Text

2016-06 Draft Operating Test
	ML16158A461
Person / Time
Site:	Callaway
Issue date:	06/01/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16158A461 (262)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Rev 0 Facility: Callaway Date of Examination: 5/23/2016 Examination Level: RO Operating Test Number: 2016-1 Administrative Topic Type Code* Describe activity to be performed (see Note)

Conduct of Operations 2.1.26 (3.4) Knowledge of industrial safety procedures S, D A1 JPM: Respond to an Industrial Injury 2.1.25 (3.9) Ability to interpret reference materials such as Conduct of Operations graphs, curves, tables, etc.

R, M A2 JPM: Determine RV Venting Time (EOP ADD 33) 2.2.37 (3.6) Ability to determine operability and/or availability Equipment Control of safety related equipment.

R, D, P A3 JPM: Determine Amperage Limits for 480 VAC Safety Related busses.

2.3.7 (3.5) Ability to comply with radiation work permit Radiation Control requirements during normal or abnormal conditions.

R, M A4 JPM: Determine entry requirements for HRA in the RCA.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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)

The JPMs from the 2013 exam were randomly selected by placing 4 slips of paper labeled A1.a 2013 through A4 2013 in a hardhat. A2 2013was drawn from the hardhat.

NUREG-1021, Revision 10 Page 1 of 2

ES-301 Administrative Topics Outline Form ES-301-1 Rev 0 A1 This is a BANK JPM. The parent JPM (Set 4 RSA-1) has not been used on an ILT NRC Exam administered at Callaway between 2004 and 2014. This JPM is based on the event that occurred in the switchyard in 2013. The candidate will contact the Staff for Life Helicopter Service and complete page 5 of CA1073 Control Room Checklist for Injuries at Callaway.

A2 This is a MODIFIED JPM. The parent JPM was used on the 2009 ILT NRC exam. The candidate is to determine the maximum RV Venting time using EOP Addendum 33. A marked up FR-I.3 will be provided.

A3 This BANK JPM was used on the 2013 ILT NRC Exam. The applicant will review planned maintenance which requires load centers NG01 and NG03 to be cross-connected. The applicant will be required to determine what equipment can be started on the cross-connected load centers without overloading the buses.

A4 This is a MODIFIED JPM from the 2013 Palo Verde ILT NRC Exam. This JPM requires the RO to review given conditions and determine dose received for a task, required authorization for that dose, and posting requirements for the area where the task will be performed; in accordance with APA-ZZ-01004, Radiological Work standards, and HDP-ZZ-01500, Radiological Postings.

NUREG-1021, Revision 10 Page 2 of 2

ES-301 Administrative Topics Outline Form ES-301-1 Rev 0 Facility: Callaway Date of Examination: 5/23/2016 Examination Level: SRO Operating Test Number: 2016 - 1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.37 (4.6) Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity R, D management A5 JPM: Review a QPTR Calculation 2.1.25 (4.2) Ability to interpret reference materials such as Conduct of Operations graphs, curves, tables, etc R, M A6 JPM: Determine RV Venting Time (EOP ADD 33) 2.2.37 (4.6) Ability to determine operability and/or availability Equipment Control of safety related equipment R, D, P A7 JPM: Determine Amperage Limits for 480 VAC Safety Related busses 2.3.4 (3.7) Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions R, M A8 JPM: Select Volunteer for Emergency Exposure 2.4.44 (4.4) Make a Protective Action Recommendation Emergency Procedures/Plan R, M JPM: Determine the Protective Action A9 Recommendation (PAR)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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)

No JPMs from the last 2 SRO exams (including the 2013 re-exam) were selected for this exam. JPM A7 was on the 2013 RO exam. This JPMs was randomly selected by placing 4 slips of paper labeled A1.a 2013 through A4 2013 in a hardhat. A2 2013was drawn from the hardhat.

NUREG-1021, Revision 10 Page 1 of 2

ES-301 Administrative Topics Outline Form ES-301-1 Rev 0 A5 This is a BANK JPM. The parent JPM (SRO-MAS-04-A006J) has not been used on an NRC Exam administered at Callaway between 2004 and 2014. The SRO candidate will be required to review a QPTR calculation and determine that an error occurred in the calculation and determine the QTPR is not within the limits of TS 3.2.4 and that required actions A.1, A.2, A.3, A.4, A.5 AND A.6 must be performed.

A6 This is a MODIFIED JPM. The parent JPM was used on the 2009 ILT NRC exam. The candidate is to determine the maximum RV Venting time using EOP Addendum 33. A marked up FR-I.3 will be provided.

A7 This BANK JPM was used on the 2013 ILT NRC Exam. The applicant will review planned maintenance which requires load centers NG01 and NG03 to be cross-connected. The applicant will be required to determine what equipment can be started on the cross-connected load centers without overloading the buses.

A8 This is a MODIFIED JPM. The parent JPM (SRO-RER-03-A203J) was used on the 2009 ILT NRC exam. The SRO candidate will be given a set of conditions and the appropriate procedures in an emergency radiological situation. The SRO candidate, acting as the Emergency Coordinator, will determine which volunteer is the most eligible to receive an emergency dose.

A9 This is a MODIFIED JPM. The parent JPM (SRO-RER-02-A031J(TC)) was used on the 2011 ILT NRC exam. The applicant will be assigned the task of determining the Protective Action Recommendation (PAR) within the allotted amount of time. Upon completion of this JPM the operator will have determined the PAR to be Evacuate 5 miles all sectors and Evacuate 10 miles sectors J, H, and G.

NUREG-1021, Revision 10 Page 2 of 2

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A1 JPM Bank No: Set 4 RSA-1 KSA No: 2.1.26 Revision Date: 02/13/2016 KSA Rating: 3.4 Job

Title:

URO/SRO Duty: Administrative Task

Title:

Respond to an Industrial Injury 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:

Evaluator Signature: Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab Plant Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

APA-ZZ-00835, REPORTING AND PROCESSING OF ACCIDENTS, INJURIES, AND ILLNESSES CA1073, CONTROL ROOM CHECKLIST FOR INJURIES AT CALLAWAY Tools / Equipment: none Page 1 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: A contractor was connecting grounds in the Switchyard when an electrical fault occurred CA1073 Control Room Checklist for Injuries at Callaway is in progress.

The MERT has been activated and dispatched to the scene.

10 minutes ago the MERT Leader reported that a helicopter was needed to transport the individual to University of Missouri Medical Center.

The Callaway County Ambulance Service was contacted 3 minutes ago.

Initiating Cues: The Shift Manager directs you to complete Section 5 of CA1073 and contact the Staff for Life Helicopter Service.

Note: This JPM needs to be performed in an area where the applicant can simulate phone communications Task Standard: Upon completion of this JPM, the applicant will have simulated contacting the Staff for Life Helicopter Service and completed page 5 of CA1073 Control Room Checklist for Injuries at Callaway in accordance with the key Start Time:

Stop Time:

Page 2 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. CONTACT the Staff For Respond with Staff for Applicant simulated dialing S U Life Helicopter Service Life Helicopter Service 800-325-5400.

via 800-325-5400. after phone call is simulated.

Step 5.1.1 Comments:

2. DELIVER the message in When asked for time of Applicant filled in the S U the right hand column of arrival of the helicopter information from page 5 of page 5 of CA1073 respond 30 minutes CA1073 Control Room Control Room Checklist from now Checklist for Injuries at for Injuries at Callaway Callaway and Comments When asked for you communicated this Step 5.1.2 name respond Tom information to the Smith helicopter service, See attached KEY for correct information.

3. NOTIFY Security to Respond as security Applicant contacted S U perform the following: security with the information and requests.

5.2.1. ESTABLISH landing zone (helicopter) ESTABLISH landing zone Comments using frequency 155.340. (helicopter) using frequency 155.340.

5.2.2. PROVIDE Security Officer to escort PROVIDE Security Officer ambulance to loading to escort ambulance to zone. loading zone.

5.2.3. INFORM Security INFORM Security of of estimated time of estimated time of arrival of arrival of the helicopter. the helicopter.

Step 5.2 Page 3 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

4. IF the patient(s) is Applicant determined this S U contaminated: step is NOT applicable since the injured person is 5.3.1. NOTIFY Security NOT contaminated to provide contamination Comments emergency kit.

5.3.2. ENSURE Radiation Protection personnel meet the ambulance at the loading zone.

Step 5.3

5. IF the patient was Applicant determined this S U exposed to a hazardous step is NOT applicable material, ENSURE a since the injured person copy of the MSDS for the was NOT exposed to hazard is provided to the hazardous material Comments helicopter crew.

Step 5.4

6. WHEN the helicopter Applicant determined S U arrives on site, section 7.0 needs to be COMPLETE Section 7.0. completed when helicopter arrives on site.

Comments

7. JPM IS COMPLETE S U Comments Page 4 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: A contractor was connecting grounds in the Switchyard when an electrical fault occurred CA1073 Control Room Checklist for Injuries at Callaway is in progress.

The MERT has been activated and dispatched to the scene.

10 minutes ago the MERT Leader reported that a helicopter was needed to transport the individual to University of Missouri Medical Center.

The Callaway County Ambulance Service was contacted 3 minutes ago.

Initiating Cues: The Shift Manager directs you to complete Section 5 of CA1073 and contact the Staff for Life Helicopter Service.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A2 JPM Bank No: RA2 2009 ILT NRC Exam KSA No: 2.1.25 Revision Date: 02/13/2016 KSA Rating: 3.9 Job

Title:

URO/SRO Duty: Administrative Task

Title:

Determine Reactor Vessel Venting Tims 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

EOP Addendum 33, Determine Reactor Vessel Venting Time, Rev 1 Tools / Equipment: Calculator Page 1 of 4

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The crew is responding to plant conditions using FR-I.3, Response to Voids in the Reactor Vessel.

The following conditions exist:

Containment pressure is 3.8 psig.

Containment Temperature is 167°F.

Containment Hydrogen Concentration is 2.3%.

RCS Pressure is 1925 psig.

Initiating Cues: The CRS now directs you to determine RV Venting Time in accordance with EOP Addendum 33.

Task Standard: Upon completion of this JPM, the applicant will have determined RV Venting time to be between 1.72 and 1.84 minutes.

Start Time:

Stop Time:

Page 2 of 4

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. S U PROVIDE CANDIDATE CANDIDATE REVIEWED WITH MATERIAL AND ADMIN JPM INITIAL ALLOW TIME FOR CONDITIONS AND Comments:

REVIEW OF WORK TO INITIATING CUES BE PERFORMED

2. S U DETERMINE See KEY CANDIDATE CONTAINMENT AIR DETERMINED VOLUME AT STP = A CONTAINMENT AIR Comments:

VOLUME IS BETWEEN 6 6 STEP 1 2.4 X 10 AND 2.5 X 10 3

FT

3. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE MAXIMUM DETERMINED THAT HYDROGEN VOLUME BETWEEN 16800 AND 3 Comments THAT CAN BE VENTED 1.7500 FT CAN BE

=B VENTED STEP 2

4. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE DETERMINED THAT HYDROGEN FLOW HYDROGEN FLOW RATE Comments RATE AS A FUNCTION IS BETWEEN 9500 AND OF RCS PRESSURE = C 9750 FT3/MINUTE USING FIGURE 1 Step 3

5. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE MAXIMUM DETERMINED THAT THE VENTING TIME MAXIMUM VENTING Comments TIME IS BETWEEN 1.72 STEP 4 AND 1.84 MINUTES

6. JPM IS COMPLETE S U Comments Page 3 of 4

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The crew is responding to plant conditions using FR-I.3, Response to Voids in the Reactor Vessel.

The following conditions exist:

Containment pressure is 3.8 psig.

Containment Temperature is 167°F.

Containment Hydrogen Concentration is 2.3%.

RCS Pressure is 1925 psig.

Initiating Cues: The CRS now directs you to determine RV Venting Time in accordance with EOP Addendum 33.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A3 JPM Bank No: A3, Rev 2 from the 2013 ILT NRC KSA No: 2.2.37 exam Revision Date: 02/13/2016 KSA Rating: 3.6 Job

Title:

URO/SRO Duty: Administrative Task

Title:

Ability to determine operability and/or availability of safety related equipment: Determine amperage limits for 480 VAC safety related busses when cross-connecting for maintenance.

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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

OTN-NG-00001, Class 1E 480 VAC Electrical System, Rev 16 Tools / Equipment: none Page 1 of 8

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The plant is at 100% power.

NG01 local ammeter indicates 712 amps.

NG03 local ammeter indicates 344 amps.

The following Train A equipment is NOT in service:

DG Vent Supply Fan A, CGM01A

Air Compressor A, CKA01A

Fuel Pool Clg Pump A, PEC01A

CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to prepare cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.

Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.

Provide your answer on the cue sheet below:

Task Standard: Upon completion of this JPM, the Applicant reported that the following equipment could be started:

CGM01A, DG Vent Sply Fan A SGK04A, Ctrl Rm A/C Unit A PEC01A, Fuel Pool Clg Pmp A Start Time:

Stop Time:

Page 2 of 8

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD EXAMINER NOTE:

JPM refers to OTN-NG-00001, Section 5.10. This section will not be performed by the Applicant but does contain information that the Applicant will need to perform the assigned task. Though not expected to be performed by the Applicant, Section 5.10 steps will be contained in JPM A3.

1. S U Applicant providedd working copy of OTN-NG-00001 Comments:

2. S U Refers to Section 5.10, Applicant referred to Cross-Connecting Load Section 5.10, Cross-Centers NG01 And Connecting Load Centers Comments:

NG03 NG01 And NG03 Page 3 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

3. S U The following cautions If asked if the impact of Applicant read caution apply when cross- starting current on and understood that total connecting load center cycling loads has been amperage drawn by both Comments NG01 and NG03, due to considered, respond load centers shall not transformer and power that engineering has exceed 1200 amps on supply limitations: reviewed starting local ammeters

Cross Tie Breaker current for NG01 and NG0116 is only NG03 loads and allowed to be closed determined that it has to repair failed or no impact on degraded limitations for current equipment loading when cross

Closing NG0116 connecting NG01 and makes all 4 NG03.

degraded bus voltage channels for NB01 inoperable per T/S B 3.8.9, and requires entry into T/S ACT 3.3.5.B.1 and T/S ACT 3.8.1.F

Total amperage drawn by both load centers shall not exceed 1200 amps on local ammeters

Total allowed load of 1200 amps includes cycling loads

No major loads should be added without referring to Attachment 1 to account for additional load Caution prior to Step 5.10.1

4. S U Initiate an EOSL item Step will not be performed for inoperability of all 4 channels for Bus NB01 Comments degraded voltage with reference to applicable T/S:

Step 5.10.1 Page 4 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

5. S U Check load centers Given in Initiating Cue NG01 and NG03 are energized Comments Step 5.10.2

6. S U Using local ammeters, Local ammeter values ensure combined total given in Initiating Cue load amperage for Comments NG01 and NG03 is less than 1200 amps Step 5.10.3

7. S U The bus transfer is a Note not read due to not break-before-make being applicable to operation which will assigned task Comments cause a momentary power loss of approximately 8 to 10 cycles. Alarms may actuate and breakers may trip. Attachment 1 provides load lists to determine effects on plant operation.

Note prior to Step 5.10.4

8. S U If removing the NG01 Step is not applicable feeder from service, perform the following:

Comments Step 5.10.4

9. S U If removing the NG03 Step is not applicable feeder from service, perform the following:

Comments Step 5.10.5 Page 5 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

10. S U Check loads on NG01 Step is not applicable and NG03 for breaker trips than may have Comments occurred during the transfer Step 5.10.6

11. S U Using local ammeters, Step is not applicable check combined total load amperage for Comments NG01 and NG03 is less than 1200 amps Step 5.10.7

12. S U If necessary to start Applicant determined loads on NG01 or loads that could be NG03, ensure toal load started - see JPM Step Comments will not exceed 1200 15 amps, by referring to Attachment 1 Step 5.10.8

13. S U If necessary, start loads Step is not applicable on NG01 and NG03 Comments Step 5.10.9

14. S U Refers to Attachment 1, Applicant referred to Load Centers NG01 & Attachment 1, Load NG03 Loads Centers NG01 & NG03 Comments Loads Page 6 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

15. S U Using Att 1 and Applicant determined that provided cues, CGM01A, SGK04A and determines what PEC01A can be started Comments equipment can be but that CKA01A could started on NG01 and not be started, as based NG03 after they are on the following cross-connected calculations:

Current amperage on both busses is 712 + 344

= 1056 (Provided in cue)

Margin for starting additional equipment is 1200 - 1056 = 144 Amperage for equipment not running would be:

CGM01A-130 -

Acceptable

CKA01A-276 - Not Acceptable

PEC01A-132 -

Acceptable

SGK04A Acceptable Acceptable equipment to start would be CGM01A OR PEC01A OR SGK04A.

Information is provided to the CRS (Examiner)

16. JPM IS COMPLETE S U Comments Page 7 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The plant is at 100% power.

NG01 local ammeter indicates 712 amps.

NG03 local ammeter indicates 344 amps.

The following Train A equipment is NOT in service:

DG Vent Supply Fan A, CGM01A

Air Compressor A, CKA01A

Fuel Pool Clg Pump A, PEC01A

CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to prepare cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.

Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.

Provide your answer on the cue sheet below:

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A4 JPM Bank No: Based on PVNGS 2013 KSA No: 2.3.7 Revision Date: 03/08/2016 KSA Rating: 3.5 Job

Title:

URO/SRO Duty: Radiation Exposure Control Task

Title:

Determine entry requirements for in the RCA Completion Time: 12 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

RWP 160501ROUTINE HDP-ZZ-01500, RADIOLOGICAL POSTINGS Survey CA-M-20160203-2, CA-M-20160308-1 Tools / Equipment: none Page 1 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: In room 1322 below the platform grating, a label needs to be replaced on penetration P39 Initiating Cues: Using the survey map and RWPs provided determine the following:

1. RWP to be used

2. Required Dosimetry

3. Dose Alarm

4. Dose Rate Alarm

5. Protective Clothing Requirements

6. Required RP briefing and/or authorization Task Standard: Upon completion of the JPM the applicant will have identified the following:

RWP to be used 160501ROUTINE Required Dosimetry OSLD and Electronic Dosimeter Dose Alarm 11 mRem Dose Rate Alarm 100 mRem Full set of Protective Clothing in Contaminated Areas.

Protective Clothing OR Requirements Partial PC's allowed for tours, inspections, and work below grating as allowed by RP.

Required RP briefing and/or Contact RP for Survey Prior to Entry (CRP) authorization Start Time:

Stop Time:

Page 2 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. S U Applicant determined Applicant determines RWP 160501ROUTINE is RWP to be used to be used Comments:

2. S U Applicant determined Applicant determines OSLD and Electronic required Dosimetry Dosimeter is required Comments:

3. S U Applicant determines Applicant determined Dose Alarm Dose Alarm is 11 mRem Comments:

4. S U Applicant determined Applicant determines Dose Rate Alarm 100 Dose Rate Alarm mRem Comments

5. Applicant determined S U Protective Clothing Requirements are Full set of Protective Clothing in Comments Applicant determines Contaminated Areas.

Protective Clothing OR Requirements Partial PC's allowed for tours, inspections, and work below grating as allowed by RP.

6. S U Applicant determined the Applicant determines need Contact RP for Required RP briefing Survey Prior to Entry and/or authorization Comments (CRP)

7. JPM IS COMPLETE Page 3 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE KEY RWP to be used 160501ROUTINE Required Dosimetry OSLD and Electronic Dosimeter Dose Alarm 11 mRem Dose Rate Alarm 100 mRem Full set of Protective Clothing in Contaminated Areas.

Protective Clothing OR Requirements Partial PC's allowed for tours, inspections, and work below grating as allowed by RP.

Required RP briefing and/or Contact RP for Survey Prior to Entry (CRP) authorization KEY Page 4 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: In room 1322 below the platform grating, a label needs to be replaced on penetration P39 Initiating Cues: Using the survey map and RWPs provided determine the following:

1. RWP to be used

2. Required Dosimetry

3. Dose Alarm

4. Dose Rate Alarm

5. Protective Clothing Requirements

6. Required RP briefing and/or authorization Provide answers below RWP to be used Required Dosimetry Dose Alarm Dose Rate Alarm Protective Clothing Requirements Required RP briefing and/or authorization

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A5 JPM No: SRO-MAS-04-A006J KSA No: 2.1.37 Revision Date: 02/13/2016 KSA Rating: 4.6 Job

Title:

URO/SRO Duty: Nuclear Instrumentation Task

Title:

Review a QPTR Calculation 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

OSP-SE-00003, .QUADRANT POWER TILT RATIO, REVISION 22 CURVE BOOK TABLE 11-1, REVISION 257 Tools / Equipment: Calculator Page 1 of 7

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: Callaway Plant is at MOL, 100% power with the indicated axial flux difference (AFD) equal to 0%.

Control Room annunciators 78B, 78C, and 78F are not operable.

All power range nuclear instruments are operable.

The Control Room Plant Computer System is not available for use.

Initiating Cue: The RO has performed a QPTR calculation per OSP-SE-00003, Quadrant Power Tilt Ratio Calculation, using the NI detector currents provided.

The RO has submitted the results to you for a second check.

CHANNEL Itop Ibottom N41 185.8 195.2 N42 163.2 190.8 N43 191.6 198.3 N44 188.2 196.1 Perform the second check of the ROs calculations and submit the data you have entered in OSP-SE-00003 to the Examiner.

Curve Book Table 11-1 has been provided Task Standard: Upon completion of this JPM, the applicant will have reviewed a manual QPTR calculation with a final QPTR tolerance of +/- 0.01 and determined that N44 Lower detector is greater than 1.02 and entered T/S 3.2.4.A, and entered the data on Attachment 2.

Start Time:

Stop Time:

Page 2 of 7

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. Obtain a verified working CANDIDATE OBTAINED S U copy of OSP-SE-00003, A COPY OF OSP-SE-QPTR Calculation. 00003, QUADRANT Comments:

POWR TILT RATIO CALCULATION PROVIDE CANDIDATE WITH COPY OF OSP-SE-00003 and Table 11-1

2. Review Precautions and If asked All Precautions Applicant reviewed S U Limitations and Limitations are Precautions and satisfied. Limitations Comments:

STEP 4.0

3. Review Prerequisites If asked Prerequisites Applicant reviewed S U are satisfied. Prerequisites STEP 5.0 Comments:

4. Record each power Using the data sheet S U range upper and lower provided the Operator current output on located the correct upper Comments:

Attachment #1. and lower current meters for the power range STEP 6.2.1 detectors and verified the values in the correct area of OSP-SE-00003, Attachment 1.

5. Use Table 11.1 from the Applicant used Table 11-1, S U Curve Book to obtain the AFD Calibration value current values for the Table, AFD = 0%, to Comments:

upper and lower record power range upper detectors. AFD = 0% and lower current values.

values should be used.

Applicant identified Lower STEP 6.2.2 Detector N44 100%

Detector Current was recorded incorrectly as 193.4 instead of 192.7 SEE KEY Page 3 of 7

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

6. Divide each upper and Applicant divided each S U lower detector current by upper and lower detector its 100%, 0% AFD power current by its 100% power, Comments:

detector current value 0% AFD detector current and enter it in the value and entered it as the normalized detector normalized detector current for each channel. current for each channel.

STEP 6.2.3 The calculated values should be as shown in the Attachment 1 KEY.

Values within +/- 0.01 on each calculation are acceptable.

Applicant identified Lower Detector N44 Normalized Detector Current was calculated incorrectly

7. Add the normalized Applicant added up the S U upper detector currents normalized upper detector and divide by four (4) to currents and divided by 4 Comments:

derive the upper detector to derive the upper normalized current detector normalized average and record it in current averages and Attachment #1. recorded it in Attachment

1.

STEP 6.2.4 The calculated values should be as shown in the Attachment 1 KEY.

Values within +/- 0.001 on each calculation are acceptable.

Page 4 of 7

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

8. Add the normalized lower Applicant added up the S U detector currents and normalized lower detector divide by four (4) to currents and divided by 4 Comments:

derive the lower detector to derive the lower normalized current detector normalized averages and record it in current averages and Attachment #1. recorded it in Attachment

1.

STEP 6.2.5 The calculated values should be as shown in the Attachment 1 KEY.

Values within +/- 0.001 on each calculation are acceptable.

Applicant identified Lower Detector Average Normalized Current was calculated incorrectly

9. NOTE: The QPTR should The applicant calculated S U be calculated as two the QPTR, to two (2) significant digits to the significant digits to the Comments:

right of the decimal point. right of the decimal point.

Note before 6.2.6

10. Divide each upper Applicant divided each S U normalized detector upper normalized detector current by the upper current by the upper Comments:

normalized detector normalized detector current average to obtain average to obtain the the power tilt ration for power tilt ratio for each each upper channel and upper channel.

RECORD on Attachment 1 The calculated values should be as shown in the STEP 6.2.6 Attachment 1 KEY.

Values within +/- 0.01 on each calculation are acceptable.

Page 5 of 7

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

11. Divide each lower Applicant divided each S U normalized detector lower normalized detector current by the lower current by the lower Comments:

normalized detector normalized detector current average to obtain current average to obtain the power tilt ratio for the power tilt ratio for each each lower channel and lower channel.

RECORD on Attachment

1. The calculated values should be as shown in the STEP 6.2.7 Attachment 1 KEY.

Values within +/- 0.01 on each calculation are acceptable.

Applicant identified Lower Detector N44 Power Tilt Ratio was calculated incorrectly

12. IF the manual QPTR N44 Lower is S U calculations do NOT Greater than 1.02. The confirm a QPTR of Applicant should N/A this Comments:

greater than 1.02, step.

DECLARE the Plant Computer Points and QPTR alarm INOPERABLE.

STEP 6.2.8

13. If any channel of QPTR Applicant determines that S U is greater than 1.02, N44 Lower QPTR is Refer to T/S Action greater than 1.02, referred Comments:

3.2.4.A and INITIATE to T/S Action 3.2.4.A and Attachment 2. INITIATED Attachment 2.

STEP 6.2.9 Applicant RECORDED highest QPTR of 1.03 and Rx Power of 100% on Attachment 2. See KEY

14. THE JPM IS COMPLETE Page 6 of 7

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: Callaway Plant is at MOL, 100% power with the indicated axial flux difference (AFD) equal to 0%.

Control Room annunciators 78B, 78C, and 78F are not operable.

All power range nuclear instruments are operable.

The Control Room Plant Computer System is not available for use.

Initiating Cue: The RO has performed a QPTR calculation per OSP-SE-00003, Quadrant Power Tilt Ratio Calculation, using the NI detector currents provided.

The RO has submitted the results to you for a second check.

CHANNEL Itop Ibottom N41 185.8 195.2 N42 163.2 190.8 N43 191.6 198.3 N44 188.2 196.1 Perform the second check of the ROs calculations and submit the data you have entered in OSP-SE-00003 to the Examiner.

Curve Book Table 11-1 has been provided

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A6 JPM Bank No: RA2 2009 ILT NRC Exam KSA No: 2.1.25 Revision Date: 02/13/2016 KSA Rating: 3.9 Job

Title:

URO/SRO Duty: Administrative Task

Title:

Determine Reactor Vessel Venting Tims 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

EOP Addendum 33, Determine Reactor Vessel Venting Time, Rev 1 Tools / Equipment: Calculator Page 1 of 4

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The crew is responding to plant conditions using FR-I.3, Response to Voids in the Reactor Vessel.

The following conditions exist:

Containment pressure is 3.8 psig.

Containment Temperature is 167°F.

Containment Hydrogen Concentration is 2.3%.

RCS Pressure is 1925 psig.

Initiating Cues: The CRS now directs you to determine RV Venting Time in accordance with EOP Addendum 33.

Task Standard: Upon completion of this JPM, the applicant will have determined RV Venting time to be between 1.72 and 1.84 minutes.

Start Time:

Stop Time:

Page 2 of 4

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. S U PROVIDE CANDIDATE CANDIDATE REVIEWED WITH MATERIAL AND ADMIN JPM INITIAL ALLOW TIME FOR CONDITIONS AND Comments:

REVIEW OF WORK TO INITIATING CUES BE PERFORMED

2. S U DETERMINE See KEY CANDIDATE CONTAINMENT AIR DETERMINED VOLUME AT STP = A CONTAINMENT AIR Comments:

VOLUME IS BETWEEN 6 6 STEP 1 2.4 X 10 AND 2.5 X 10 3

FT

3. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE MAXIMUM DETERMINED THAT HYDROGEN VOLUME BETWEEN 16800 AND 3 Comments THAT CAN BE VENTED 1.7500 FT CAN BE

=B VENTED STEP 2

4. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE DETERMINED THAT HYDROGEN FLOW HYDROGEN FLOW RATE Comments RATE AS A FUNCTION IS BETWEEN 9500 AND OF RCS PRESSURE = C 9750 FT3/MINUTE USING FIGURE 1 Step 3

5. S U CANDIDATE SHOULD See KEY CANDIDATE DETERMINE MAXIMUM DETERMINED THAT THE VENTING TIME MAXIMUM VENTING Comments TIME IS BETWEEN 1.72 STEP 4 AND 1.84 MINUTES

6. JPM IS COMPLETE S U Comments Page 3 of 4

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The crew is responding to plant conditions using FR-I.3, Response to Voids in the Reactor Vessel.

The following conditions exist:

Containment pressure is 3.8 psig.

Containment Temperature is 167°F.

Containment Hydrogen Concentration is 2.3%.

RCS Pressure is 1925 psig.

Initiating Cues: The CRS now directs you to determine RV Venting Time in accordance with EOP Addendum 33.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A7 JPM Bank No: A3, Rev 2 from the 2013 ILT NRC KSA No: 2.2.37 exam Revision Date: 02/13/2016 KSA Rating: 3.6 Job

Title:

URO/SRO Duty: Administrative Task

Title:

Ability to determine operability and/or availability of safety related equipment: Determine amperage limits for 480 VAC safety related busses when cross-connecting for maintenance.

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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

OTN-NG-00001, Class 1E 480 VAC Electrical System, Rev 16 Tools / Equipment: none Page 1 of 8

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The plant is at 100% power.

NG01 local ammeter indicates 712 amps.

NG03 local ammeter indicates 344 amps.

The following Train A equipment is NOT in service:

DG Vent Supply Fan A, CGM01A

Air Compressor A, CKA01A

Fuel Pool Clg Pump A, PEC01A

CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to prepare cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.

Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.

Provide your answer on the cue sheet below:

Task Standard: Upon completion of this JPM, the Applicant reported that the following equipment could be started:

CGM01A, DG Vent Sply Fan A SGK04A, Ctrl Rm A/C Unit A PEC01A, Fuel Pool Clg Pmp A Start Time:

Stop Time:

Page 2 of 8

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD EXAMINER NOTE:

JPM refers to OTN-NG-00001, Section 5.10. This section will not be performed by the Applicant but does contain information that the Applicant will need to perform the assigned task. Though not expected to be performed by the Applicant, Section 5.10 steps will be contained in JPM A3.

1. S U Applicant providedd working copy of OTN-NG-00001 Comments:

2. S U Refers to Section 5.10, Applicant referred to Cross-Connecting Load Section 5.10, Cross-Centers NG01 And Connecting Load Centers Comments:

NG03 NG01 And NG03 Page 3 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

3. S U The following cautions If asked if the impact of Applicant read caution apply when cross- starting current on and understood that total connecting load center cycling loads has been amperage drawn by both Comments NG01 and NG03, due to considered, respond load centers shall not transformer and power that engineering has exceed 1200 amps on supply limitations: reviewed starting local ammeters

Cross Tie Breaker current for NG01 and NG0116 is only NG03 loads and allowed to be closed determined that it has to repair failed or no impact on degraded limitations for current equipment loading when cross

Closing NG0116 connecting NG01 and makes all 4 NG03.

degraded bus voltage channels for NB01 inoperable per T/S B 3.8.9, and requires entry into T/S ACT 3.3.5.B.1 and T/S ACT 3.8.1.F

Total amperage drawn by both load centers shall not exceed 1200 amps on local ammeters

Total allowed load of 1200 amps includes cycling loads

No major loads should be added without referring to Attachment 1 to account for additional load Caution prior to Step 5.10.1

4. S U Initiate an EOSL item Step will not be performed for inoperability of all 4 channels for Bus NB01 Comments degraded voltage with reference to applicable T/S:

Step 5.10.1 Page 4 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

5. S U Check load centers Given in Initiating Cue NG01 and NG03 are energized Comments Step 5.10.2

6. S U Using local ammeters, Local ammeter values ensure combined total given in Initiating Cue load amperage for Comments NG01 and NG03 is less than 1200 amps Step 5.10.3

7. S U The bus transfer is a Note not read due to not break-before-make being applicable to operation which will assigned task Comments cause a momentary power loss of approximately 8 to 10 cycles. Alarms may actuate and breakers may trip. Attachment 1 provides load lists to determine effects on plant operation.

Note prior to Step 5.10.4

8. S U If removing the NG01 Step is not applicable feeder from service, perform the following:

Comments Step 5.10.4

9. S U If removing the NG03 Step is not applicable feeder from service, perform the following:

Comments Step 5.10.5 Page 5 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

10. S U Check loads on NG01 Step is not applicable and NG03 for breaker trips than may have Comments occurred during the transfer Step 5.10.6

11. S U Using local ammeters, Step is not applicable check combined total load amperage for Comments NG01 and NG03 is less than 1200 amps Step 5.10.7

12. S U If necessary to start Applicant determined loads on NG01 or loads that could be NG03, ensure toal load started - see JPM Step Comments will not exceed 1200 15 amps, by referring to Attachment 1 Step 5.10.8

13. S U If necessary, start loads Step is not applicable on NG01 and NG03 Comments Step 5.10.9

14. S U Refers to Attachment 1, Applicant referred to Load Centers NG01 & Attachment 1, Load NG03 Loads Centers NG01 & NG03 Comments Loads Page 6 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

15. S U Using Att 1 and Applicant determined that provided cues, CGM01A, SGK04A and determines what PEC01A can be started Comments equipment can be but that CKA01A could started on NG01 and not be started, as based NG03 after they are on the following cross-connected calculations:

Current amperage on both busses is 712 + 344

= 1056 (Provided in cue)

Margin for starting additional equipment is 1200 - 1056 = 144 Amperage for equipment not running would be:

CGM01A-130 -

Acceptable

CKA01A-276 - Not Acceptable

PEC01A-132 -

Acceptable

SGK04A Acceptable Acceptable equipment to start would be CGM01A OR PEC01A OR SGK04A.

Information is provided to the CRS (Examiner)

16. JPM IS COMPLETE S U Comments Page 7 of 8

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: The plant is at 100% power.

NG01 local ammeter indicates 712 amps.

NG03 local ammeter indicates 344 amps.

The following Train A equipment is NOT in service:

DG Vent Supply Fan A, CGM01A

Air Compressor A, CKA01A

Fuel Pool Clg Pump A, PEC01A

CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to prepare cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.

Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.

Provide your answer on the cue sheet below:

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A8 JPM No: SRO-RER-03-A203J KSA No: GEN 2.3.4 Revision Date: 02/15/2016 KSA Rating: 3.7 Job

Title:

SRO Duty: Administrative Task

Title:

SELECT VOLUNTEER FOR EMERGENCY EXPOSURE 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

HDP-ZZ-01450, Authorization To Exceed Federal Occupational Dose, Rev 11 CA0276, Authorization to Exceed Federal Occupational Radiation Dose Limits Page 1 of 6

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: A LOCA has occurred.

An operator has a life threatening injury in the Train A Residual Heat Removal Pump Room.

Extremely high radiation levels require a volunteer to attempt a rescue to extract the injured operator from the RHR pump room.

The estimated dose to the rescuer is 55 Rem.

Four individuals have volunteered to attempt a rescue of the injured operator.

Initiating Cues: You are the Emergency Coordinator and must select the best volunteer to attempt the rescue in accordance with HDP-ZZ-01450, Authorization To Exceed Federal Occupational Dose.

Notify the selected individual, AND complete CA0276, Authorization To Exceed Federal Occupational Dose Limits Task Upon completion of this JPM, Candidate selected Volunteer #2 to attempt the Standard: rescue of the injured operator in accordance with HDP-ZZ-01450 and filled out CA0276 correctly in accordance with the KEY Start Time:

Stop Time:

Page 2 of 6

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. Operator obtains copy of Operator obtained copy of S U HDP-ZZ-01450, HDP-ZZ-01450, Authorization To Exceed Authorization To Exceed Federal Occupational Federal Occupational Comments:

Dose, CA0276, Dose, CA0276, Authorization To Exceed Authorization To Exceed Federal Occupational Federal Occupational Dose Limits, and list of Dose Limits, and list of volunteers volunteers

2. Operator reviews data Operator selected Bob S U and selects volunteer Smith (Volunteer #2) from the list of volunteers Comments:

3. Completes CA0276 When individual has Operator completed S U correctly been selected: CA0276 in accordance Attestation has been with the KEY (required signed items are circled) Comments:

Record stop time on S U Page 2 The JPM is complete Comments:

Page 3 of 6

Critical Step

Authorization to Exceed Federal Occupational Radiation Dose Limits KEY

1. Name: Bob Smith ID (SSN, PPN): 23456 Age (years): 45 Estimated lifetime whole body dose (rem TEDE) provided by worker: 22.5 Has worker ever received a dose in excess of 10CFR20.1201 limits? YES NO Purpose of task: Accident Mitigation Personnel Safety Life Saving Task to be performed and justification for dose in excess of the limits of 10cfr20.1201 (attach additional pages if needed):

Attempt a rescue to extract the injured operator from the RHR pump room.

2. ATTESTATION:

I am aware of the risks involved in receiving a dose within the authorized limits and I have not previously received a dose in excess of the federal limits. For life saving dose limits above the Category 2 limits, I certify that I have volunteered.

Signature PIN Date WOMEN ONLY:

I have read and understand the potential effects on the fetus/embryo from doses in excess of the Occupational Dose Limits of 10CFR20.1201, and I voluntarily accept this assignment. I understand that I am encouraged to not volunteer for this task, and that there will be no repercussions if I elect to not volunteer.

Signature PIN Date

3. AUTHORIZATION:

The above individual is authorized to receive a dose in excess of the limits of 10CFR20.1201 within the following limits:

Category 1 - Life Saving Category 2 - Accident Mitigation/Personnel or Public Safety 100 rem DDE (guideline) 10 rem DDE 30 rem LDE 100 rem SDE 100 rem TODE APPROVED BY: Sr. Vice President Generation and Chief Nuclear Officer Vice President-Nuclear Operations Emergency Coordinator Recovery Manager Signature PIN Date Page 4 of 6

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: A LOCA has occurred.

An operator has a life threatening injury in the Train A Residual Heat Removal Pump Room.

Extremely high radiation levels require a volunteer to attempt a rescue to extract the injured operator from the RHR pump room.

The estimated dose to the rescuer is 55 Rem.

Four individuals have volunteered to attempt a rescue of the injured operator.

Initiating Cues: You are the Emergency Coordinator and must select the best volunteer to attempt the rescue in accordance with HDP-ZZ-01450, Authorization To Exceed Federal Occupational Dose.

Notify the selected individual, AND complete CA0276, Authorization To Exceed Federal Occupational Dose Limits

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE List of Volunteers

1. Abe Ross (PPN 12345) is a 50 year old male with a lifetime dose of 52.5 Rem

2. Bob Smith (PPN 23456) is a 45 year old male with a lifetime exposure of 22.5 Rem

3. Cindy Jones (PPN 34567) is a 42 year old female that tells you she is pregnant

4. Dan Parker (PPN 45678) is a 36 year old male who has a prior emergency exposure in excess of 10CFR20 limits at another utility

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE A9 JPM Bank No: SRO-RER-02-A031(TC) KSA No: 2.4.44 Revision Date: 03/17/2016 KSA Rating: 4.4 Job

Title:

SRO Duty: ADMINISTRATIVE Task

Title:

MAKE PROTECTIVE ACTION RECOMMENDATION DURING A GENERAL EMERGENCY (TIME CRITICAL)

Completion Time: Less than 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 Classroom Method of Performance: Simulated Performed Alternate Path Time Critical RCA

References:

EIP-ZZ-00212, Protective Action Recommendations Rev 28 Tools / Equipment: None (Sentry computer use is NOT allowed during this JPM)

Page 1 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial This JPM is TIME CRITICAL from the moment you acknowledge understanding of the Initiating Conditions: Conditions and Initiating Cues.

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.

A General Emergency has been declared due to EAL FG1.1, Loss of any two barriers AND loss or potential loss of a third barrier.

Containment radiation on GT RE-59 and GT RE-60 indicate 1.02E+05 Rem/hr.

There are no indications of travel conditions that would present an extreme hazard during any recommended evacuation.

Wind speed is 5 mph heading from 337°

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.

The SENTRY Computer is NOT working Initiating Make the Initial Protective Action Recommendation (PAR) based on the above conditions including Cues: affected sectors.

Task Standard: Upon completion of this JPM the applicant will have identified the PAR as Evacuate 2 Mile Radius and 10 miles downwind (Sectors G, H, J).

Start Time:

Stop Time:

Page 2 of 5

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM TASK ELEMENT EXAMINER CUE PERFORMANCE SCORE STEP STANDARD

1. S U OPERATOR MAY USE Applicant reviewed copies THE EIP PROCEDURES of the various required procedures.

Comments:

2. Applicant will have S U Determine PAR determined this is a Rapidly Progressing accident Comments:

3. Applicant determined S U Determine PAR EVACUATE 2 mile radius and 10 miles downwind due to no impediments Comments:

4 Applicant determined the S U Include affected sectors affected sectors are G, H, and J using the table on page 6 of EIP-ZZ-00212 Comments:

4. JPM IS COMPLETE JPM must be S U completed within 15 minutes from the time the applicant Comments acknowledged the cues Page 3 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE KEY PAR: Evacuate 2 mile radius and 10 miles downwind, affected sectors are G, H, and J Page 4 of 5

Critical Step

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE Initial Conditions: This JPM is TIME CRITICAL from the moment you acknowledge understanding of the Initiating Conditions and Initiating Cues.

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.

A General Emergency has been declared due to EAL FG1.1, Loss of any two barriers AND loss or potential loss of a third barrier.

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 1.02E+05 Rem/hr.

There are no indications of travel conditions that would present an extreme hazard during any recommended evacuation.

Wind speed is 5 mph heading from 337°

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.

The SENTRY Computer is NOT working Initiating Cues: Make the Initial Protective Action Recommendation (PAR) based on the above conditions including affected sectors and document below.

PAR: __________________________________

(include affected sectors)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Callaway___________________________ Date of Examination: _5/23/2016___

Exam Level: RO SRO-I SRO-U Operating Test No.: __2016-1_______

Control Room Systems: 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function S1 001 Control Rod Drive System (SF) / Perform Control Rod D, S 1 Partial Movement Test S2 004 CVCS (BG) / Swap From the NCP to 'B' CCP A, D, S 2 S3 010 Pressurizer Pressure Control System (BB) / Initiate Cold A, D, L, S 3 Overpressure Mitigation With PORV Malfunction S4 059 Main Feedwater System (AE) / Transfer Steam A, N, S 4S Generator Water Level Control 1

S5 005 Residual Heat Removal System (EJ) / Transfer to Cold A, D, P , EN, 4P Leg Recirculation S 1

S6 062 A.C. Electrical Distribution (PA) / Perform Operational D, P , S 6 Testing of the Alternate Emergency Power Source S7 015 Nuclear Instrumentation System (SE) / Respond to a D, S 7 Failed Power Range Instrument S8 Containment Purge System (GT) / Remove Shutdown Purge N, L, S 8 System From Service In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 006 Emergency Core Cooling System (EP) / Secure Safety D, L 2 Injection Accumulators P2 035 Main and Reheat Steam System (AB) / Isolate a Failed A, M, E, R 4S Open Atmospheric Steam Dump P3 062 AC Electrical Distribution System (NN) / Transfer NN01 M 6 from Manual Bypass to Normal

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 Page 1 of 4

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator Note 1. The JPMs from the 2013 exam were randomly selected by placing 11 slips of paper labeled S1 through P3 in a hardhat. Two of these items (S6 and S7) were drawn from the hardhat.

S1 This is a BANK JPM. The JPM (URO-SSF-01-C005J) was used on the 2009 ILT NRC Exam. The applicant will be assigned the task of performing control rod partial movement for all shutdown banks, per OSP-SF-00002, Control Rod Partial Movement, beginning at step 6.1 Upon completion of this JPM, the applicant will have inserted all shutdown bank A control rods at least 12 steps into the core and restored them to their pretest position.

S2 This is an ALTERNATE PATH, BANK JPM. The JPM (URO-SBG-02-C160J (A))

has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014.The applicant will perform the actions of OTN-BG-00001, Addendum 1 to shift from the NCP to the B CCP. After the B CCP is started and during the transition from the NCP flow controller to the B CCP flow controller, the B CCP will Trip, requiring the applicant to restore charging flow. Upon completion of this JPM the applicant will have restored charging flow to normal.

S3 This is an ALTERNATE PATH, BANK JPM. The JPM (URO-SBB-02-C065J (A))

was used on the 2007 ILT NRC Exam. The applicant will be directed to ARM the Pressurizer Power Operated Relief Valves for Cold Overpressure Mitigation in accordance with Section 5.6 of OTN-BB-00005, Pressurizer and Pressurizer Pressure Control. When the Train B COM Switch is placed in ARM, Pressurizer PORV BB-HIS-456A will open. Upon completion of this JPM, the applicant will have armed both Pressurizer PORVs for Cold Overpressure Mitigation and isolated or closed BB PV-456A after it fails open.

Page 2 of 4

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S4 This is an ALTERNATE PATH, NEW JPM. The applicant will be assigned the task transferring Steam Generator Water Level Control from the MFRV Bypass Valves to the Main Feedwater Regulating Valves using OTN-AE-00001, Feedwater System. During the transfer the D MFRV will not open. The applicant will abort the automatic valve transfer and manually maintain SGWL. Upon completion of this JPM, the applicant will have transferred Steam Generator Water Level Control from the MFRV Bypass Valves to the MFRVs for SG A, B, and C and taken manual control of SG D water level without causing a Feedwater Isolation Signal due to high or low Steam Generator water level.

S5 This is an ALTERNATE PATH, BANK JPM that was used on the 2013 ILT NRC Exam (S7 on 2013 exam). It was randomly selected using the method described above. The simulator will be set up following a large Loss of Coolant Accident.

The applicant will be directed to transfer the Emergency Core Cooling System to the recirculation mode in accordance with ES-1.3, Transfer to Cold Leg Recirculation. During performance, the applicant finds valves out of position and must use the Response Not Obtained column to complete the task. Upon completion of this JPM, the applicant will have aligned the RHR pumps for cold leg recirculation and aligned the SI pumps and CCPs suction to the RHR pumps IAW ES-1.3.

S6 This is a BANK JPM that was used on the 2013 ILT NRC Exam (S6 on 2013 exam). It was randomly selected using the method described above. The applicant will be assigned the task of performing an online test of Alternate Emergency Power Source Diesel Generator #4 from the Control Room. The diesel will be started, readings taken and then secured from the Control Room.

S7 This is a BANK JPM. The JPM (URO-SSE-03-C126J) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will perform the actions of OTO-SE-00001, Nuclear Instrument Malfunction, Attachment A to bypass the Power Range NIS Channel N41 current comparator and rod stop inputs. Upon Completion of this JPM, Power Range NIS channel N41 current comparator and rod stop inputs will be bypassed. The control power fuses for N41 will be removed.

S8 This is a NEW JPM. The applicant will perform the actions of OTN-GT-00001, Containment Purge System, to remove containment shutdown purge from service. Upon completion of this JPM, the applicant will have removed containment shutdown purge from service IAW OTN-GT-00001.

P1 This is a BANK JPM. The JPM (RO-SRO Au j) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will be assigned the task of locally securing Safety Injection accumulators per OTG-ZZ-00006, Addendum. Upon completion of this JPM, the applicant will have closed the SI Accumulator Outlet Isolation Valves and opened the feeder breakers to the SI accumulator outlet isolation valves.

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ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 P2 This is an ALTERNATE PATH, MODIFIED JPM. The parent JPM (EOP-SAB08077J(A)) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will be assigned the task of locally closing Atmospheric Steam Dumps, AB PV-3 AND AB PV-4. Upon completion of this JPM, the applicant will have closed AB PV-3 and isolated AB PV-4. AB PV-3 was closed by isolating Air/N2 from the valve. AB PV-4 was isolated by closing the manual isolation valve, ABV0007.

P3 This is a MODIFIED JPM. The parent JPM (EOS-SNN-03-P010J) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014.

The applicant will be assigned the task of transferring NN01 to the normal power source per OTN-NN-00001. Upon completion of this JPM the applicant will have transferred NN01 to the normal power supply (inverter and NK01) without a loss of voltage.

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ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Callaway___________________________ Date of Examination: _5/23/2016___

Exam Level: RO SRO-I SRO-U Operating Test No.: __2016-1_______

Control Room Systems: 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function S1 001 Control Rod Drive System (SF) / Perform Control Rod D, S 1 Partial Movement Test S2 004 CVCS (BG) / Swap From the NCP to 'B' CCP A, D, S 2 S3 010 Pressurizer Pressure Control System (BB) / Initiate Cold A, D, L, S 3 Overpressure Mitigation With PORV Malfunction S4 059 Main Feedwater System (AE) / Transfer Steam A, N, S 4S Generator Water Level Control 1

S5 005 Residual Heat Removal System (EJ) / Transfer to Cold A, D, P , EN, 4P Leg Recirculation S 1

S6 062 A.C. Electrical Distribution (PA) / Perform Operational D, P , S 6 Testing of the Alternate Emergency Power Source S7 015 Nuclear Instrumentation System (SE) / Respond to a D, S 7 Failed Power Range Instrument In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 006 Emergency Core Cooling System (EP) / Secure Safety D, L 2 Injection Accumulators P2 035 Main and Reheat Steam System (AB) / Isolate a Failed A, M, E, R 4S Open Atmospheric Steam Dump P3 062 AC Electrical Distribution System (NN) / Transfer NN01 M 6 from Manual Bypass to Normal

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 Page 1 of 4