ML15126A265

Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML15126A265
Person / Time
Site:	Susquehanna
Issue date:	01/08/2015
From:	Susquehanna
To:	Todd Fish Operations Branch I
Shared Package
ML14350A011	List: ML15014A270 ML15049A349 ML15049A350 ML15126A262 ML15126A263 ML15126A264 ML15126A265 ML15126A266 ML15128A470
References
TAC U01933
Download: ML15126A265 (211)

Text

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Compute the Average Drywell Air Temperature IAW S0-100-007 S/RO 00.S0.2103.101 4 08/07/2014 Simulator Applicability JPM Number Revision Date Setting 223001 2.2.12 3.0 / 3.4 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Authp v:* 12/04/2014 Date ln~tructor 12/13/2014 Date Review 12/13/2014 Date Date 10 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

/.,u,n1/11;.:f*,,.,.,'!"n" CONFIDENTIAL Examination Material

00.S0.2103.101 Rev 4 08/07/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM Changed 100% power to rated. Added specific temperatures. Updated to new 1

forms.

2 Edit to match steps in current rev of procedure and specify acceptance criteria.

3 Minor editorial changes, changed number from OO.S0.003.151.

4 Reformatted to the "TO" procedure format Updated Reference revision to revision 70 from 68. No changes following 5

validation.

CONFIDENTIAL Examination Material

00.S0.2103.101 Rev 4 08/07/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

8. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or .eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. S0-100-007, Daily Surveillance Operating Log (Rev 70)

3. TASK CONDITIONS Unit 1 is in Mode 1 at rated power.

The Process Computer is unavailable

4. INITIATING CUE Determine the average Drywell air temperature in accordance with S0-100-007

5. TASK STANDARD Calculates the correct average Drywell air temperature using readings obtained from recorders and substituting values for two inoperable instruments CONFIDENTIAL Examination Material

00.S0.2103.101 Rev 4 08/07/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to any full-power IC, or an exam-specific IC if prepared (IC-101).

2. Fail TE-15798A and TE-157998 downscale from sim PID PC14.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.S0.2103.101Rev4 08/07/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-_, or configure the simulator per the Simulator Setup Instructions.

• Mark-up a copy of S0-100-007, Attachment A, item 10 and Attachment G.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Verifies S0-100-007 is governing procedure and Controlled copy of S0-100-007 obtained, obtains controlled copy. selects Attachment A, Item 10. b.

2 Determines if process computer available Observe from Task Conditions process computer is not available, select Attachment G to complete CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.S0.2103.101 Rev 4 08/07/2014 Examinee Page 2 of 3 Step Action Standard Eva I Comments

• 3 Records Drywell temperatures. Record the following temperatures from the Drywell Atmosphere Temperature Recorders on Panel 1C693 on S0-100-007 Attachment G, Item 1.a-h

• Top Area 0 TE-15791A (124) 0 TE-15791 B (124)

• Middle Area 0 TE-15790A (139) 0 TE-157908 (140)

• Bottom Area 0 TE-15798A ( 50. 7) 0 TE-157988 (139)

• Pedestal Area 0 TE-15799A (118) 0 TE-157998 (50.7)

• 4 Substitutes value indicated for INOP indications Substitute the following values (150 °F for Top, Middle or Bottom; 130 °F for

• 150 °F forTE-15798A (Item 1.e)

Pedestal).

• 130 °F for TE-157998 (Item 1.h)

EVALUATOR NOTE Verify value calculated by operator if simulator as-found conditions vary due to other activities in-progress during the evaluation.

=

Example: (124+124+139+140+150+139+118+130) I 8 1064 I 8 133.0 °F =

• 5 Calculates the average Drywell temperature Perform the following:

• Sum eight temperatures (with two substitutions)

• Divide the sum by 8

• 6 Records the average Drywell temperature Record the calculated Drywell average temperature on Attachment G, Item 2.0.

7 Determines if the calculated value meets the Observe that the calculated temperature is Technical Specification requirement  ::; 135 °F CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.S0.2103.101 Rev 4 08/07/2014 Examinee Page 3 of 3 Step J Action J Standard J Eval J Comments EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is in Mode 1 at rated power.

The Process Computer is unavailable INITIATING CUE Determine the average Drywell air temperature in accordance with S0-100-007 CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET .

Task Title Determine Estimated Time to 200 °F and Required T.S. Actions SRO 49.0N.1869.103 5 10/23/2014 Classroom Applicability JPM Number Revision Date Setting 2.1.25 N/A 4.2 N N NUREG-1123 KIA Number K/A Importance Alternate Path Time Critical E/APE I Sys Prepared Validated 12/04/2014 12/13/2014 Aut1T6f Date Date Review 12/13/2014 Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

(,, .. ,.,i!/it>,.; f\(*rl/111;"

CONFIDENTIAL Examination Material

49.0N.1869.103 Rev 5 10/23/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM 1 Revise for TO procedures, minor editorial corrections CONFIDENTIAL Examination Material

49.0N.1869.103 Rev 5 10/23/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

8. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety R*ule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. TS 3.4.9

8. ON-149-001, Loss of Shutdown Cooling Mode (Revision 34)

3. TASK CONDITIONS Unit 1 is in Mode 4. The reactor has been shutdown for 12. 5 days. Reactor coolant temperature is 170 °F and stable.

Recirc MG sets A and 8 are out of service for maintenance.

RPV level is being maintained at 90 inches by the CRD and RWCU systems.

RHR 8 LPCI injection valve HV-151-F0158 breaker is tripped, all other RHR 8 components are available and operable.

RHR Pump A is operating, RHR Pump C is in standby.

HV-151-F009, RHR SHUTDOWN CLG SUCT 18 ISO, closes due to a spurious PCIS isolation signal and cannot be reopened. RHR Pump A is tripped.

All other low pressure ECCS systems are operable.

4. INITIATING CUE Determine the estimated time for coolant temperature to reach 200 °F, identify the Technical Specification Required Action(s) for this event, if any, and identify the methods*

to comply with any applicable Required Action(s).

5. TASK STANDARD Determines estimated time for reactor coolant temperature to reach 200 °F is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />(+/-

5 minutes). Determines TS 3.4.9 Required Actions A.1, 8.1 and 8.2 are applicable; identifies 2 alternate methods of decay heat removal, recognizes reactor coolant circulation by natural circulation, and directs reactor coolant temperature monitoring commences.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.103 Rev 5 10/23/2014 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a *. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a * .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM may be performed in the simulator or the classroom .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of ON-149-001 controlled copy. obtained, selects Section 3.3.

2* Complies with TS 3.4.9. Identifies entry into TS 3.4.9 Conditions A and B is required.

EVALUATOR NOTE Other combinations of low-pressure ECCS may be identified that satisfy the TS 3.4.9 Required Action A.1.

3* Identifies applicable Required Actions and Performs the following:

associated Completion Times for entry into TS 3.4.9

• Identifies Required Action A.1, "Verify an Condition A and method to satisfy TS requirements. alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem", must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.

• Identifies at least 2 alternate method of decay heat removal are available

1. CS A(B) and 2 SRVs open, RHR B aligned for Suppression Pool cooling

2. RHR A aligned for LPCI injection from Suppression Pool with 2 SRVs open.

EVALUATOR CUE Another operator will make the required log entries.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.103 Rev 5 10/23/2014 Examinee Page 2 of 2 Step Action Standard Eva I Comments 4* Identifies applicable Required Actions and Performs the following:

associated Completion Times for entry into TS 3.4.9

• Identifies Required Action B.1, "Verify Condition B and method to satisfy TS requirements. reactor coolant circulating by an alternate method", must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

• Identifies Required Action 8.1 is satisfied by natural circulation, as RPV level of 90" as specified in Task Conditions is> 45" required for natural circulation.

• Identifies Required Action B.2, "Monitor reactor coolant temperature", must be performed once per hour.

• Directs performance of S0-100-011, Reactor Vessel Temperature and Pressure Recording to determine heatup rate.

EVALUATOR CUE Another operator will perform S0-100-011.

5* Determines estimated time for reactor coolant to Plots on ON-149-001 Attachment G days reach 200 °F. after shutdown as 12.5, and from line for initial reactor coolant temperature (Ti) of 170 °F (+symbol) reads Time to 200 Fas 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (+/-5 minutes).

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is in Mode 4. The reactor has been shut down for 12.5 days. Reactor coolant temperature is 170 °F and stable.

Recirc MG sets A and B are out of service for maintenance.

RPV level is being maintained at 90 inches by the CRD and RWCU systems.

RHR B LPCI injection valve HV-151-F015B breaker is tripped, all other RHR B components are available and operable.

RHR Pump A is operating, RHR Pump C is in standby.

HV-151-F009, RHR SHUTDOWN CLG SUCT IB ISO, closes due to a spurious PCIS isolation signal and cannot be reopened. RHR Pump A is tripped.

All other low pressure ECCS systems are operable.

INITIATING CUE Determine the estimated time for coolant temperature to reach 200 °F, identify the Technical Specification Required Action(s) for this event, if any, and identify the methods to comply with any applicable Required Action(s).

CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Authorize Bypassing the Rod Block Monitor In Accordance With NDAP-QA-0338 SRO 00.AD.1021.101 3 12/04/2014 Classroom Applicability JPM Number Revision Date Setting 215002 2.1.37 4.6 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Authef/z /~....-=: 12/04/2014 Date lnstrutfOr LZJk 12/13/2014 Date Review 12/13/2014 Date Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments lCAM SUSQUEHANNA.

( " II< I((/ fn ~ f '_,*1*f/,-,,, <'

CONFIDENTIAL Examination Material

OO.AD.1021.101 Rev3 12/04/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 3 Added validator recommendation to add notch position 04 to the task conditions CONFIDENTIAL Examination Material

OO.AD.1021.101 Rev3 12/04/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. NDAP-QA-0338, Reactivity Management and Controls Program B. AR-103-001 (C04), RSM UPSCALE OR INOP ROD BLOCK C. TS 3.3.2.1, Control Rod Block Instrumentation D. TRM 3.2.1, Core Operating Limits Report

3. TASK CONDITIONS A plant startup is in progress on Unit 1. Reactor Power is 30%.

Control Rod 10-43 was shown not in its intended position on PPC OD?.

When PCOM selected Rod 10-43, the RBM UPSCALE OR INOP ROD BLOCK, AR-103-001 (C04), annunciator alarmed.

It has been determined that Rod Block Monitor A has a Critical Self Test Fault.

All external inputs to the Rod Block Monitor A have been determined to be valid.

The Reactor Engineer suggests bypassing the Rod Block Monitor A and returning Control Rod 10-43 to notch 04 per AR-103-001 (C04).

4. INITIATING CUE Determine if Rod Block Monitor A can be bypassed and identify any applicable Technical Specification LCO Required Actions.

5. TASK STANDARD Complete the Reactivity Control System Bypass Authorization Form, determine that bypassing the Rod Block Monitor is allowed, Tech Spec action 3.3.2.1 action A.1 is required CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.1021.101Rev3 12/04/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a *. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a * .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-_, or configure the simulator per the Simulator Setup Instructions.

• Ensure the following material is available to support performance of this JPM:

0 NDAP-QA-0338 0 NDAP-QA-0338, Attachment A 0 Unit 1 TS 3.3.2.1 0 Unit 1 TRM (COLR) 0 AR-103-001 (C04), RBM UPSCALE OR INOP ROD BLOCK EVALUATOR CUE Record JPM start time:

1 Verifies NDAP-QA-0338 is governing procedure Controlled copy of NDAP-QA-0338 and obtains controlled copy. obtained.

2 Completes NDAP-QA-0338, Attachment A. Reviews NDAP-QA-0338, Section 6.4.1.f and Attachment A.

3 Enters initiating condition data. Enters the following data for Initiating Condition:

• Rod ID 10-43

• Notch 04

• Unit 1

• Circle RBM Channel A

• Power Level 30 percent

• Date/Time 4 Determines if reactor power is <28%. Places checkmark in "NO" Box, from Task Conditions Reactor Power is 30%.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.1021.101 Rev 3 12/04/2014 Examinee Page 2 of 3 Step Action Standard Eva I Comments 5* Determines if Rod Block Monitor A is providing a Performs the following:

valid rod block per TRM 3.2 Table 7.2-1.

• Refers to Table 7.2-1 and cue sheet

• Determines Rod Block is being generated due to the Critical Self Test Fault, not as a result of exceeding a Table 7.2-1 setpoint

• Places a checkmark in the "NO" Box 6* Determines if inputs to the Rod Block Monitor A are Refer to provided task conditions, and place valid. a checkmark in the "NO" Box.

7 Contacts l&C to repair the Rod Block Monitor A Contacts l&C to investigate and repair the Rod Block Monitor A failure.

EVALUATOR CUE l&C has been contacted.

8* Determines if RBM is required to be OPERABLE Performs the following:

• Refers to TS LCO 3.3.2.1, Table 3.3.2.1-1 for Functions 1.a. - 1.d., and associated footnotes

• Refers to TRM 3.2 COLR, Table 7.2.-2

• Determines that MCPR is below the value specified in the COLR and that 2 channels of RBM are required 9* Determines Technical Specification impact of Determines that LCO 3.3.2.1 Condition A, bypassing RBM. Required Action A.1 requires RBM A channel to be restored to operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.1021.101 Rev3 12/04/2014 Examinee Page 3 of 3 Step Action Standard Eva I Comments 1O* Authorizes bypassing Rod Block Monitor A. Performs the following:

• Determines that Rod Block Monitor A can be bypassed.

• Signs, dates, and enters time on Attachment A in the "Shift Supervision Authorization To bypass the RBM channel" block on the lower right-hand side of the page, and enters current time/date.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS A plant startup is in progress on Unit 1. Reactor Power is 30%.

Control Rod 10-43 was shown not in its intended position on PPG OD7.

When PCOM selected Rod 10-43, the RBM UPSCALE OR INOP ROD BLOCK, AR-103-001 (C04), annunciator alarmed.

It has been determined that Rod Block Monitor A has a Critical Self Test Fault.

All external inputs to the Rod Block Monitor A have been determined to be valid.

The Reactor Engineer suggests bypassing the Rod Block Monitor A and returning Control Rod 10-43 to notch 04 per AR-103-001 (C04).

INITIATING CUE Determine if Rod Block Monitor A can be bypassed and identify any applicable Technical Specification LCO Required Actions.

CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review and Approve Radioactive Liquid Release Permit SRO OO.AD.2175.001 1 12/04/2014 Classroom Applicability JPM Number Revision Date Setting Generic 2.3.6 3.7 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Author 7 u 12/04/2014 Date LZ/k-lnstfUctor 12/13/2014 Date Review 12/13/2014 Op er Date 25 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

f,,q,r,o;i,,*/"""jl,* 1"1 CONFIDENTIAL Examination Material

OO.AD.2175.001 Rev 1 12/04/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM Revise for incorporate validator comments to the faulted marked-up procedure 1 handout (OP-069-050).

Updated Reference revisions CONFIDENTIAL Examination Material

OO.AD.2175.001 Rev 1 12/04/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-069-050, Release of Liquid Radioactive Rad Waste (Revision 56)

3. TASK CONDITIONS Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments D, F and H have been prepared.

4. INITIATING CUE Shift Manager directs you to review and approve OP-069-050 Attachments D, F and H

5. TASK STANDARD Identify less than required LRW sample tank recirculation time, incorrect settings for Actual High Rad setpoint and Actual Alert Rad setpoint, and determine that U1 & U2 Cooling Tower Slowdown Flow instrumentation is inoperable, requiring blowdown flow instruments to be bypassed CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.2175.001 Rev 1 12/04/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• Mark-up a copy of OP-069-050, Attachments D,F and H, filled in with data from the answer key .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of OP-069-050.

controlled copy.

EVALUATOR CUE If at any point during the review of the permit the examinee indicates that the release is not allowed at this time due to problems with the permit, direct the examinee to finish review of the entire permit.

2* Verifies calculation of required recirculation time. Performs the following:

• Calculates required recirc time .

• Compares this number with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes

• Determines that calculated required recirculation time is incorrect, the earliest possible sample time would be 10:09 (not 10:03).

3* Verifies High Rad setpoint. Performs the following:

=

• Calculates 1.64E4 + 1.89E3 1.829E4 and compares this to the number in block 2.3.6.n (4.02E4).

• Identifies that high rad countrate was calculated incorrectly as 3.53E4

• Determines that correct rad setpoint value should be 1.829E4.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.2175.001 Rev 1 12/04/2014 Examinee Page 2 of 3 Step I Action Standard Eval I Comments 4* I Compares calculated required High Rad setpoint Determines that the actual setpoint of the with required setpoint and actual setpoint in step LRW rad monitor High Rad setpoint in the 2.3.7. field is incorrectly set and requires correction before release can begin.

5* I Determines that Unit 2 Cooling Tower Flowrate

• Reviews Attachment F, to determine the Instrument is INOPERABLE, and requires satisfactory test results of blowdown flow permission from shift supervisor to bypass cooling instrumentation for Unit 1 and Unit 2.

tower low flow interlock.

• Determines that for Unit 1 based on actual Cooling T ewer Basin Slowdown valve position indication (45%) and blowdown flow rate (5000gpm) Unit 1 blowdown flow instrumentation falls within the Acceptable Region of the Graph on Page 160 of Attachment F.

• Determines that for Unit 2 based on actual Cooling Tower Basin Slowdown valve position indication (45%) and blowdown flow rate (3500gpm) Unit 2 blowdown flow instrumentation falls within the Unacceptable Region of the Graph on Page 164 of Attachment F.

• Determines that based on the Graph results, Unit 2 Slowdown flow instrumentation should be declared INOPERABLE and require to be bypassed.

EVALUATOR NOTE Once the examinee indicates that the release permit will not be authorized due to not enough recirculation time prior to sample, incorrect RAD setpoint, AND flowrate instrument is INOPERABLE, then proceed with the JPM.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.2175.001 Rev 1 12/04/2014 Examinee Page 3 of 3 Step Action Standard Eva I Comments EVALUATOR CUE The following actions have been taken

• Recirculation time has been satisfactory been met per the corrected calculation

• High Rad setpoint is properly set in accordance with the corrected calculation

• U2 flowrate instrument is INOPERABLE Complete review and approval of OP-069-050 attachment D, F and H and determine whether a discharge can continue and if it can under what conditions.

6* Determines that HS-01503 is required to be in Marks up Attachment H to proper Switch UNIT 2 BYPASS when U-2 Cooling tower Alignment of HS-01503, indicating the HS-blowdown instrument is INOPERABLE. 01503, COOLING TOWER SLOWDOWN should be placed in the U2 BYPASS position.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments D, F and H have been prepared.

INITIATING CUE Shift Manager directs you to review and approve OP-069-050 Attachments D, F and H CONFIDENTIAL Examination Material

EVALUATOR TASK CONDITIONS Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments D, F and H have been prepared.

INITIATING CUE Shift Manager directs you to review and approve OP-069-050 Attachments D, F and H CONFIDENTIAL Examination Material

OO.AD.2175.001 Rev 1 12/04/2014 Page 1 of 1 VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 10-13 below.

Instructor Initials

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an

---

asterisk (*).

8. Verify cues both verbal and visual are free of conflict.

9. Ensure performance time is accurate.

G.v. 10. Verify the JPM reflects the most current revision of the procedure.

Procedure OP-069-050 Rev 56 Procedure Rev Procedure Rev G.v. 11. Pilot the JPM.

For Sim JPMs, ensure simulator response is unchanged. Run concurrent JPMs simultaneously to ensure proper simulator response and there is no interaction between JPMs.

For plant JPMs, ensure the JPM is consistent with conditions in the plant (labeling, radiological, etc.).

N/A 12. If the JPM cannot be performed as written, then revise as necessary and revalidate.

G.v. 13. When JPM is validated, sign and date JPM cover page.

Revise for incorporate validator comments to the faulted marked-up procedure handout (OP-069-050).

Updated Reference revisions CONFIDENTIAL Examination Material

OO.AD.2175.001 Rev 1 12/04/2014 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose OP-069-050 Attachment D and F (marked-

2. exam staple up)

3. Evaluator cue sheet cue loose

4. JPM jpm loose CONFIDENTIAL Examination Material

EXAM IN EE TASK CONDITIONS Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments D, F and H have been prepared.

INITIATING CUE Shift Manager directs you to review and approve OP-069-050 Attachments D, F and H CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Classify an Emergency Condition and Complete Emergency Notification Report SRO OO.EP.1132.180 1 12/04/2014 Classroom Applicability JPM Number Revision Date Setting Generic 2.4.41 4.6 N y NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Author 12/04/2014 Date L-z~

Ir1'Structor 12/13/2014 Date Review 12/13/2014 Date 15 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: Exam Duration (Min) - - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material

OO.EP.1132.180 Rev 1 12/04/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

OO.EP.1132.180 Rev 1 12/04/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. EP-PS-100, Emergency Director, Control Room B. EP-RM-004, EAL CLASSIFICATION BASES (Revision 2)

C. EP-PS-001, EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS (Revision 2)

3. TASK CONDITIONS Each examinee evaluated in the SRO position for a scenario will be required to classify the event once the scenario concludes. Task Conditions for each scenario are provided.

4. INITIATING CUE Make the initial emergency classification and as Emergency Director complete any associated notification form(s) in accordance with the applicable procedures for activation of the Emergency Plan.

5. TASK STANDARD Classify the event at the appropriate level on the correct EAL and complete the Emergency Notification Report.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.180Rev1 12/04/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• Ensure that a copy of EP-RM-004, EP-PS-100 and blank ENR and PAR forms are available .

EVALUATOR NOTE This is a TIME CRITICAL JPM.

EVALUATOR CUE Record JPM start time:

1 Obtains copy of EP-PS-100, Emergency Director, Obtains copy of EP-PS-100, Emergency Control Room and EP-RM-004, EAL Classification Director, Control Room and EP-RM-004, Bases. EAL Classification Bases.

2 Refers to classification matrix. Selects the correct Table.

• 3 Chooses appropriate emergency action level. Declares the correct event level per the JPM key for the scenario within 15 minutes of start time.

4 Determines appropriate procedure section. Identifies the appropriate procedure attachment for the event classification of EP-PS-100.

5 Documents and communicates the Emergency Announces the following:

Classification.

• I am assuming duties of the Emergency Director

• [Event] declared based on [EAL summary]

• Time and Date of Classification 6 If not performed earlier appoints an Emergency Appoints an Emergency Plan Communicator Plan Communicator. and instructs communicator to immediately perform EP-PS-126, E-Plan Communicator.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.180Rev1 12/04/2014 Examinee Page 2 of 3 Step Action Standard Eva I Comments 7 If not performed earlier, appoints an NRC Appoints an NRC Communicator and communicator. instructs communicator to perform EP-PS-135, NRC Communicator.

8 Initiates an ENR form. Performs the following:

• Refers to ENR Form under Att J and IF necessary EP-PS-001-4 for instructions on filling out the form

• Records CR-1 as the control#

• Line 1, places checkmark in THIS IS A DRILL box EVALUATOR NOTE The time recorded on Line 3 of the ENR form is compared to the start time recorded at the beginning of the JPM to determine if the examinee is successful in meeting the 15 minute event declaration requirement of the JPM.

• 9 Completes Line 3 of the ENR Performs the following:

• *Places checkmark in the correct event box

• Places checkmark in the correct unit box

• Records declaration time and date

• Places checkmark in INITIAL DECLARATION box 10 Completes Line 4 of the ENR Performs the following:

• Records EAL in Classification Description

• Records a brief non-technical description of EAL or applies appropriate sticker marked-up to reflect actual event CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.180Rev1 12/04/2014 Examinee Page 3 of 3 Step Action Standard Eva I Comments 11 Completes Line 5 of the ENR Performs the following:

• Refers to EP-PS-001-48 Att. QQ for guidance in determining if there is a radiological release in progress due to the event

• Places checkmark in release box as appropriate 12 Completes Lines 6 and 7 of the ENR Performs the following:

• Records wind direction, wind speed .

• Places checkmark in THIS IS A DRILL box

• 13 Approves the ENR. Signs the ENR and records the current date and time.

14 Provides the ENR to the Emergency Plan Performs the following:

Communicator.

• Provides the approved ENR to the Emergency Plan Communicator.

• Reviews the ENR with the Communicator

• Directs the Communicator to complete the notification within 15 minutes of the event declaration time EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Respond To Multiple Rod Notching IAW ON-155-001 S/RO 55.0N.2003.151 3 08/08/2014 Simulator Applicability JPM Number Revision Date Setting 201002 A1.02 3.4/3.3 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated KufhJ /~ 12/04/2014 Date IFlstructor 7 12/13/2014 Date Review 12/13/2014 Date Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: 0 Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

t., "* r.l/in*. /.\,,-;/,.,,,.,.

CONFIDENTIAL Examination Material

55.0N.2003.151 Rev 3 08/08/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM Revise for TO procedures, minor editorial corrections 1

Reformatted to the "TO" procedure format Incorporated validator comments; Add "or stuck rods" to task conditions Provide mark-up of S0-156-010 Att A 2

Provide copy of ON-155-001 Att A Add evaluator cue for US to direct returning rod 02-27 to position 48 Change "and" to "and/or" for rod position indication CONFIDENTIAL Examination Material

55.0N.2003.151 Rev 3 08/08/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A S0-156-010 Monthly Control Rod Exercising (Rev 6)

B. OP-156-001 Reactor Manual Control System (RMCS) (Rev 20)

C. ON-155-001 Control Rod Problems (Rev 38)

D. AR-104-001 (HOS) (Rev 37)

3. TASK CONDITIONS S0-156-010 is in progress. S0-156-010 is complete up to step 5.2.

There are no control rods currently documented as multiple notch rods or stuck rods

4. INITIATING CUE Continue performing S0-156-010, step 5.2

5. TASK STANDARD Control rod 02-27 is returned to its intended position of 46 IAW ON-155-001 CONFIDENTIAL Examination Material

55.0N.2003.151 Rev 3 08/08/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

• Reset the simulator to IC-20, or an exam-specific IC if prepared.

• To double notch rod 02-27 from 48 to 44, activate the following Event Trigger.

ET55.0N.2003.151 lssblpos(71) < 47 IOR doC12110DSSIB f :OFF IOR doC12110DS2S f :ON IOR doC12110DS1 f:OFF IOR doHSC121SlO f :OFF IOR diHSC121SlO f:INSERT

• To delete double notch malfunction at position 44 for rod 02-27, activate the following Event Trigger.

ET55.0N.2003.151 Delete lssblpos(71) < 44 DOR diHSC121S10

+1 DOR doC12110DSSIB DOR doC12110DS1 DOR doHSC121S10

+3 DOR doC12110DS2S CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev 3 08/08/2014 Examinee Page 1 of 8 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a *. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a * .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-20, or configure the simulator per the Simulator Setup Instructions .

• Markup a copy of S0-156-010 complete up to step 5.2 EVALUATOR NOTE The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Identifies governing procedure and obtain Obtains controlled copy of S0-156-010.

controlled copy.

• 2 Selects control rod 02-19. Performs the following:

• *Depresses the 02 and 19 CONTROL ROD SELECTION PBs

• Observes 02 and 19 CONTROL ROD SELECTION PBs backlit WHITE

• Observes FULL CORE DISPLAY for control rod 02-19 illuminated GREEN

• Observes 02-19 indicates selected on RWM and/or OD7 displays

• Observes RTIME and/or SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 48 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev 3 08/08/2014 Examinee Page 2 of 8 Step Action Standard Eva I Comments

• 3 Inserts control rod 02-19 to position 46. Performs the following:

• *Momentarily depresses INSERT ROD PB

• Observes ROD INSERT and ROD SETLG lights lit in series

• Observes RTIME and/or SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 46

• 4 Withdraws control rod 02-19 to position 48. Performs the following:

• *Momentarily depresses W/DRAW ROD PB until the ROD INSERT light illuminates

• Observes ROD INSERT, ROD W/DRAWG and ROD SETLG lights lit in series

• Observes RTIME and/or SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 48 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151Rev3 08/08/2014 Examinee Page 3 of 8 Step Action Standard Eva I Comments

• 5 Obtains control rod 02-19 withdraw stall flow and Performs the following:

verifies control rod coupled. * *Depresses and hold the W/DRAW ROD and CONT W/DRAW ROD PBs

• Observes ROD INSERT light lit then extinguished, ROD W/DRAWG remains lit

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 48

• Notes CRD drive water flow

• Observes absence of ROD OVERTRAVEL alarm

• *Releases W/DRAW ROD and CONT W/DRAW ROD PBs

• Observes ROD SETLG light lit, then extinguished

• Records withdraw stall flow for control rod 02-19 on Attachment A

• *Circles Rod Coupling Check SAT for control rod 02-19 on Attachment A 6 Verifies control rod 02-19 at position 48. Performs the following:

• Depresses DISPLAY RODS FULL-IN FULL-OUT PB

• Observes FULL CORE DISPLAY for control rod 02-19 illuminated RED

• Releases DISPLAY RODS FULL-IN FULL-OUT PB

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 48 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev 3 08/08/2014 Examinee Page 4 of 8 Step Action Standard Eva I Comments 7 Documents completion oftest for control rod Performs the following:

02-19.

• Circles Operability Check SAT for control rod 02-19 on Attachment A

• Initials Confirm for control rod 02-19 on Attachment A EVALUATOR CUE Initial Verify for control rod 02-19 on Attachment A

• 8 Selects control rod 02-23. Performs the following:

• *Depresses the 02 and 23 CONTROL ROD SELECTION PBs

• Observes 02 and 23 CONTROL ROD SELECTION PBs backlit WHITE

• Observes FULL CORE DISPLAY for control rod 02-23 illuminated GREEN

• Observes 02-23 indicates selected on RTIME RWM and/or OD7 displays

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 48

• 9 Inserts control rod 02-23 to position 46. Performs the following:

• *Momentarily depresses INSERT ROD PB

• Observes ROD INSERT and ROD SETLG lights lit in series

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 46 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev3 08/08/2014 Examinee Page 5 of 8 Step Action Standard Eva I Comments

• 10 Withdraws control rod 02-23 to position 48. Performs the following:

• *Momentarily depresses W/DRAW ROD PB until the ROD INSERT light illuminates

• Observes ROD INSERT, ROD W/DRAWG and ROD SETLG lights lit in series

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 48

• 11 Obtains control rod 02-23 withdraw stall flow and Performs the following:

verifies control rod coupled. * *Depresses and hold the W/DRAW ROD and CONT W/DRAW ROD PBs

• Observes ROD INSERT light lit then extinguished, ROD W/DRAWG remains lit

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 48

• Notes CRD drive water flow

• Observes absence of ROD OVERTRAVEL alarm

• *Releases W/DRAW ROD and CONT W/DRAW ROD PBs

• Observes ROD SETLG light lit, then extinguished

• Records withdraw stall flow for control rod 02-23 on Attachment A

• *Circles Rod Coupling Check for control rod 02-23 SAT on Attachment A CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev3 08/08/2014 Examinee Page 6 of 8 Step Action Standard Eva I Comments 12 Verifies control rod 02-23 at position 48. Performs the following:

• Depresses DISPLAY RODS FULL-IN FULL-OUT PB

• Observes FULL CORE DISPLAY for control rod 02-23 illuminated RED

• Releases DISPLAY RODS FULL-IN FULL-OUT PB

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 48 13 Documents completion of test for control rod Performs the following:

02-23.

• Circles Operability Check SAT for control rod 02-23 on Attachment A

• Initials Confirm for control rod 02-23 on Attachment A EVALUATOR CUE Initial Verify for control rod 02-23 on Attachment A

• 14 Selects control rod 02-27. Performs the following:

• *Depresses the 02 and 27 CONTROL ROD SELECTION PBs

• Observes 02 and 27 CONTROL ROD SELECTION PBs backlit WHITE

• Observes FULL CORE DISPLAY for control rod 02-27 illuminated GREEN

• Observes 02-27 indicates selected on RTIME RWM and/or OD7 displays

• Observes RTIME and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-27 position 48 FAULT STATEMENT CONTROL ROD 02-27 WILL DOUBLE NOTCH TO POSITION 44.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev 3 08/08/2014 Examinee Page 7 of 8 Step Action Standard Eva I Comments 15 Observe control rod 02-27 position indicator Observe at FOUR ROD DISPLAY control responds correctly. rod inserts and double notches from 48 position to 44 position AND position indicated is an even number.

Informs US that control rod 02-27 double notched to position 44 and entry into ON-155-001 is required.

16 Identifies ON-155-001, Control Rod Problems, step Controlled copy of ON-155-001 obtained, 4.7 for multiple rod notching as the governing selects section 4.7.

procedure and obtain a controlled copy.

17 Documents multiple notch rod on Attachment A of Documents 02-27 at a multiple notch rod on ON-155-01 Attachment A of ON-155-001 EVALUATOR CUE As US, direct examinee to return rod 02-27 to position 48 EVALUATOR NOTE Provide examinee with copy of ON-155-001 Att A 18* Move the rod to intended location per procedure Ensure control rod 02-27 selected or Select governing original control rod motion control rod 02-27 to be withdrawn one notch by Depressing corresponding CONTROL ROD SELECTION pushbuttons

• Depress W/DRAW ROD pushbutton 19* Observe control rod 02-27 has return to its Observe at FOUR ROD DISPLAY control intended position rod withdraws from position 44 to position 46 AND position indicated is an even number.

20 If multiple notch rod is not currently listed in CRC Indicated that a CR is required.

book, initiate a CR EVALUATOR CUE Record JPM stop time:

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.2003.151 Rev 3 08/08/2014 Examinee Page 8 of 8 Step j Action I Standard I Eval j Comments EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS S0-156-010 is in progress. S0-156-010 is complete up to step 5.2.

There are no control rods currently documented as multiple notch rods INITIATING CUE Continue performing S0-156-010, step 5.2 CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title HPCI Full-Flow Test Quarterly Surveillance, Test Return Valve Fails to Open S/RO 52.50.1964.151 2 10/23/2014 Simulator Applicability JPM Number Revision Date Setting 206000 A2.06 3.3/3.5 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated

/"!

Adt'fior

~ 12/04/2014 Date

/7-Instrtld"or 4~ 12/13/2014 Date Review 12/13/2014 Date 15 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) _ _ _ _ __

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material

52.S0.1964.151 Rev 2 10/23/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM 1 Revise for TQ procedures, minor editorial corrections Incorporated recommended changes from validating operators.

Added verbiage to the evaluator cue prior to action 15 regarding Electrical Maintenance input.

2 Added an evaluator note to direct the examinee to continue if they stop to wait for 5ooogpm.

Updated the surveillance authorization sheet to denote Post Maintenance Test.

CONFIDENTIAL Examination Material

52.S0.1964.151 Rev 2 10/23/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. S0-152-002, Quarterly HPCI Flow Verification (Revision 62)

3. TASK CONDITIONS Unit 1 is operating at 90% power.

HPCI is inoperable following a system outage window.

A full-flow test is required to return HPCI to an OPERABLE status. This full-flow test will NOT be used to satisfy Tech Spec quarterly surveillance requirements. IST data collection is not required.

NPOs, Maintenance and HP personnel are standing by to support HPCI operations.

A manual start of HPCI was performed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago. HPCI has been returned to standby per OP-152-001.

S0-152-002 has been completed through Step 5.1.3.c(2)

Other operators will perform all timing operations during HPCI startup.

4. INITIATING CUE Perform a full-flow test of HPCI by completing S0-152-002

5. TASK STANDARD Aligns HPCI for full-flow test back to the CST at a flow rate of at least 5000 gpm at a discharge pressure of at least 1140 psig CONFIDENTIAL Examination Material

52.S0.1964.151 Rev 2 10/23/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS Reset the simulator to IC-18, or an exam-specific IC 385 Place the following systems in service per the respective OP RHR Bin Suppression Pool Cooling, OP-149-005 Run EVAL52S01964151 Insert the following Event Triggers ET52S01964151 hpvsphv155f008 > 0.3 IMF cmfMV07_HV155F008 f :38 ET52S01964151A hpvsphv155f011 > 0. 35

!RF rfDC188110 f:OPEN Perform the following expert commands to align HPCI floor drain and start SGTS and ESW

!RF rfLD120003 f:OPEN

!OR diHS07555B c:1 f:OPEN

!OR diHS07551B f:STR

!OR diHS01102A c:1 f:RUN

!OR diHS01102B c:1 f:RUN Perform the following expert commands to assign keys to manually trigger the required simulator events.

(Key [21 JI !RF rfDC188118 f: OPEN (Key [22] I IMF cmfMV06_HV155F011 (Key[23]} !RF rfDC188135 f:OPEN (Key[24]) IMF cmfMV07_HV155F011 c:2 f:Asls (Key[24]} !RF rfDC188110 f:CLOSE (Key[25]} !RF rfDC188135 f:CLOSE (Key[25]} DMF cmfMV07_HV155F008 Flag annunciators as necessary IAW with the procedure Open breaker for F006 Insert CMF MV06-HV155F011 to disable F011 auto closure CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151Rev2 10/23/2014 Examinee Page 1 of 6 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-18, or configure the simulator per the Simulator Setup Instructions .

EVALUATOR NOTE The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Identifies governing procedure and obtain Obtains controlled copy of S0-152-002 controlled copy. obtained.

2 Verifies all prerequisites are satisfied and HPCI Observes prerequisites are met and HPCI support systems are aligned. support systems are aligned as specified by Task Conditions.

BOOTH OPERATOR CUE Monitor value of sim parameter hpvsphv155f008 to determine position of HV-155-F008.

3* Opens HV-155-FOOS, HPCI Test Line To CST lso, Places HV-155-F008, HPCI TEST LINE TO to 32 percent. CST ISO, to OPEN and CLOSE as necessary to obtain valve position of 32 percent.

BOOTH OPERATOR CUE Ensure Event Trigger ET52S01964151 fires when FOOS is greater than 30 percent open to position the valve as desired.

EVALUATOR CUE (As NPO) Report valve position as 32 percent when the event trigger fires.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151 Rev2 10/23/2014 Examinee Page 2 of 6 Step Action Standard Eva I Comments 4 Opens breaker 1D274-081, HPCI Test Line To Directs N PO to open 1D274-081, H PC I CST Isa Viv HV-155-F008. TEST LINE TO CST ISO VLV HV-155-FOOS BKR.

BOOTH OPERATOR CUE Depress KEY 23 to open breaker 1D274-081 and report breaker open.

EVALUATOR CUE Initial as verifier in step 5.3.5 of S0-152-002.

5 Evacuates HPCI room and ensures watertight Directs NPO to clear HPCI room of all doors are closed. personnel and close HPCI room watertight doors.

EVALUATOR CUE (As NPO) HPCI room evacuated, watertight doors closed.

6* Arms HPCI manual initiation PB. Performs the following:

• Rotates HS-E41-1S33, HPCI MAN INIT, collar to ARMED position

• Observes AR-114-A05 in alarm 7 Starts TRA. Notifies STA to start TRA.

EVALUATOR CUE (As STA) TRA initiated.

EVALUATOR CUE Other operators will start and record F001 stroke time and time to reach 5000 gpm HPCI flow.

8* Initiates HPCI. Depresses and holds HS-E41-1 S33 HPCI MAN INIT, PB until HV-155-F001, 1

TURBINE STEAM SUPPLY starts to open.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151Rev2 10/23/2014 Examinee Page 3 of 6 Step Action Standard Eva I Comments 9 Confirms HPCI response. Observes the following:

• HPCI INIT SIG RESET HS-E41-1S17 indicating light illuminates

• HPCI BARO COSR VACUUM PP 1P216 starts

• HPCI L-0 CLG WTR HV-156-F059 opens

• HPCI TURBINE STEAM SUPPLY HV 155-F001 opens

• HPCI STM LINE ORN TO COSR IB ISO HV-155-F028 closes

• HPCI STM LINE ORN TO COSR OB ISO HV-155-F029 closes

• HPCI BARO COSR CONO PP OSCH ORN HV-156-F026 closes

• HPCI BARO CDSR CONO PP OSCH ORN HV-156-F025 closes if open

• HPCI Rm Unit Cir 1V209A(B) starts at 1C681 EVALU A TOR NOTE If candidate stops to wait for 5000gpm, as US, direct to continue with the procedure.

FAULT STATEMENT HV-155-F011 BREAKER TRIPS WHEN VALVE STROKED OPEN 1O* Opens HV-155-F011, HPCI Test Line To CST lso, Performs the following:

when HPCI pump discharge pressure reaches

• Observes Pl-E41-1R601, HPCI PP 100 psig. DSCH PRESS, greater than 100 psig and then places HV-155-F011, HPCI TEST LINE TO CST ISO, to OPEN

• Observes HV-155-F011 indicates dual

• Observes loss of indication for HV-155-F011 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151Rev2 10/23/2014 Examinee Page 4 of 6 Step Action Standard Eva I Comments EVALUATOR CUE (As PCO) The HPCI response time was NOT acceptable. IF ASKED:F001 stroke time was 16.7 seconds and 26.1 seconds to 5000 gpm.

11 Notifies System Engineering to evaluate effect on Informs Unit Supervisor to notify System system components. Engineering to evaluate effect on system components if loud banging noise heard during system initiation.

EVALUATOR CUE (As NPO) No banging was heard in the HPCI room during the start.

12* Reduces HPCI pump speed to approximately Places FC-E41-1R600, HPCI TURBINE 2200 rpm. FLOW CONTROL, in MANUAL and depresses LOWER PB to obtain HPCI pump speed less than 2500 rpm, as indicated on Sl-E41-1R604, HPCI TURB SPEED.

13* Resets HPCI initiation. Performs the following:

• Rotates HS-E41-1S33, HPCI MAN INIT, collar to DISARMED position

• Observes AR-114-A05 clear

• Depresses HS-E41-1S17, HPCI INIT SIG RESET, PB

• Observes HS-E41-1S17 initiating light extinguished 14 Ensures HV-155-F011, HPCI Test Line To CST Directs NPO to manually close HV-155-lso, closed. F011, HPCI TEST LINE TO CST ISO.

BOOTH OPERATOR CUE Depress KEY 24 to delete the F011 malfunction and reclose 1D624-01.

EVALUATOR CUE (As Unit Supervisor) I have been contacted by Electrical Maintenance, they have recommended 1D624-01 be reset and reclosed. Continue with the procedure to establish conditions for re-performing the test.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151Rev2 10/23/2014 Examinee Page 5 of 6 Step Action Standard Eva I Comments 15* Closes HV-155-F011, HPCI Test Line To CST lso. Places HV-155-F011, HPCI TEST LINE TO CST ISO, to close and observes valve indicates full closed.

16 Trips HPCI. Depresses and holds HS-E41-1S19, HPCI TURBINE TRIP, PB.

17* Closes HV-155-F001, HPCI Turbine Steam Places HV-155-F001, HPCI TURBINE Supply. STEAM SUPPLY, to close.

18 Releases HPCI trip PB. Releases HS-E41-1S19, HPCI TURBINE TRIP, PB.

19 Confirms HV-156-F059, HPCI L-0 Clg Wtr, Observes HV-156-F059, HPCI L-0 CLG closed. WTR, indicates full closed.

EVALUATOR NOTE Proceed when the HPCI stop valve indicates full open.

EVALUATOR CUE Five minutes have elapsed.

20 Stops HPCI auxiliary oil pump. Places 1P213, HPCI AUXILIARY OIL PP, to STOP.

EVALUATOR CUE Fifteen minutes have elapsed.

EVALUATOR NOTE Pump may not be running.

21 Stops HPCI barometric condenser vacuum pump. Places 1P216, HPCI BARO CDSR VACUUM PP, to STOP.

22* Resets HPCI turbine flow controller. Places FC-E41-1R600, HPCI TURBINE FLOW CONTROL, in AUTO with a setpoint of 5100 gpm.

EVALUATOR CUE Record JPM stop time:

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 52.S0.1964.151Rev2 10/23/2014 Examinee Page 6 of 6 Step I Action I Standard I Eval J Comments EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is operating at 90% power.

HPCI is inoperable following a system outage window.

A full-flow test is required to return HPCI to an OPERABLE status. This full-flow test will NOT be used to satisfy Tech Spec quarterly surveillance requirements. IST data collection is not required.

NPOs, Maintenance and HP personnel are standing by to support HPCI operations.

A manual start of HPCI was performed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago. HPCI has been returned to standby per OP-152-001.

S0-152-002 has been completed through Step 5.1.3.c(2).

Other operators will perform all timing operations during HPCI startup.

INITIATING CUE Perform a full-flow test of HPCI by completing S0-152-002 CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Main Steam Line Isolation and Quick Recovery in accordance with ON-184-001 S/RO 84.0N.2392.101 6 12/04/2014 Simulator Applicability JPM Number Revision Date Setting 123456 X1.23 1.1/1.1 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated

/rlk 12/04/2014 12/13/2014 Autifur Date Date

,._~~~.~-

Review

_JW5_}_tf

___ LJ;{u_~7 - 12/13/2014 Date Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

{,, ,.r; dft!I~,. ",.:t, ,., "

CONFIDENTIAL Examination Material

84.0N.2392.101Rev6 12/04/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision Revised from 84.0N.003.101 Rev 4; removed separate RO/SRO cues.

5 Re-validation not required.

Revised Action 24 to place switches to NORM not TEST. Identified during 6

validation.

CONFIDENTIAL Examination Material

84.0N.2392.101 Rev 6 12/04/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

8. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A ON-184-001, Main Steam Line Isolation And Quick Recovery (Revision 17)

3. TASK CONDITIONS An MSIV isolation and reactor scram occurred from rated power.

The cause of the MSIV isolation was a faulty isolation logic surveillance test procedure.

RCIC injection is controlling reactor level.

Reactor pressure is controlled by manual SRV actuation.

Restoration of normal steam loads and Main Turbine bypass valves is required for a reactor cooldown.

4. INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MS IVs per ON-184-001.

5. TASK STANDARD Pressure equalized around MSIVs and MSIVs re-opened CONFIDENTIAL Examination Material

84.0N.2392.101 Rev 6 12/04/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

• From a power operating IC, insert the following to cause a spurious MSIV isolation on high steam line flow:

IMF cmfRLOl_B211K3A IMF cmfRLOl_B211K3D

• Insert the following malfunctions as need to assist in stabilizing Reactor pressure:

cmfRV04_PSV141F13A(B)(C)(D) f:8

• Place the Mode Switch in SHUTDOWN.

• Place the simulator in RUN.

• Reduce reactor pressure to approximately 500 psig using SRVs.

• Take action to stabilize reactor level and pressure. Establish level control with RCIC and pressure control with SRVs.

• Allow plant conditions to stabilize.

• Delete the malfunctions listed above to allow re-opening MSIVs.

• Place the simulator in Freeze.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev 6 12/04/2014 Examinee Page 1 of 6 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-386, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Verifies ON-184-001 is governing procedure and Controlled copy of ON-184-001 obtained.

obtains controlled copy.

2* Places MSIV handswitches to CLOSE. Place control switches for following to CLOSE:

• Mn Stm Line A IB lso HV-141-F022A

• Mn Stm Line BIB lso HV-141-F022B

• Mn Stm Line C IB lso HV-141-F022C

• Mn Stm Line D IB lso HV-141-F022D

• Mn Stm Line A OB lso HV-141-F028A

• Mn Stm Line BOB lso HV-141-F028B

• Mn Stm Line COB lso HV-141-F028C

• Mn Stm Line DOB lso HV-141-F028D 3 Ensures Mn Stm Line IB Drain HV-141-F016 Observe Mn Stm Line IB Drain HV-141-CLOSED. F016 indicates FULL CLOSED.

4 Ensures Mn Stm Line OB Drain HV-141-F019 Observe Mn Stm Line OB Drain HV-141-CLOSED. F019 indicates FULL CLOSED.

5 Ensures Mn Stm Line Drain to Cdsr HV-141-F021 Observe Mn Stm Line Drain to Cdsr HV-CLOSED. 141-F021 indicates FULL CLOSED.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev6 12/04/2014 Examinee Page 2 of 6 Step Action Standard Eva I Comments 6 Ensures following steam turbines TRIPPED: Observe the following:

• Main Turbine

• MSV 1(2)(3)(4) POSITION ZI-

• Reactor Feed Pump Turbine A 10141 A(B)(C)(D) indicate O percent

• Reactor Feed Pump Turbine B OR

• Reactor Feed Pump Turbine C Annunciator MAIN TURB MASTER TRIP (AR-105-A01) in alarm

• On ICS HMI FW_OVERVIEW RFPT A(B)(C) icon GREY and indicate TRIPPED OR Annunciators RFPT A(B)(C) TRIP (AR-101-A10(A12)(A14)) in alarm 7 Determines if MSIVs closed due to Main Turbine Observe from Task Conditions MSIVs EHC malfunction. closed due to surveillance test.

8 Closes drip leg drain valves. Perform the following:

• Depress Drip Leg Orn HS-10112 AUTO PB

• Observe the following indicate FULL CLOSED 0 Drip Leg Orn HV-10112A1 0 Drip Leg Orn HV-1011281 0 Drip Leg Orn HV-10112C1 0 Drip Leg Orn HV-1011201 9 Closes bypass valve header drip leg drain valves. Perform the following:

• Depress BPV Hdr Drip Leg Orn Byps HS-10109AAUTO PB

• Observe BPV Hdr Drip Leg Orn Byps HV-10108A indicates FULL CLOSED CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev6 12/04/2014 Examinee Page 3 of 6 Step Action Standard Eva I Comments EVALUATOR NOTE The examinee may elect to depress the CLOSE PB for the following two valves even though the valves are already closed.

10 Closes Main Turbine stop valve below seat drain Observe MSV Bst Orn HV-10101A(B)(C)(D) valves. indicate FULL CLOSED.

11 Closes Seal Steam Evaporator main steam supply Observe SSE Mn Stm Sup CV HV-10703 control valve. indicates FULL CLOSED.

12 Ensures Seal Steam Evaporator main steam Observe the following indicate FULL supply line drain valves are closed. CLOSED

• SSE Mn Stm Sup Ln Orn HV-10767

• SSE Mn Stm Sup Ln Orn HV-10768 13* Closes Seal Steam pressure control valve isolation Depress SSE Press Ctlr lso HV-10704 valve. CLOSE PB.

EVALUATOR NOTE Pressure will not rise in this step because the Main Steam Line is depressurized. If the examinee anticipates this response, they may NIA this step.

14 Throttles Seal Steam Evaporator pressure control Perform the following:

bypass valve to establish seal steam header

• Depress and hold SSE Press Ctlr Byps pressure of 0.25 to 0.50 psig. HV-10705 OPEN PB until valve indicates DUAL

• Observe no change in seal steam header pressure as indicated on SSE Pressure Pl-10723

• Proceeds with procedure to re-open MS IVs EVALUATOR CUE If asked how to proceed based on pressure not rising, direct examinee to respond in accordance with the procedure.

15 Closes Seal Steam Evaporator pressure control Depress SSE Press Ctlr Byps HV-10705 bypass valve. CLOSE PB.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev 6 12/04/2014 Examinee Page 4 of 6 Step Action Standard Eva I Comments 16 Closes SJAE main steam supply isolation valve. Depress Mn Stm SJAE lso HV-10107 CLOSE PB.

EVALUATOR CUE If asked in the next step, direct examinee to continue with procedure.

17* Resets NSSSS logic. Depress and release the following PBs:

• Mn Stm Line Div 1 lso Reset HS-621-1 S32 Reset

• Mn Stm Line Div 2 lso Reset HS-B21-1 S33 Reset 18* Opens inboard MSIVs. Place the following HS to OPEN and observe valve indicates FULL OPEN:

• Mn Stm Line A IB lso HV-141-F022A

• Mn Stm Line BIB Isa HV-141-F022B

• Mn Stm Line C IB lso HV-141-F022C

• Mn Stm Line D IB Isa HV-141-F022D 19 Places MSIV drain valve thermal overloads in Perform the following:

service.

• Notify US to enter TRO 3.8.2.1

• Place AC MOV OL Byps HS-B21-1S37A to TEST

• Place DC MOV OL Byps HS-B21-1S37B to TEST EVALUATOR CUE As US acknowledge TRO 3.8.2.1 entry.

20* Opens Mn Stm Line IB Drain HV-141-F016. Place Mn Stm Line IB Drain HV-141-F016 HS to OPEN and observe valve indicates FULL OPEN.

21* Opens Mn Stm Line OB Drain HV-141-F019. Place Mn Stm Line OB Drain HV-141-F019 HS to OPEN and observe valve indicates FULL OPEN.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev 6 12/04/2014 Examinee Page 5 of 6 Step Action Standard Eva I Comments 22 Ensures Mn Steam Line Warm Up HV-141-F020 Observe Mn Steam Line Warm Up HV-141-OPEN. F020 indicates FULL OPEN.

23 Observes main steam line pressure RISING. Observe main steam line pressure RISING as indicated on Main Turbine Generator Recorder XR-19201.

EVALUATOR CUE Two minutes have passed.

24 Bypasses MSIV drain valve thermal overloads after Perform the following:

two minutes.

• Place AC MOV OL Byps HS-821-1S37A to NORM

• Place DC MOV OL 8yps HS-821-18378 to NORM

• Notify US to exit TRO 3.8.2.1 EVALUATOR CUE As US acknowledge TRO 3.8.2.1 exit.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 84.0N.2392.101 Rev 6 12/04/2014 Examinee Page 6 of 6 Step Action Standard Eva I Comments EVALUATOR NOTE MSIVs may be re-opened when !lP across the outboard MSIVs is less than 400 psid without inducing a severe reactor level transient or an MSIV re-isolation on high flow.

EVALUATOR CUE Once examinee displays ability to determine differential pressure across MSIVs and DIP is less than 400 psig, inform the candidate that the !lP requirements have been met and the MSIVs may be opened.

25 Opens outboard MSIVs. Place the following HS to OPEN and observe the associated valve indicates FULL OPEN

• Mn Stm Line A OB Isa HV-141-F028A

• Mn Stm Line BOB Isa HV-141-F028B

• Mn Stm Line COB Isa HV-141-F028C

• Mn Stm Line DOB Isa HV-141-F028D EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS An MSIV isolation and reactor scram occurred from rated power.

The cause of the MSIV isolation was a faulty isolation logic surveillance test procedure.

RCIC injection is controlling reactor level.

Reactor pressure is controlled by manual SRV actuation.

Restoration of normal steam loads and Main Turbine bypass valves is required for a reactor cooldown.

INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MS IVs per ON-184-001.

CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Perform Manual Component by Component S/U of Core Spray System IAW OP-151-001 S/RO 51.0P.1934.101 0 12/04/2014 Simulator Applicability JPM Number Revision Date Setting 209001 A2.06 3.2/3.2 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg Author 7

/'t j....--+2104/2014 Date Greg van den Berg ....

Instructor

//¥ 12/13/2014 Date Review Date 10 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material

51.0P.1934.101Rev0 12/04/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM CONFIDENTIAL Examination Material

51.0P.1934.101 Reva 12/04/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-151-001, Core Spray System (Revision 36)

3. TASK CONDITIONS A loss of coolant accident occurred 30 minutes ago.

E0-000-112, Rapid Depressurization, has been performed.

Both Core Spray subsystems failed to initiate automatically and manually using the Manual Initiation pushbuttons Core Spray Loop A was started manually component by component Reactor water level was being controlled +13" to +54" using Core Spray loop A Core Spray pump C has tripped

4. INITIATING CUE Manually start Core Spray Loop B, component by component IAW OP-151-001 to establish injection to the vessel to restore and maintain reactor water level +13" to +54".

5. TASK STANDARD Manually start Core Spray Loop B component by component per OP-151-001 and establish injection to restore and maintain reactor water level +14" to +54".

CONFIDENTIAL Examination Material

51.0P.1934.101 Rev O 12/04/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

• Reset simulator to IC 20

• Run scenario EVAL510P1934101 EVAL51OP1934101 inserts the following malfunctions to initiate a LOCA and fail all high-capacity injection sources other than Core Spray:

IMF mfRR164011A f:10 IMF mfRH149007A IMF mfRH149007C IMF mfRH1490078 IMF mfRH149007D IMF mfRC150007 IMF mfHP152011 IMF mfFW144003D IMF mfFW144003C IMF mfFW1440038 IMF mfFW144003A

• Place the Mode Switch in SHUTDOWN.

• Place all ADS valve control switches to OPEN.

• Place the simulator in RUN.

• Close MSIV's and Drains

• Insert Ni's

• Secure Core Spray loop B per OP-151-001 section 2.7.3.b (shutdown both pumps).

• Throttle Core Spray loop A inboard injection valve as necessary to maintain Reactor water level + 13" to +54".

• Allow plant conditions to stabilize.

• Place the simulator in Freeze.

• Consider snapping an IC for multiple performances of this JPM.

• When student is ready to begin JPM, place the simulator in RUN.

CONFIDENTIAL Examination Material

PERFur<MANCE CHECKLIST 51.0P.1934. ,..., I Rev 0 12/04/2014 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-387, or configure the simulator per the Simulator Setup Instructions.

• Mark-up a copy of OP-151-001 complete through Step 2.3.3 EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Identifies governing procedure and obtain Obtains controlled copy of OP-151-001, controlled copy. Core Spray System.

2 Determines section 2.3 is the correct section of the Performs Section 2.3.4 procedure.

3* Starts Core Spray pumps 1P206B and/or 1P206D Starts Core Spray Pump 1P206B by rotating control switch clockwise to START.

and/or Starts Core Spray Pump 1P206D by rotating control switch clockwise to START.

EVALUATOR NOTE Operator may ask if pumps will be on Minimum Flow for continuous operation for more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

EVALUATOR CUE If asked, Core Spray system operation at minimum flow will be less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

4 Verifies Core Spray loop injection valve is Open. Open OR Check Open CORE SPRAY LOOP BOB INJ SHUTOFF HV-152F004B CONFIDENTIAL Examination Material

PERFOKMANCE CHECKLIST 51.0P.1934 .. 01 Reva 12/04/2014 Examinee Page 2 of 2 Step Action Standard Eva I Comments 5 Bypasses Lo Reactor Pressure Permissive WHEN Reactor pressure < 420 psig, Place LO RX PRESS PERM switch HS-15249B to BYPASS 6* Throttle Open CORE SPRAY LOOP BIB INJ Throttles open HV-152-F005B by rotating SHUTOFF HV-152F005B to establish loop flow as control switch clockwise to OPEN follows:

• : : : 90 amps and : : : 7900 gpm for two pump operation (emergency operation)

• : : : 90 amps and : : : 3950 gpm for one pump operations (emergency operation) 7 WHEN flow to reactor vessel::::: 635 gpm, Ensure WHEN Core Spray loop flow rises to 635 CORE SPRAY LOOP B MIN FLOW HV-152F031B gpm, observes HV-152F031 B amber light CLOSES on, red light off 8 Check Core Spray Room Unit Coolers 1V211 B Observes 1V211B and/or D red light on, and/or D AUTO STARTS indicated on Heating and amber light off Ventilation Panel 1C681 EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS A loss of coolant accident occurred 30 minutes ago.

E0-000-112, Rapid Depressurization, has been performed.

Both Core Spray subsystems failed to initiate automatically and manually using the Manual Initiation pushbuttons Core Spray Loop A was started manually component by component Reactor water level was being controlled +13" to +54" using Core Spray loop A Core Spray pump C has tripped INITIATING CUE Manually start Core Spray Loop B, component by component IAW OP-151-00 section 2.3.4 to establish injection to the vessel to restore and maintain reactor water level +13" to +54".

CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Placing RHRSW In-Service for Suppression Pool Cooling with Piping Rupture S/RO 16.0P.1354.151 3 08/08/2014 Simulator Applicability JPM Number Revision Date Setting 219000 A4.05 3.4/3.4 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated AuifuS'r

~t [Z/

l 12/04/2014 Date

/-t~

irrrtrUCtOr 12/13/2014 Date Review 12/13/2014 Date Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

(,. "' r,uin.; F~11*J/" .,, ,.

CONFIDENTIAL Examination Material

16.0P.1354.151 Rev 3 08/08/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM 1 Revise for TO procedures, minor editorial corrections 2 Reformatted to the "TQ" procedure format Validation comment to remove bullet in action 18 referencing Fl-E11-1 R602A 3

pegging high CONFIDENTIAL Examination Material

16.0P.1354.151 Rev3 08/08/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-149-005, RHR Suppression Pool Cooling (Rev 28)

B. OP-054-001, ESW System (Rev 38)

C. OP-116-001, RHR Service Water (Rev 46)

D. AR-109-H04, RHRSW PUMP A DISCHARGE LO PRESS (Rev. 33)

E. AR-109-H08, RHR LOOP A PUMP ROOM FLOODED (Rev. 33)

3. TASK CONDITIONS Unit 1 is operating in Mode 1.

A quarterly RCIC surveillance test has been scheduled. Suppression Pool cooling is required.

Radwaste is unable to accept Suppression Pool water for processing.

All systems are aligned for normal standby operation in accordance with their respective OP.

4. INITIATING CUE Place RHR A in service in Suppression Pool cooling

5. TASK STANDARD Starts ESW; trips RHRSW Pump A on evidence of RHRSW leakage into RHR A room CONFIDENTIAL Examination Material

16.0P.1354.151 Rev 3 08/08/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

• Reset the simulator to IC-18, or an exam-specific IC if prepared (IC 388).

• Insert the following Event Triggers ET160P1354151 diHS11202A2. CurrValue =#OR. diHS11202A2. START IMF mfEW116001 d:5 r:15 f:lOO IMF cmfTR02_PT11203A d:5 r:15 f:10 IMF annAR109H04 d:15 f:ALARM_ON CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 16.0P.1354.151 Rev3 08/08/2014 Examinee Page 1 of 5 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-388, or configure the simulator per the Simulator Setup Instructions.

EVALUATOR NOTE The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Verifies OP-149-005 Section 2.1 is governing Controlled copy of OP-149-005 obtained, procedure and obtains controlled copy. select Section 2.1.

2 Verifies prerequisites are satisfied. Observe RHR, RHRSW and ESW are in normal standby alignment is specified in Task Conditions.

EVALUATOR CUE Suppression Chamber access is closed.

EVALUATOR CUE Suppression Pool cleanup is not required.

3 Verifies OP-054-001 Section 2.2 is governing Controlled copy of OP-054-001 obtained, procedure for placing ESW in service and obtains select Section 2.2.

controlled copy.

4* Starts ESW pump in A loop. Depress ESW Pump OP504A(C) RUN pushbutton EVALUATOR CUE Another operator will update the Spray Pond Operations Log.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 16.0P.1354.151Rev3 08/08/2014 Examinee Page 2 of 5 Step Action Standard Eva I Comments 5 Ensures flow path to Spray Pond. Observe one of the following:

• HV-01222A ESW POND SPR 8PV A, indicates full open.

• HV-01224A1, ESW POND SPR IN A1, indicates full open.

• HV-01224A2, ESW POND SPR IN A2, indicates full open.

6 Ensures ESW pumphouse ventilation fan starts Perform the following:

and damper aligned.

• At OC681, observe OV521A(C) ESW PP SUPPLY FAN running

• Direct NPO to verify ESW pumphouse ventilation aligned per OP-128-001 EVALUATOR CUE ESW pumphouse ventilation is aligned per procedure.

7 Starts ESW pump in other loop. Depress ESW Pump OP504B(D) RUN pushbutton 8 Ensures flow path to Spray Pond. Observe one of the following:

• HV-012228 ESW POND SPR BPV B, indicates full open

• HV-0122481, ESW POND SPR IN 81, indicates full open

• HV-0122482, ESW POND SPR IN 82, '

indicates full open 9 Ensures ESW pumphouse ventilation fan starts Perform the following:

and damper aligned.

• At OC681, observe OV521 B(D) ESW PP SUPPLY FAN running

• Direct NPO to verify ESW pumphouse ventilation aligned per OP-128-001 EVALUATOR CUE ESW pumphouse ventilation is aligned per procedure.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 16.0P.1354.151Rev3 08/08/2014 Examinee Page 3 of 5 Step Action Standard Eva I Comments 10 Verifies ESW flows within applicable limits. Observe A/C DSCH HOR LOOP A FLOW Fl-01109A and B/D DSCH HOR LOOP B FLOW Fl-011098 indicate approximately 4200-4800 gpm.

EVALUATOR CUE Another operator will place Spray Pond spray networks in service.

11 Verifies OP-116-001 Section 2.2 is governing Controlled copy of OP-116-001 obtained, procedure for placing RHRSW in service and select Section 2.2.

obtains controlled copy.

12 Complies with TRO 3.8.2.1. Inform Unit Supervisor to comply with TRO 3.8.2.1.

EVALUATOR CUE As Unit Supervisor, acknowledge TRO entry.

13 Places RHRSW Division 1 MOV overloads in At OC697 Motor Overload Bypass Control service. Panel, Place HS-11210A1 RHRSW Sys Unit 1 Div 1 to TEST 14 Ensures HV-21210A, RHRSW HX A Inlet, closed. Contact Unit 2 PCO and request HV-21210A UNIT 2 RHRSW HX A INLET CLOSED if not already full closed.

EVALUATOR CUE HV-21210A is closed.

15* Opens HV-11210A, RHRSW Hx A Inlet, 10 percent Place HV-1121 OA, UNIT 1 RHRSW HX A(B) open. INLET, to OPEN until 10 percent indicated on Zl-11210A, RHRSW HX A INLET VLV POSN.

16* Opens HV-11215A, RHRSW Hx A Outlet. Place HV-11215A, RHRSW HX A OUTLET, to OPEN.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 16.0P.1354.151Rev3 08/08/2014 Examinee Page 4 of 5 Step Action Standard Eva I Comments 17 Ensures flow path to Spray Pond. Observe one of the following:

• HV-01222A(B) ESW POND SPR BPV A(B), indicate full open

• HV-01224A1(B1), ESW POND SPR IN A 1(81 ), indicate full open

• HV-01224A2(B2), ESW POND SPR IN A2(82), indicate full open EVALUATOR CUE If questioned, as Unit Supervisor respond that the system was NOT drained for maintenance.

FAULT STATEMENT A MAJOR LEAK DEVELOPS FROM RHRSW A INTO THE RHR A ROOM WHEN THE PUMP IS STARTED.

18* Starts RHRSW Pump A. Perform the following:

• *Place 1P506A, RHRSW PUMP A, to START

• Observe AR-109-H04 in alarm

• Observes AR-109-H08 in alarm

• Informs Unit Supervisor of suspected RHRSW leak into RHR A room, E0-100-104 entry EVALUATOR CUE Respond to RHRSW and RHR room flooded alarms. I will enter E0-100-104 and have another operator perform actions in that procedure.

EVALUATOR NOTE Actions to close RHRSW A inlet/outlet valves permissible, but not required for successful completion of task.

• 19 Trips RHRSW Pump A. Place 1P506A, RHRSW PUMP A, to STOP.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 16.0P.1354.151 Rev 3 08/08/2014 Examinee Page 5 of 5 Step ) Action ) Standard ) Eval ) Comments EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is operating in Mode 1.

A quarterly RCIC surveillance test has been scheduled. Suppression Pool cooling is required.

Radwaste is unable to accept Suppression Pool water for processing.

All systems are aligned for normal standby operation in accordance with their respective OP.

INITIATING CUE Place RHR A in service in Suppression Pool cooling CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Implement Placing Alternate TBCCW Pump In Service S/RO 15.0P.1347.151 1 10/23/2014 Simulator Applicability JPM Number Revision Date Setting 400000 A2.01 3.3/3.4 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated

~/v/- 11/26/2014 fi-IL 12/13/2014 Date lnstfUctor Date Review 12/13/2014 Date Date 10 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material

15.0P.1347.151 Rev 1 10/23/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections CONFIDENTIAL Examination Material

15.0P.1347.151 Rev 1 10/23/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-115-001, Turbine Building Closed Cooling Water System (Revision 24)

B. ON-115-001, Loss of Turbine Building Closed Cooling Water (Revision 22)

C. AR-123-802, TBCCW PUMP B MOTOR TRIP (Revision 25)

D. AR-123-804, TBCCW HEAT EXCHANGER HEADER LO PRESS (Revision 25)

3. TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1Bis in standby.

TBCCW Pump 1A is to be removed from service for planned maintenance.

Pre-start checks for TBCCW Pump 1B are sat.

An NPO is stationed in the Unit 1 TBCCW pump area.

4. INITIATING CUE Place TBCCW Pump 1B in service and shutdown TBCCW Pump 1A.

5. TASK STANDARD TBCCW Pump 1A restarted and supplying cooling to TBCCW loads CONFIDENTIAL Examination Material

15.0P.1347.151Rev1 10/23/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

• Reset the simulator to IC-18, or an exam-specific IC if prepared.

• Insert the following Event Triggers ET150P1347151 tw_1p103a(1) = 0 &twvp114011 > 0. 9 IMF cmfPM02_1P103B ET150P1347151A diHS11405A. CurrValue =#OR. diHS11405A.RUN

+30 !OR di1C140ACK_O f:ACK

+2 MOR di1C140ACK_Q f:NORMAL

+2 DOR di1C140ACK_Q

+2 !OR di1C140RST_Q f:RESET

+2 MOR di1C140RST_Q f:NORMAL

+2 DOR di1C140RST_Q

!RF rf!A119003 f:RESET

• Perform the following expert commands IMF cmfPM04_1P103A i/a xtie to U2

• Perform the following expert commands to assign keys to perform the required operator actions for the JPM.

[Key [26)) !RF rfTW115001 f: 0

[Key [27]} !RF rfTW115001 f: 100 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 15.0P.1347.151Rev1 10/23/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on ~espective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-18, or configure the simulator per the Simulator Setup Instructions .

EVALUATOR NOTE The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Identifies OP-115-001 Section 2.2 is governing Obtains controlled copy of OP-115-001 procedure and obtains controlled copy. obtained, selects Section 2.2 ..

2* Starts TBCCW Pump 1B Depresses TBCCW PP 1P103B RUN PB 3 Closes TBCCW Pump 1A discharge valve Directs NPO to slowly close 114011, TBCCW PUMP A DSCH BOOTH OPERATOR CUE Depress KEY 26 to close 114011.

EVALUATOR CUE 114011 is closed.

4 Checks TBCCW Pump 1B discharge pressure 86- Performs the following:

100 psig.

• Requests from NPO current indication on Pl-114058, TBCCW PUMP B DSCH PRESS.

• Confirms value is within 86-100 psig band.

EVALUATOR CUE Pl-114058 indicates 98 psig.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 15.0P.1347.151Rev1 10/23/2014 Examinee Page 2 of 3 Step Action Standard Eva I Comments 5* Stops TBCCW Pump 1A. Depresses TBCCW PP 1P103A STOP PB.

6 Checks TBCCW HX 1A outlet temperature 92- Performs the following:

98 °F.

• Requests from NPO current indication on Tl-11407 A, TBCCW HX A OUTLET TEMP.

• Confirms value is within 92-98 °F band.

EVALUATOR CUE Tl-11407 A indicates 95 °F.

7 Checks TBCCW system pressure stabilizes at Observes Pl-11409, TB CCW HX OUTLET approximately 64-66 psig. HEADER, indicates approximately 64-66 psig.

EVALUATOR NOTE The following step is a critical step only if the TBCCW Pump 1A discharge valve was closed in the preceeding steps.

FAULT STATEMENT TBCCW PUMP 18 TRIPS WHEN TBCCW PUMP 1A DISCHARGE VALVE IS STROKING OPEN.

8* Opens TBCCW Pump 1A discharge valve. Performs the following:

• Directs NPO to open 114011, TBCCW PUMP A DSCH

• Observes AR-123-G02, TBCCW PUMP B MOTOR TRIP, in alarm.

• Informs Unit Supervisor of TBCCW Pump 1B trip.

BOOTH OPERATOR CUE

• Depress KEY 27 to open 114011 .

• Ensure Event Trigger ET150P1347151 fires as 114011 strokes open to trip TBCCW Pump 1B.

EVALUATOR CUE As NPO: 114011 is open.

As Unit Supervisor: Respond per procedure.

As NPO if contacted about TBCCW Pump 1B status: TBCCW Pump 1B tripped. I don't know why.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 15.0P.1347.151 Rev 1 10/23/2014 Examinee Page 3 of 3 Step j Action I Standard Eva I Comments

• EVALUATOR NOTE Direction to start TBCCW Pump 1A is provided in AR-123-G02, AR-123-G04, or ON-115-001.

9* I Starts TBCCW Pump 1A. I Depresses TBCCW PP 1P103A RUN PB.

BOOTH OPERATOR CUE Ensure Event Trigger ET150P1347151A fires when TBCCW Pump 1A is re-started to reset I/A and SIA compressors.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS TBCCW Pump 1A is in service, TBCCW Pump 1B is in standby.

TBCCW Pump 1A is to be removed from service for planned maintenance.

Pre-start checks for TBCCW Pump 1B are sat.

An NPO is stationed in the Unit 1 TBCCW pump area INITIATING CUE Place TBCCW Pump 1 Bin service and shutdown TBCCW Pump 1A CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Restore Offgas System IAW ON-143-011 S/RO 72.0N.1786.101 0 12/05/2014 Simulator Applicability JPM Number Revision Date Setting 271000 A2.11 2.8/2.9 N N NUREG-1123 KIA Number K/A Importance Alternate Path Time Critical E/APE I Sys Prepared Validated

/Iv~ 11/26/2014 12/15/2014 Authe? Date Date Review 12/15/2014 Date Date 15 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material

72.0N.1786.101Rev0 12/05/2014 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM CONFIDENTIAL Examination Material

72.0N.1786.101Rev0 12/05/2014 Page 3 of 4 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. ON-143-001, Main Condenser Vacuum and Offgas System (Revision 38)

3. TASK CONDITIONS Unit 1 is operating in Mode 1.

A spurious closure of HV-10721 occurred, causing an ARESD ON-143-001 has been entered

4. INITIATING CUE Restore the Offgas System IAW ON-143-001, step 3.6.7

5. TASK STANDARD Restores the Offgas System IAW ON-143-001, Step 3.6.7 CONFIDENTIAL Examination Material

72.0N.1786.101 Rev O 12/05/2014 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to IC 390.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 72.0N.1786.101Rev0 12/05/2014 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the simulator. Reset to exam-specific IC-390, or configure the simulator per the Simulator Setup Instructions.

• Mark-up a copy of ON-143-001 complete through Step 3.6.6 .

EVALUATOR CUE Record JPM start time:

BOOTH OPERATOR CUE When the evaluator indicates the examinee is ready to begin the JPM, place the simulator in RUN.

1 Identifies ON-143-001 is the governing procedure Obtains controlled copy of ON-143-001, and obtains controlled copy. selects step 3.6.7.

CONFIDENTIAL Examination Material

PERFOt<i\llANCE CHECKLIST 72.0N.1786 .. .,, I Rev 0 12/05/2014 Examinee Page 2 of 4 Step Action Standard Eva I Comments 2*  !.E Offgas System Automatic Isolation OR an

• Ensure Isolation occurred by ARESD Signal occurred, THEN Performs following: checking SJAE Suet Isa Vlvs HV-10716, HV-10717, HV-10718 and HV-10719 CLOSED, as indicated by Amber light ILLUMINATED at HS-10716 SJAE Suet Isa

• *JE isolation originated from Low Dilution Steam Flow, OR an ARESD Signal THEN Perform following:

0 *IF on Main Steam, THEN Ensure following valves are OPEN:

0 *HV 10721 SJAE Dsch Isa.

0 *HV 10702 SJAE Sec. Eject Isa.

0 *HV 10701A SJAE Mn Stm Sup Isa.

0 *HV 10701 B SJAE Mn Stm Sup Isa.

0 *HV 10107 Mn Stm SJAE Isa.

0 *HV 10722 SJAE Sup. Pri.

Eject Isa.

3 Check steam pressure _:::110 psig on Pl-10701 Check Steam Supply Pressure is >110 psig SJAE Stm Sup Press on Pl 10701 4 IF steam pressure on Pl-10701 <110 psig, THEN Evaluates the need to transfer to an Evaluate transferring steam supply to the alternate alternate steam supply source in accordance with OP-172-001.

EVALUATOR NOTE Alternate steam supply will not be necessary CONFIDENTIAL Examination Material

PERFut<.MANCE CHECKLIST 72.0N.1786 .* 01Rev0 12/05/2014 Examinee Page 3 of 4 Step Action Standard Eva I Comments 5 IF Dilution Steam Flow is <10,700 lb/hr, THEN at

• Check FIC 10702A(B) Dilution Stm OC145, Perform following: Flow Viv A(B) Controller in AUTO, with setpoint at 10,800 lb/hr.

• IF necessary, THEN Place FIC 10702A(B) Dilution Stm Flow Viv A(B) Controller in MANUAL.

• Adjust FIC 10702A(B) Dilution Stm Flow Viv A(B) Controller to establish 10,800 lb/hr flow.

• WHEN automatic controls functional, THEN Place FIC 10702A(B) Dilution Stm Flow Viv A(B) Controller in AUTO, with setpoint at 10,800 lb/hr.

• Place FIC 10702B(A) Dilution Steam Flow Viv B(A) Controller in AUTO as backup, with a setpoint at 10,700 lb/hr.

BOOTH OPERATOR CUE Insert Key 1 when requested to perform field actions at OC145.

6 Return Unit 1 (Common) Recombiner to service by:

• Notify HP that Ops will be returning Unit 1 (Common) Recombiner to service.

• At OC673 Offgas Recombiner Panel, Ensure Dilution Steam flow :2! 10,700 lb/hr on Fl 10702, Dilution Steam Flow.

• Momentarily Depress HS 10716 (1 C668) Open pushbutton to open SJAE Suet lso Vlvs HV 10716, HV 10717, HV 10718 and HV 10719.

EVALUATOR CUE Record JPM stop time:

CONFIDENTIAL Examination Material

PERFur<.MANCE CHECKLIST 72.0N.1786 .. v1Rev0 12/05/2014 Examinee Page 4 of 4 Step \ Action j Standard j Eval j Comments EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is operating in Mode 1.

A spurious closure of HV-10721 occurred, causing an ARESD ON-143-001 has been entered INITIATING CUE Restore the Offgas System IAW ON-143-001, step 3.6.7 CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Shifting CRD Drive Water Filters S/RO 55.0P.2016.001 4 08/08/2014 Plant Applicability JPM Number Revision Date Setting 201001 K1.02 3.0/3.0 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Autho/ ~7 12/04/2014 Date Instructor Lz )~gr 12/13/2014 Date Review 12/13/2014 1

Date Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: - - - - - - - Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

(;,l'<'r,<lin:\ f'.",-r1*f/1 .,, ..

CONFIDENTIAL Examination Material

55.0P.2016.001 Rev 4 08/08/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM 1 Revise for TQ procedures, minor editorial corrections 2 Revised due to reference revision 3 Reformatted to the "TQ" procedure format 4 Updated reference revision, removed Unit 2 references CONFIDENTIAL Examination Material

55.0P.2016.001 Rev 4 08/08/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-155-001, CRDH SYSTEM (Revision 61)

3. TASK CONDITIONS Unit 1 is operating at 100% power.

Foreign material has entered the Unit 1 CST.

The CRD pump suction filter has been bypassed to keep a CRD pump in-service.

CRD Drive Water Filter A differential pressure is rising

4. INITIATING CUE Shift CRD Drive Water Filters, placing B in service and removing A from service, per OP-155-001 Section 2.12

5. TASK STANDARD Shift CRD drive water filters, with B in service and A removed from service and isolated CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0P.2016.001 Rev 4 08/08/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a *. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a * .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Unit 1(2) CRD drive water filter area.

• Unit 2 equipment designations are in parentheses () after Unit 1.

EVALUATOR CUE Record JPM start time:

1 Verifies OP-155-001 Section 2.12 is governing Controlled copy of OP-155-001 obtained, procedure and obtains controlled copy. selects Section 2.12.

2* Aligns 1F204B, Drive Water Filter B vent path Performs the following:

• Opens 146004, DRIVE WTR FILTER B VENT, by rotating the valve handwheel in the counter-clockwise direction until resistance is felt

• Opens 146F0228, DRIVE WTR FILTER B VENT, by rotating the valve handwheel in the counter-clockwise direction until resistance is felt EVALUATOR CUE You feel resistance in the counter-clockwise direction.

3* Vents 1F2048, Drive Water Filter B Performs the following

• Slowly throttles open 146F021 B, CRD DRIVE WTR FILTER B OUTLET ISO VLV, by rotating the valve handwheel in the counter-clockwise direction

• Observes steady stream of water from vent line CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0P.2016.001 Rev 4 08/08/2014 Examinee Page 2 of 3 Step Action Standard Eva I Comments EVALUATOR CUE You observe a steady stream of water from the B filter vent.

4* Isolates 1F204B, Drive Water Filter B vent path. Performs the following:

• Slowly closes 146F022B, DRIVE WTR FILTER B VENT, by rotating the valve handwheel in the clockwise direction until resistance is felt

• Closes 146004 (146006), DRIVE WTR FILTER B VENT, by rotating the valve handwheel in the clockwise direction until resistance is felt EVALUATOR CUE You feel resistance in the clockwise direction.

5* Opens 146F021 B, CRD Drive Wtr Filter B Outlet Slowly throttles open 146F021 B, CRD lso Viv fully. DRIVE WTR FILTER B OUTLET ISO VLV, by rotating the valve handwheel in the counter-clockwise direction until resistance is felt.

EVALUATOR CUE You feel resistance in the counter-clockwise direction.

6* Opens 146F020B, CRD Drive Wtr Filter B Inlet lso Slowly throttles open 146F020B, CRD Viv. DRIVE WTR FILTER B INLET ISO VLV, by rotating the valve handwheel in the counter-clockwise direction until resistance is felt.

EVALUATOR CUE You feel resistance in the counter-clockwise direction.

7* Closes 146F020A, CRD Drive Wtr Filter A Inlet lso Closes 146F020A, CRD DRIVE WTR Viv. FILTER A INLET ISO VLV, by rotating the valve handwheel in the clockwise direction until resistance is felt.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0P.2016.001 Rev 4 08/08/2014 Examinee Page 3 of 3 Step Action Standard Eva I Comments EVALUATOR CUE You feel resistance in the clockwise direction 8* Closes 146F021A, CRD Drive Wtr Filter A Outlet Closes 146F021A, CRD DRIVE WTR lso Viv. FILTER A INLET ISO VLV, by rotating the valve handwheel in the clockwise direction until resistance is felt.

EVALUATOR CUE You feel resistance in the clockwise direction EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Unit 1 is operating at 100% power.

Foreign material has entered the Unit 1 CST.

The CRD pump suction filter has been bypassed to keep a CRD pump in-service.

CRD Drive Water Filter A differential pressure is rising INITIATING CUE Shift CRD Drive Water Filters, placing B in service and removing A from service, per OP-155-001 Section 2.12 CONFIDENTIAL Examination Material

PPLSUSQUEHANNA,LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Establish and Maintain Reactor Vessel Level (RCIC Not Injecting) from the U2 RSDP S/RO 50.0P.1916.201 4 08/08/2014 Plant Applicability JPM Number Revision Date Setting 295016 AA1.06 4.0 / 4.1 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated 12/04/2014 12/13/2014 Author-?' V Date Date Review 12/13/2014 Date Date 15 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA.

'" ;, '""_.I ., ..

CONFIDENTIAL Examination Material

50.0P.1916.201 Rev3 08/08/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM 1 Revise for TQ procedures, minor editorial corrections 2 Updated to reflect procedure revision of OP-250-001 Rev 40 3 Reformatted to the "TQ" procedure format Updated reference revision 4 Minor typo corrections and editorial changes No other changes identified during validation CONFIDENTIAL Examination Material

50.0P.1916.201 Rev3 08/08/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. ON-200-009 Rev 31, Control Room Evacuation B. OP-250-001 Rev 43, Reactor Core Isolation Cooling (RCIC) System

3. TASK CONDITIONS A condition has occurred requiring abandonment of the Control Room.

All required immediate operator actions of ON-200-009 have been completed prior to abandoning the Control Room.

Control has been transferred to the Remote Shutdown Panel per ON-200-009 Section 4.3.

Reactor vessel water level is decreasing.

Reactor pressure is being maintained by SRVs cycling.

RCIC is not running. There has been no initiation signal.

An NPO is stationed outside the Unit 2 RCIC room.

4. INITIATING CUE Manually initiate RCIC and establish 625 gpm flow to the reactor

5. TASK STANDARD RCIC started and feeding the reactor vessel at 625 gpm CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.0P.1916.201 Rev 3 08/08/2014 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step.

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to the Unit 2 Remote Shutdown Panel.

EVALUATOR CUE Record JPM start time:

1 Verifies OP-250-001 Section 2.15 is governing Controlled copy of OP-250-001 obtained, procedure and obtains controlled copy. selects Section 2.15.

EVALUATOR NOTE Student may review previous sections of ON-200-009.

2 Verifies prerequisites satisfied. Observe from Task Conditions prerequisites for RCIC operation from RSDP are met per Task Conditions.

EVALUATOR NOTE Per OP-250-001, if at any time RCIC flow becomes unstable, the examinee may elect to place RCIC Flow Controller in MANUAL. For this JPM leaving the RCIC Flow Controller in MANUAL at the end of the task represents unacceptable performance.

3 Observes ES-24901 RCIC STATIC INVERTER On panel ES-24901, RCIC STATIC light ILLUMINATED .. INVERTER, observe status light illuminated GREEN.

EVALUATOR CUE Status light is illuminated.

4 Ensures RCIC TURBINE FLOW CONTROLLER Observe RCIC TURBINE FLOW FIC-24903 in AUTO set at 625 gpm. CONTROLLER FIC-24903 in AUTO with setpoint set to approximately 625 gpm.

EVALUATOR CUE Controller is selected to AUTO with setpoint at 625 gpm.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.0P.1916.201 Rev 3 08/08/2014 Examinee Page 2 of 4 Step Action Standard Eva I Comments 5 Notify HP of intent to start RCIC and Evacuate Dispatches NPO to check RCIC and HPCI personnel from RCIC and HPCI pump rooms and pump rooms, 670' RCIC/HPCI pipe tunnel 670' RCIC/HPCI pipe tunnel. clear of personnel.

EVALUATOR CUE Requested areas are clear of personnel.

• 6 Place RCIC TURBINE FLOW CONTROLLER Perform the following on FIC-24903, RCIC FIC-24903 in MANUAL and set for MINIMUM TURBINE FLOW CONTROLLER:

SPEED.

• Place the AIM toggle to M

• Depress the CLOSE PB until 0 percent controller output indicated EVALUATOR CUE Controller is selected to MANUAL and minimum speed.

7 Start RCIC BARO CDSR VACUUM PP 2P219. Place 2P219 RCIC BARO CDSR VACUUM PP HS to START.

EVALUATOR CUE HS is in START. AMBER light EXTINGUISHED, RED light LIT.

• 8 Open STEAM TO RCIC TURBINE HV-250-F045. Place STEAM TO RCIC TURBINE HV-250-F045 HS to OPEN and release.

EVALUATOR CUE HS to OPEN. RED light LIT.

After a brief time delay: AMBER light EXTINGUISHED.

9 Observe RCIC Turbine ACCELERATES. Observe RCIC turbine speed rising on RCIC TURBINE SPEED Sl-25001 B.

EVALUATOR CUE RCIC turbine speed is approximately 1000 rpm, steady.

• 10 Open MIN FLOW TO SUPP POOL FV-249-F019. Place MIN FLOW TO SUPP POOL FV-249-F019 HS to OPEN and release (Springs back to normal CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.0P.1916.201 Rev 3 08/08/2014 Examinee Page 3 of 4 Step Action Standard Eva I Comments EVALUATOR CUE HS to OPEN. RED light LIT.

After a brief time delay: AMBER light EXTINGUISHED.

• 11 Open RCIC INJECTION HV-249-F013. Place RCIC INJECTION HV-249-F013 HS to OPEN and release EVALUATOR CUE HS to OPEN. RED light LIT.

After a brief time delay: AMBER light EXTINGUISHED.

• 12 Establish desired flow using RCIC TURBINE On RCIC TURBINE FLOW CONTROLLER FLOW CONTROLLER FIC-24903. FIC-24903 depress OPEN and CLOSE PB as necessary to raise controller output and RCIC turbine speed to inject to reactor at approximately 625 gpm as indicated on RCIC PUMP INJECTION FLOW Fl-14903.

EVALUATOR CUE Controller output rising.

RCIC indicates as expected.

13 Close MIN FLOW TO SUPP POOL FV-249-F019 Place MIN FLOW TO SUPP POOL when RCIC flowrate above 250 gpm. FV-249-F019 HS to CLOSE and release.

EVALUATOR CUE HS to CLOSE. AMBER light LIT.

After a brief time delay: RED light EXTINGUISHED.

14 Null RCIC TURBINE FLOW CONTROLLER On RCIC TURBINE FLOW CONTROLLER FIC-24903. FIC-24903 adjust setpoint up and down as necessary until red flow indication within the GREEN band.

15 Place RCIC TURBINE FLOW CONTROLLER On FIC-24903, RCIC TURBINE FLOW FIC-24903 in AUTO. CONTROLLER place the AIM toggle to A CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.0P.1916.201 Rev 3 08/08/2014 Examinee Page 4 of 4 Step Action Standard Eva I Comments EVALUATOR CUE Controller is in AUTO.

16 Place ESW System in operation in accordance with EVALUATOR CUE OP-054-001 to supply RCIC Pump Room Unit Another operator will perform that task.

Cooler.

17 Place Suppression Pool cooling in operation in EVALUATOR CUE accordance with OP-249-005. Another operator will perform that task.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAM I NEE TASK CONDITIONS A condition has occurred requiring abandonment of the Control Room.

All required immediate operator actions of ON-200-009 have been completed prior to abandoning the Control Room.

Control has been transferred to the Remote Shutdown Panel per ON-200-009 Section 4.3.

Reactor vessel water level is lowering.

Reactor pressure is being maintained by SRVs cycling.

RCIC is not running. There has been no initiation signal.

An NPO is stationed outside the Unit 2 RCIC room.

INITIATING CUE Manually initiate RCIC and establish 625 gpm flow to the reactor CONFIDENTIAL Examination Material

PPL SUSQUEHANNA, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Start Containment Hydrogen Recombiner S/RO 73.0P.011.202 8 12/04/2014 Plant Applicability JPM Number Revision Date Setting 223001 A2.01 4.3/4.4 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated 12/04/2014 12/13/2014 Author Date Instf'Uctor Date Review 12/13/2014 Date Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: Exam Duration (Min) - - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments TEAM SUSQUEHANNA_

... ,,, ... ,;11,/\1*,*i!,,,,,

CONFIDENTIAL Examination Material

73.0P.011.202 Rev 8 08/07/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 New JPM Revise for TQ procedures, minor editorial corrections, updated reference 6

revisions.

7 Format change 8 Revision to incorporate updated reference revision CONFIDENTIAL Examination Material

73.0P.011.202 Rev 8 08/07/2014 Page 3 of 3 REQUIRED TASK INFORMATION

1. SAFETY CONSIDERATiONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment such as hearing or eye protection, safety shoes, hardhats, etc., is required and/or posted as being necessary.

C. If, in the judgment of the Evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

D. Peer checking is the expectation for all evolutions; however, since a JPM is an individual effort, no peer check will be provided and Self Checking is required.

2. REFERENCES A. OP-273-001Rev47, CONTAINMENT ATMOSPHERE CONTROL SYSTEM

3. TASK CONDITIONS A. Unit 2 is in a post-LOCA condition approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the event.

B. Containment H2 and 0 2 concentrations are below combustible limits.

C. Pre-LOCA containment temperature was 135°F.

D. Post-LOCA containment pressure is 6 psig.

4. INITIATING CUE Start Containment Hydrogen Recombiner 2E440A(B)(C)(D) in Manual per OP-273-001 Section 2.9.

5. TASK STANDARD Selected Recombiner operating in Manual IAW OP-273-001.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 73.0P.011.202 Rev 8 08/07/2014 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

• Marking a step as UNSAT requires written comments on respective step .

• Critical steps are marked with a*. If elements of the Standard are non-critical, the critical elements of the Standard are marked with a* .

• The time clock starts when the candidate acknowledges the Initiating Cue .

• This JPM must be performed in the plant. Obtain Shift Manager authorization to proceed. This JPM requires access to Upper or Lower Relay rooms.

EVALUATOR CUE Record JPM start time:

1 Identifies controlled copy of OP-273-001, select Obtains a controlled copy of OP-273-001 correct section, and review procedure. from evaluator. Selects Section 2.9.

Reviews prerequisites and precautions.

EVALUATOR NOTE If asked, inform the candidate that all prerequisites have been met 2 (Step 2.9.3) Ensure Hz Recombiner aligned as Simulates rotating H2 Rcb A(B)(C)(D) Heater follows prior to startup: Power Adj Control HC-25796A(B)(C)(D) counterclockwise until potentiometer STOPS (Step 2.9.3.a) Turn H2 Rcb A(B)(C)(D) Heater Power Adj Control HC-25796A(B)(C)(D) in counter clockwise direction until potentiometer STOPS EVALUATOR CUE Indicate H2 Rcb A(B)(C)(D) Heater Power Adj Control HC-25796A(B)(C)(D) is rotated fully counterclockwise 3 (Step 2.9.3.b) Set Hz Rcb A(B)(C)(D) Heater Power Simulates rotating Hz Rcb A(B)(C)(D) Heater Adj Control HC-25796A(B)(C)(D) to ZERO (000) Power Adj Control HC-25796A(B)(C)(D) potentiometer to ZERO (000).

EVALUATOR CUE Indicate H2 Rcb A(B)(C)(D) Heater Power Adj Control HC-25796A(B)(C)(D) is at ZERO (000).

4 (Step 2.9.3.c) Observe Hz RCB A(B)(C)(D) Power In Observes Hz RCB A(B)(C)(D) Power In Available White light ILLUMINATED indicating MCC Available White light.

feeder closed.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 73.0P.011.202 Rev 8 08/07/2014 Examinee Page 2 of 4 Step Action Standard Eva I Comments EVALUATOR CUE Indicate H2 RCB A(B)(C)(D) Power In Available White light is ILLUMINATED.

5* (Step 2.9.5) To start H2 Recombiner in Manual: Simulates placing H2 Rcb A(B)(C)(D) Temp Ctl Select HSS-25796A(B)(C)(D) to MAN (Step 2.9.5.a) Place H2 Rcb A(B)(C)(D) Temp Ctl Select HSS-25796A(B)(C)(D) to MAN.

EVALUATOR CUE Indicate H2 Rcb A(B)(C)(D) Temp Ctl Select HSS-25796A(B)(C)(D) is in MAN 6* (Step 2.9.5.b) Place H2 Rcb A(B)(C)(D) Power Out Simulates placing H2 Rcb A(B)(C)(D) Power Switch HS-25796A(B)(C)(D) to ON Out Switch HS-25796A(B)(C)(D) to ON.

EVALUATOR CUE Indicate H2 Rcb A(B)(C)(D) Power Out Switch HS-25796A(B)(C)(D) is in ON 7 (Step 2.9.5.c) Verify Red light above HS- Observes Red light above HS-25796A(B)(C)(D) ILLUMINATES 25796A(B)(C)(D).

EVALUATOR CUE Indicate Red light above HS-25796A(B)(C)(D) is ILLUMINATED.

8 (Step 2.9.5.d) Determine required power setting Determines required power setting from from Attachment A Attachment A is approximately 54 KW 9* (Step 2.9.5.e) Raise power out to heater as follows: Simulates adjusting H2 Rcb A(B)(C)(D)

Heater Power Adj Control HC-25796A(B)(C)(D) until H2 Rcb A(B)(C)(D)

(Step 2.9.5.e(1)) Adjust H2 Rcb A(B)(C)(D) Heater Power Out to Heater Xl-25796A(B)(C)(D)

Power Adj Control HC-25796A(B)(C)(D) until H2 indicates 5 KW.

Rcb A(B)(C)(D) Power Out to Heater XI-25796A(B)(C)(D) indicates 5 KW.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 73.0P.011.202 Rev 8 08/07/2014 Examinee Page 3 of 4 Step Action Standard Eva I Comments EVALUATOR CUE H2 Rcb A(B)(C)(D) Power Out to Heater Xl-25796A(B)(C)(D) indicates 5 KW EVALUATOR CUE 10 minutes have elapsed 10* (Step 2.9.5.e(2)) After 10 minutes, Adjust HC- Simulates adjusting H2 Rcb A(B)(C)(D) 25796A(B)(C)(D) until Xl-25796A(B)(C)(D) indicates Heater Power Adj Control HC-10 KW 25796A(B)(C)(D) until H2 Rcb A(B)(C)(D)

Power Out to Heater Xl-25796A(B)(C)(D) indicates 10 KW EVALUATOR CUE H2 Rcb A(B)(C)(D) Power Out to Heater Xl-25796A(B)(C)(D) indicates 10 KW EVALUATOR CUE 10 minutes have elapsed 11 * (Step 2.9.5.e(3)) After 10 minutes, Adjust HC- Simulates adjusting H2 Rcb A(B)(C)(D) 25796A(B)(C)(D) until X2-15796A(B)(C)(D) Heater Power Adj Control HC-indicates 20 KW 25796A(B)(C)(D) until H2 Rcb A(B)(C)(D)

Power Out to Heater Xl-25796A(B)(C)(D) indicates 20 KW EVALUATOR CUE H2 Rcb A(B)(C)(D) Power Out to Heater Xl-25796A(B)(C)(D) indicates 20 KW EVALUATOR CUE 5 minutes have elapsed 12* (Step 2.9.5.e(4)) After 5 minutes, Adjust HC- Simulates adjusting H2 Rcb A(B)(C)(D) 25796A(B)(C)(D) until required power setting Heater Power Adj Control HC-determined in 2.10.5.c of this procedure observed 25796A(B)(C)(D) until H2 Rcb A(B)(C)(D) on Xl-25796A(B)(C)(D) Power Out to Heater Xl-25796A(B)(C)(D) indicates approximately 54 KW CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 73.0P.011.202 Rev 8 08/07/2014 Examinee Page 4 of 4 Step Action Standard Eva I Comments 13 (Step 2.9.5.f) Monitor temperature periodically Simulates rotating H2 Rcb A(B)(C)(D) Temp placing H2 Rcb A(B)(C)(D) Temp Chan Select TSS- Chan Select TSS-25796A(B)(C)(D) and 25796A(B) (C)(D) in following while observing monitoring temperature temperature:

• Position #1

• Position #2

• Position #3 EVALUATOR CUE Temperature indicates 1250°F and stable 14 (Step 2.9.5.g) Adjust HC-25796A(B)(C)(D) between Determines temperature is approximately 0 KW and calculated required power setting to 1250°F and further adjustment is not maintain following: required

• H2 Recombiner temperature - 1250°F not to exceed 1400°F.

• Required power setting on H2 Rcb A(B)(C)(D) Power Out to Heater XI-25796A(B)(C)(D) not to exceed 75 KW EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets? Procedures?

CONFIDENTIAL Examination Material

EXAM INEE TASK CONDITIONS A. Unit 2 is in a post-LOCA condition approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the event.

B. Containment H2 and 0 2 concentrations are below combustible limits.

C. Pre-LOCA containment temperature was 135°F.

D. Post-LOCA containment pressure is 6 psig INITIATING CUE Start Containment Hydrogen Recombiner 2E440A(B)(C)(D) in Manual per OP-273-001 Section 2.9.

CONFIDENTIAL Examination Material

PPL-SUSQUEHANNA,LLC LEARNING CENTER SIMULATOR SCENARIO SLC Squib Failure I RHR Pump Start and Leak I Main Scenario

Title:

Generator Voltage Regulator Failure I HPCI Steam Leak I Rapid Depressurization Scenario Duration: 75 minutes Scenario Number: LOC26R-N-01 Revision I Date: 0 I December 16, 2014

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PC017 SRO License Course:

PC018 RO License Prepared By: Tom Hooper 12/16/2014 Instructor Date Reviewed By: Bob Spadoni 12/16/2014 Operations Training Management Date Approved By: Mike Jaco etti 12/16/2014 Operations Line Management Date CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

LOC26R-N-01 Rev D 12/16/201 ;::.

Page 3 of 37 I SCENARIO

SUMMARY

I The scenario begins with Unit 1 at 87% power following a control rod pattern adjustment, near the end of the operating cycle. EHC pump 1B is out of service for maintenance.

The crew will begin by raising power to 95% in accordance with a RMR from Reactor Engineering.

SLC squib valve 1B will lose continuity in the firing circuit. The crew will diagnose the failure. The SRO will declare the valve inoperable and determine the Technical Specification impact.

RHR pump 1B will spuriously start. Shortly after start, a leak will develop on the suction flange of the pump. RHR pump room water level will rise and Suppression Pool level will lower. The crew will secure the pump and isolate the leak by closing the suction valve. The crew will enter ON-169-002 due to flooding in the Reactor Building, E0-100-104 due to high Reactor Building area water level, and possibly E0-100-103 due to low Suppression Pool level. The SRO will review Technical Specifications and determine the impact.

The Main Generator voltage regulator will fail to maximum demand while in automatic. The crew will respond per ON-198-001. The crew may attempt to fix the automatic voltage regulator demand signal, but will eventually place the manual voltage regulator in service and lower reactive load.

A steam leak will develop in the HPCI equipment room. HPCI will fail to automatically isolate. When the crew attempts to manually isolate the leak, both HPCI steam isolation valves will fail mid-position due to power loss during valve stroke. The crew will re-enter E0-100-104, Secondary Containment Control. With an un-isolable primary system discharging into the Reactor Building and one area temperature approaching or exceeding the maximum safe value, the crew will insert a manual Reactor scram. The crew will enter E0-100-102, RPV Control, and take actions for the scram. HPCI room coolers will fail to start, requiring the crew to attempt manual start the coolers per E0-100-104. Four of the five Turbine Bypass Valves will fail closed, limiting the crew's ability to depressurize the Reactor prior to Rapid Depressurization. A second steam leak will develop from the HPCI steam isolation valves in the HPCI pipe routing area. This will lead to a second area temperature exceeding the maximum safe value. The crew will perform a Rapid Depressurization of the Reactor per E0-100-112.

The scenario may be terminated when Rapid Depressurization is complete or in progress and Reactor level is controlled above -161".

The highest expected EAL classification at scenario termination is expected to be Site Area Emergency FS1, based on un-isolable primary system (HPCI) discharging outside primary containment reaching maximum safe temperatures.

CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

LOC26R-N-01 Rev '

12/16/2014 Page 5 of 37 I SCENARIO REFERENCES I

1. OP-AD-001 Operations Standards For System And Equipment Operation

2. OP-AD-002 Standards For Shift Operations

3. OP-AD-004 Operations Standards For Error And Event Prevention

4. OP-AD-055 Operations Procedure Program

5. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

6. OP-164-001 Reactor Recirculation System

7. AR-107-A03 SBLC Squib Vlvs Loss of Ckt Continuity

8. ON-169-002 Flooding in Reactor Building

9. ON-198-001 Unit 1 Main Generator MVAR Control for Auto Voltage Regulator Operation When Synched to Grid

10. ON-100-101 Scram, Scram Imminent

11. E0-100-102 RPV Control

12. E0-100-103 Primary Containment Control

13. E0-100-104 Secondary Containment Control

14. E0-100-112 Rapid Depressurization

15. EP-RM-004 EAL Classification Levels

16. TS 3.1.7 Standby Liquid Control System 17.TS3.5.1 ECCS - Operating

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CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev 0 12/16/2014 Page 7of37 I SCENARIO TASKS I

Crew Task Description Position PCO 2780 Implement Standards for Shift Operations Implement Reactor Power Maneuvering Envelope for 4764 Normal Daily Power Operations (ICS)

Implement Actions to Reduce Reactor Core Flow for 4721 Scram Imminent (ICS)

Implement Manual Operation of Automatic 2383 Depressurization System (Adherence Level: STEP-BYSTEP)

Implement RFP Operating Mode Changes During 4842 Transient Conditions Ensure Plant Operates In Accordance With The Operating us 1183 License, Technical Specifications (TS), and Technical Requirements Manual (TRM)

Apply Technical Specification (TS) And Technical 1185 Requirements Manual (TRM) Requirements 1125 Implement RPV Control 1127 Implement Secondary Containment Control 1129 Implement Rapid Depressurization Implement Appropriate Portions Of Operations Standards ALL 1081 For System and Equipment Operation Implement Operations Standards For Error And Event 1091 Prevention Implement Reactivity Manipulations Standards and 2784 Communication Requirements Implement Main Condenser Vacuum and Offgas System 1786 Off-Normal Operation CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

LOC26R-N-01 Rev \J 12/16/2014 Page 9 of 37 I CRITICAL TASKS I

Manually scram the reactor when any Secondary Containment Area temperature I radiation approaches or exceeds Max Safe Temperature.

High-energy leakage into the Secondary Containment Area impacts the Safety Significance integrity of Secondary Containment. Failure of the Secondary Containment directly relates to the 10CFR100 design criteria of dose to the General Public.

Consequences for Failure to take actions to mitigate the energy released to the secondary Failure To Perform Task containment directly affects the radiation dose to the General Public.

Indications/Cues for Simplex Fire Detection alarms indicating High temperatures in RB Areas Event Requiring Critical Increasing area radiation and alarms for RB Areas Task Increasing Steam Leak Detection System temperatures and alarms Manually Scram the Reactor when approaching or exceeding any Max Safe Performance Criteria Temperature/Radiation as indicated by associated control room alarms and PICSY radiation indications.

Initiating a reactor scram reduces the heat load that will be absorbed and released by the Secondary Containment as well as the radioactive source Performance Feedback term.

Rods inserted and power lowering.

Rapidly depressurize the reactor when two Secondary Containment Areas exceed Max Safe Rad I Temperature I Water levels.

A high-energy leak in the Secondary Containment area impacts the integrity of Secondary Containment. Failure of the Secondary Containment Safety Significance directly relates to the 10CFR100 design criteria of dose to the General Public.

Consequences for Failure to take actions to mitigate the energy released to the Secondary Failure To Perform Task Containment directly affects the radiation dose to the General Public.

Indications/Cues for Increasing Steam Leak Detection System temperatures and alarms Event Requiring Critical indicating levels at Max Safe values.

Task Perform a Rapid Depressurization per E0-100-112 when two or more RB Performance Criteria areas exceed max safe temperatures per E0-100-104 Table 8.

Initiate ADS I Manually Open all 6 ADS valves Initiating a rapid depressurization causes Reactor pressure to lower which lowers the driving force of any primary system breach.

Performance Feedback Verify ADS valves are open using red light indication, acoustic monitoring, lowering Reactor pressure and rising Reactor water level.

CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev CJ 12/16/2014 Page 11of37 I SCENARIO MALFUNCTIONS I

Event Description Crew Response Diagnose failure; determine Technical 2 SLC Squib Valve Continuity Loss Specification impact RHR Pump 1B Spurious Start and Secure and isolate pump; determine Technical 3

Suction Flange Leak Specification impact Main Generator Auto Voltage Take manual control of Main Generator voltage 4

Regulator Failure regulator; restore MVARs HPCI Steam Leak into Reactor 5 Building, HPCI Fails to Attempt to isolate leak; scram the Reactor Automatically Isolate Attempt to isolate leak with other valve; initiate HPCI Isolation Valve Power Loss 6 Reactor cool down; eventual Rapid When Manual Closure Attempted Depressurization HPCI Room Coolers Fail to 7 Manually start HPCI room coolers Automatically Start Attempt other methods to open Turbine Bypass Four Turbine Bypass Valves Fail 8 Valves; limits Reactor cool down; eventual Rapid Closed Depressurization HPCI Steam Leak in Second Area Rapid Depressurization when max safe 9

of Reactor Building temperature exceeded in 2 areas ABNORMAL EVENTS I MAJOR TRANSIENTS I TECH SPEC Malfunction Description R Raise Power with Recirc Flow per RMR AE1 RHR Pump 1B Spurious Start and Suction Flange Leak AE2 Main Generator Auto Voltage Regulator Failure -

MT1 HPCI Steam Leak into Reactor Building, HPCI Fails to Automatically Isolate MT2 HPCI Steam Leak in Second Area of Reactor Building TS1 SLC Squib Valve Continuity Loss TS2 RHR Pump 1B Spurious Start and Suction Flange Leak CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev 0 12/16/2014 Page 13 of 37 I SCENARIO SPECIAL INSTRUCTIONS I

1. Simulator setup

a. Initialize to an exam-specific IC (IC-398). If an exam-specific IC is not available, then setup the simulator as follows:

i) Initialize to IC-20.

ii) Place the simulator in RUN.

iii) Lower Reactor power to approximately 87% using Recirculation flow.

iv) Place appropriate tags for EHC pump 1B OOS.

b. Run SCN file exam\LOC26R-N01.scn

c. Open trend files rat.tnd.

2. Verify the following malfunctions/overrides, event triggers and key assi gnments:

MF RF OR SCN ET COND 8:8 1:1 2:2 0:0 2:0 7

3. Prepare the simulator for evaluation

a. Complete a simulator exam checklist, TQ-106-0315

b. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms

c. Ensure EOL CRC book is staged and marked-up for current plant conditions

d. Ensure G0-100-012 is marked up to appropriate step (5.4.20)

4. Prepare a Turnover Sheet including the following:

a. Unit 1 i) Power ascension in progress. Reactor power 87 percent.

ii) EHC pump 1B out of service for maintenance.

iii) Continue power ascension using Recirculation flow per RMR.

b. Common i) Unit 2 is at rated power

5. Document training participation and feedback

a. Ensure all present have signed Security Agreements per NUREG-1021 and TQ-104-0306

b. Show the crew that the Evaluators and Booth Operators are qualified

c. Complete an Operator Fundamental Score Card CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev O 12/16/201 tl Page 15 of 37 I SCENARIO FILES I

LOC26R-N01.scn LOC26R-N01-MP .sen SCN rat_mp insmp ldtee41n24b SCN exam\LOC26R-N01-MP changemp ldtee4ln24b . , ,HPCI equipment room temperature

EHC pump B breaker racked out IRF crfPM10_1Pll3B f

OUT LOC26R-N01-1.et/scn

LIGHT

HPCI STEAM SUPPLY IB ISO

SLC B squib loss of continuity doHS15502_1.CurrValue = #OR.doHS15582_1.0N

{Key[l]} IMF cmfRL01_XYC411M600B IMF cmfMV01_HV155F002 d:3

RHR pump B spuriously starts; leak on suction line LOC26R-N01-2.et/scn

{Key[2]} IMF cmfRL02 ElllKllA ;LIGHT:HPCI STEAM SUPPLY OB ISO

{Key[2]} IMF mfRH149G04B d:30 r:2:00 f:40 doH515503_1.CurrValue = #OR.doHS15583 1.0N

NPO may open room drain valve IMF cmfMV01_HV155F003 d

4

{Key[l2]} IRF rfLD120005 f:OPEN IMF mfHP152003 d:5:00 r:2:08 f:l

NPO may open RHR pump B knife switch

{Key[22]} IRF cmfPM01_1P202B

Main Generator voltage regulator failure

{Key[3]} IOR aiHS10001 r:8:00 f:l

HPCI leak into RB (equipment room)

{Key[4]} IMF mfHP152009 f:0.5

HPCI equipment room coolers fails to auto-start IMF cmf PM04_1V209B IMF cmf PM04_1V209A

HPCI equipment room coolers fail to manually start IOR diHS17663B f

AUTO IOR diHS17663A f:AUTO

HPCI fails to automatically isolate IMF cmfMV06_HV155F002 IMF cmfMV06_HV155F003

HPCI fails to fully isolate manually

2nd HPCI leak into RB (pipe tunnel) aet LOC26R-N01-l aet LOC26R-N01-2

Four Turbine Bypass Valves failed closed IMF mfTC193023B f

Asis IMF mfTC193023C f:Asis IMF mfTC193023D f:Asis IMF mfTC193023E f:Asis CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev '--

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I SCENARIO EVENT DESCRIPTION FORM I

Initial Conditions: Ensure shift positions are assigned, have the Crew conduct the turnover and perform a panel walk down before the start of the scenario.

EVENT TIME DESCRIPTION N/A 0 Crew assumes shift 1 10 Raise Power with Recirc Flow per RMR 2 20 SLC Squib Valve Continuity Loss 3 30 RHR Pump 1B Spurious Start and Suction Flange Leak 4 40 Main Generator Auto Voltage Regulator Failure HPCI Steam Leak into Reactor Building, HPCI Fails to Automatically Isolate, HPCI Isolation Valve Power Loss When Manual Closure Attempted, HPCI 5-9 55 Room Coolers Fail to Automatically Start, Four Turbine Bypass Valves Fail Closed, HPCI Steam Leak in Second Area of Reactor Building N/A 75 Termination CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 18 of 37 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES (

EVENT 1 BRIEF DESCRIPTION Raise Power with Recirc Flow per RMR INSTRUCTOR ACTIVITY

1. None ROLE PLAY

1. As RxEng contacted for assistance, report Core thermal limits are within our predictions. You may proceed with power ascension.

2. As RxEng contacted for how fast to raise power, report The normal 1 percent power per minute rate is appropriate.

3. As Shift Manager contacted for approval to commence the reactivity manipulation, report The reactivity manipulation may proceed per the RMR.

4. If directed by the lead evaluator, contact the Control Room as GCC and report We request you hold power at this level for one hour while we make some adjustments to the voltage schedule because of a trip at Montour.

5. Role play any other directed actions as required.

EVALUATOR NOTES

1. The power ascension may be stopped when desired. Perform Role Play 4.

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I SCENARIO EVENT FORM I

EVENT 1 BRIEF DESCRIPTION Raise Power with Recirc Flow per RMR POSITION TIME STUDENT ACTIVITIES PCOM Raise reactor power with recirc flow in accordance with RMR and OP-AD-338 ATT. K.

Per G0-100-012, plot power change on power/flow map.

Depress the single or double chevron button on selected RRP and observes correct HMI response releasing the double chevron button if used, to achieve target controller output % (typically 2 percent on each pump).

Monitor diverse indications of reactor power (APRMs, heat balance, Main Generator output) per OP-AD-001 Attachment G.

PCOP Confirm the correct RRP, Direction, Intended Manipulation as directed by RMR and OP-AD-338.

us Direct PCOM to raise reactor power using recirc flow in accordance with RMR from RE and OP-AD-338.

Direct PCOP to provide peer check to PCOM during power ascension.

Provides oversight for reactivity manipulation.

'NOTES I CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 20 of 37 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2 BRIEF DESCRIPTION SLC Squib Valve Continuity Loss INSTRUCTOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 1 to initiate event.

{Key[1]} IMF cmfRL01_XYC411 M600B ROLE PLAY As NPO dispatched to investigate SLC continuity meters, wait 2 minutes and report The continuity meter for SLC squib A indicates 4mA. The continuity meter for SLC squib B indicates OmA.

As WWM contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES None

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\

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I SCENARIO EVENT FORM I

EVENT 2 BRIEF DESCRIPTION SLC Squib Valve Continuity Loss POSITION TIME STUDENT ACTIVITIES Recognize I report:

• Annunciator AR-107-A03, SBLC Squib Vlvs Loss of Ckt TEAM Continuity

• White SBLC Squib Ready B light extinguished Monitor plant parameters.

PCOM Execute AR-107-A03:

PCOP

• Dispatch NPO to check power monitor meters for squib valves at 1C617 in Upper Relay Room Ensure execution of AR-107-A03.

Declare SLC squib valve B inoperable.

us Determine Technical Specification 3.1.7 Condition B must be entered (restore to operable within 7 days).

INOTES I CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 22 of 37 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 3 BRIEF DESCRIPTION RHR Pump 1 B Spurious Start and Suction Flange Leak OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 2 to initiate event.

{Key[2]} IMF cmfRL02_E111K11A

{Key[2]} IMF mfRH149004B d:30 r:2:00 f:40

2. If directed as NPO to open RHR pump room B drain valve, wait 2 minutes, then depress KEY 12 and report task completion.

{Key[12]} IRF rfLD120005 f:OPEN

3. If directed as NPO to open RHR B DC knife switch, wait 2 minutes, then depress KEY 22 and report task completion.

{Key[22]} IRF cmfPM01_1P202B ROLE PLAY

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As NPO dispatched to RHR pump 8, wait 2 minutes and report the pump and leak status based on current plant condition. If the leak is still un-isolated, report at a minimum, "There is a leak coming from a flange on RHR pump B. The leak is between the pump and the suction valve."

As NPO dispatched to investigate if RHR leak has been isolated, report that the leak is slowing.

If dispatched as NPO to ensure closed water tight doors, wait 2 minutes and report that all water tight doors on elevation 645' are closed.

If asked as Radwaste about capacity to take on water, report that you have room for water and will align to surge tanks.

If dispatched as NPO open RHR pump room B drain valve (161121), wait 2 minutes and depress KEY 12, as described above, and report the valve is open.

If directed to open RHR 8 DC knife switch, wait 2 minutes and depress KEY 22, as described above, and report completion.

As WWM (or equivalent) contacted for assistance with RHR pump B, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None CONFIDENTIAL Examination Material

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I SCENARIO EVENT FORM I

EVENT 3 BRIEF DESCRIPTION RHR Pump 1B Spurious Start and Suction Flange Leak POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

• Annunciator AR-110-C03, RHR/CORE SPRAY LOOP B OPERATING ADS PERMISSIVE

• RHR pump B is running

• Annunciator AR-113-HOS, RHR LOOP B PUMP ROOM FLOODED

• Suppression Pool level is lowering PCOM Monitor plant parameters.

PCOP Stop RHR pump B by placing 1P2028 to STOP.

Close RHR pump B suction valve by placing HV-151-F0048 to CLOSE.

us Ensure execution of AR-11 O-C03 and AR-113-H08.

Determine RHR pump B operation is not required.

Direct PCOP to stop RHR pump B.

Enter E0-100-104, Secondary Containment Control, on high RB area water level.

Enter ON-169-002, Flooding in Reactor Building.

Direct PCOP to close RHR pump B suction valve.

May direct start of ESW and Unit Coolers.

If Suppression Pool level lowers to 22', enter E0-100-103, Primary Containment Control.

May direct makeup to the Suppression Pool using Suppression Pool Cleanup per OP-159-001 section 2.4.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 24 of 37 POSITION TIME STUDENT ACTIVITIES (

US (cont.) Declare RHR pump B inoperable.

Determine Technical Specification 3.5.1 Condition B applies which requires restoration of RHR pump B within 7 days.

If Suppression Pool level lowers below 22 feet, determine Technical Specification 3.6.2.2 Condition A requires restoring level within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

INOTES I CONFIDENTIAL Examination Material

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LOC26R-N-01 Rev 0 12/16/2014 Page 26 of 37 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES (

EVENT 4 BRIEF DESCRIPTION Main Generator Auto Voltage Regulator Failure OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 3 to initiate event.

{Key[3]} IOR aiHS10001 r:8:00 f:1 ROLE PLAY Provide the following role plays either when called or 4 minutes after event initiation (call as GCC):

"We have noticed SSES Unit 1 MVAR output rising. Other grid conditions are stable. We need SSES Unit 1 to supply approximately 150 MVAR to the grid."

If asked as GCC/TCC, give permission to make any changes to the voltage regulator that SSES requests (Auto to Manual, Manual to Auto, wiping potentiometers).

As WWM (or equivalent) contacted for assistance, acknowledge request.

(

Role play any other directed actions as required.

EVALUATOR NOTES

1. The procedural path taken in this event may vary depending on how the crew diagnoses failure of the auto voltage regulator. Multiple procedure sections are described, however the crew may not perform all sections.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev _!

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Page 27 of 37 I SCENARIO EVENT FORM I

EVENT 4 BRIEF DESCRIPTION Main Generator Auto Voltage Regulator Failure POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

• Annunciator AR-106-C09, GEN VOLT REG AUTO TO MAN SETPOINT UNBALANCED

• Main Generator reactive load high PCOM Execute AR-106-C09:

• Determine Generator field overvoltage alarm is NOT in .

• Determine grid is stable .

• Ensure AC MVARS, Xl-10004, within limits of OP-198-001 Attachment A, Main Generator Reactive Capability curve.

• Determine Main Generator is in Auto Voltage Regulator control.

• Monitor Main Generator parameters (MVars, MWe, Stator Cooling Temps Gen H2 Press. and Temp).

• May attempt to null Manual and Automatic regulators using MAN VOLT REG ADJUST HC-10002 potentiometer.

Execute ON-198-001, Unit 1 Main Generator MVAR Control for AUTO Voltage Regulator Operation when Synched to Grid:

• Bring Up Group Display ON198 or PICSY PIO menu (GENB) and Record parameters.

• If MVAR is approaching or exceeding Generator Capability Curve OR Generator Field Current exceeding 6000 Amps as viewed on Unit 1 Computer Point GNI01, Perform Section 3.5:

0 May attempt to slowly Lower generator output voltage by using AUTO VOLT REG ADJUST HC-10001 potentiometer in order to control the Generator MVAR output CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 28 of 37 POSITION TIME STUDENT ACTIVITIES (

PCOM (cont.)

• If a problem is suspected of the Voltage Regulator, Perform either of the following as required:

0 To wipe the auto and manual voltage regulator

- potentiometers, Perform Section 3.9.1:

• Ensure both Rx Recirc Pump controllers are operating in the Manual Mode in accordance with OP-164-002.

• Contact TCC to request permission to wipe the manual and auto voltage regulator potentiometers.

• IF generator voltage becomes unstable at any time during or after transfers between regulators, Promptly Transfer to the regulator that provides stable operation.

• Ensure HS-10006, VOLT REG XFER SELECT, switch is in the AUTO position.

• Rotate Slightly HC-10002, MAN VOLT REG ADJUST, and Ensure Auto Voltage Reg in control.

• Rapidly Rotate HC-10002, MAN VOLT REG ADJUST, from end to end a few times to clean its brush surface.

• Return HC-10002, MAN VOLT REG ADJUST, to null volts at Xl-10012, VR XFER.

• Transfer HS-10006, VOLT REG XFER SELECT, switch to MAN position.

• Ensure HS-10006, VOLT REG XFER SELECT, switch is in the MAN position.

• Rotate Slightly HC-10001, AUTO VOLT REG ADJUST and Ensure Manual Voltage Reg in control.

• Rapidly Rotate HC-10001, AUTO VOLT REG ADJUST, from end to end a few times to clean its brush surface (may not continue in procedure if diagnoses failure here)

• Return HC-10001, AUTO VOLT REG ADJUST, to null volts at Xl-10012, VR XFER.

• Transfer HS-10006, VOLT REG XFER SELECT, switch back to AUTO position.

• Ensure HS-10006, VOLT REG XFER SELECT, switch is in the AUTO position.

• Observe operation of the auto voltage regulator voltage adjust controls to verify proper operation and response.

• Select the desired modes of operation for the Rx Recirc Pump controllers in accordance with OP-164-002.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 29 of 37

( POSITION TIME STUDENT ACTIVITIES PCOM (cont.)

0 To transfer the voltage regulator from auto to manual and back to auto without performing a wiping action, Perform Section 3.9.2:

• Contact TCC to request permission to transfer to the manual regulator for a period of time to ride out MVAR oscillations.

• Ensure both Rx Recirc Pump controllers are operating in the Manual Mode in accordance with OP-164-002.

• IF generator voltage becomes unstable at any time during or after transfers between regulators, Promptly Transfer to the regulator that provides stable operation.

• Ensure HS-10006, VOLT REG XFER SELECT, switch is in the AUTO position.

• Adjust HC-10002, MAN VOLT REG ADJUST, to null volts at Xl-10012, VR XFER if required.

• Transfer HS-10006, VOLT REG XFER SELECT, switch to MAN position.

• Adjust HC-10001, AUTO VOLT REG ADJUST, to null volts at Xl-10012, VR XFER if required.

• Transfer HS-10006, VOLT REG XFER SELECT, switch back to AUTO position.

• Observe operation of the auto voltage regulator voltage adjust controls to verify proper operation and response.

• Select the desired modes of operation for the Rx Recirc Pump controllers in accordance with OP-164-002.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 30 of 37 POSITION TIME STUDENT ACTIVITIES PCOM (cont.) May use OP-198-001 section 2. 7 to transfer to manual voltage regulator:

• Obtain Unit Supervisor Permission to Transfer.

• Cohtacf GCC and TCC to Request permission to transfer to the MANUAL regulator.

• IF generator voltage becomes UNSTABLE at any time during OR after transfers between regulators, Promptly Transfer to the regulator that provides STABLE operation.

• Ensure HS-10006, VOLT REG XFER SELECT, switch is in the AUTO position.

• Adjust HC-10002, MAN VOLT REG ADJUST, to Null volts at Xl-10012, VR XFER IF Required.

• Transfer HS-10006, VOLT REG XFER SELECT, switch to MAN position.

• Check operation of the Manual voltage regulator voltage adjust controls AND Observe proper Response.

Adjust HC-10002, MAN VOLT REG ADJUST, as necessary to obtain desired Main Generator reactive load.

PCOP Monitor plant parameters.

Assist PCOM as requested. (

us Ensure execution of AR-106-C09.

Enter ON-198-001, Unit 1 Main Generator MVAR Control for AUTO Voltage Regulator Operation when Synched to Grid Direct placing Main Generator voltage regulator in MANUAL.

Direct lowering Main Generator reactive load.

INOTES I

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LOC26R-N-01 Rev 0 12/16/2014 Page 32 of 37 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES (

EVENTS 5-9 BRIEF DESCRIPTION HPCI Steam Leaks into Reactor Building, Isolation Failures, Room Coolers Fail to Auto Start, Four TBVs Fail Closed OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 4 to initiate HPCI pump room steam leak.

{Key[4]} IMF mfHP152009 f:0.5

2. When crew takes action to isolate HPCI, verify the following triggers activate to fail the HPCI inboard and outboard steam isolation valves and initiate the 2nct HPCI steam leak.

aet LOC26R-N01-1, aet LOC26R-N01-2 ROLE PLAY

1. As NPO dispatched to investigate HPCI fire or area temperature alarm wait 2 minutes then report, I can hear a steam leak in the HPCI room.

2. As NPO dispatched to F002 breaker 18237-08 and/or F003 breaker 10264-08, wait 2 minutes and report, The breaker(s) is(are) tripped open.

3. As NPO dispatched to manually close HPCI isolation valve, wait 2 minutes, then report that the valve is stuck and cannot be closed.

4. As WWM contacted for assistance with HPCI isolation valves, acknowledge request.

5. As Security contacted for status of blowout panels, report No blowout panels have ruptured at this time.

6. As HP contacted for HPCI room survey, wait 10 minutes and report Preliminary report is maximum dose rates below 150 mR/hr in the HPCI room. HP techs are continuing the survey.

7. Role play any other directed actions as required.

EVALUATOR NOTES

1. Once the crew attempts to manually isolate HPCI, a second steam leak will occur in the HPCI pipe routing area where the isolation valves are located. This will drive a second area temperature to exceed maximum safe and require a rapid depressurization.

2. Due to the quick rise in HPCI equipment room temperature, the crew may not scram the Reactor prior to exceeding the maximum safe temperature of 167°F. In this case, the crew should take prompt action to scram the Reactor once the HPCI equipment room temperature exceeds 167°F.

CONFIDENTIAL Examination Material

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I SCENARIO EVENT FORM I

EVENTS 5-9 BRIEF DESCRIPTION HPCI Steam Leaks into Reactor Building, Isolation Failures, Room Coolers Fail to Auto Start, Four TBVs Fail Closed POSITION TIME STUDENT ACTIVITIES

• TEAM Manually scram the reactor when any Secondary Containment Area temperature approaches or exceeds Max Safe temperature.

Rapidly depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels.

TEAM Recognize I report:

• Annunciator AR-114-E05, HPCI LEAK DETECTION HI TEMP/HI DIFF TEMP

• Annunciator AR-016-G15, FIRE PROTECTION PANEL OC650 SYSTEM TROUBLE

• Elevated temperatures in the HPCI equipment area on recorder 1 R604 and Riley Tempmatic readings at 1C614.

PCOM As directed I time permits, perform scram imminent actions of ON-100-101, Scram, Scram Imminent:

• REDUCE Reactor Power PER RE Instructions in the CRC Book:

0 INITIATE the required Flow/Power reduction by performing either of the following:

• INITIATE a Manual Rx Recirc Limiter #2 Runback using CORE POWER OFF NORMAL POWER REDUCTION HARD CARD (OP-164-001 Attachment E), OR

• TOUCH double chevron DEC buttons on REACTOR RECIRC PUMP A(B) SPEED controllers SY-B31-1 R621A & Bas required to establish the final Core Flow value stated in the CRC Book.

0 INSERT Control Rods, as necessary, to obtain a Rod Line which is less than the value stated in the CRC Book.

• NOTIFY GCC that the Unit is coming Off Line .

Rotate Mode Switch to SHUTDOWN.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 34 of 37 POSITION TIME STUDENT ACTIVITIES (

PCOM (cont.) Execute scram actions of ON-100-101, Scram, Scram Imminent:

• Observe all Control Rods indicate fully inserted (using two indications, OD 7 completed as soon as possible).

• Insert IRMs and SRMs .

• Observe Scram Discharge Volume Vent and Drain valves CLOSED.

• Check Reactor water level between 13" and 54" .

• Check Reactor pressure <1087 psig .

• WHEN main generator load< 150 MWe, at 1C651, Depress Trip Pushbutton for Main Turbine.

• Check Turbine speed is lowering .

• Check status of MSIVs .

• STOP Condensate Pumps 1P102A(B)(C)(D) as necessary to leave 2 pumps in operation.

• ENSURE Feedwater is in a Startup Level Control alignment per OP-145-001.

Control Reactor water level between +13" and +54" (+20" to +45" preferred band) using Condensate/Feedwater.

May initiate Reactor cooldown.

May attempt to open all Turbine Bypass Valves irrespective of

(

cooldown rate.

Recognize I report failure of four of the five Turbine Bypass Valves to open.

Prevent uncontrolled Condensate injection.

Restore I maintain Reactor water level to +13 to +54" ( +20" to +45" preferred band) using Condensate I Feedwater.

CONFIDENTIAL Examination Material

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( POSITION TIME STUDENT ACTIVITIES PCOP Determine HPCI equipment area temperature is elevated and rising.

Recognize/report failure of HPCI room coolers to start.

Start ESW and attempt to start all individual Room Coolers.

Attempt to manually isolate HPCI by closing:

• HV-155-F002

• HV-155-F003 Recognize/report HPCI isolation valves failed mid-position and HPCI is NOT isolated.

Dispatch NPOs to attempt manual closure and/or breaker reset.

Recognize/report high temperature in HPCI pipe routing area (2nd area).

May isolate RCIC (HPCI pipe routing area leak causes RCIC steam leak detection annunciator also).

Recognize/report two area temperatures above Max Safe.

Open all 6 ADS valves.

If time permits, initiate Suppression Pool cooling.

CONFIDENTIAL Examination Material

LOC26R-N-01 Rev 0 12/16/2014 Page 36 of 37 I SCENARIO EVENT FORM I (

EVENTS 5-9 HPCI Steam Leaks into Reactor Building, Isolation Failures, Room Coolers BRIEF DESCRIPTION Fail to Start, Four TBVs Fail Closed POSITION TIME STUDENT ACTIVITIES us Enter I re-enter E0-100-104, SECONDARY CONTAINMENT CONTROL, based on HPCI equipment area temperature:

• Directs starting ESW, all individual Room Coolers .

• Acknowledge failure of HPCI room coolers to start .

• Directs manual isolation of HPCI.

• Acknowledge failure of HPCI to isolate May direct scram-imminent actions, if time permits.

Enter E0-100-102, RPV CONTROL, after determining that a primary system is discharging into an area and cannot be isolated:

• Direct Mode Switch to SHUTDOWN when area temperature approaches or exceeds Maximum Safe temperature.

• Direct Reactor water level controlled +13 to +54" (+20" to (

+45" preferred band) using Condensate/Feedwater.

• Direct Reactor pressure controlled 800-1050 psig using Turbine Bypass Valves.

• May direct initiating Reactor cooldown .

• May anticipate Rapid Depressurization and direct open all Turbine Bypass Valves.

• Acknowledge failure of four of the five Turbine Bypass Valves to open.

When HPCI pipe routing area and equipment area temperatures exceed 167°F (2 > max safe):

• Enter E0-000-112, Rapid Depressurization .

• Exit Pressure Leg of E0-100-102 .

• Answers, "Can RPV Lvl Be Determined?" Yes .

• Direct preventing uncontrolled Condensate injection .

• Answers, "Is More Than 1 Control Rod > 00?" No .

• Answers, "Is Supp Pool Lvl > 5'?" Yes .

• Directs opening all ADS valves .

• Answers, "Are all ADS valves open?" Yes .

If Suppression Pool temperature exceeds 90°F, enter I re-enter EO-100-103, Primary Containment Control:

• Direct initiation of Suppression Pool cooling .

• Denotes Critical Task CONFIDENTIAL Examination Material

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UNIT SUPERVISOR TURNOVER SHEET

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UNIT 1 t'o-/dd(yy Date SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE MODE POWER LEVEL 87  % POWER LEVEL  %

GENERATOR OUTPUT 1158 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED: YES/NO CASK STORAGE GATE INSTALLED: YES/NO REMARKS:

1) 500 days on-line, 20 months into the operating cycle.

2) EHC pump 1B is out of service for maintenance.

3) Power ascension in progress following control rod pattern adjustment.

4) Raise power per RMR Step #4 to 95%.

5 6) 7 8) 9)

10 11 12) 13) 14) 15)

COMMON:

1) Unit 2 at rated power.

2) 3 4) 5 6

7) 8)

9 FORM OP-AD-003-7, Rev. 23, DUPLEX Page 1 of 2 (Electronic Form)

CONFIDENTIAL Examination Material

OFFGOING UNIT SUPERVISOR CHECKLIST:

NRC CODE PRIOR TO 0800 FOXTROT DELTA HOTEL OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM BRAVO ROMEO 1900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.

4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.

1900 - 0700 - - - - - - - - - - - -

0700 -1900 - - - - - - - - - - -

Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:

0700 1900

1. LCOffRO Log reviewed.

) 2. SOMS Log reviewed for entries made in past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. Report any changes to license or medical status PER NDAP-QA-0723.

0700 -1900 1900-0700 - - - - - - - - - - -

Oncoming Qualified Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

2. CRC Book reviewed and Reactivity Brief performed with PCO.

3. Completed System Status Operable audit for open PMT this shift.

4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (20 l 0700 - 1900 - - - - - - - - - - -

1900 - 0700 - - - - - - - - - - - -

Oncoming Unit Supervisor FORM OP-AD-003-7, Rev. 23, DUPLEX Page 2 of 2 (Electronic Form)

CONFIDENTIAL Examination Material

PPL-SUSQUEHANNA,LLC LEARNING CENTER SIMULATOR SCENARIO RRP Speed Drift I Control Rod Drift I Coolant Leak in Drywell /

Scenario

Title:

Electrical ATWS I SLC Pump Shaft Shear I Loss of Condensate I HPCI and RCIC Trip Scenario Duration: 75 minutes Scenario Number: LOC26R-N-02 Revision I Date: 0IDecember16, 2014 PC017 SRO License Course:

PC018 RO License Prepared By: Tom Hooper 12/16/2014 Instructor Date Reviewed By: Bob Spadoni 12/16/2014 Operations Training Management Date Approved By: Mike Jaco etti 12/16/2014 Operations Line Management Date CONFIDENTIAL Examination Material

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SUMMARY

I The scenario begins with Unit 1 at 100% power. CRD pump 1B is out of service for maintenance.

The crew wlll receive a call from the grid operator requesting a power reduction due to a Minimum Generation Emergency Notification. The crew will lower Reactor power using Recirculation flow. As the crew is performing the power reduction, Reactor Recirculation pump 1B speed will begin to drift low.

The crew will identify the unanticipated reactivity change and either lockup the scoop tube to stop the transient or trip Reactor Recirculation pump 1B. The SRO will determine the status of Recirculation loops and ensure compliance with Technical Specification 3.4.1.

One control rod will drift outward from the full-in position. The crew will execute ON-155-001, Control Rod Problems. The control rod will be selected and driven to the full-in position. The control rod HCU will be valved out and the control rod will remain at the full-in position. The SRO will determine compliance with Technical Specification 3.1.3.

A coolant leak will develop in the Drywell. Drywell pressure and temperature will rise. As Drywell pressure approaches 1.72 psig, the crew may lower Reactor power and will attempt to manually scram the Reactor. RPS will fail to scram the Reactor and ARI will also fail to insert control rods. The crew will execute E0-100-113, Level/Power Control. The crew will lower Recirculation flow, trip Recirculation pumps, injection boron using SLC, and lower Reactor water level to lower Reactor power.

The first SLC pump started will have a sheared shaft. The crew will diagnose that the pump is not injecting boron. The other SLC pump will be started and inject successfully.

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'* Once Reactor power has been lowered, the Main Generator will trip. Reactor pressure control will shift to the Turbine Bypass Valves and may be augmented initially by use of SRVs. With Drywell pressure

>1.72 psig, the Main Generator trip will also cause a trip of all Condensate pumps due to load shedding. The Condensate pumps will fail to re-start, if re-start is attempted. Reactor water level will be able to be maintained using HPCI, RCIC, CRD, and SLC. CRD pump 1A will trip as the crew attempts to use CRD to drift in control rods. The crew will insert all control rods by dispatching an operator to either pull RPS fuses or vent the scram air header.

Once all control rods are inserted, the crew will stop boron injection, exit E0-100-113, and re-enter E0-100-102. The crew will also be in E0-100-103 and will spray the Suppression Chamber and possibly the Drywell. HPCI and RCIC will trip and the coolant leak in the Drywell will degrade. Reactor water level will lower. The crew will be unable to maintain Reactor water level above -161". ADS will fail to automatically initiate on low Reactor water level, if un-bypassed. The crew will perform a Rapid Depressurization per E0-100-112 and restore Reactor water level using low pressure injection systems. The scenario may be terminated when all control rods are inserted, Rapid Depressurization is complete, and Reactor water level has been restored above -161 ".

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Page 5 of 40 I SCENARIO REFERENCES I

1. OP-AD-001 Operations Standards For System And Equipment Operation

2. OP-AP::002 Standards For Shift Operations

3. OP-AD-004 Operations Standards For Error And Event Prevention

4. OP-AD-055 Operations Procedure Program

5. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

6. OP-164-001 Reactor Recirculation System

7. ON-156-001 Unanticipated Reactivity Change

8. ON-178-002 Core Flux Oscillations

9. ON-164-002 Loss of Reactor Recirculation Flow

10. ON-155-007 Loss of CRD System Flow

11. ON-155-001 Control Rod Problems

12. ON-100-101 Scram, Scram Imminent

13. E0-100-102 RPV Control

14. E0-100-103 Primary Containment Control

15. E0-100-112 Rapid Depressurization

16. E0-100-113 Level/Power Control

17. EP-RM-004 EAL Classification Levels

18. TS 3.1.3 Control Rod Operability

19. TS 3.4.1 Recirculation Loops Operating CONFIDENTIAL Examination Material

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I SCENARIO TASKS I

Crew Task Description Position PCO 2780 Implement Standards for Shift Operations Implement Reactor Power Maneuvering Envelope for 4764 Normal Daily Power Operations (ICS)

Implement Actions to Reduce Reactor Core Flow for 4721 Scram Imminent (ICS)

Implement Manual Operation of Automatic 2383 Depressurization System (Adherence Level: STEP-BYSTEP)

Implement RFP Operating Mode Changes During 4842 Transient Conditions Ensure Plant Operates In Accordance With The Operating us 1183 License, Technical Specifications (TS), and Technical Requirements Manual (TRM)

Apply Technical Specification (TS) And Technical 1185 Requirements Manual (TRM) Requirements 1125 Implement RPV Control 1127 Implement Secondary Containment Control 1129 Implement Rapid Depressurization Implement Appropriate Portions Of Operations Standards ALL 1081 For System and Equipment Operation Implement Operations Standards For Error And Event 1091 Prevention Implement Reactivity Manipulations Standards and 2784 Communication Requirements Implement Main Condenser Vacuum and Offgas System 1786 Off-Normal Operation I\,

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I CRITICAL TASKS I

Lower Reactor power using one or more of the following methods IAW E0-100-113:

• Trip Recirculation pumps**

• Inject boron

• Lower Reactor water level Lowering Reactor power using one or more of these methods causes an Safety Significance immediate Reactor power reduction, which limits challenges to fission product barriers during a failure to scram prior to control rod insertion.

Failure to lower Reactor power using one or more of these methods raises Consequences for the potential for damage to fuel and energy addition to the Primary Failure To Perform Task Containment.

Indications/Cues for Exceeding a RPS scram setting with NO reactor scram signal, or RPS/ARI Event Requiring Critical fail to fully insert all control rods, and Reactor power remains above 5%.

Task Lowers Reactor power by tripping Recirculation pumps, injecting boron, Performance Criteria and/or throttling injection to lower Reactor water level.

Performance Feedback Reactor power lowers.

Insert control rods IAW E0-100-113 Sht. 2.

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Control rod insertion initiates power reduction and provides for long-term Safety Significance shutdown of the Reactor.

Consequences for Failure to insert control rods allows power to remain elevated with resultant Failure To Perform Task power oscillations and potential core damage.

Indications/Cues for Exceeding a RPS scram setting with NO reactor scram signal, or RPS/ARI Event Requiring Critical fail to fully insert all control rods.

Task Insert Control Rods by one or more of the following methods:

Maximize CRD to drift control rods.

Drive control rods after bypassing RWM and RSCS.

Performance Criteria Reset and Scram again by performing ES 158 002 Bypass RPS logic trips.

De energizing RPS solenoids by performing ES 158 001.

Local venting of Scram Air Header.

Successful insertion of control rods will be indicated by:

Rod position full in indication for manual insertion of control rods, venting scram air header or de energizing RPS solenoids.

Rod position full in after resetting scram, draining scram discharge volume and re scram.

Performance Feedback CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 10 of 40 Perform Rapid Depressurization when RPV level drops to -161" IAW E0-100-102. (

RPV leakage or loss of injection systems impacts the ability to provide Safety Significance continued adequate core cooling through core submergence based on inventory loss.

-Consequences for Failure to take the EOP actions wilrresl.M-in ul1-coverlngthe-core-and Failure To Perform Task breach of the fuel clad due to over-heating.

Indications/Cues for Reactor water level trending downward, eventually indicating less than the Event Requiring Critical top of active fuel height on the Fuel Zone Level Indicator.

Task Perform a Rapid Depressurization per EO 100 112 when water level Performance Criteria reaches the TAF -161" as read on the Fuel Zone Instrument.

Initiate ADS I Manually open all 6 ADS valves Initiating a rapid depressurization causes Reactor pressure to lower to the shutoff head of the low pressure injection systems allowing water level to Performance Feedback rise on the Fuel Zone and Wide Range level instruments.

Verify ADS valves are open using red light indication, acoustic monitoring, and lowering Reactor pressure and rising reactor water level.

CONFIDENTIAL Examination Material

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I SCENARIO MALFUNCTIONS I

Event Description Crew Response Reactor Recirculation Pump 1B Lock scoop tube; ensure Technical Specification 2

Speed Drifts Low compliance Select and insert control rod; valve out control rod 3 One Control Rod Drifts Out to prevent further drifting; ensure Technical Specification compliance Lower Reactor power; attempt a Reactor scram; 4 Coolant Leak in Drywell spray Suppression Chamber Attempt ARI; trip Recirculation pumps; inject 5 Electrical A TWS boron; lower Reactor water level; insert control rods by alternate methods SLC Pump Shaft Shear, CRD Start other SLC pump; utilize other methods for 6

Pump Trip inserting control rods Main Generator Trip, Loss of All Control Reactor water level using HPCI and/or 7

Condensate Pumps RCIC HPCI and RCIC Trip, Coolant Leak in Drywell Degrades, ADS Fails to Rapidly Depressurize the Reactor; inject with low 8 Automatically Initiate; Rapid pressure ECCS pumps; spray the Drywell Depressurization Required Due to Low Reactor Water Level ABNORMAL EVENTS I MAJOR TRANSIENTS I TECH SPEC Malfunction Description R Power Reduction Due to Minimum Generation Emergency Notification AE1 Reactor Recirculation Pump 1B Speed Drifts Low AE2 One Control Rod Drifts Out AE3 Coolant Leak in Drywell MT1 Electrical A TWS HPCI and RCIC Trip, Coolant Leak in Drywell Degrades, ADS Fails to Automatically MT2 Initiate; Rapid Depressurization Required Due to Low Reactor Water Level TS1 Reactor Recirculation Pump 1B Speed Drifts Low TS2 One Control Rod Drifts Out CONFIDENTIAL Examination Material

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I SCENARIO SPECIAL INSTRUCTIONS I

1. Simulator setup

a. ll}iti~lize tQ an exam-specific IC (IC-399). If an exam-specific IC is not available, then setup the simulator as follows:

i) Initialize to IC-20.

ii) Place the simulator in RUN.

iii) Place appropriate tags for CRD pump 1B OOS.

b. Run SCN file exam\LOC26R-N02.scn

c. Open trend files rat.tnd.

2. Verify the following malfunctions/overrides, event triggers and key assignments:

I 1::o I ~: I ~:: I 50~: I :,: I c~~o I

3. Prepare the simulator for evaluation

a. Complete a simulator exam checklist, TQ-106-0315

b. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms

c. Ensure EOL CRC book is staged and marked-up for current plant conditions

4. Prepare a Turnover Sheet including the following:

a. Unit 1 i) Reactor power 100 percent.

ii) CRD pump 1B out of service for maintenance.

b. Common i) Unit 2 is at rated power

5. Document training participation and feedback

a. Ensure all present have signed Security Agreements per NUREG-1021 and TQ-104-0306

b. Show the crew that the Evaluators and Booth Operators are qualified

c. Complete an Operator Fundamental Score Card CONFIDENTIAL Examination Material

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I SCENARIO FILES I

LOC26R-N02.scn LOC26R-N02-MP .sen SCN rat_mp insmp rdsdrposnotch(121)

SCN exam\LOC26R-N02-MP changemp rdsdrposnotch(121) ,,,Rod 22-39

CRD pump B OOS position IRF crfPM13_1P132B f

OUT

'B' Reactor Recirculation Pump Speed LOC26R-N02-1.et/scn Drifts Low ;METER

APRM FLUX CHAN A (RED) aet LOC26R-N02-1 I aet LOC26R-N02-2 aoNRC511R603AA.CurrValue <= 96

Allows manual control of RRP lB scoop tube in field IMF annAR102D05 f

ALARM_OFF

{Key[27]} IRF rfRR164018 f :OFF IRF rfRR164018 f:OFF

{Key[27]} IRF rfRR164020 IRF rfRR164020 r:4:00 f:40

One Control Rod Drifts Out

{Key[l]} IMF mfRD1550052239

NPO valves out HCU for control rod 22-39 LOC26R-N02-2.et/scn

{Key[?]} IRF rfRD1550072239 f:DISARM ;SWITCH:SCOOP TUBE B LOCK OR RESET

{Key[?]} DMF mfRD1550052239 diHSB311S03B.CurrValue

Coolant Leak in Drywell #OR.diHSB311S03B.TRIP

{Key[2]} IMF mfRR164011A i:0.01 r:4:00 f:0.03 ITO rfRR164020

Electrical ATWS IMF mfRP158004A I IMF mfRP158004B DMF annAR102D05 IMF mfRP158004C I IMF mfRP158004D IMF mfRP158003 LOC26R-N02-3.et/scn IMF cmfRL01_63X114725Dl ;METER

APRM FLUX CHAN A (RED)

IMF cmfRL01_63X214725Dl aoNRC511R603AA.CurrValue <= 14

CRD pump lA trips to prevent crew from drifting in rods IMF mf EG198004 aet LOC26R-N02-6 IMF mfFW144003D d

S

First SLC pump started has sheared shaft IMF mfFW144003C d

S IMF cmf PM05 1P208A IMF mfFW144003B d:S IMF cmf PM05_1P208B IMF mfFW144003A d:S aet LOC26R-N02-4 I aet LOC26R-N02-5

Main Generator Trip, Loss of All Condensate Pumps LOC26R-N02-4.et/scn aet LOC26R-N02-3 ;LIGHT

SBLC MANUAL INITIATION (1P208A)

HPCI and RCIC Trip, Coolant Leak doHSS14804A_2.CurrValue Degrades, ADS Fails to Auto Initiate #OR.doHSS14804A_2.0N

{Key[3]} IMF mfRC150011

{Key[3]} IMF mfHP152015 DMF cmf PM05_1P208B

{Key[3]} MMF mfRR164011A d:3:00 i :0.03 cet LOC26R-N02-5 r:5:00 f:l IMF mf AD183001 LOC26R-N02-5.et/scn

NPO pulls RPS A fuses in upper relay room ;LIGHT

SBLC MANUAL INITIATION (1P208B)

{Key[10]} IMF cmfFU01_1C609F18C doHSS14804B_2.CurrValue

{Key[10]} IMF cmfFU01_1C609F18G d:S #OR.doHSS14804B_2.0N

{Key[l0]} IMF cmfFU01_1C609F18A d:l5

{Key[10]} IMF cmfFU01_1C609Fl8E d:20 DMF cmf PM05_1P208A

NPO pulls RPS B fuses in lower relay room cet LOC26R-N02-4

{Key[20]} IMF cmfFU01_1C611Fl8D

{Key[20]} IMF cmfFU01_1C611F18H d:S

{Key[20]} IMF cmfFU01_1C611Fl8B d:lS LOC26R-N02-6.et/scn

{Key[20]} IMF cmfFU01_1C611F18F d:20 ;Trips CRD pump lA when CRD is being

NPO vents scram air header maximized

{Key[30]} IRF rfRD155018 f:100 ycpxnep02>20

{Key[30]} !RF rfRD155025 d:S f:0

{Key[30]} IRF rfRD155016 d:l0 f:l00 IMF cmf PM03 1P132A

NPO closes charging water header isolation

{Key[40]} !RF rfRD155017 f:0 CONFIDENTIAL Examination Material

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I SCENARIO EVENT DESCRIPTION FORM I

Initial Conditions: Ensure shift positions are assigned, have the Crew conduct the turnover and perform a panel walk down before _the start of the scenario.

EVENT TIME DESCRIPTION N/A 0 Crew assumes shift 1 5 Power Reduction Due to Minimum Generation Emergency Notification 2 15 Reactor Recirculation Pump 1B Speed Drifts Low 3 25 One Control Rod Drifts Out 4 35 Coolant Leak in Drywell Electrical A TWS, SLC Pump Shaft Shear, CRD Pump Trip, Main Generator Trip, Loss of All Condensate Pumps, HPCI and RCIC Trip, Coolant Leak in 5-8 45 Drywell Degrades, ADS Fails to Automatically Initiate; Rapid Depressurization Required Due to Low Reactor Water Level N/A 75 Termination CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 18 of 40 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES (

EVENT 1

~*- . - *- -- . - - . ~ - .. - . .. .... -

BRIEF DESCRIPTION Power Reduction Due to Minimum Generation Emergency Notification INSTRUCTOR ACTIVITY

1. When directed by Lead Examiner, make the following report to initiate event:

"This is Lou Spinelli at GCC. A Minimum Generation Emergency is required and we need Susquehanna Unit 1 to reduce output by 100 MWe as quickly as possible."

ROLE PLAY Role play any directed actions as required.

EVALUATOR NOTES

1. Event 2 (RRP 1B speed drifts low) automatically activates when Reactor power lowers to approximately 96% on APRMs. Event 2 may also be manually forced if desired to facilitate the scenario.

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I SCENARIO EVENT FORM I

EVENT 1 BRIEF DESCRIPTION Power Reduction Due to Minimum Generation Emergency Notification POSITION TIME STUDENT ACTIVITIES TEAM Acknowledge Minimum Generation Emergency notification from GCC.

PCOM Reduce power by approximately 100 MWe:

• Using the RRP Dual Screen HMI, lower A and B Recirc speeds by depressing the double chevron DEC buttons, as necessary.

• Observe diverse plant indications:

0 APR Ms 0 Core Thermal Power 0 MWe 0 RRP parameters 0 Core flow (Recirc loop mismatch <5%)

0 Reactor water level

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• Plot power reduction on Power to Flow Map .

PCOP Monitor plant parameters.

Provide peer checks for reactivity manipulations.

us May refer to 01-AD-029 attachment D and CRC Book.

Direct PCOM to reduce power by 100 MWe with Recirculation flow.

Provide oversight of reactivity maneuver.

INOTES I CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 20 of 40 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2

---

*-* ----- - ---~----- --~---*-*----- ---- -- -- ------- --- -- -* - , - - - ---- *-- ---

BRIEF DESCRIPTION Reactor Recirculation Pump 1B Speed Drifts Low INSTRUCTOR ACTIVITY

1. When Reactor power lowers to approximately 96% on APRMs, ensure the following trigger activates to initiate the event.

aet LOC26R-N02-1

2. When the pushbutton is depressed to lock RRP 1B scoop tube, ensure the following trigger activates to secure the speed drift.

aet LOC26R-N02-2

3. If dispatched to manually control RRP 1B scoop tube position, wait 3 minutes, then depress KEY

27. Then modify the remote function to adjust the scoop tube as requested by crew.

{Key[27]} IRF rfRR164018 f:OFF

{Key[27]} IRF rfRR164020

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ROLE PLAY If dispatched to manually control Recirculation pump A scoop tube position, wait 3 minutes, then depress KEY 27 as described abov~ an.d report:

"I have manual control of Recirculation pump A scoop tube."

Make subsequent reports regarding scoop tube positioning as applicable.

If asked as Reactor Engineering, Operations or Plant Management for permission to lower Recirculation pump A flow, concur with the crew's request to lower Recirculation pump A flow.

As Reactor Engineering, acknowledge any reports I requests.

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. The PCOM may lock the scoop tube prior to referencing ON-156-001 because this is an immediate operator action.

2. It is an immediate action of ON-156-001 to lock the scoop tube and/or trip the Recirc pump. It is expected the crew will lock the scoop tube first. Once the scoop tube is locked, generator speed will continue to lower for a moment while scoop tube oil uptake stabilizes. The crew may trip the Recirc pump based on this delay in stabilization.

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Page 21 of 40 I SCENARIO EVENT FORM I

EVENT 2 BRIEF DESCRIPTION Reactor Recirculation Pump 1B Speed Drifts Low POSITION TIME STUDENT ACTIVITIES Recognize I report:

TEAM

• Reactor power lowers .

• Recirc pump 1B speed and flow lower.

Executes ON-156-001, Unanticipated Reactivity Change:

• IF a rapid speed change is experienced on a Reactor Recirc Pump, take immediate action to Reduce Power AND Lock the affected Scoop Tube OR Trip the affected pump.

• Check current rod position, OD 7 against rod patterns provided in the CRC Book to determine drifted or scrammed rods.

• IF time permits, Initiate TRA .

• AS REQUIRED, Take Action to correct any apparent change in any following variable which could affect reactivity:

0 Recirculation flow PCOM

• Notify Reactor Engineering .

• Check off gas monitors at discharge of SJAE for change in activity.

• Check that applicable nuclear safety limits were not exceeded.

• Check that applicable thermal hydraulic limits were not exceeded. (Powerplex Core Monitor).

If directed, lower flow on Recirculation pump A to restore flow mismatch to within limits.

Monitor plant parameters.

PCOP CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 22 of 40 POSITION TIME STUDENT ACTIVITIES

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Enter ON-156-001, Unanticipated Reactivity Change.

Direct lockup of Recirculation pump 1B scoop tube.

May direct trip of Recirculation pump 18.

• Enter ON-164-002, Loss of Reactor Recirculation Flow

• Enter ON-178-002, Core Flux Oscillations Analyze compliance with Technical Specification 3.4.1:

• Requires :::; 5 Mlbm/hr mismatch when operating at::::: 75 Mlbm/hr total core flow us o If mismatch not within limits, enter Condition B (declare the loop with lower flow "not in operation" within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).

• If Recirc pump tripped, requires establishing single loop limits within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

If Recirc pump tripped, determine TRO 3.4.6 requires core flow <54 Mlbm/hr within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

May direct lowering Recirculation pump A flow to restore mismatch to within limits.

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'NOTES I CONFIDENTIAL Examination Material

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EVENT 3 BRIEF DESCRIPTION One Control Rod Drifts Out OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 1 to initiate event.

{Key[1]} IMF mfRD1550052239

2. When directed as NPO to disarm HCU 22-39, wait 3 minutes, then depress KEY 7.

{Key[7]} IRF rfRD1550072239 f:DISARM

{Key[7]} DMF mfRD1550052239 ROLE PLAY As NPO dispatched to disarm HCU 22-39, wait 3 minutes, then depress KEY 7 as described above, and report, "HCU 22-39 has been hydraulically disarmed."

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

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EVALUATOR NOTES

1. The control rod will continue to drift out if the insert pushbutton is released prior to valving out the HCU. The crew will need to hold the insert pushbutton until the field operator reports the HCU is valved out.

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I SCENARIO EVENT FORM I

EVENT 3

~-- " ' ' - - ....

BRIEF DESCRIPTION One Control Rod Drifts Out POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

• Annunciator AR-104-H05, ROD DRIFT

• Control rod 22-39 moves out with no withdraw signal PCOM Execute ON-155-001, Control Rod Problems:

• IF three or more rods have drifted or scrammed from their target positions, Immediately Scram Reactor IAW ON-100-101, Scram, Scram Imminent.

• Proceed to section 4.4 for rod drift.

• Check Full Core Display for identification of any drifting control rod by Depressing DISPLAY RODS DFTING pushbutton. *

• Check for any open scram valves by Depressing DISPLAY SCRAM VALVES OPEN pushbutton.

• Select each drifted or scrammed rod to determine position.

• Reset the Rod Drift Alarm as follows:

o Depress the Rod Drift Reset pushbutton.

o Verify Rod Drift Alarm CLEARS.

• Ensure proper cooling water diff/pressure being maintained by observing PDl-C 12-1 R603 Cooling Water Diff Pressure indicator and Fl-C12-1 R605 Cooling Water Flow.

• Perform the following for any drifted or partially scrammed rod(s):

o Promptly Insert rod to position 00.

o Hydraulically Disarm HCU in accordance with OP-155-001 Control Rod Drive Hydraulic System.

o IF drifted rod cannot be maintained at position 00:

• Immediately Re Arm HCU in accordance with OP-155-001 AND

• Proceed to Step 4.4.11.

o Declare rod inoperable.

o Comply with TS 3.1.3 Condition C.

• Contact Reactor Engineering.

PCOP Monitor plant parameters.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 26 of 40 POSITION TIME STUDENT ACTIVITIES (

us Enter ON-155-001, Control Rod Problems.

Determine control rod 22-39 is inoperable.

Determines Technical Specification 3.1.3 Condition C applies and is met with the control rod fully inserted and disarmed.

'NOTES I

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EVENT 4 BRIEF DESCRIPTION Coolant Leak in Drywell OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 2 to initiate event.

{Key[2]} IMF mfRR164011A i:0.01 r:4:00 f:0.03 ROLE PLAY As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. If the crew attempts to reset the locked scoop tube on RRP 1B, the scoop tube lock with NOT reset properly, limiting the ability to lower RRP 1B speed.

2. When the crew attempts to scram the Reactor, actions will then continue in the next event.

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CONFIDENTIAL Examinatio-n Material

LOC26R-N-02 Rev 1_;

12/16/2014 Page 29 of 40

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I SCENARIO EVENT FORM I

EVENT 4

• -~-- - r-- -*e - -- --- ~-~--- -*-* -* ---- -- *-- ---, -~- -------- .. ....

BRIEF DESCRIPTION Coolant Leak in Drywell POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report rising:

• Drywell leakage

• Drywell temperature

• Drywell pressure PCOM As directed I time permits, perform scram imminent actions of ON-100-101, Scram, Scram Imminent:

• REDUCE Reactor Power PER RE Instructions in the CRC Book:

0 INITIATE the required Flow/Power reduction by performing either of the following:

• INITIATE a Manual Rx Recirc Limiter #2 Runback using CORE POWER OFF NORMAL POWER REDUCTION HARD CARD (OP-164-001 Attachment E), OR

• TOUCH double chevron DEC buttons on REACTOR RECIRC PUMP A SPEED controllers SY-831-1R621A as required to establish the final Core Flow value stated in the CRC Book.

0 INSERT Control Rods, as necessary, to obtain a Rod Line which is less than the value stated in the CRC Book.

• NOTIFY GCC that the Unit is coming Off Line .

Rotate Mode Switch to SHUTDOWN.

PCOP Monitor plant parameters.

us EnterON-100-101, Scram, Scram Imminent.

May direct scram-imminent actions, if time I plant conditions permit.

Direct a manual Reactor scram.

INOTES I CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 30 of 40 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES (

EVENTS 5-8 Electrfcal ATINS, slc Pump Shaft shear, Main Generator trip~ Loss of All BRIEF DESCRIPTION Condensate Pumps, HPCI and RCIC Trip, Coolant Leak in Drywell Degrades OPERATOR ACTIVITY

1. When the crew attempts to start the first SLC pump, ensure one of the following triggers activates to allow the second SLC pump to operate properly.

aet LOC26R-N02-4 I aet LOC26R-N02-5

2. When Reactor power lowers to approximately 15% on APRMs, ensure the following trigger activates to trip the Main Generator and prevent re-start of Condensate pumps.

aet LOC26R-N02-3

3. When CRD is being maximized, ensure the following trigger activates to trip CRD pump 1A.

aet LOC26R-N02-6

4. When requested to pull RPS fuses, wait until given permission from lead examiner, then depress (

Keys 10 and 20 as described in role play below (and when directed to re-install fuses, immediately delete these malfunctions):

{Key[10]} IMF cmfFU01_1C609F18C I {Key[10]} IMF cmfFU01_1C609F18G d:5

{Key[10]} IMF cmfFU01_1C609F18A d:15 / {Key[10]} IMF cmfFU01_ 1C609F18E e:20

{Key[20]} IMF cmfFU01_1C611 F18D I {Key[20]} IMF cmfFU01_1C611F18H d:5

{Key[20]} IMF cmfFU01_1C611F188 d:15 / {Key[20]} IMF cmfFU01_1C611F18F d:20

5. When requested to vent scram air header, wait until given permission from lead examiner, then depress Key 30:

{Key[30]} IRF rfRD155018 f:100 I {Key[30]} IRF rfRD155025 d:5 f:O

{Key[30]} IRF rfRD155016 d:10 f:100

6. If requested to close CRD charging water header isolation valve, wait 2 minutes, depress Key 7, then report task completion:

{Key[40]} IRF rfRD155017 f:O

7. Once all control rods are inserted and when directed by Lead Examiner (and recommended as soon as all control rods are inserted), depress KEY 3 to trip HPCI and RCIC and make the coolant leak worse.

{Key[3]} IMF mfRC150011 I {Key[3]} IMF mfHP152015

{Key[3]} MMF mfRR164011A d:3:00 i:0.03 r:5:00 f:1 CONFIDENTIAL Examination Material

LOC26R-N-02 Rev u 12/16/20 i L!*

Page 31 of 40 ROLE PLAY

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As NPO dispatched to pull RPS fuses, wait at least 2 minutes and obtain Lead Examiner permission, then report, "I am about to pull RPS Channel A fuses, expect BACKUP/GROUP SYSTEM A POWER FAILURE ale1rms Qn tC651."

Then depress Key 10 as described above. Wait one minute, then report, "I am about to pull RPS Channel B fuses, expect BACKUP/GROUP SYSTEM B POWER FAILURE alarms on 1C651."

Then depress Key 20 as described above and report, "The RPS fuses have been pulled per ES-158-001."

As NPO dispatched to vent scram air header, wait at least 3 minutes and obtain Lead Examiner permission.

Contact the crew and report you are ready to vent the scram air header. When given permission depress Key 30 as described above and report, "The scram air header has been depressurized."

As NPO dispatched to investigate CRD or Condensate pumps, wait 2 minutes and report:

"Condensate(CRD) pump(s) have tripped on overcurrent."

As NPO dispatched to crosstie to Unit 2 CRD, acknowledge report.

As NPO dispatched to investigate HPCI or RCIC after it trips, wait 2 minutes and report:

"It looks like the HPCl(RCIC) turbine is damaged."

Role play any other directed actions as required.

EVALUATOR NOTES

1. HPCI and RCIC should not be tripped (KEY 3) until all control rods are in.

2. If Containment Sprays are in service prior to the Rapid Depressurization, the crew will need to re-align RHR to LPCI mode and then eventually back to Containment Sprays.

3. Recommended termination criteria:

• All control rods inserted.

• ADS vaJves open.

• Reactor water level controlled in assigned band above -161 ".

• Containment pressure controlled per E0-100-103.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 32 of 40 I SCENARIO EVENT FORM I

EVENTS 5-8 BRIEF DESCRIPTION Electrical A nf.JS, SLC Pump Shaft Shear, Main Gene-rator Trip, Loss of All Condensate Pumps, HPCI and RCIC Trip, Coolant Leak in Drywell Degrades POSITION TIME STUDENT ACTIVITIES

• TEAM Lower Reactor power using one or more of the following methods IAW E0-100-113:

• Trip Recirculation pumps

• Inject boron

• Lower Reactor water level Insert control rods IAW E0-100-113 Sht. 2.

Perform Rapid Depressurization when RPV level drops to -161" IAW E0-100-102.

TEAM Recognize I report failure to scram PCOM ARM AND DEPRESS Manual Scram pushbuttons: (

• RPS MAN SCRAM CHAN A 1 HS C72A 1 S03A

• RPS MAN SCRAM CHAN 81 HS C72A 1 S038

• RPS MAN SCRAM CHAN A2 HS C72A 1S03C

• RPS MAN SCRAM CHAN 82 HS C72A 1 S03D ARM AND DEPRESS ARI Pushbuttons to initiate ARI:

• ARI DIV 1 MAN TRIP HS 147103A1 TRIP

• ARI DIV 2 MAN TRIP HS 14710381 TRIP Report failure of RPS pushbuttons and ARI to insert control rods.

Insert SRMs/IRMs.

Runs Recirc to minimum From any RRP HMI screen by:

• Selects MANUAL FLOW REDUCTION INITIATION .

• Selects RRP SPEED TO MINIMUM .

• Selects INITIATE RRP FLOW REDUCTION .

Trips Recirculation pumps A and Bone at a time.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev*,:

12/16/2014-Page 33of40

( POSITION TIME STUDENT ACTIVITIES PCOM (cont.) Throttles and prevents RPV injection from FW and Cond until level is between -60" and -110" per OP-145-001 hard card:

• IF RFP A(B)(C) is operating in FCM:

0 Place FW LOLOAD-OEMAND SIGNALTO LV-10641, controller LIC-C32-1 R602 in MANUAL with a controller output of 0%.

0 Place FW LEVEL CTL/DEMAND SIGNAL controller LIC-C32-1 R600 in MANUAL.

0 Perform following for RFP A(B)(C) which will continue feeding:

• Touch A(B)(C) RFPT MAN VLV CTL button .

• Place feeding RFP A(B)(C) SPD CTL/DEMAND SIGNAL controller SIC-C32-1R601A(B)(C) in MANUAL.

0 Lower FW LEVEL CTL/DEMAND SIGNAL controller LIC-C32-1R600 output by - 20%.

0 Place remaining in service RFP B(C)(A) in IDLE MODE. (Fast Rate) 0 Adjust INC/DEC buttons on feeding RFP A(B)(C)

SPD CTL/DEMAND SIGNAL controller SIC-C32-1R601A(B)(C) in MANUAL to establish and maintain assigned level band.

• IF RFP A(B)(C) is in DPM, or transfer to DPM is in progress:

0 Control level in MANUAL via LV-10641 FW Startup Control Viv controller LIC-C32-1 R602.

0 As required, Adjust INC/DEC button on feeding RFP A(B)(C) SPD CTL/DEMAND SIGNAL controller SIC C32 1R601A(B)(C) in MANUAL to establish and maintain assigned level band. (2.19.9b)

• Stop Condensate pumps as necessary to leave 2 pumps in operation.

Maintains Reactor water level between -60" and -161" using Table 15 systems (SLC, FW, Cond, CRD, RCIC, HPCI).

Dispatch NPO to pull RPS fuses.

Dispatch NPO to vent scram air header.

Recognize I report all control rods inserted.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 34 of 40 POSITION TIME STUDENT ACTIVITIES (

PCOM (cont.) Once all control rods are inserted, attempt to slowly raise injection to restore and maintain Reactor water level -60" to -161" using Table 15 systems (SLC, FW, Cond, HPCI).

- c May reset Main Generator lockouts.

May attempt to restart Condensate pumps.

• Recognize I report failure of Condensate pumps to restart .

Recognize I report trip of HPCI and/or RCIC.

Recognize I report lowering Reactor water level and degraded injection capability.

Recognize I report Reactor water level <-161 ".

After Rapid Depressurization, restore and maintain Reactor water level >-161" using RHR and/or CS (+13" to +54" band normal).

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CONFIDENTIAL Examination Material

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12/16/2014 Page 35 of 40

( POSITION TIME STUDENT ACTIVITIES PCOP Inject SLC per OP-153-001:

• Place HS-14804 SBLC MANUAL INITIATION keylock control switch to A(B) START.

' *--. -Observe SBLC PUMPS 1P208A(B) STARTS.

Recognize I report first SLC pump started does not develop discharge pressure (sheared shaft)

Start alternate SLC pump.

Inhibit ADS by placing ADS A and ADS B LOGIC CONTROL switches in INHIBIT.

Maximize CRD per OP-155-001:

• Using FC-C12-1R600, CRD Flow Controller, in MANUAL, fully Opens FV-146-F002A(B), CRD Flo Ctl.

• Fully Open THTLG PV-146-F003, DRIVE WTR PRESS THTLG valve.

• Recognize/report trip of CRD pump 1A.

Override RCIC per OP-150-001:

• To prevent Auto Injection if RCIC NOT initiated, Close RCIC TURBINE TRIP AND THROTTLING HV-15012.

(

Override HPCI per OP-152-001:

• To prevent auto injection if HPCI not initiated, Place HPCI TURBINE FLOW CONTROL FC-E41-1 R600 in MANUAL AND Reduce demand to zero (0).

Bypass MSIV and CIG interlocks per OP-184-001:

• Bypass MSIV Low Water Level 1 Isolation at 1C645 by Placing the following to BYPASS:

0 HS-B21-S38A Rx Wtr Lvl 1 MSIV Bypass Logic A.

0 HS-B21-S38C RxWtr Lvl 1 MSIV Bypass Logic C.

• Bypass CIG Low Water Level 1 and High Drywell Pressure Isolation by Placing the following to BYPASS:

0 At 1C645, HS-12694 Low Lvl 1/Hi Drywell Press CIG Bypass (HV-12603) 0 At 1C645, HS-12695 Low Lvl 1/Hi Drywell Press CIG Bypass (SV-12651) 0 At 1C644, HS-12696 Low Lvl 1/Hi Drywell Press CIG Bypass (SV-12605)

• IF 1.72# High Drywell Pressure isolation has occurred, Restore CIG as follows:

0 Open Instr Gas Cmp Suet Isa HV-12603.

0 Open Instr Gas To Contn lso SV-12651.

0 Open Instr Gas Cmp OB Suet ISO SV-12605.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 36of40 POSITION TIME STUDENT ACTIVITIES (

PCOP (cont.) As time permits, initiate Suppression Chamber spray per OP-149-004:

• IF available, Place Emergency Service Water System in operation~upplying RHR Room Cooler and RHR Pump to be placed in service.

• IF LOCA signal present, Place HS-E11-1S17A(B) LOCA ISOLATION MANUAL OVERRIDE Switch to OVERRIDE.

0 Observe White Indicating Light ILLUMINATED above HS-E11-1S17A(B) LOCA ISOLATION MANUAL OVERRIDE.

0 Observe LOCA ISO SWITCH LOOP (A)B MANUAL OVERRIDE (AR-109(113)-CS) Annunciator alarms.

• Open HV-151-F028A(B) SUPP CHMBR SPR TEST SHUTOFF.

• Close HV-151-F017A(B)RHR INJ FLOW CTL.

• IF a RHR Pump not in service, Start 1P202A(B)(C)(D)RHR PUMP.

• Throttle Open HV-151-F027A(B) SUPP POOL SPRAY CTL, as necessary, to maintain : :; ; 500 GPM as indicated on Fl-15120A(B) CONTN SPRAY DIV 1(2) AND maintain total loop flowrate : :; ; 10,000 gpm.

• Monitor Suppression Chamber pressure .

• IF Suppression Chamber pressure drops to 0 psig, THEN

(

Stop Suppression Chamber Sprays.

• IF required, Place RHRSW in service to RHR HX per section 4.0:

0 Place RHR Service Water in service to the RHR Heat Exchanger per OP-116-001 OR as follows:

• Ensure Closed Unit 2 HV-21210A(B) RHRSW Hx A(B) INLET.

• Open HV-11210A(B) Unit 1 RHRSW HxA(B)

INLET to 10% Open.

• OPEN HV-11215A(B) Unit 1 RHRSW Hx A(B)

OUTLET.

• IF required, Place HS-11202A3(83) RHRSW PUMP A(B) LOCA TRIP switch to RESET.

• Start 1P506A(B) RHRSW Pump A(B) .

• Throttle HV-11210A(B) Unit 1 RHRSW Hx A(B) INLET to establish 8000 to 9000 gpm on Fl-E11-1 R602A(B) RHRSW HX A(B) INLET FLOW.

0 Place HV-151-F048A(B) HXA(B) SHELL SIDE BYPS Control Switch to OFF/LOCA RESET position.

0 Observe White Indicating Light ILLUMINATED above HV-151-F048A(B) Control Switch.

o

• Close HV-151-F048A(B) HX A(B) SHELL SIDE BYPS.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev ll 12/16/2014 Page 37 of 40

( POSITION TIME STUDENT ACTIVITIES PCOP (cont.) As time permits, initiate Drywell spray per OP-149-001, with flow limited to between 1000 and 2800 gpm for first 30 seconds:

• Open HV-151-F021A(B) DRYWELL SPRAY 18 ISO .

• Ensure both RX Recirc Pumps, all OW Coolers and Fans are Shutdown.

• Throttle HV-151-F016A(B) DRYWELL SPRAY OB ISO, as necessary, to establish a flowrate BETWEEN 1000 AND 2800 GPM for the first 30 seconds as indicated on Fl-15120A(B) CONTN SPRAY DIV 1(2) AND maintain total loop flowrate::;; 10,000 gpm.

• AFTER 30 seconds, Throttle Open HV-151-F016A(B) to establish a total loop flowrate 9,500 to 10,000 GPM as indicated on Fl-E11-1 R603A(B) RHR NC(B/D) FLOW.

• Monitor Drywell pressure .

• IF Suppression Chamber pressure drops to 0 psig, THEN Stop Suppression Chamber Sprays.

• IF required, Place RHRSW in service to RHR HX per section 4.0.

• AFTER Primary Containment parameters show a decreasing trend, IF DESIRED, Throttle HV-151-F016A(B) DRYWELL SPRAY OB ISO to establish a reduced flowrate.

Open all 6 ADS valves.

\.

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev 0 12/16/2014 Page 38 of 40 I SCENARIO EVENT FORM I (

EVENTS 5-8 BRIE_F __~ESCRl~TION- Electrical ATvVS~!:fLC-PumpShaffShear, Main Generator Trip, Loss of All Condensate Pumps, HPCI and RCIC Trip, Coolant Leak in Drywell Degrades POSITION TIME STUDENT ACTIVITIES us Enter E0-100-102, RPV Control, on high power and/or high Drywell pressure.

Exit E0-100-102 and enter E0-100-113, Level/Power Control:

• Direct ARI initiated .

• Record initial A TWS power level.

• Execute Power Leg:

0 Answer, "Is initial ATWS pwr >5% or cannot be determined?" Yes 0 Direct SLC injection.

• Acknowledge failure of first SLC pump started.

• Direct start of other SLC pump .

0 Direct ADS inhibited.

0 Ensure RWCU isolated. (

0 Ensure SRMs and IRMs inserted.

0 Direct Recirc run back to minimum.

0 Direct Recirc pumps tripped.

0 Direct CRD maximized.

• Acknowledge trip of CRD pump 1A.

• May enter ON-155-007 and direct crosstie with Unit 2.

0 Enter E0-100-113 sheet 2 for control rod insertion:

• Answer, "Is more than 1 rod >00?" Yes .

• Determine ATWS is electrical.

• Direct control rod insertion by pulling RPS fuses and/or venting scram air header.

• Execute Level Leg:

0 Direct verification of isolations and initiations.

0 Answer, "Is initial ATWS pwr >5% or cannot be determined?" Yes 0 Direct overriding RCIC and HPCI injection 0 Direct injection throttled and prevented until level between -60" and -110".

0 Direct bypassing of MSIV and CIG interlocks.

0 Direct Reactor water level controlled -60" to -161" using Table 15 systems (SLC, FW, Cond, CRD, HPCI, RCIC).

CONFIDENTIAL Examination Material

LOC26R-N-02 Rev ,_:

12/16/2014*

Page 39 of 40

( POSITION TIME STUDENT ACTIVITIES US (cont.)

• Execute Pressure Leg:

0 Direct Reactor pressure controlled 800-1050 psig using Turbine Bypass Valves.

As time permits, enter E0-100-103, Primary Containment Control, due to high Drywell pressure and temperature:

• Direct initiation of Suppression Chamber Spray .

• When Suppression Chamber pressure exceeds 13 psig or Drywell average temperature approaches 340°F:

0 Ensure shutdown of Drywell coolers and fans.

0 Direct initiation of Drywell sprays with flow limited to between 1000 and 2800 gpm for first 30 seconds.

• Determine Containment parameters are within the Pressure Suppression Limit.

Acknowledge all control rods are inserted.

Direct stopping boron injection.

Exit E0-100-113 and enter E0-100-102, RPV Control.

Direct Reactor water level restored and maintained +13" to +54".

Acknowledge trip of HPCI and/or RCIC.

May direct reset of Main Generator lockouts.

May direct restart of Condensate pumps.

• Acknowledge failure of Condensate pumps to restart .

Determine Reactor water level cannot be maintained above -129".

Direct lineup for injection and starting of pumps for all Table 3 injections systems.

Determine more than 1 injection subsystem is lined up with a pump running.

When Reactor water level drops to -161 ", enter E0-100-112, Rapid Depressurization:

• Exit E0-100-102 pressure leg .

• Determine Suppression Pool level is >5' .

• Direct opening all ADS valves .

• Determine all ADS valves are open .

Direct Reactor water level restored and maintained >-161" using LPCI, Core Spray, and/or SLC (+13" to +54" normal band).

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• Denotes Critical Task CONFIDENTIAL Examination Material

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I THIS PAGE IS INTENTIONALLY LEFT BLANK I

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CONFIDENTIAL Examination Material

UNIT SUPERVISOR TURNOVER SHEET

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UNIT 1 "to{dd/yy Date SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1 MODE P0 WE R LEVEL _1_0_0_ _ _ _ _  % POWER LEVEL  %

GENERATOR OUTPUT 1339 MWe GENERATOR OUTPUT MWe CASK STORAGE GATE INSTALLED: YES/NO CASK STORAGE GATE INSTALLED: YES/NO REMARKS:

1) 500 days on-line, 20 months into the operating cycle.

2) CRD pump 1B is out of service for maintenance.

4 5

6 7

8 9) 10

( 11

\

12) 13) 14) 15)

COMMON:

1) Unit 2 at rated power.

2 3

4) 5)

6 7) 8)

9)

FORM OP-AD-003-7, Rev. 23, DUPLEX Page 1 of 2 (Electronic Form)

CONFIDENTIAL Examination Material

OFFGOING UNIT SUPERVISOR CHECKLIST:

(

NRC CODE PRIOR TO 0800 FOXTROT DELTA HOTEL OSCAR NRC CODE AFTER 0800 FOXTROT UNIFORM BRAVO ROMEO 1900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor (including special evolutions, i.e. SICT/E, OPDRVs, etc.).

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

3. Information in SOMS Log is complete and discussed with oncoming Unit Supervisor.

4. As applicable, turnover plastic Security Badge cover and CRS Monitor function to oncoming Unit Supervisor.

0700 -1900 ~~---,~~~~~---~

Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:

0700 1900

1. LCOfTRO Log reviewed.

(

c) 2. SOMS Log reviewed for entries made in past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. Report any changes to license or medical status PER NDAP-QA-0723.

0700-1900 - - - - - - - - - - -

1900- 0700 ~-~~~-~~~~-~

Oncoming Qualified Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

.. .. 2. CRC Book reviewed and Reactivity Brief performed with PCO .

3. Completed System Status Operable audit for open PMT this shift.

4. From the OPS Web page, Review OPS Aggregate Index for Challenges, Work Arounds, and Deficiencies Reports for impact on scheduled work activities and compensatory actions. (20l 0700-1900 ~-~-~-~--~~~

1900- 0700

~---~-~--~~~

Oncoming Unit Supervisor FORM OP-AD-003-7, Rev. 23, DUPLEX Page 2 of 2 (Electronic Form)

CONFIDENTIAL Examination Material