm causing a Safety Injection Signal. The Automatic Safety Injection Signal (SIS) is overridden forcing the crew to manually actuate Safety Injection. Train B components will fail to actuate due to failure of the B LOCA Sequencer. The crew will continue in E-0 and transition to E-1, Loss of Primary or Secondary Coolant.

Upon receipt of the SIS, EJ HV-8811B loses power and RHR Pump A trips causing a loss of Emergency Recirculation capability. This will cause the crew to transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

The scenario can be terminated when the crew completes Step 7 of ECA-1.1, Loss of Emergency Coolant Recirculation, or at the discretion of the Chief Examiner.

Scenario Event Description NRC Scenario 4 rev. 2 Critical Tasks:

Event #3 CT - Manually Trip the Reactor from the control room when it is determined that RCS leakage is > 50 gpm Event #4 CT - Trip all RCPs such that the core does not uncover (RVLIS<55%) AND prior to commencing an operator controlled cooldown.

Event #5 CT - Manually actuate a Safety Injection before transitioning from E-0.

References OTG-ZZ-00004 OTG-ZZ-00004, Addendum 03 OTO-AB-00001 OTO-AE-00002 OTO-BB-00003 OTO-BB-00006 E-0 E-1 ECA-1.1

Scenario Event Description NRC Scenario 4 rev. 2 Scenario Setup Guide:

Establish the initial conditions of IC-161, MOL 100% power:

RCS boron concentration 960 ppm

CCP A 976 ppm minus 5 days

CCP B 986 ppm minus 15 days

Rod Control Bank D 215 steps, Other banks 228 steps

=======SCENARIO PRELOADS / SETUP ITEMS==========

RCS Large Break LOCA resulting in Safety Injection after reactor Trip

Insert Malfunction (BB) BB002_A to, Value = 10000, ramp = 1 min, conditional = jcrftr eq true Safety Injection Fails to Actuate in Auto

Insert Remote Function (SB) JINHBSI, Value = Both Sequencer B fails to actuate equipment as required

Insert Malfunction (NF) NF039B_1, value = step 0 Loss of power to EJ HV8811B following SI

Insert Remote Function (NG) NG02BEF2, Value = Open, conditional = jpplsia eq true RHR Pump A Trip

Insert Malfunction (EJ) PEJ01A, Value = True, delay = 5 minutes, conditional = jpplsia eq true

=======EVENT 2 ==============================

SG D Controlling Pressure Channel, ABPT545, fails to 0% over 15 sec

Insert Malfunction (AB) ABPT0545, Value = 0, ramp = 15 secs

=======EVENT 3 =============================

PZR Spray Valve, BBPCV0455B, fails open over 2 mins

Insert Malfunction (BB) BBPCV0455B_1, value = 1, ramp = 2 mins

=======EVENT 4 ==============================

A Atmospheric Steam Dump, AB PV-0001, fails open over 2 mins

Insert Malfunction (AB) ABPV0001_1, Value = 1, ramp = 2 mins

=======EVENT 5 ==============================

RCS Small Break LOCA requiring a Reactor Trip

Insert Malfunction (BB) BB002_A, Value = 80, ramp = 1 min

=======EVENT 6 PRELOADED===================

RCS Large Break LOCA resulting in Safety Injection / Insert after reactor is tripped SEE PRELOADS ABOVE

=======EVENT 7 PRELOADED===================

Safety Injection Fails to Actuate Automatically and sequencer fails to actuate SEE PRELOADS ABOVE

=======EVENT 8 PRELOADED===================

Loss of Power to EJ HV8811B and A RHR Pump Trips following SI SEE PRELOADS ABOVE

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 1 Page 5 of 27 Event

Description:

Reduce Power to 90% to remove A Condensate Pump From Service Time Position Applicants Actions or Behavior Upon Lead Examiner Cue Booth Operator Instructions Reduce Power to 90% to Remove A Condensate Pump from service Indications Available:

OTG-ZZ-00004, Power Operation, Addendum 03 Reduce CRS (Step 5.2) Direct the power reduction in Section 5.2 Power (Step 5.2.1) Perform the following in any order to prepare for RO lowering power:

(Step 5.2.1a) If needed, prior to beginning a load reduction, request I&C adjust NIS power coarse gains.

CRS/RO STEP HAS BEEN COMPLETED (Step 5.2.1b) Initiate Additional Actions Section 5.4 to prepare CRS for reducing power Addl CRS Section 5.4 items are complete through Step 5.4.1.g Actions (Step 5.4.1.e) Perform a Dilution/Boration Calculation for the RO anticipated change in power (Should be performed during turnover).

(Step 5.4.1.h) If directed by the SRO to energize Pressurizer RO Heaters

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 1 Page 6 of 27 Event

Description:

Reduce Power to 90% to remove A Condensate Pump From Service Time Position Applicants Actions or Behavior (Step 5.4.1.h1) Using the following hand switches, ENSURE at least one group of Pressurizer Back-up Heaters is ENERGIZED to equalize RCS and Pressurizer boron RO concentrations.

BB HIS-51A, PZR HTR B/U GROUP A, in CLOSE

BB HIS-52A, PZR HTR B/U GROUP B, in CLOSE (Step 5.4.1.h2) PLACE BB PK-455A, PZR PRESS MASTER RO CTRL, in MANUAL and LOWER to 40%.

(Step 5.4.1.h3) PLACE BB PK-455A, PZR PRESS MASTER RO CTRL, in AUTO.

Reduce CRS/RO (Step 5.2.2) Initiate Power Reduction as follows Power (Step 5.2.2.a) BORATE the RCS as required to support RO lowering power to the desired final load.

OTN-BG- (Attachment 8) Borate Mode of RMCS Operation 00002, 1. Place BG HS-26 , RCS M/U CTRL, in STOP Att. 8

2. Place BG HS-25, RCS M/U CTRL SEL, in BOR

3. RESET BG FY-110B, BA Counter, to 000

4. ENSURE BG-FY-110B is set to deliver the desired amount of boron

5. Place BG HS-26, RCS M/U CTRL, in RUN RO 6. When the desired amount of borated water has been added, PLACE BG HS-26, RCS M/U CTRL, in STOP.

7. If required, PERFORM the following:

a. Place BG HS-25, RCS M/U CTRL SEL, in AUTO

b. Place BG HS-26, RCS M/U CTRL, in RUN

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 1 Page 7 of 27 Event

Description:

Reduce Power to 90% to remove A Condensate Pump From Service Time Position Applicants Actions or Behavior (Step 5.2.2.b) ENSURE SE HS-9, ROD BANK AUTO/MAN RO SEL, is in MAN.

(Step 5.2.2.c) IF using MANUAL turbine control, INITIATE load BOP reduction by slowly turning LOAD LIMIT SET potentiometer counter-clockwise.

(Step 5.2.2.d) IF using AUTOMATIC turbine control, PERFORM the following:

Using EHC Panel DECREASE LOAD pushbutton, SLOWLY LOWER load until the following conditions are met:

LOAD LIMIT LIMITING light OFF

DECREASE LOADING RATE OFF light LIT

LOADING RATE LIMIT %/MIN 1/2 light LIT BOP TURN LOAD LIMIT SET potentiometer fully clockwise.

SELECT DECREASE LOADING RATE ON SELECT desired loading rate.

Use 0.05 for 3%/hr.

Use 0.166 for 10%/hr.

Use 1/2 for 30%/hr.

Using EHC Panel DECREASE LOAD pushbutton, INITIATE load reduction.

(Step 5.2.3) WHEN the desired power level is achieved PERFORM the following:

CREW

Set Turbine Controls for steady state operation

Borate/Dilute as needed to maintain power level

Insert/withdraw rods as needed to maintain power level (Step 5.2.4) ENSURE annunciator 77A, REACT DEV, setpoint RO is 1.0°F.

At the Discretion of the Lead Examiner Move to the next Event

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 2 Page 8 of 27 Event

Description:

SG D Pressure Channel Failure Low Time Position Applicants Actions or Behavior Booth Operator Instructions

Insert Malfunction (AB) ABPT0545, Value = 0, ramp = 15 secs

When contacted, respond as I&C. Acknowledge the request to investigate the instrument/channel failure.

When contacted, respond as EDO. Acknowledge entry into the OTO.

Indications Available:

T = 10 ANN 111D, SG D FLOW MISMATCH OTO-AE-00002, Steam Generator Water Level Control Malfunctions CRS Implement OTO-AE-00002, SG Water Level Control Malfunctions BOP (Step 1) Check SG FW Flow Channels Normal (Step 2) Check SG Steam Flow Channels Normal - NO BOP RNO - Select operable steam flow channel on SG D using AB FS-542C BOP (Step 3) Check SG Level Channels Normal (Step 4) Check SG Pressure Channels Normal - NO BOP RNO - Select operable steam flow channel on SG D using AB FS-542C (Step 5) Check SG NR level within one of the following:

BOP Trending to 45-55% or between 45-55%

(Step 6) Review Attachment A, Effects of Instrument Failure BOP Steam Press Transmitter AB PT-545 compensates Steam Flow Transmitter AB FT-543

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 2 Page 9 of 27 Event

Description:

SG D Pressure Channel Failure Low Time Position Applicants Actions or Behavior (Step 7) Review Applicable Tech Specs-Refer to Attachment F CRS TS 3.3.2, Item 1.e, Condition D, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TS 3.3.2, Item 4.e, Condition D, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CRS (Step 8) Perform Notifications per ODP-ZZ-00001 Addendum 13 CRS (Step 9) Direct I&C to trip bistables for failed channel CRS (Step 10) Place inoperable channel in EOSL CRS (Step 11) Initiate actions to repair failed channel At the Discretion of the Lead Examiner Move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 3 Page 10 of 27 Event

Description:

Pressurizer Spray Valve Drifts Open Time Position Applicants Actions or Behavior Booth Operator Instructions

Insert Malfunction (BB) BBPCV0455B_1, value = 1, ramp = 2 mins

If Work Control is contacted, report investigation and repair of BB PCV-455B will be initiated.

When contacted as EDO, acknowledge entry into the OTO.

Indications Available:

T = 20 ANN 33C, PZR PRESS LO HTRS ON OTO-BB-00006, Pressurizer Pressure Control Malfunction CRS Implement OTO-BB-00006, PZR Pressure Cont Malfunction (Step 1) Check PZR Pressure Indicator - Failed - NO RO RNO - Go to Step 17 RO (Step 17) Check PZR Pressure less than 2235 (Step 18) Check Both PZR Spray Valves - Closed - NO RNO: Place affected PZR Spray Loop Controller in Manual RO and Close the Valve: BB PK-455B Energize PZR Backup Heaters as necessary (Step 19) Check PZR Pressure Greater than 2250 - NO RO RNO - Go to Step 21 (Step 21) Check PZR Pressure Between 2225 and 2250 -

RO Continue with next Step when pressure is between 2225 and 2250

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 3 Page 11 of 27 Event

Description:

Pressurizer Spray Valve Drifts Open Time Position Applicants Actions or Behavior (Step 22) Check PZR Pressure Master Controller - Controlling RO in Auto RO (Step 23) Check PZR Heaters - Aligned for Automatic Control (Step 24) Check PZR Spray Loop Controllers - in Auto RO (Note - BB PK-455B will be left in manual due to failure)

RO/BOP (Step 25) Check PZR PORVs - in Auto RO/BOP (Step 26) Check Both PZR PORV Block Valves - Open CRS (Step 27) Review Applicable Tech Specs Refer to Attachment J TS 3.4.1, Condition A, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (DNB <2223 psig)

At the Discretion of the Lead Examiner Move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 4 Page 12 of 27 Event

Description:

Atmospheric Steam Dump A Fails Open Time Position Applicants Actions or Behavior Booth Operator Instructions

Insert Malfunction (AB) ABPV0001_1, value = 1, ramp = 2 mins

If Work Control is contacted, report investigation and repair of AB PV-0001 will be initiated.

When contacted as EDO, acknowledge entry into the OTO.

When contacted as Count Room Tech, acknowledge opening and closing of ASD.

Indications Available:

T= 25 ANN 109F, SG PORV OPEN OTO-AB-00001, STEAM DUMP MALFUNCTION CRS Implement OTO-AB-00001, Steam Dump Malfunction (Step 1) Check Reactor Power - Less Than 100%

RO RNO - Reduce Main Turbine load to maintain less than 100%

Reactor Power BOP (Step 2) Check at least one SG ASD - Failed Open (Step 3) Place the affected SG ASD controller in manual and BOP close the valve: AB PIC-1A (SG A)

(Step 4) Notify Count Room Tech of opening and closing times CRS/BOP of the SG ASD CRS (Step 5) Go to Step 12 CRS (Step 12) Initiate actions to repair the failed ASD

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 4 Page 13 of 27 Event

Description:

Atmospheric Steam Dump A Fails Open Time Position Applicants Actions or Behavior (Step 13) Review Tech Spec 3.7.4 CRS Condition A, Restore Operable within 7 days At the Discretion of the Lead Examiner Move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 5 Page 14 of 27 Event

Description:

RCS Small Break LOCA Requiring Plant Shutdown Time Position Applicants Actions or Behavior Booth Operator Instructions

Insert Malfunction (BB) BB002_A, value = 80, ramp = 1 min Indications Available:

T = 35 ANN 61A, PROCESS RAD HIHI min ANN 61B, PROCESS RAD HI OTO-BB-00003, RCS EXCESSIVE LEAKAGE CRS Implement OTO-BB-00003, RCS Excessive Leakage (Step 1) Check if PZR Level can be Maintained - Level Stable or Rising - NO RNO - Perform the following:

1) Establish maximum charging flow from one pump RO 2) IF pressurizer level cannot be maintained - CLOSE Letdown Orifice isolations and RHR Cleanup to Letdown HX Flow Control valve BG HC-128

3) IF pressurizer level cannot be maintained - CLOSE RCS Letdown to Regen HX Isolation valves BG HIS-459 and BG HIS-460 RO (Step 2) Check Pressurizer Level - stable or rising CRS/RO (Step 3) Evacuate non-essential personnel in Containment RO (Step 4) Check if VCT level can be maintained (Step 5a) Determine if Plant Trip is required: Determine leak size and rate of change using any of the following:

RO/BOP

Use trends of VCT level and PZR level

Compare charging and letdown flows

Utilize GD SG17 or T4 SG17

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 3 Event # 5 Page 15 of 27 Event

Description:

RCS Small Break LOCA Requiring Plant Shutdown Time Position Applicants Actions or Behavior (STEP 5b) Leak rate - less than 50 GPM - NO RO/BOP RNO - Manually trip the Reactor and go to E-0, Reactor Trip or Safety Injection NOTE to Evaluator: After scenario complete ask CRS what the Tech Spec for initial RCS leakage during this scenario:

TS 3.4.13 RCS Operational Leakage Condition B - Pressure boundary leakage exists Be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Mode 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Critical Manually Trip the Reactor from the control room when Task CREW it is determined that RCS leakage is > 50 gpm Once the reactor is tripped Events #6, 7 and 8 will be initiated.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 16 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior Booth Operator Instructions-ensure the following initiate after reactor is tripped.

Insert Malfunction (BB) BB002_A to, value = 10000, ramp = 1 min, conditional

= jcrftr eq true (PRELOADED)

Insert Remote Function (SB) JINHBSI, Value = Both (Auto SI Failure)

(PRELOADED)

Insert Malfunction (NF) NF039B_1, value = step 0 (PRELOADED)

Insert Remote Function (NG) NG02BEF2, Value = Open, conditional = jpplsia eq true (PRELOADED)

Insert Malfunction (EJ) PEJ01A, Value = True, delay = 5 mins, conditional =

jpplsia eq true (PRELOADED)

If contacted as Primary OT to locally check breaker for EJ HV8811B (NG02BEF2), inform CR that breaker is tripped. If asked to close breaker, report that breaker will not close.

If contacted as Secondary OT to check A RHR pump breaker (NB0101),

inform CR that breaker has an instantaneous OC lockout relay dropped.

E-0, Reactor Trip or Safety Injection CRS Implement E-0, Reactor Trip or Safety Injection (Step 1) Check Reactor Trip Rod Bottom Lights - All Lit RO Reactor Trip and Bypass Breakers - Open Neutron Flux - Lowering (Step 2) Check Turbine Trip BOP Turbine Stop Valves - Closed

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 17 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior (Step 3) Check Power to AC Emergency Buses BOP At Least One Emergency Bus - Energized Both Emergency Buses - Energized (Step 4) Check SI Status:

Actuated or Required Manually Actuate SI (If not actuated)

RO Check both Trains of SI Actuated LOCA Sequencer ANN 30A - Lit LOCA Sequencer ANN 31A - Lit SB069 SI Actuate Red Light - Lit Solid RNO - Check if SI is required - YES Auto SI is inhibited, SI must be manually initiated Critical Manually actuate a Safety Injection before transitioning CREW Task from E-0.

(Step 5) Perform Attachment A, Automatic Action Verification, RO/BOP while continuing with this procedure E-0 Att A RO/BOP (Step A1) Check Charging Pumps - Both CCPs running RO/BOP (Step A2) Check SI and RHR Pumps - All running NOTE: A RHR pump trips 5 minutes after SI - may not be tripped when Step A2 is performed. If not caught at this time, it should be identified later.

RO/BOP (Step A3) Check ECCS Flow - BIH flow indicated RO/BOP (Step A4) CHECK ESW Pumps - BOTH RUNNING

EF HIS-55A

EF HIS-56A

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 18 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0 Att A RO/BOP (Step A5) CHECK CCW Alignment:

CCW Pumps - ONE RUNNING IN EACH TRAIN

Red Train:

EG HIS-21 or EG HIS-23

Yellow Train:

EG HIS-22 or EG HIS-24

CCW Service Loop Supply and Return valves for one operating CCW pump - OPEN

EG ZL-15 AND EG ZL-53 OR

EG ZL-16 AND EG ZL-54

OPEN CCSW To RHR HX valves:

EG HIS-101

EG HIS-102

CLOSE Spent Fuel Pool HX CCW Outlet Valves:

EG HIS-101

EG HIS-102

CLOSE Spent Fuel Pool HX CCW Outlet Valves:

EC HIS-11

EC HIS-12

STOP Spent Fuel Pool Cooling Pump(s):

EC HIS-27

EC HIS-28

RECORD The Time Spent Fuel Pool Cooling Pump Secured

MONITOR Time Since CCW Flow Isolated to SFP HX LESS THAN 4 HOURS (Step A6) CHECK Containment Cooler Fans - RUNNING IN RO/BOP SLOW SPEED

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 19 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0 Att A

GN HIS-9

GN HIS-17

GN HIS-5

GN HIS-13 (Step A7) CHECK Containment Hydrogen Mixing Fans -

RO/BOP RUNNING IN SLOW SPEED

GN HIS-2

GN HIS-4

GN HIS-1

GN HIS-3 RO/BOP (Step A8) CHECK If Containment Spray should Be Actuated:

CHECK the following:

Containment pressure - GREATER THAN 27 PSIG OR

GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 27 PSIG OR

Annunciator 59A CSAS LIT OR

Annunciator 59B CISB - LIT

Containment Spray Pumps -

EN HIS-3

EN HIS-9

ESFAS status panels CSAS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

ESFAS status panels CISB sections:

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 20 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0 Att A

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

ESFAS status panels CISB sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

STOP all RCPs RO/BOP (Step A9) CHECK If Main Steamlines Should Be Isolated:

CHECK for any of the following:

Containment pressure - GREATER THAN 17 PSIG OR

GN PR-934 indicates containment pressure - HAS BEEN GREATER THAN 17 PSIG OR

Steamline pressure - LESS THAN 615 PSIG OR

AB PR-514 or AB PR-535 indicates steamline pressure

- HAS BEEN LESS THAN 615 PSIG

CHECK MSIVs and Bypass valves - CLOSED (Step A10) CHECK ECCS Valves - PROPER EMERGENCY RO/BOP ALIGNMENT

ESFAS status panels SIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A11) CHECK Containment Isolation Phase A:

ESFAS status panels CISA sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 21 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0 Att A RO/BOP (Step A12) CHECK SG Blowdown Isolation:

ESFAS status panels SGBSIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT (Step A13) CHECK Both Trains of Control Room Ventilation RO/BOP Isolation:

ESFAS status panels CRVIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A14) CHECK Containment Purge Isolation:

ESFAS status panels CPIS sections:

SA066X WHITE lights - ALL LIT

SA066Y WHITE light - ALL LIT RO/BOP (Step A14 RNO) Manually ACTUATE CPIS:

SA HS-11

SA HS-15 IF CPIS damper(s) are NOT closed, THEN manually CLOSE damper(s) as necessary RO/BOP (Step A15) NOTIFY CRS of the following:

Unanticipated Manual actions taken.

Failed Equipment status

Attachment A, Automatic Action Verification, completed.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 22 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0, REACTOR TRIP OR SAFETY INJECTION E-0 BOP (Step 6) Check Generator Output Breakers - Open (Step 7) Check Feedwater Isolation Main Feedwater Pumps - Tripped BOP Main Feedwater Reg Valves - Closed Main Feedwater Reg Bypass Valves - Closed Feedwater Isolation Valves - Closed (Step 8) Check AFW Pumps BOP MD AFW Pumps - Both Running TD AFW Pump - Running if Necessary (Step 9) Check AFW Valves - Proper Alignment BOP MD AFP Flow Control Valves - Throttled TD AFP Flow Control Valves - Full Open BOP (Step 10) Check Total AFW Flow > 355,000 lbm/hr (Step 11) Check PZR PORVs and Spray Valves PZR PORVs - Closed RO PZR PORVs - Both in AUTO PORV Block Valves - Both Open Normal PZR Spray Valves - Closed (Step 12) Check if RCPs should be Stopped RCPs - Any Running ECCS Pumps - At least One Running RO RCS Pressure - Less than 1425 psig YES - Stop all RCPs RNO - Go To Step 13 Critical Trip all RCPs such that the core does not uncover Task CREW (RVLIS<55%) AND prior to commencing an operator controlled cooldown.

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 23 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior E-0 (Step 13) Check RCS Temperatures RO RCPs Running - Tavg 557 Deg F No RCPs Running - Tcold 557 Deg F (Step 14) Check if any SG is Faulted:

RO/BOP Any SG pressure lowering uncontrollably Any SG completely depressurized (Step 15) Check if SG Tubes are intact:

Levels in all SGs - none rising in uncontrolled manner

SG Steamline N16 radiation - Normal BOP

Condenser air removal radiation - Normal

SG blowdown and sample radiation - Normal

SG ASD radiation - Normal

TDAFW pump exhaust radiation - Normal (Step 16) Check if RCS is Intact

Containment pressure - Normal - NO RO/BOP

Containment normal sump level - Normal - NO

Containment radiation - Normal - NO RNO - Go to E-1, Loss of Reactor or Secondary Coolant E-1, LOSS OF REACTOR OR SECONDARY COOLANT Initiate CSF Monitoring E-1 (Step 1) Check if RCPs should be stopped:

Any running RO/BOP ECCS pumps - at least one running RCS pressure - less than 1425 psig Stop all RCPs BOP (Step 2) Check if any SG is Faulted - NO BOP (Step 3) Check intact SG levels

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 24 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior

Narrow range levels greater than 7% [25%]

Control feed flow to maintain levels between 7% and 52%

BOP (Step 4) Check secondary radiation - Normal

Perform the following:

Perform EOP Addendum 11 Direct Chem to periodically sample all SGs for activity Direct RP to survey steamlines in Area 5 as necessary

Check unisolated secondary radiation monitors:

SG sample radiation SG ASD radiation TDAFW pump exhaust radiaiton

Secondary radiation - Normal BOP/RO (Step 5) Check PZR PORVs and block valves:

Power to block valves - Available

PZR PORVs - Closed

Block valves - Both Open BOP/RO (Step 6) Check is ECCS flow should be reduced:

RCS subcooling - greater than 30°

Secondary heat sink:

Narrow range level in at least on SG greater than 7%

Total feed flow to SGs greater than 355,000 lbm/hr

RCS pressure - stable or rising

PZR level - greater than 9%

RNO - Go to Step 7 BOP/RO (Step 7) Check if Containment Spray should be stopped:

(NOT IN SERVICE)

RNO - Go to Step 8

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 25 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior BOP/RO (Step 8) Check if RHR pumps should be stopped:

Check RCS pressure:

Greater than 325 psig Stable or rising

Any running with suction aligned to RWST

Reset SI if necessary

Stop RHR pumps and place in standby BOP/RO (Step 9) Check SG and RCS pressures:

Check pressure in all SGs - stable or rising

Check RCS pressure - stable or lowering BOP/RO (Step 10) Check if Diesel Generators should be stopped:

AC emergency buses - energized by offsite power

Reset SI if necessary

Perform EOP Addendum 8 NOTE: BOOTH OPERATOR: Use the following to complete Add 08 Addendum 8 Actions Use the following to close the Boric Acid Transfer Pump /

BGHV8104 / CRDM Cooling Fans B&D breakers:

Insert Remote Function (NG) KNG1AHF4, Value = Closed Insert Remote Function (NG) KNG2AAF4, Value = Closed Insert Remote Function (NG) KNG4CPF2, Value = Closed Insert Remote Function (NG) JGNC01B, Value = Closed Insert Remote Function (NG) JGNC01D, Value = Closed

Stop any unloaded DG and place in standby BOP/RO (Step 11) Check Ultimate Heat Sink - Normal - YES BOP/RO (Step 12) Initiate evaluation of plant status

Check Cold Leg recirculation capability

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 26 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior Train A - Available - NO (RHR pump tripped)

Train B - Available - NO (No power to EJ HV8811B)

RNO - If at least one train of cold leg recirculation capability can not be verified, Go to ECA-1.1, Loss of Emergency Coolant Recirculation ECA-1.1, Loss of Emergency Coolant Recirculation NOTE: Plant Computer System TOC SUMPBLK is available for indication of sump blockage.

ECA-1.1 BOP/RO (Step 1) Check ECCS pumps - not affected by sump blockage:

CCPs

SI Pumps

RHR Pumps (Step 2) Check emergency coolant recirculation equipment -

BOP/RO Available - NO RNO - Try to restore at least one train while continuing with subsequent actions.

BOP/RO (Step 3) Reset SI if necessary BOP/RO (Step 4) Reset SI (RWST) switchover signal (Step 5) Check containment cooler fans - Running in slow speed:

GN HIS-9 BOP/RO GN HIS 17 GN HIS 5 GN HIS-13 BOP/RO (Step 6) Check RWST level - greater than 6%

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011301 Scenario # 4 rev. 2 Event # 6, 7, 8 Page 27 of 27 Event

Description:

Large Break LOCA with Auto SI and B Sequencer Failure Loss of Power to EJ HV8811B and A RHR Pump Trip Time Position Applicants Actions or Behavior ECA-1.1 (Step 7) Determine Containment Spray requirements (suction BOP/RO from RWST)

The scenario can be terminated at the discretion of the Lead Examiner

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 2/7/2011 Examination Level: RO Operating Test Number: (NRC)

Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Hydrogen Recombiner Power Settings (A1) Conduct of Operations R, N 2.1.25 (3.9): Ability to interpret reference materials, such as graphs, curves, tables, etc.

Written by NRC*

Calculate RCS Boration Required to Reach Cold Shutdown Conditions (A2) Conduct of Operations R, N 2.1.37 (4.3): Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Review Pump Run Data and Determine if Acceptance Criteria are Met.

(A3) Equipment Control R, N 2.2.12 (3.7): Knowledge of surveillance procedures.

Determine Radiological Requirements for HRA Entry (A4) Radiation Control R, D 2.3.12 (3.2): Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Emergency Procedures/Plan N/A N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

RO ADMIN JPM

SUMMARY

A1 This is a New JPM. The candidate will determine Hydrogen Recombiner Settings based on data and tables given. (RO)

A2 This is a New JPM. The candidate will be given a copy of the Curve Book and will have to determine the amount of Boron required to place the plant in Mode 5. (RO)

A3 This is a New JPM. The candidate will be given a copy of the data recorded on Attachment 4 of OSP-EN-P001B, Train B Containment Spray Pump Comprehensive Test data Sheet. The candidate will be required to complete the calculations and determine whether the acceptance criteria is satisfied.(RO)

A4 This is a Bank JPM from the Kewaunee Nuclear Power Plant. Given dose rates and dose limits as established by Radiation Protection, the candidate will be required to determine stay time allowed to perform hanging of WPA in a High Radiation Area. (RO)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 2/7/2011 Examination Level: SRO Operating Test Number: (NRC)

Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Time to Boil for a Loss of Shutdown Cooling

- Computer not Available (A5) Conduct of Operations R, N 2.1.25 (3.9): Ability to interpret reference materials, such as graphs, curves, tables, etc.

Written by NRC*

Determine Shift Staffing (Fatigue Rule)

(A6) Conduct of Operations R, N 2.1.5 (3.9): Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Review Completed Surveillance (ESF Power Availability

/ Offsite Power Availability)

(A7) Equipment Control R, N 2.2.42 (4.6): Ability to recognize system parameters that are entry-level conditions for Technical Specifications Determine Reportability Requirements for Overexposure (A8) Radiation Control R, D 2.3.4 (3.7): Knowledge of radiation exposure limits under normal and emergency conditions Make a Protective Action Recommendation (A9) Emergency R, N 2.4.44 (4.4): Knowledge of emergency plan protective Procedures/Plans action recommendations NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

SRO ADMIN JPM

SUMMARY

A5 This is a New JPM. Following a Loss of Shutdown Cooling, the candidate will determine the Time to Boil based on data and tables given. (SRO)

A6 This is a new JPM. Given the schedules of six (6) different Operators, the candidate will be required to choose which ones will be able to man the shift on a certain day and not violate the Fatigue Rule. Guidance will be provided in APA-ZZ-00905, Limitations of Callaway Plant Staff Working Hours. (SRO)

A7 This is a new JPM. The candidate will be given completed Attachments 1 and 2 of OSP-NB-00001, Class 1E Electrical Source Verification. The candidate will have to determine that NK01 is inoperable determine when it must be returned to opearable status per Tech Specs. (SRO)

A8 This is a Bank JPM. Given an Overexposure event in the plant, the candidate will be required to determine whether the event is reportable, who to call, and the time limit which the call must be made.(SRO)

A9 This is a new JPM. Given a set of conditions and the appropriate Emergency Response procedure forms, the candidate will prepare the EIP-ZZ-00102, Att. 4, Control Room Offsite Notification Form, and Form CA2843, PAR Flowchart, in accordance with EIP-ZZ-00102, Emergency Implementing Actions to make a Protective Action Recommendation (PAR). EIP-ZZ-00212, Protective Action Recommendations will also be provided. (SRO)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __CALLAWAY__________________ Date of Examination: ___02/07/11___

Exam Level: RO (only)/SRO(I)/SRO(U) Operating Test No.: ______________

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 001 Control Rod Drive System N, S, A 1 Perform Partial Rod Movement test (When rods are moved inwards, continuous rod insertion will require tripping the reactor)

b. 006 Emergency Core Cooling System D, S, EN 2 Lower Accumulator Level

c. 003 Reactor Coolant Pump System (RCPS) N, S, L, A 4-P Start A RCP (Trip on high vibration)

d. 059 Main Feedwater System N, C, E 4-S FWIS Bypass Operation (EOP Addendum 29 - simulate in CR)

e. 026 Containment Spray System (CSS) N, S, EN, A 5 Swap Containment Spray Pump suction to Containment Sump; (CS Pump B Sump Suction Valve cannot be opened, must secure pump.)

f. 064 Emergency Diesel Generator N, L, S, A 6 Manually start Diesel Generator (Both EDGs fail to auto start following loss of offsite power.

Perform Step 5 of ECA-0.0 to restore power)

g. 073 Process Radiation Monitoring System D, S, P, A 7 Radiation Monitor source check (Repeat from 11/07 exam)

h. 029 Containment Purge System D, S, P 8 Re-establish Containment Purge After Isolation (Repeat from 6/09 exam)

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 061 Auxiliary Feedwater System D, E, EN 4-S Reset TDAFW Pump Mechanical Overspeed Trip

j. APE 068 Control Room Evacuation D, R, E, L 8 Control Room Inaccessibility - BOP actions. (URO-AEO15057J)

k. 062 A.C. Electrical Distribution N, E, A 6 Switch NK01 power supply from Swing Charger NK25 to Normal Charger NK21 (NK21 DC Breaker CB2 trips open on transfer; operator re-aligns NK01 to NK25)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 (6) / 4-6 (6) / 2-3 (3)

(C)ontrol room (1) / (1) / (0)

(D)irect from bank 9 (5) / 8 (4) / 4 (2)

(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (3)

(EN)gineered safety feature (3) / (3) / 1 (2)(control room system)

(L)ow-Power / Shutdown 1 (3) / 1 (3) / 1 (1)

(N)ew or (M)odified from bank including 1(A) 2 (6) / 2 (6) / 1 (3)

(P)revious 2 exams 3 (2) / 3 (1) / 2 (0) (randomly selected)

(R)CA 1 (1) / 1 (1) / 1 (1)

(S)imulator (7) / (6) / (3)

ITEMS ABOVE IN RED WRITTEN BY NRC

JPM Summary Sim A This is a new JPM. The candidate will start the task by performing steps of OSP-SF-00002, Control Rod Partial Movement, for Control Bank D. When the Control Rods are inserted for the test, they continue to insert, forcing the candidate to take the ALTERNATE PATH and trip the Reactor based on continuous rod motion.

(RO/SROI/SROU)

Sim B This is a Bank JPM. The candidate will be given a high level in one of the SI Accumulators. The candidate will lower level to within the appropriate band.

(RO/SROI/SROU)

Sim C This is a New JPM. The simulator will be set up in a Low Mode. The candidate will start an RCP. The RCP will at first run normally, then develop high vibration, forcing the candidate to take actions per the ALTERNATE PATH and Trip the RCP. (RO/SROI)

Sim D This is a New JPM. This JPM will be done at the Control Room back panels. The candidate will be given direction to perform EOP Addendum 29. The Candidate will successfully identify all components required in the Control Room and Simulate Bypassing the Feedwater Isolation System. (RO/SROI)

Sim E This is a New JPM. The simulator will be set up with conditions that will require the candidate to Swap Containment Spray Pump suction to the Containment Sump. When the candidate gets to the B Containment Spray system, the B Containment Spray Suction valve cannot be opened, forcing the candidate to take the ALTERNATE PATH by stopping the B Containment Spray Pump. (RO/SROI/SROU)

Sim F This is a New JPM. The simulator will be set up with a Loss of Offsite power. Both EDGs fail to Auto Start, but then must be started manually - ALTERNATE PATH. Once the Diesel Generators are started, the operator verifies adequate cooling to the EDGs and sees that the A ESW Pump is not running and must start it. ALTERNATE PATH (RO/SROI)

Sim G This is a Bank JPM repeated from the 2007 License Exam. The candidate will be required to perform a Source Check at the RM-11 panel using OSP-SP-00001, Radiation monitors Source Check. The Source Check will fail (CUE by Examiner) forcing the candidate to take an ALTERNATE PATH to address Actions required by the FSAR.

Sim H This is a Bank JPM. The candidate will re-establish Containment Purge following a Containment Purge Isolation Signal. Repeat from the 2009 exam. (RO ONLY)

Sim I This is a Bank JPM. In the Plant, the candidate will simulate how to Reset the TDAFW Pump Mechanical Overspeed Trip. (RO/SROI)

Sim J This a Bank JPM. In the Plant, the candidate will locate and demonstrate how to manually/locally close SG Atmospheric Steam Dumps A and C, EGHV0061 and BGHV8105. (RO/SROI/SROU)

Sim K This is a New JPM. In the Plant, the candidate will simulate aligning NK01 from the swing charger NK25 to the Normal Charger NK21 per OTN-NK-00001. When the Normal Charger NK21 is attempted to be put in service, its output trips and the operator must place NK25 back in service. (RO/SROI/SROU)

ES-301-5 Facility: Callaway Date of Exam: 2/7/2011 Operating Test No.: Rev. 4 2011301 A E Scenarios P V 1 2 3 4 T M P E O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)

T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX 0 0 NOR 0 1 4 2 SROU-1 I/C 12 35 MAJ 47 2 1 TS 13 2 2 RX 0 0 NOR 1 1 1 8 2 SROU-2 I/C 12 24 35 67 MAJ 47 5 3 1 TS 13 2 2 RX 0 0 NOR 1 1 1 SROU-3 I/C 23 6 46 2 78 MAJ 5 1 1 TS 24 3 2 5

RX 0 1 NOR 1 1 1 SROI-1 I/C 12 23 9 4 5 46 78 MAJ 47 5 3 2 TS 24 3 2 5

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301-5 Facility: Callaway Date of Exam: 2/7/2011 Operating Test No.: Rev. 4 2011301 A E Scenarios P V 1 2 3 4 T M P E O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)

T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX 0 1 NOR 1 1 2 1 SROI-2 I/C 24 12 24 11 4 5 35 67 MAJ 6 47 5 4 2 TS 13 2 2 RX 0 1 NOR 1 1 1 13 4 SROI-3 I/C 34 12 23 57 5 46 78 MAJ 6 47 5 4 2 TS 24 3 2 5

RX 1 1 1 NOR 1 1 1 SROI-4 I/C 23 36 36 10 4 45 78 MAJ 6 47 5 4 2 TS 34 2 2 RX 0 1 NOR 1 1 1 7 4 RO-1 I/C 12 24 5 67 MAJ 47 5 3 2 TS 0 0 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301-5 Facility: Callaway Date of Exam: 2/7/2009 Operating Test No.: Rev. 4 2011301 A E Scenarios P V 1 2 3 4 T M P E O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)

T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX 1 1 1 NOR 0 1 RO-2 I/C 36 36 6 4 78 MAJ 47 5 3 2 TS 0 0 RX 1 1 1 NOR 0 1 4

RO-3 I/C 36 36 6 78 MAJ 47 5 3 2 TS 0 0 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301-5 SRO ATC BOP Scenario #

I4 I2 I3 1 I2 I3 I4 3 U1 R1 R2 3 U2 I1 R3 3 I3 I4 I2 4 U3 R2 R1 4 I1 R3 U3 4 Standby scenario used as needed

ES-301 Competencies Checklist Form ES-301-6 Facility: Callaway Date of Examination: 2/7/2011 Operating Test No.:

2011301 APPLICANTS SRO RO BOP Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 1, 3 1, 2, 1-5, 1, 3, 2, 4, 3, 4, Events and 2-7 1-7 1-7 2-7 4-6 4, 5, 7 4-6 3-7 5, 6 6, 7 1-5 7

Conditions Comply With and Use 1, 2, 1, 3 1-5, 1, 3, 2, 4, 3, 4, 1-7 1-7 1-7 1-7 4, 5, 3-7 1-5 Procedures (1) 4-7 7

7 4-6 5, 6 6, 7 Operate Control 1, 2, 1, 3 1-5, 1, 3, 2, 4, 3, 4, N/A N/A N/A N/A 4, 5, 3-7 1-5 Boards (2) 4-6 7

7 4-6 5, 6 6, 7 Communicate and 1, 2, 1, 3 1-5, 1, 3, 2, 4, 3, 4, 1-7 1-7 1-7 1-7 4, 5, 3-7 1-5 Interact 4-7 7

7 4-6 5, 6 6, 7 Demonstrate Supervisory Ability 1-7 1-7 1-7 1-7 N/A N/A N/A N/A N/A N/A N/A N/A (3)

Comply With and Use 3, 4 2, 4 1, 3 2, 3 N/A N/A N/A N/A N/A N/A N/A N/A Tech. Specs. (3)

Instructions:

Circle the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

NUREG-1021, Revision 9

ML110660642

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