Text

Final Operating Test Sections a, B, and C) (Folder 3)
	ML17013A457
Person / Time
Site:	Susquehanna
Issue date:	11/10/2016
From:	; Operations Branch I
To:	;
Shared Package
ML16076A438	List: IR 05000387/2016301; ML16155A069; ML16315A244; ML17013A454; ML17013A455; ML17013A457; ML17013A458; ML17013A459; ML17013A460; ML17013A461; ML17013A462; ML17102A838; ML17102A839;
References
	U01931
	Download: ML17013A457 (320)
	v • d • e

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review pressure/temperature plots and determine compliance with TS 3.4.10 S/RO OO.G0.1178.101 0 4/24/2015 Classroom Applicability JPM Number Revision Date Setting Generic 2.1.25 3.9/4.2 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/24/2015 Greg van den Berg 06/02/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket_>>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

OO.G0.1178.101 Rev 0 4/24/2015 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM

OO.G0.1178.101 Rev 0 4/24/2015 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. S0-100-011, Rx Vessel Temperature and Pressure Recording (Revision 26)

3. TASK CONDITIONS Unit 1 is in MODE 3 A reactor shutdown/cooldown is in progress S0-100-011, Rx Vessel Temperature and Pressure Recording, is being conducted You have just relieved the PCO performing the surveillance; your first set of data has been added to Table 2.

4. INITIATING CUE Perform a review of the data recorded in S0-100-011 for 2230 through 2345 to confirm procedural compliance and document discrepancies found, if any.

5. TASK STANDARD This JPM has the operator review surveillance data for temperature/pressure plots recorded during a reactor shutdown/cooldown to determine procedural compliance with all cooldown rates. See attached key.

PERFORMANCE CHECKLIST OO.G0.1178.101Rev0 4/24/2015 Examinee <<LastName>>, <<FirstName>> 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 cab be performed in the classroom or simulator.

Mark-up a copy of S0-100-011 complete through Step 5.2 .

Ensure Unit 1 Tech Specs and a calculator is available for the candidate .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of S0-100-011 and controlled copy. reviews data.

2 Verify temperature change calculations Verify cooldown rate calculations for each 15 minute and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during which the cooldown was conducted.

3 Confirm calculated cooldown rates comply with Confirm compliance with:<100°F cooldown Tech Spec and procedure requirements in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

Determines Steam Dome cooldown rate between 2230 and 2345 does not exceed 100°F Evaluator Note:

TS Required Actions should only be entered if Rx Steam Dome Temperature L1T's are> 100°F in any one hour. However, ALL L1 T's should be maintained <22° in any 15 minute period during cooldown.

4 Additional calculation and 15 minute cooldown rate Candidate should identify:

excursions

Recirc Loop B L1T 0 F:

0 2330-2345 L1T=23.3

Bottom Head Drain L1T °F:

0 2330-2345 L1T=24.0

PERFORMANCE CHECKLIST OO.G0.1178.101 Reva 4/24/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 2 Step Action Standard Eva I Comments

5 Identifies Temperature violation Notifies Supervisor that temperature violation has occurred twice for 15 minute averages.

SR 3.4.10 and TS 3.4.10 entry NOT required.

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?

EXAM I NEE TASK CONDITIONS Unit 1 is in MODE 3 A reactor shutdown/cooldown is in progress S0-100-011, Rx Vessel Temperature and Pressure Recording, is being conducted You have just relieved the PCO performing the surveillance; your first set of data has been added to Table 2.

INITIATING CUE Perform a review of the data recorded in S0-100-011 for 2230 through 2345 to confirm procedural compliance and document discrepancies found, if any.

EVALUATOR TASK CONDITIONS Unit 1 is in MODE 3 A reactor shutdown/cooldown is in progress S0-100-011, Rx Vessel Temperature and Pressure Recording, is being conducted You have just relieved the PCO performing the surveillance; your first set of data has been added to Table 2.

INITIATING CUE Perform a review of the data recorded in S0-100-011 for 2230 through 2345 to confirm procedural compliance and document discrepancies found, if any.

OO.G0.1178.101Rev0 4/24/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure S0-100-011 Rev 26 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.

OO.G0.1178.101Rev0 4/24/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet and handout cue loose

2. S0-100-011 (marked-up through step 5.2) exam staple

3. Evaluator cue sheet cue loose

4. Answer key cue loose

5. JPM jpm loose

SUSQUEHANNA NUCLEAR, 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 2 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 Greg van den Berg 12/04/2014 Rich Bolduc 05/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 6/5/15 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 15 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

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

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Minor editorial changes Updated references and individual scenario task conditions to accommodate the 2

LOC 27 NRC exam.

OO.EP.1132.180 Rev 2 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, CR Emergency Director (revision 33)

B. EP-RM-004, EAL CLASSIFICATION BASES (Revision 4)

C. EP-PS-001, EMERGENCY PLANNING FORMS AND SUPPLEMENTARY INSTRUCTIONS (Revision 7)

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 on the cue sheet.

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.

PERFORMANCE CHECKLIST OO.EP.1132.180 Rev 2 12/04/2014 Examinee <<LastName>>, <<FirstName>> 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.

PERFORMANCE CHECKLIST OO.EP.1132.180 Rev 2 12/04/2014 Examinee <<LastName>>, <<FirstName>> 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

PERFORMANCE CHECKLIST OO.EP.1132.180 Rev 2 12/04/2014 Examinee <<LastName>>, <<FirstName>> 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?

OO.EP.1132.180 Rev 2 12/04/2014 Page 1 of 10 JPM KEY Scenario Classification EAL Release 1 Site Area Emergency FS1 No 2 Site Area Emergency FS1 Yes 3 Site Area Emergency MS3 No 4 Unusual Event MU1/FU1 No

OO.EP.1132.180 Rev 2 12/04/2014 Page 2of10 EXAMINEE - SCENARIO 1 TASK CONDITIONS Unit 1 was at rated power A reactor coolant leak occurred in the drywell Unit 1 was manually scrammed - all control rods fully inserted Unit 1 experienced the following conditions:

Suppression Chamber and Drywell sprays were placed in service

RPV level was being maintained with HPCI and RCIC

HPCI Turbine Tripped

RPV level lowered below -179"

Emergency Depressurization was performed

RPV level was recovered with low pressure ECCS 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 3of10 EVALUATOR - SCENARIO 1 TASK CONDITIONS Unit 1 was at rated power A reactor coolant leak occurred in the drywell Unit 1 was manually scrammed - all control rods fully inserted Unit 1 experienced the following conditions:

Suppression Chamber and Drywell sprays were placed in service

RPV level was being maintained with HPCI and RCIC

HPCI Turbine Tripped

RPV level lowered below -179"

Emergency Depressurization was performed

RPV level was recovered with low pressure ECCS 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 4of10 EXAMINEE - SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 3%

Unit 1 experienced the following conditions:

An uncoupled control rod dropped causing fuel failure

The reactor failed to auto scram, requiring a manual scram

All Control Rods fully inserted when the mode switch was placed in shutdown

MSIV are isolated due to Main Steam Line High Rad

SDIV vents and drains failed to close causing a high rad in secondary containment

RWCU system leak occurred in secondary containment, the system failed to isolate

Emergency Depressurization was performed due to 2 areas above Max Safe Radiation

Security reports no blowout panels have ruptured 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 5 of 10 EVALUATOR - SCENARIO 2 TASK CONDITIONS Unit 1 Reactor Power was approximately 3%

Unit 1 experienced the following conditions:

An uncoupled control rod dropped causing fuel failure

The reactor failed to auto scram, requiring a manual scram

All Control Rods fully inserted when the mode switch was placed in shutdown

MSIV are isolated due to Main Steam Line High Rad

SDIV vents and drains failed to close causing a high rad in secondary containment

RWCU system leak occurred in secondary containment, the system failed to isolate

Emergency Depressurization was performed due to 2 areas above Max Safe Radiation

Security reports no blowout panels have ruptured 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 6of10 EXAMINEE - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 20%

A shutdown was in progress for a turbine outage Unit 1 experienced the following conditions:

A loss of Aux Bus 11 B occurred.

Vacuum degraded due to air in leakage into the Main Condenser, which prompted a manual scram

An A TWS condition occurred with reactor power initially at 10%

Full scram was achieved by venting the scram air header 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 7of10 EVALUATOR - SCENARIO 3 TASK CONDITIONS Unit 1 Reactor Power was approximately 20%

A shutdown was in progress for a turbine outage Unit 1 experienced the following conditions:

A loss of Aux Bus 11 B occurred.

Vacuum degraded due to air in leakage into the Main Condenser, which prompted a manual scram

An A TWS condition occurred with reactor power initially at 10%

Full scram was achieved by venting the scram air header 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 8of10 EXAMINEE - SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 97%

Unit 1 experienced the following conditions:

HPCI is declared INOP due to a spurious start

A manual scram was inserted due to Main Steam Line steam leak into the Turbine Building

MSIV 's on 'D' MSL fail to isolate requiring manual isolation to stop steam leak into Turbine Building

A Loss Of Offsite Power (LOOP) occurred and Emergency Diesel Generators failed to start

Emergency Diesel Generators were manually started to remove the plant from a station blackout within 5 minutes of the LOOP

HPCI and RCIC required manual start to control RPV level and pressure

Security reports no blowout panels have ruptured 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.

OO.EP.1132.180 Rev 2 12/04/2014 Page 9of10 EVALUATOR- SCENARIO 4 TASK CONDITIONS Unit 1 Reactor Power was approximately 97%

Unit 1 experienced the following conditions:

HPCI is declared INOP due to a spurious start

A manual scram was inserted due to Main Steam Line steam leak into the Turbine Building

MSIV 's on 'D' MSL fail to isolate requiring manual isolation to stop steam leak into Turbine Building

A Loss Of Offsite Power (LOOP) occurred and Emergency Diesel Generators failed to start

Emergency Diesel Generators were manually started to remove the plant from a station blackout within 5 minutes of the LOOP

HPCI and RCIC required manual start to control RPV level and pressure

Security reports no blowout panels have ruptured 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.

OO.EP.1132.180 Rev2 12/04/2014 Page 10of10 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure EP-RM-004 Rev 33 Procedure EP-PS-100 Rev 4 Procedure EP-PS-001 Rev 7 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.).

NIA 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.

OO.EP.1132.180 Rev2 12/04/2014 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue PC*

2. Evaluator cue sheet cue PC*

3. JPM jpm Loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review and Verify Blocking Required per NDAP-QA-0322 "ECP" SRO OO.AD.3274.201 1 03/27/2015 Classroom Applicability JPM Number Revision Date Setting Generic 2.2.41 3.5/3.9 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 03/27/2015 Greg van den Berg 05/28/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examines Name: <<LastName>>, <<FirstName>> (<<Docket >>} <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

OO.AD.3274.201 Rev 1 03/27/2015 Page 2 of 3 JPM REVISION

SUMMARY

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

OO.AD.3274.201 Rev 1 03/27/2015 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-0322, Energy Control Process (Revision 53)

B. E-145 sh. 8 C. E-4 sh. 3 D. M-2109 sheet 1 E. M-2109 sheet 2

3. TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means

4. INITIATING CUE Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. If any inaccuracies are identified provide a recommendation for correction(s). The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service

5. TASK STANDARD Review the list of proposed blocking for 2A Service Water Pump; discrepancies identified and noted IAW attached Key

PERFORMANCE CHECKLIST OO.AD.3274.201 Rev 1 03/27/2015 Examinee <<LastName>>, <<FirstName>> 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 can be performed in the classroom or simulator.

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

0 Prints: E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2, NDAP-QA-0322, Energy Control Process, Library clearance for SW Pump 2A EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of NDAP-QA-0322, controlled copy. supporting prints and clearance order.

2 Identifies the requested 13.8kV breaker listed Using E-145; (2A 10103) is incorrect

Candidate identifies the requested 13.8kV breaker listed (2A 10103) is incorrect

Candidate identifies 2A 10106 as correct 13.8kV breaker for 2A Service Water Pump.

3 Identifies the requested Service Water Pump vent Using M-2109, Sheet 2; valve is incorrect and is actually for 28 Service

Candidate identifies the requested Water Pump (209167) Service Water Pump vent valve is incorrect and is actually for 28 Service Water Pump (209167)

Candidate identifies 209166 as the correct 2A Service Water Pump vent valve EVALUATOR CUE Role play the Unit Supervisor and acknowledge the receipt of the corrected blocking and inform candidate that it will be forwarded to the wee

PERFORMANCE CHECKLIST OO.AD.3274.201 Rev 1 03/27/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 2 Step I Action I Standard Eva I Comments EVALUATOR CUE Once candidate turns in list of corrected blocking sheet, the JPM is complete.

EVALUATOR NOTE DUE TO THE NATURE OF THIS JPM OTHER BLOCKING POINTS MAY BE ACCEPTABLE. CONSULT WITH ADDITIONAL SMEs AS NECESSARY TO DETERMINE ACCEPTABILITY OF ALTERNATE BLOCKING POINTS.

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?

EXAM INEE TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. If any inaccuracies are identified provide a recommendation for correction(s). The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service

EVALUATOR TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. If any inaccuracies are identified provide a recommendation for correction(s). The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service

OO.AD.3274.201 Rev 1 03/27/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure NDAP-QA-0322 Rev 53 Procedure E-145, E-4 Rev 8/17 Procedure M-2109 Sh 1-2 Rev 46/13 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.

OO.AD.3274.201 Rev 1 03/27/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. NDAP-QA-0322 exam staple

3. SWP 2a Library Clearance exam staple

4. E-145 (C or 17x22" landscape) N/A loose

5. E-4 (C or 17x22" landscape) N/A loose

6. M-2109 Sh 1 and 2 (C or 17x22" landscape) N/A loose

7. Evaluator cue sheet cue loose

8. JPM jpm loose

9. Procedure (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review and Verify Blocking Required per NDAP-QA-0322 "ECP" S/RO OO.AD.327 4.202 1 03/27/2015 Classroom Applicability JPM Number Revision Date Setting Generic 2.2.41 3.5/3.9 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 03/27/2015 Greg van den Berg 05/28/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments

OO.AD.3274.202 Rev 1 03/27/2015 Page 2 of 3 JPM REVISION

SUMMARY

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

OO.AD.3274.202 Rev 1 03/27/2015 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-0322, Energy Control Process (Revision 53)

B. E-145 sh. 8 C. E-4 sh. 3 D. M-2109 sheet 1 and 2 E. Provide blank proposed blocking sheet

3. TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means

4. INITIATING CUE Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service. Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type

5. TASK STANDARD Provide a list of proposed blocking for 2A Service Water Pump IAW NDAP-QA-0322 IAW the attached Proposed Blocking List Key

PERFORMANCE CHECKLIST OO.AD.3274.202 Rev 1 03/27/2015 Examinee <<LastName>>, <<FirstName>> 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 can be performed in the classroom or simulator.

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

0 Prints: E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2, NDAP-QA-0322, Energy Control Process, Blank proposed blocking sheet EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of NDAP-QA-0322, controlled copy. and supporting prints.

2 Develops a list of proposed blocking points based Develops proposed blocking list that upon print review and NDAP-QA-0322 guidance. matches the answer key.

EVALUATOR CUE Role play the Unit Supervisor and acknowledge the receipt of the proposed blocking points/corrected blocking and inform candidate that it will be forwarded to the wee.

EVALUATOR CUE Once candidate turns in list of proposed blocking points, the JPM is complete.

EVALUATOR NOTE DUE TO THE NATURE OF THIS JPM OTHER BLOCKING POINTS MAY BE ACCEPTABLE. CONSULT WITH ADDITIONAL SMEs AS NECESSARY TO DETERMINE ACCEPTABILITY OF ALTERNATE BLOCKING POINTS.

EVALUATOR CUE Record JPM stop time:

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

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

EXAMINEE TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service. Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type

PROPOSED BLOCKING EVALUATOR TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump seal replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service. Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type

PROPOSED BLOCKING KEY DO NOT GIVE TO CANDIDATE Component Position Tag Type

1. *2A10106 Service Water Pump A 2P502A 13.SkV *OPEN, *RACKED *Red tag breaker OUT, (applicant may also request breaker REMOVED)

2. *209001 Service Water Pump A Suction ISO VLV *CLOSED *Red tag

3. *209004 Service Water Pump A Discharge ISO VLV *CLOSED *Red tag

4. *209014 Service Wtr Pump A Seal Water Press *CLOSED *Red tag TL VLV Bypass VLV

..,. *209015 Service Wtr Pump A Seal Water Press CTL *CLOSED *Red tag VLV Inlet ISO VLV OR

209016 Service Wtr Pump A Seal Water Press CTL VLV Outlet ISO VLV

6. *209166 Service Wtr Pump A Vent VLV *CLOSED *Red tag

7. 209801 Service Water Pump A OB Casing Vent VL V OPEN No tag/Pink tag

8. 209802 Service Water Pump A IB Casing Vent VL V OPEN No tag/Pink tag

9. 209048 Service Water Pump A Drain VL V OPEN No tag/Pink tag

10. 209119 Service Water Pump A Drain VL V OPEN No tag/Pink tag

- - Applicant may or may not identify these valves (#7,8,9and10)***

OO.AD.3274.202 Rev 1 03/27/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure NDAP-QA-0322 Rev 53 Procedure E-145, E-4 Rev 8/17 Procedure M-2109 Sh 1-2 Rev 46/13 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.

OO.AD.3274.202 Rev 1 03/27/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. NDAP-QA-0322 exam staple

3. SWP 2A Library Clearance exam staple

4. E-145 (C or 17x22" landscape) N/A loose

5. E-4 (C or 17x22" landscape) N/A loose

6. M-2109 Sh 1 and 2 (C or 17x22" landscape) N/A loose

7. Evaluator cue sheet cue loose

8. JPM jpm loose

9. Procedure (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Calculate and Approve Emergency Exposure S/RO OO.EP.1132.185 2 08/08/2014 Classroom Applicability JPM Number Revision Date Setting G 2.3.4 3.7 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/28/2015 Rich Bolduc 06/02/2015 Author Date Instructor Date Review Approval Manu Sivaraman 6/5/15 Greg van den Burg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<LicenseType>>) <<Employee>>

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

Evaluation Result: D Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments

OO.EP.1132.185 Rev 2 08/08/2014 Page 2 of 4 JPM REVISION

SUMMARY

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

Reformatted to the "TQ" procedure format Updated procedure references. Updated Task Conditions for Worker A; was 2

"planned special exposure" now "Emergency Exposure Extension"

OO.EP.1132.185 Rev 2 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. EP-PS-001, Emergency Planning Forms and Supplementary Instructions, Attachment H (Revision 7)

3. TASK CONDITIONS A Site Area Emergency is in progress.

You have assumed the responsibilities of the Emergency Director.

A steam leak from RCIC into the Reactor Building cannot be isolated without manually shutting a valve in the field.

Entry to the Reactor Building is required to manually close this valve to stop a release to the environment.

Time to complete the task for an experienced NPO will be approximately 24 minutes.

Time to complete the task for a new NPO will be approximately 30 minutes.

Radiation levels at the valve are approximately 15 R/hr.

The operator will be wearing a respirator, such that no thyroid dose is expected.

Four (4) individuals are available to perform the task:

Worker A is a volunteer who is an experienced NPO, has previously received an emergency exposure extension at another facility, and has received a dose of 150 mR this year (Age= 47 years, TLD Badge No. 11111, SSN 111-11-1111).

Worker B is a volunteer who is an experienced NPO and is a declared pregnant worker and has received a dose of 15 mR this year (Age = 35 years, TLD Badge No. 22222, SSN 222-22-2222).

Worker C is a volunteer who is an experienced NPO and has received a dose of 1800 mR this year (Age = 46 years, TLD Badge No. 33333, SSN 333-33-3333).

Worker D is a volunteer who is a new NPO that has received a dose of 500 mR this year (Age= 32 years, TLD Badge No. 44444, SSN 444-44-4444).

4. INITIATING CUE

OO.EP.1132.185 Rev 2 08/08/2014 Page 4 of 4 Choose an individual to enter the Reactor Building and close the valve, state the reason why that worker was chosen, estimate the expected radiation exposure, and document your authorization for an Emergency Exposure Extension.

5. TASK STANDARD Generate and approve an Emergency Exposure Authorization Form and estimate exposure

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee <<LastName>>, <<FirstName>> 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 should be performed in the classroom .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains a controlled copy of the applicable controlled copy. procedure(s).

2 Determine the expected exposure for the task

For an experienced worker -

Calculates that a 24 minute exposure in a 15 R/hr field will cause a dose of 6 R.

For a new worker - Calculates that a 30 minute exposure in a 15 R/hr field will cause a dose of 7.5 R.

3* Select the best worker to perform the task Determines the best worker for the task:

Does NOT select Worker A

Does NOT select Worker B

Selects Worker C

Does NOT select Worker D

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee <<LastName>>, <<FirstName>> Page 2 of 3 Step Action Standard Eva I Comments EVALUATOR NOTE The following rationale supports worker selection:

Worker A should NOT be chosen due to previously receiving an emergency exposure extension .

Worker B should NOT be chosen due to being a declared pregnant worker .

Worker C should be chosen because both their dose for the emergency exposure (6 R) will be less than that for Worker D; additionally, the dose to the public will be minimized by the shorter task completion time of this experienced worker.

Worker D should NOT be chosen because their dose for the emergency exposure (7.5 R) will be greater than that for Worker C .

4 State reason for choosing the selected worker States that Worker C was chosen to minimize dose.

States that Worker A was NOT chosen due to a previous emergency exposure extension.

States that Worker B was NOT chosen due to being a declared pregnant worker.

States that Worker D was NOT chosen due to higher dose.

5* Estimate expected exposure Determines Worker C will receive an estimated 6 R while completing the task (24 minutes x 15 R/hr I 60 min/hr).

EVALUATOR NOTE The examinee may choose to brief the worker on radiological conditions, potential for steam leakage in the area, planned task, applicable ALARA measures, and contingency measures. Role play as Worker C and acknowledge the briefing.

EVALUATOR NOTE The Candidate may ask for an RWP to be generated. Role play as HP and state that an RWP has been generated.

6* Generate an Emergency Exposure Extension Completes an Emergency Exposure Request Form. Extension Request Form (see attached key).

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee <<LastName>>, <<FirstName>> Page 3 of 3 Step I Action I Standard I Eval I 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?

EXAM INEE TASK CONDITIONS A Site Area Emergency is in progress.

You have assumed the responsibilities of the Emergency Director.

A steam leak from RCIC into the Reactor Building cannot be isolated without manually shutting a valve in the field.

Entry to the Reactor Building is required to manually close this valve to stop a release to the environment.

Time to complete the task for an experienced NPO will be approximately 24 minutes.

Time to complete the task for a new NPO will be approximately 30 minutes.

Radiation levels at the valve are approximately 15 R/hr.

The operator will be wearing a respirator, such that no thyroid dose is expected.

Four (4) individuals are available to perform the task:

Worker A is a volunteer who is an experienced NPO, has previously received an emergency exposure extension at another facility, and has received a dose of 150 mR this year (Age= 47 years, TLD Badge No. 11111, SSN 111-11-1111 ).

Worker B is a volunteer who is an experienced NPO and is a declared pregnant worker and has received a dose of 15 mR this year (Age = 35 years, TLD Badge No. 22222, SSN 222-22-2222).

Worker C is a volunteer who is an experienced NPO and has received a dose of 1800 mR this year (Age = 46 years, TLD Badge No. 33333, SSN 333-33-3333).

Worker D is a volunteer who is a new NPO that has received a dose of 500 mR this year (Age = 32 years, TLD Badge No. 44444, SSN 444-44-4444).

INITIATING CUE Choose an individual to enter the Reactor Building and close the valve, state the reason why that worker was chosen, estimate the expected radiation exposure, and document your authorization for an Emergency Exposure Extension.

EVALUATOR TASK CONDITIONS A Site Area Emergency is in progress.

You have assumed the responsibilities of the Emergency Director.

A steam leak from RCIC into the Reactor Building cannot be isolated without manually shutting a valve in the field.

Entry to the Reactor Building is required to manually close this valve to stop a release to the environment.

Time to complete the task for an experienced NPO will be approximately 24 minutes.

Time to complete the task for a new NPO will be approximately 30 minutes.

Radiation levels at the valve are approximately 15 R/hr.

The operator will be wearing a respirator, such that no thyroid dose is expected.

Four (4) individuals are available to perform the task:

Worker A is a volunteer who is an experienced NPO, has previously received an emergency exposure extension at another facility , and has received a dose of 150 mR this year (Age= 47 years, TLD Badge No. 11111, SSN 111-11-1111).

Worker Bis a volunteer who is an experienced NPO and is a declared pregnant worker and has received a dose of 15 mR this year (Age = 35 years, TLD Badge No. 22222, SSN 222-22-2222).

Worker C is a volunteer who is an experienced NPO and has received a dose of 1800 mR this year (Age = 46 years, TLD Badge No. 33333, SSN 333-33-3333).

Worker Dis a volunteer who is a new NPO that has received a dose of 500 mR this year (Age = 32 years, TLD Badge No. 44444, SSN 444-44-4444).

INITIATING CUE Choose an individual to enter the Reactor Building and close the valve, state the reason why that worker was chosen, estimate the expected radiation exposure, and document your authorization for an Emergency Exposure Extension.

OO.EP.1132.185 Rev 2 08/08/2014 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

-- - - 7.

G.v. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure EP-PS-001 Att. H Rev 7 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.

This JPM revised to reflect new reference procedure, EP-PS-001.

This JPM was reformatted to the TQ procedure format.

No other changes required following validation.

OO.EP.1132.185 Rev 2 08/08/2014 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Evaluator cue sheet cue loose

3. JPM jpm loose

4. JPM Key jpm loose

5. EP-PS-001, Att. H (replacement) sim PC

t- DI

/:::- T {a_n

~e_fl~ ~(\!~ ~rt~or~a~

\ C1 Q_( u Jec,l cn -:r~ M.

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review Failed Surveillance Test and Determine Required Action S/RO 51.S0.1944.151 1 03/27/2015 Classroom Applicability JPM Number Revision Date Setting Generic 2.2.12 3.7/4.1 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 03/27/2015 Greg van den Berg 06/02/2015 Author Date Instructor Date Review Approval Manu Sivaraman 6/5/15 Durand Adams 6/3/15 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket_>>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

51.S0.1944.151Rev1 03/27/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revised to incorporate revised procedure changes and testing requirements.

51.S0.1944.151Rev1 03/27/2015 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. S0-151-A02 Quarterly Core Spray Flow Verification Division 1, (Revision 24)

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

S0-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

4. INITIATING CUE RO:

Review the provided surveillance testing data for S0-151-A02 in Attachment A and document findings below.

SRO:

Unit 1 was in a normal electrical line up, then B EOG was taken OOS unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EOG is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Review and Complete S0-151-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

5. TASK STANDARD This JPM has the operator review surveillance data for Core Spray pump A and determine its operability. The RO and SRO applicants will determine the pump to be inoperable. The RO will inform the SRO on the operability status. The SRO applicant will also determine that the Core Spray Pump to be inoperable and determine that TS 3.5.1 Action A.1 to Restore low pressure ECCS injection/spray subsystem to OPERABLE status within ?days applies. Also TS 3.8.1 Action B.2 to declare Core Spray Pump B INOPERABLE within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of entering TS 3.5.1 Action A.1. SRO will further determine that TS 3.5.1 Action 1.1 applies when 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months has been elapsed since declaring Core Spray Pump A INOPERABLE.

51.S0.1944.151Rev1 03/27/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to any rated-power IC.

2. Run scenario file XXX.SCN file

3. Other actions

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee <<LastName>>, <<FirstName>> 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 can be performed in the classroom or simulator

Mark-up a copy of S0-151-A02 complete through Step 5.2 to include Attachment A marked up through step 12 .

Ensure that pump A discharge pressure is recorded as 262.5 psig (step 5.2.6.c) and calculated delta-p value recorded in Attachment A acceptance criteria 4 is recorded as 264.5 psid.

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:

1 Identifies governing procedure and obtain Provide marked-up copy of S0-151-A02 controlled copy. through step 5.2 and Attachment A through step 12.

Reviews As-Found Column data on Attachment 'A' Reviews data on S0-151-A02, Quarterly 2 Core Spray Flow Verification Division 1, Attachment A.

3 . Identifies that there is a calculation error for Compares the calculated CS pump A delta-P calculating CS pump A delta-P. (Attachment A of 264.5 psid with the actual discharge acceptance criteria 4) pressure and suction pressure valves (262.5 psig - 8psig) and determines that there is a math error. The actual calculated value would be 254.5 psid, and determines this to be UNACCEPTABLE due to being outside the criteria of 256.5 and 313.5 psid.

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments

4 Notifies Shift Supervision that SO 151-A02 has IAW Attachment A. Under Required Action:

failed its acceptance criteria.

Notifies Shift Supervision that S0-151-A02 A CS pump failed its acceptance criteria.

AND Initials the Confirm space.

EVALUATOR NOTE This completes the JPM for the RO candidate. If JPM is being used for a SRO candidate, continue the JPM.

5 Declares CS pump A inoperable IAW Attachment B. Required Action:

Determines that the measured values of pump delta-P fall outside of their acceptance criteria, and the pump shall be Declared INOPERABLE.

AND Marks the Surveillance Authorization Sheet (Part VI) as FAILED

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action Standard Eva I Comments 6 Ensures applicable action statements are in effect. Determines TS 3.5.1 Condition A.1 applies.

One low pressure ECCS injection/spray subsystem inoperable for reasons other than Condition B (One LPCI pump in one or both LPCI subsystems inoperable) Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7 days.

AND TS 3.8.1 Condition B.2 applies When one required DG is inoperable, Declare the required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)

INOPERABLE, EVALUATOR CUE Inform the applicant that 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months has been elapsed since TS 3.5.1 Action A.1 entry and there is no change in equipment operability status. 'E' EOG is unavailable for substitution.

Identify TS required actions

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 Step Action Standard Eva I Comments

7 Identifies TS 3.0.3 entry Determines Condition I Action 1.1 is applicable and LCO entry 3.0.3 is required.

For Two Core Spray subsystems inoperable TS 3.0.3 Identifies that actions need to be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place Unit 1 in Mode 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

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?

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

S0-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE Review the completed surveillance testing data for S0-151-A02 in Attachment A and document findings below.

RO EVALUATOR TASK CONDITIONS Unit 1 is at 100% power.

S0-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE Review the completed surveillance testing data for S0-151-A02 in Attachment A and document findings below.

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

S0-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE Unit 1 was in a normal electrical line up, then B EOG was taken OOS unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EOG is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Review and Complete S0-151-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

SRO EVALUATOR TASK CONDITIONS Unit 1 is at 100% power.

S0-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE Unit 1 was in a normal electrical line up, then B EOG was taken OOS unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EOG is 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Review and Complete S0-151-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

51.S0.1944.151Rev1 03/27/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure S0-151-A02 Rev 24 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.

51.S0.1944.151 Rev 1 03/27/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Surveillance Authorization form marked up exam loose S0-151-A02 (marked-up through step 5.2

3. exam staple and Att. A marked-up through step 12)

4. Evaluator cue sheet cue loose

5. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Determine NRC Notification Requirements S/RO 00.AD.1032.001 3 08/05/2014 Classroom Applicability JPM Number Revision Date Setting G 2.1.18 3.8 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 4/24/2015 Greg van den Berg 06/02/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments

00.AD.1032.001 Rev 3 08/05/2014 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections 2 Reformatted to the "TQ" procedure format Added additional options to the key for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reportability of a declaration of an 3

emergency

00.AD.1032.001 Rev 3 08/05/2014 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-0720, Station Report Matrix and Reportability Evaluation Guide (Revision 26)

B. NUREG 1022, Event Reporting Guidelines 10CFR50.72 and 50.73 (Revision3)

C. EP-RM-004, EAL Classification Bases (Revision 4)

3. TASK CONDITIONS Both Units were operating at 100 percent power with no equipment out of service.

A primary coolant leak developed in the Unit 1 Drywell.

Operators inserted a manual reactor scram.

All control rods inserted.

Reactor water level reached a low of -32" before recovering to the normal band.

RCIC auto-started and performed as designed.

Drywell pressure is now 0.85 psig up slow.

Drywell floor drain in-leakage is 60 gpm up slow.

4. INITIATING CUE Determine the applicable 10 CFR 50. 72 reportability requirements, the reason that they apply, and the associated time limitations for reporting under that category. Record your findings on the sheet provided

5. TASK STANDARD Determine 10 CFR 50.72 reportability requirements (see answer key)

PERFORMANCE CHECKLIST 00.AD.1032.001 Rev 3 08/05/2014 Examinee <<LastName>>, <<FirstName>> 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 can be performed in the classroom or simulator.

Ensure the following references are available if requested: NDAP-QA-0720, NU REG 1022, and EP-RM-004 .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtain a controlled copy of applicable controlled copy. procedures and/or regulations, which may include:

NDAP-QA-0720 .

NUREG 1022 .

10CFR50.72.

EAL Matrix .

2* Locate and identify applicability of 10 CFR Identifies reportability per 10 CFR

50. 72(a)(1 )(i) 50.72(a)(1)(i) for declaration of emergency May also select: May also select:

10 CFR 50. 72(a)(3) 10 CFR 50. 72(a)(3) 10 CFR 50.72(a)(4) 10 CFR 50.72(a)(4)

EVALUATOR NOTE Alert FA 1 applies due to potential loss of the RCS barrier as evidenced by unisolable RCS leakage > 50 gpm inside Primary Containment

PERFORMANCE CHECKLIST 00.AD.1032.001 Rev 3 08/05/2014 Examinee <<LastName>>, <<FirstName>> Page 2 of 3 Step Action Standard Eva I Comments 3* Determine required reporting time for 10 CFR Identifies report for 10 CFR 50.72(a)(1)(i) is

50. 72(a)(1 )(i). required immediately after notification of the appropriate State or local agencies and not later than one hour after the time of declaration of the emergency.

May also select:

10 CFR 50.72(a)(3) 10 CFR 50.72(a)(3) 10 CFR 50.72(a)(4) 10 CFR 50.72(a)(4) 4* Locate and identify applicability of 10 CFR Identifies reportability per 10 CFR 50.72(b)(2)(iv)(B). 50. 72(b)(2)(iv)(B) for actuation of the Reactor Protection System while the Reactor was critical 5* Determine required reporting time for 10 CFR Identifies report for 10 CFR

50. 72(b)(2)(iv)(B) 50.72(b)(2)(iv)(B) is required within four hours 6* Locate and identify applicability of 10 CFR Identifies reportability per 10 CFR 50.72(b)(3)(iv)(A). 50.72(b)(3)(iv)(A) for valid actuation of RCIC and +13" isolation signal 7* Determine required reporting time for 10 CFR Identifies report for 10 CFR

50. 72(b)(3)(iv)(A) 50.72(b)(3)(iv)(A) is required within eight hours EVALUATOR NOTE The examinee may identify additional 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reports. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report is for making an off-site notification under 10 CFR 50. 72(b)

(2)(xi) and an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report under 10 CFR 50. 72(b)(3)(ii)(A) for degradation of principle safety barrier (RCS). These reporting criteria are applicable; however, they are bounded by the other notifications. Therefore, they are not included in the grading criteria.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

PERFORMANCE CHECKLIST 00.AD.1032.001 Rev 3 08/05/2014 Examinee <<LastName>>, <<FirstName>> Page 3 of 3 Step I Action I Standard I Eval I Comments EVALUATOR:

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

JPM ANSWER KEY Identify the applicable 10 CFR 50. 72 reportability requirements, the reason that they apply, and the associated time limitations for reporting under that category.

Reportability Requirement and Reason Time Limit 10 CFR 50. 72(a)(1 )(i) for declaration of emergency Immediately after notification of 10 CFR 50.72(a)(3) the appropriate State or local 10 CFR 50.72(a)(4) agencies and not later than one hour after the time of declaration of the emergency.

10 CFR 50.72(b)(2)(iv)(B) for valid Reactor Protection Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months System (RPS) actuation while the Reactor is critical 10 CFR 50. 72(b)(3)(iv)(A) for valid actuation of RCIC Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and +13" isolation signal EVALUATOR NOTE May alternately refer to 10CFR 50.72(b)(3)(iv)(B)(2 & 5) for these reportability requirements.

EVALUATOR NOTE The examinee may identify an additional 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report. The additional 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report is for making an off-site notification under 10 CFR 50. 72(b) (2)(xi) and the additional 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report under 10 CFR 50. 72(b)(3)(ii)(A) is for degradation of principle safety barrier (RCS).

These reporting criteria are applicable; however, they are bounded by the other notifications. Therefore, they are not included in the qradinq criteria.

EXAMINEE TASK CONDITIONS Both Units were operating at 100 percent power with no equipment out of service.

A primary coolant leak developed in the Unit 1 Drywell.

Operators inserted a manual reactor scram.

All control rods inserted.

Reactor water level reached a low of -32" before recovering to the normal band.

RCIC auto-started and performed as designed.

Drywell pressure is now 0.85 psig up slow.

Drywell floor drain in-leakage is 60 gpm up slow.

INITIATING CUE Determine the applicable 10 CFR 50. 72 reportability requirements, the reason that they apply, and the associated time limitations for reporting under that category. Record your findings on the sheet provided

JPM Answer Sheet for Examinee Use Identify the applicable 10 CFR 50. 72 re portability requirements, the reason that they apply, and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit

EVALUATOR TASK CONDITIONS Both Units were operating at 100 percent power with no equipment out of service.

A primary coolant leak developed in the Unit 1 Drywell.

Operators inserted a manual reactor scram.

All control rods inserted.

Reactor water level reached a low of -32" before recovering to the normal band.

RCIC auto-started and performed as designed.

Drywell pressure is now 0.85 psig up slow.

Drywell floor drain in-leakage is 60 gpm up slow.

INITIATING CUE Determine the applicable 10 CFR 50. 72 reportability requirements, the reason that they apply, and the associated time limitations for reporting under that category. Record your findings on the sheet provided

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

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure NDAP-QA-0720 Rev 26 Procedure NU REG 1022 Rev 3 Procedure EP-RM-004 Rev 4 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.

JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. JPM Answer Sheet exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Respond to Control Rod Drift In During Performance of Rod Exercise Test S/RO 55.0N.1998.151 2 04/28/2015 Simulator Applicability JPM Number Revision Date Setting 201003 A2.03 3.4/3.7 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/28/2015 Richard Bolduc 03/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> {<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

55.0N.1998.151Rev2 04/28/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections Revision required for updating JPM with new Off Normal (ON) procedures.

2 Revised power level to 100% to accommodate JPM pairing.

55.0N.1998.151 Rev 2 04/28/2015 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 (Revision 8)

B. OP-156-001, Reactor Manual Control System (RMCS) (Revision21)

C. ON-CRD-101, Control Rod Malfunction (Revision 0)

D. AR-104-001 (HOS), RPS DIV 2 1C651 (Revision 38)

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

All systems are in service in accordance with their respective OP.

All control rods are operable and have normal withdraw speeds. There are no control rods listed on the Problem Control Rod list.

S0-156-010 has been completed through Step 5.1.

4. INITIATING CUE Perform Monthly Control Rod exercising for all withdrawn control rods, per S0-156-010.

5. TASK STANDARD Operator performs Monthly Control Rod exercising for control rods 02-19 and 02-23 per S0-156-010. Inserts control rod 02-27 to position 00 when control rod drifts in, IAW ON-CRD-101, Condition D

55.0N.1998.151Rev2 04/28/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to any rated-power IC.

2. Run scenario file EVAL550N1998151.SCN aet ETEVAL550N1998151 aet ETEVAL550N1998151A sen exam¥EVAL550N1998151-MP EVAL550N1998151-MP.SCN insmp lssblpos(71) changemp lssblpos(71) , , ,CONTROL ROD 02-27 POS insmp diHSC12S3.CurrValue changemp diHSC12S3.CurrValue, ,bool,SWITCH:DISPLAY RODS DRIFTING insmp diHSC121S08.CurrValue changemp diHSC121S08.CurrValue, ,bool,SWITCH:ROD DRIFT RESET ETEVAL550N1998151.et/scn lssblpos(71) <= 46 IMF mfRD1550040227 f :3 ETEVAL550N 1998151 A et/sen

delete drift lssblpos(71) <= 10 DMF mfRD1550040227 SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

3. Reset the simulator to IC 392.

4. Verify Els and Commands per the above

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 1 of 10 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-392, or configure the simulator per the Simulator Setup Instructions.

Mark-up a copy of S0-156-010 complete through Step 5.1 .

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.

EVALUATOR NOTE Applicant may perform continuous withdraw from position 46.

2 Selects control rod 02-19. Performs the following using OP-156-001, RMCS:

*Selects rod by depressing the 02 and 19 CONTROL ROD SELECTION PBs

Observes 02 and 19 CONTROL ROD SELECTION PBs illuminated

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

Present position of 02-19 INDICATED on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652.

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 2of10 Step Action Standard Eva I Comments

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

*Momentarily Depress INSERT ROD pb until the rod insert light illuminates

ROD INSERT light ILLUMINATES THEN EXTINGUISHES

Insert drive flow of approx. 4-5 gpm during control rod insertion on CRT FOUR ROD DISPLAY

ROD SETLG light ILLUMINATED THEN EXTINGUISHES at end of cycle

Observe at FOUR ROD DISPLAY control rod 02-19 inserts one notch from previous position AND position indicated is an even number.

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

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

ROD INSERT light MOMENTARILY ILLUMINATED

ROD W/DRAWG light ILLUMINATED THEN EXTINGUISHED

Withdrawal drive flow of approx. 2-3 gpm during control rod withdrawal on CRT FOUR ROD DISPLAY

ROD SETLG light ILLUMINATED THEN EXTINGUISHED at end of cycle

Observe at FOUR ROD DISPLAY control rod 02-19 withdraws one notch from previous position AND position indicated is an even number

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 10 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 PPC and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-19 position 48

RECORD Drive Water Flow indication in Rod Withdrawal Stall Flow column Attachment A, Data Form

VERIFY rod remains coupled

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

Observes ROD SETLG light lit, then extinguished

CIRCLE SAT/UNSAT in Rod Coupling Check column Attachment A, Data Form

*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 test button.

VERIFY FULL OUT red indicator ILLUMINATED

OBSERVE control rod 02-19 has returned to position indicated in Rod Position column ATTACHMENT A, Data Sheet

PERFORMANCE CHECKLIST 55.0N.1998.151 Rev 2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 4of10 Step Action Standard Eva I Comments 7 Documents completion of test for control rod Performs the following:

02-19.

RECORD completion of insertion capability check by circling SAT/UNSAT in Operability Check column on Attachment A, Data Form

DOCUMENT completion of specified actions on correct control rod by Initialing in the PERFORMED column on Attachment A, Data Form.

EVALUATOR CUE Initial Verify for control rod 02-19 on Attachment A.

8 Selects control rod 02-23. Performs the following using OP-156-001, RMCS:

*Selects rod by depressing the 02 and 23 CONTROL ROD SELECTION PBs

Observes 02 and 23 CONTROL ROD SELECTION PBs illuminated

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

Present position of 02-23 INDICATED on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652.

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 5of10 Step Action Standard Eva I Comments

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

Momentarily Depress INSERT ROD pb until the rod insert light illuminates

ROD INSERT light ILLUMINATES THEN EXTINGUISHES

Insert drive flow of approx. 4-5 gpm during control rod insertion on CRT FOUR ROD DISPLAY

ROD SETLG light ILLUMINATED THEN EXTINGUISHES at end of cycle

Observe at FOUR ROD DISPLAY control rod 02-23 inserts one notch from previous position AND position indicated is an even number.

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

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

ROD INSERT light MOMENTARILY ILLUMINATED

ROD W/DRAWG light ILLUMINATED THEN EXTINGUISHED

Withdrawal drive flow of approx. 2-3 gpm during control rod withdrawal on CRT FOUR ROD DISPLAY

ROD SETLG light ILLUMINATED THEN EXTINGUISHED at end of cycle

Observe at FOUR ROD DISPLAY control rod 02-23 withdraws one notch from previous position AND position indicated is an even number

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 6of10 Step Action Standard Eva I Comments

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 PPC and SIP 1C652 FOUR ROD DISPLAY indicate control rod 02-23 position 48

RECORD Drive Water Flow indication in Rod Withdrawal Stall Flow column Attachment A, Data Form

VERIFY rod remains coupled

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

Observes ROD SETLG light lit, then extinguished

CIRCLE SAT/UNSAT in Rod Coupling Check column Attachment A, Data Form

*Circles Rod Coupling Check SAT for control rod 02-23 on Attachment A 12 Verifies control rod 02-23 at position 48. Performs the following:

Depresses DISPLAY RODS FULL-IN FULL-OUT test button.

VERIFY FULL OUT red indicator ILLUMINATED

OBSERVE control rod 02-23 has returned to position indicated in Rod Position column ATTACHMENT A, Data Sheet

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 7 of 10 Step Action Standard Eva I Comments 13 Documents completion of test for control rod Performs the following:

02-23.

RECORD completion of insertion capability check by circling SAT/UNSAT in Operability Check column on Attachment A, Data Form

DOCUMENT completion of specified actions on correct control rod by Initialing in the PERFORMED column on Attachment A, Data Form.

EVALUATOR CUE Initial Verify for control rod 02-23 on Attachment A.

14 Selects control rod 02-27. Performs the following using OP-156-001, RMCS:

*Selects rod by depressing the 02 and 27 CONTROL ROD SELECTION PBs

Observes 02 and 27 CONTROL ROD SELECTION PBs illuminated

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

Present position of 02-27 INDICATED on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652.

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 8of10 Step Action Standard Eva I Comments FAULT STATEMENT CONTROL ROD 02-27 WILL DRIFT TO POSITION 10 DURING PERFORMANCE OF THE FOLLOWING STEP BOOTH OPERATOR CUE

Ensure Event Trigger ET550N 1998151 fires when control rod 02-27 is at position 46 to drift the control rod in.

Ensure Event Trigger ET550N 1998151 A fires when control rod 02-27 is at position 10 to delete the drift malfunction.

15 Inserts control rod 02-27. Performs the following:

Momentarily Depress INSERT ROD pb until the rod insert light illuminates

ROD INSERT light ILLUMINATES THEN EXTINGUISHES

Insert drive flow of approx. 4-5 gpm during control rod insertion on CRT FOUR ROD DISPLAY

Observes AR-104-H05 in alarm

Notifies Unit Supervisor control rod 02-27 is drifting in

Observes control rod 02-27 stop at position 10 EVALUATOR CUE Respond per procedure.

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 9of10 Step Action Standard Eva I Comments 16 Identifies ON-CRD-101, Control Rod Malfunction Controlled copy of ON-CRD-101 obtained, is the governing procedure and obtains controlled selects Condition D to perform.

copy.

EVALUATOR CUE Unit Supervisor concurs with entry into ON-CRD-101.

17 Checks for control rod drifts. Performs the following:

Depresses the DISPLAY RODS DFTING PB

Observes FULL CORE DISPLAY for control rod 02-27 illuminated RED

Releases DISPLAY RODS DFTING PB 18 Checks for scram valves open. Performs the following:

Depresses the DISPLAY SCRAM VALVES OPEN PB

Observes FULL CORE DISPLAY for any open scram valves

Releases DISPLAY SCRAM VALVES OPEN PB 19 Determines control rod 02-27 position. SELECT drifted Control Rod to determine position. Control Rod 02-27 is at position 10.

20 Resets control rod drift alarm. Performs the following:

Depresses the ROD DRIFT RESET PB

Observes AR-104-H05 clears 21 Ensures cooling water ~p and flow normal. Performs the following:

Observes FC-C12-1 R600, indicates -63 gpm Cooling Water Flow.

Observes PV-146-F003, indicates< 50 psid Cooling Water delta P.

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee <<LastName>>, <<FirstName>> Page 10of10 Step Action Standard Eva I Comments

22 Inserts control rod to position 00. Performs the following:

*Depress and Hold INSERT ROD pushbutton

Observes ROD INSERT light ILLUMINATES

Observes insert drive flow of approx. 4-5 gpm during control rod insertion on CRT FOUR ROD DISPLAY

Observes changing rod position indicated on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652 for 02-27.

Releases ROD INSERT PB

Observes ROD INSERT light EXTINGUISHES

Observes ROD SETLG light ILLUMINATES THEN EXTINGUISHES at end of insert cycle.

Observe control rod 02-27 position on FOUR ROD DISPLAY at desired notch position 00 AND position indicated is an even number 23 Hydraulically disarms 02-27 HCU. Directs NPO to hydraulically disarm control rod HCU 02-27 per OP-155-001.

EVALUATOR CUE Record JPM stop time:

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

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

EXAM INEE TASK CONDITIONS Unit 1 is at 100% power.

All systems are in service in accordance with their respective OP.

All control rods are operable and have normal withdraw speeds. There are no control rods listed on the Problem Control Rod list.

S0-156-010 has been completed through Step 5.1.

INITIATING CUE Perform Monthly Control Rod exercising for all withdrawn control rods, per S0-156-010.

EVALUATOR TASK CONDITIONS Unit 1 is at 100% power.

All systems are in service in accordance with their respective OP.

All control rods are operable and have normal withdraw speeds. There are no control rods listed on the Problem Control Rod list.

S0-156-01 O has been completed through Step 5.1.

INITIATING CUE Perform Monthly Control Rod exercising for all withdrawn control rods, per S0-156-010.

55.0N.1998.151Rev2 04/28/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure S0-156-010 Rev 8 Procedure OP-156-001 Rev 21

---

Procedure ON-CRD-101 Rev 0 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.

55.0N.1998.151Rev2 04/28/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. S0-156-010 marked-up through step 5.1 exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Quick Recovery of the Condensate System, Respond to a Loss of TBCCW S/RO 44.0P.4652.151 0 06/20/2015 Simulator Applicability JPM Number Revision Date Setting 256000 A2.12 3.1/3.1 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 06/19/2015 Richard Bolduc 06/20/2015 Author Date Instructor Date Review Approval Manu Sivaraman 08/09/2015 Greg van den Berg 06/25/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>} <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

44.0P.4652.151 Rev 0 06/20/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM

44.0P.4652.151Rev0 06/20/2015 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-300, 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-144-001 Attach A, Condensate and Feedwater System (Revision 59)

3. TASK CONDITIONS Unit 1 has scrammed from rated power.

All 4 Condensate Pumps are tripped, but are available for starting.

RPV pressure has been between 700-800 psig for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

4. INITIATING CUE Perform a quick recovery of the condensate system by placing Condensate Pump 'A' in service in accordance with OP-144-001, section 2.22 OR Attachment A

5. TASK STANDARD Condensate Pump 'A' is started and available to inject into the RPV with the Recirc Flow controller in AUTO and pump is tripped within 1 minute of exceeding 265°F for any condensate pump bearing temperature. (May be tripped prior to exceeding 265°F once it is determined that TBCCW flow cannot be restored)

44.0P.4652.151 Rev 0 06/20/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to JPM Specific IC 391. If IC 391 is not available, prepare an IC as follows:

a. Reset the simulator to any low power IC

Scram the reactor and take actions.

Trip all condensate and RFPs

2. Run scenario file LOC27 JPM B.SCN or insert the following expert commands:

{Key[1]} IMF cmfPM02_1P103A

{Key[1]} IMF cmfPM02_1P1038

{Key[2]} IMF cmfTH02_TE10511A5 r:00:05:00 f:286

{Key[2]} IMF cmfTH02_TE10511A4 r:00:05:00 f:289

PERFORMANCE CHECKLIST 44.0P.4652.151 Rev 0 06/20/2015 Examinee <<LastName>>, <<firstName>> 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-391, 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 OP-144-001 and controlled copy of OP-144-001. performs section 2.22 or Attachment A (Hard Card).

EVALUATOR NOTE Operator may choose to use the governing procedure section 2.22 or the procedure Hard Card, Att A.

2 Prevent uncontrolled Condensate injection Ensures the Feedwater injection valves (603A,B,C) are closed and the FW LO Load Demand Signal to LV-10641 controller UC-C32-1 R602 is in Manual with a controller output of 0%.

PERFORMANCE CHECKLIST 44.0P.4652.151 Rev 0 06/20/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments

3 Start Condensate Pump A

Check OPEN HV-10501A, COND PP A Suet.

*Ensure the Condensate Recirc Flow controller FIC-10508 is in MANUAL, with controller output of 30%.

*Depress the Condensate Pump 'A' START pushbutton.

Observe Cond PP A Vent HV-10560A OPENS immediately upon starting Condensate Pump A

Observe COND PP A Dsch HV-10502A STARTS OPENING within five (5) seconds after Condensate Pump A starts.

4 Adjust Condensate Recirc Flow Adjust Condensate Recirc Flow controller FIC-10508 to obtain:

>2,200 gpm of Total Condensate System Flow as indicated on FIC-10508 controller.

<700 psig Condensate Pump Discharge pressure as indicated on FIC-10508 (PT-10514).

5 Check Condensate Pump motor current Ensure Condensate Pump A motor current on Computer Point CPI 10 does not exceed 143 amps (PPC FORMAY CNDPP).

PERFORMANCE CHECKLIST 44.0P.4652.151 Reva 06/20/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action Standard Eva I Comments

6 Place Condensate Recirc flow controller in Auto Place Condensate Recirc Flow controller FIC-10508 in AUTO and ENSURE the controller is maintaining:

>2,200 gpm of Total Condensate System Flow as indicated on FIC-10508 controller.

<700 psig Condensate Pump Discharge Pressure as indicated on FIC-10508 controller (PT-10514)

FAULT STATEMENT BOTH TBCCW PUMPS TRIP RESULTING IN A TOTAL LOSS OF TBCCW FLOW BOOTH OPERATOR CUE When directed, depress KEY 1 to cause a trip of both T8CCW pumps.

7 Review AR-123-01 Reviews AR-123-01 for displayed alarms and enters ON-T8CCW-101 EVALUATOR CUE State "Carry out actions for ON-T8CCW-101" EVALUATOR NOTE Operator will also be acknowledging other alarms on the same panel due the loss of T8CCW .

EVALUATOR NOTE The Operator should enter ON-T8CCW-101 section A from AR-123-01 .

8 Verifies T8CCW pump status

Ensures standby T8CCW pump is NPO will be dispatched to running (it is tripped) check supply breakers.

Checks the T8CCW supply breakers

Verifies no pumps running

Continues to Condition E EVALUATOR CUE When requested to check the T8CCW pump supply breakers, state, "T8CCW pump supply breakers 181160-24 and 181260-51 are closed and thermal overloads are tripped."

PERFORMANCE CHECKLIST 44.0P.4652.151 Rev 0 06/20/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 EVALUATOR NOTE Once the operator is monitoring condensate pump bearing, if desired, direct the booth operator to activate KEY 2 to ramp two bearing temperatures which causes exceeding 265°F within 3 minutes.

BOOTH OPERATOR CUE If directed, depress KEY 2 to cause a trip of both TBCCW pumps to ramp two bearing temperatures which causes exceeding 265°F within 3 minutes.

EVALUATOR CUE Once the operator has observed rising Condensate Pump 'A' temperatures on the PPC, state, "Your responsibility is limited to operation of Condensate Pump 'A' , another operator will monitor Instrument Air, CRD and EHC".

9 Perform ON-RPR-101 N/A 10 Recognizes Critical Condition and action for Recognizes critical condition requires condensate pump bearing temperatures tripping condensate pump if bearing temperature ~ 265°F 11 Monitor Condensate Pump 'A' bearing Monitors PPC Page CNDPP and observes temperatures. Condensate Pump 'A' bearing temperatures are rising.

12 Remove Condensate Pump 'A' from service Secures Condensate Pump 'A' by depressing the stop pushbutton within 1 minute of exceeding 265°F for any condensate pump bearing temperature.

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?

EXAM INEE TASK CONDITIONS Unit 1 has scrammed from rated power.

All 3 Reactor Feed Pumps have tripped.

RPV pressure has been between 700-800 psig for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

INITIATING CUE Perform a quick recovery of the condensate system by placing Condensate Pump 'A' in service in accordance with OP-144-001, section 2.22 OR Attachment A

EVALUATOR TASK CONDITIONS Unit 1 has scrammed from rated power.

All 3 Reactor Feed Pumps have tripped.

RPV pressure has been between 700-800 psig for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

INITIATING CUE Perform a quick recovery of the condensate system by placing Condensate Pump 'A' in service in accordance with OP-144-001, section 2.22 OR Attachment A

44.0P.4652.151Rev0 06/20/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure OP-144-001 Rev 59 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.

44.0P.4652.151 Rev 0 06/20/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Evaluator cue sheet cue loose

3. JPM jpm loose

4. OP-144-001 (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Quarterly Turbine Valve Cycling S/RO 93.S0.2467.101 0 04/23/2015 Simulator Applicability JPM Number Revision Date Setting 241000 A4.08 3.5/3.4 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/23/2015 Richard Bolduc 03/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> {<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

93.S0.2467.101 Rev 0 04/23/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM

93.S0.2467.101 Rev 0 04/23/2015 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. S0-193-001, Quarterly Turbine Valve Cycling (Revision 40)

B. AR-105-001 (F05) (Revision 53)

C. AR-104-001 (E01) (Revision 38)

3. TASK CONDITIONS Quarterly turbine testing is in progress per S0-193-001. The test is complete through Step 5.3.

A separate PCO has been briefed and will be monitoring turbine vibrations throughout the test.

Reactor Engineering has evaluated the current power level; ops will not violate any core thermal limits while performing this test.

4. INITIATING CUE Continue with quarterly turbine valve cycling per S0-193-001, continuing at Step 5.4.

5. TASK STANDARD Completes quarterly turbine valve cycling for CV-4 per S0-193-001.

93.S0.2467.101 Rev 0 04/23/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the Simulator to an IC at 63% power or less with the turbine on line.

A Run scenario file JPM C.scn or insert the following expert commands:

{Key[2]} IRF rfTU193004 f:BYPASS IRF rfRP158039 f:BYPASS IRF rfRP158040 f:BYPASS IRF rfRP158041 f:BYPASS IRF rfRP158042 f:BYPASS

2. Ensure MAXIMUM COMBINED FLOW LIMIT vernier set at 12.5 turns (125%)

3. Ensure LOAD LIMIT SET vernier set at 8.9 turns.

4. Setup RTIME screens for Turbine Testing.

5. Provide marked up copy of S0-193-00 completed through step 5.3 SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

1. Reset the simulator to IC 390.

2. Verify ETs and Commands per the above

PERFORMANCE CHECKLIST 93.S0.2467.101Rev0 04/23/2015 Examinee <<LastName>>, <<FirstName>> 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 S0-193-001 complete through Step 5.3 .

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 S0-193-001, and controlled copy. starts at section 5.4.

2 Ensure Reactor power established for surveillance. References Core Reactivity Control Book and determine reactor power is within the allowed window for performing the surveillance.

3 Record reactor power level Records reactor power level 4 Ensure MAXIMUM COMBINED FLOW LIMIT Perform the following:

vernier set at 12.5 turns (125%)

Ensure MAXIMUM COMBINED FLOW LIMIT vernier set at 12.5 turns (125%)

Record value of LOAD SET

Record value of LOAD LIMIT SET vernier EVALUATOR NOTE LOAD LIMIT SET should be verified to 8.9 turns, as this was already performed earlier in the procedure, but will adjust LOAD SET to maximum value as specified in the standard, which meets the intent of the critical step.

EVALUATOR NOTE The following step is not critical if the test is performed at power levels <85%.

PERFORMANCE CHECKLIST 93.S0.2467.101Rev0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments

5 Raise LOAD SET to maximum value (1400 MW) Perform the following:

Verifies LOAD LIMIT SET vernier to 8.9 TURNS

Raise LOAD SET to maximum value (1400 MW) to allow Control Valves to cycle open and limit BYPASS VALVE opening 6 Bypass Main Turbine vibration trips Perform the following:

Dispatches NPO to Panel 1C61 OOA, Place HS-11982 to BYPASS

Confirm Annunciator AR105, F05 MAIN TURB VIB OR RFPT VIB/THRUST TRIP BYPASS ALARMS BOOTH OPERATOR CUE When requested, bypass turbine vibration trips by depressing Key 2.

{Key[2]} IRF rfTU193004 f:BYPASS EVALUATOR CUE Turbine vibration trips are bypassed.

EVALUATOR NOTE IF any bearing on the Main Turbine exceeds 10 mils, the Test Pushbutton should be released immediately.

Candidate may request Attachments B and/or D while performing this portion of the surveillance.

7 Observe PPC points during valve testing N/A; to be performed by another operator 8 IF the "1XAMPL" value for Bearing 1X, 1Y, 2X or 2Y N/A; to be performed by another operator exceed 6.0 mils during the CV testing portion of the surveillance, THEN contact System Engineering

9 Direct l&C to install RPS Test Box at 1C611 Relay

RPS Test Box installed and continuity C72A-K8D IAW att. D part 2 and perform Att B checked.

Step1 EVALUATOR CUE l&C reports test box installed and continuity reading indicates CVTS is OPEN

PERFORMANCE CHECKLIST 93.S0.2467.101Rev0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action Standard Eva I Comments EVALUATOR NOTE If asked, an NPO is stationed to monitor EHC pump amps.

10 Determines/Records CV-4 pretest position. Records current CV-4 position

11 Test Control Valve 4 by depressing and holding the Observe the following:

CV-4 TEST pushbutton.

Confirm CV-4 slow closes then fast closes for the final 10% of travel

Observes annunciator AR104 E01 TURB CV FAST CLOSURE TRIP Alarms

12 Release CV-4 TEST pushbutton Observe the following:

Confirms CV-4 returns to pretest position as indicated at CONTROL VLV-4 POSITION indicator

!E half scram condition occurred, Reset half scram condition by placing HS-C72A-1S05 to GRP 1/4, then GRP 2/3; else NA

Confirm annunciator AR104, E01 TURB CV FAST CLOSURE TRIP CLEARS

At 1C601, Confirm four (4) MSIV STATUS LOGIC A through D lights ILLUMINATED 13 Direct l&C to remove RPS Test Box at 1C611

RPS Test Box removed Relay C72A-K8D IAW att. D part 2.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

PERFORMANCE CHECKLIST 93.S0.2467.101Rev0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 Step I Action I Standard I Eval I Comments EVALUATOR:

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

EXAM I NEE TASK CONDITIONS Quarterly turbine testing is in progress per S0-193-001. The test is complete through Step 5.3.

A separate PCO has been briefed and will be monitoring turbine vibrations throughout the test.

Reactor Engineering has evaluated the current power level; ops will not violate any core thermal limits while performing this test.

INITIATING CUE Continue with quarterly turbine valve cycling per S0-193-001, continuing at Step 5.4.

EVALUATOR TASK CONDITIONS Quarterly turbine testing is in progress per S0-193-001. The test is complete through Step 5.3.

A separate PCO has been briefed and will be monitoring turbine vibrations throughout the test.

Reactor Engineering has evaluated the current power level; ops will not violate any core thermal limits while performing this test.

INITIATING CUE Continue with quarterly turbine valve cycling per S0-193-001, continuing at Step 5.4.

93.S0.2467.101 Rev 0 04/23/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure S0-193-001 Rev 40 Procedure AR-105-001 Rev 53 Procedure AR-104-001 Rev 38 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.

93.S0.2467.101 Rev 0 04/23/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. S0-193-001 (marked-up through step 5.3) exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Core Spray System Shutdown S/RO 51.0P.1933.101 1 04/23/2015 Simulator Applicability JPM Number Revision Date Setting 209001 A4.03 3.7/3.6 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/20/2015 Richard Bolduc 03/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 15 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>} <<Employee>>

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

Evaluation Result: D Satisfactory 0 Unsatisfactory Evaluator Name Signature Comments

51.0P.1933.101Rev1 04/23/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedure JPM format.

51.0P.1933.101Rev1 04/23/2015 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 The plant is operating at 100% power Core Spray Loop B has spuriously initiated The cause of the spurious initiation has been found and corrected Misoperation in AUTOMATIC MODE has been confirmed by at least two (2) independent indications Adequate core cooling is assured by at least two (2) independent indications Switch Collar Core Spray Loop B MAN INIT HS-E211S16B is NOT ARMED

4. INITIATING CUE The Unit Supervisor has directed you to shutdown 'B' Core Spray Loop in accordance with OP-151-001, section 2.4.

5. TASK STANDARD Core Spray system shutdown IAW OP-151-001

51.0P.1933.101Rev1 04/23/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to any full power IC.

2. Initiate Core Spray loop 8. Place the Manual Initiation Pushbutton collar back to disarm once Core Spray 8 has been initiated.

SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

3. Reset the simulator to IC 392.

4. Verify conditions above.

PERFORMANCE CHECKLIST 51.0P.1933.101Rev1 04/23/2015 Examinee <<LastName>>, <<FirstName>> 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-392, 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 Identifies OP-151-001 is the governing procedure. Obtains copy of OP-151-001, selects section 2.4.

2 If Switch collar was placed in ARMED, place the Collar not in ARMED per cue sheet switch collar in the NOT ARMED position.

2 Resets Core Spray 8 Initiation signal Applicant:

a. Depresses CORE SPRAY LOOP 8 INIT SIG RESET HS-E211S178

b. Observe Core Spray Loop 8 INIT SIG RESET HS-E211 S178 Green Initiation light EXTINGUISHES.

EVALUATOR NOTE Roleplay as Unit Supervisor and acknowledge applicant request to enter TRO 3.8.2.1 3 Enter TRO 3.8.2.1 Applicant notifies Unit Supervisor of need to enter TRO 3.8.2.1

4 Place CORE SPRAY LOOP 8 MOV OL 8YPS HS- Applicant acquires key from below bench E211S128 to TEST position board, inserts key and turns CORE SPRAY LOOP 8 MOV OL 8YPS HS-E211 S128 to TEST position

PERFORMANCE CHECKLIST 51.0P.1933.101 Rev 1 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments EVALUATOR NOTE CORE SPRAY LOOP BOUT OF SERVICE (AR-113-001 802) and CORE SPRAY LOOP B MOV'S IN TEST (BIS) are expected alarms EVALUATOR NOTE Inboard injection valve will be closed due to spurious initiation and low pressure valve permissive signal not active 5 Close Core Spray Loop B injection valve Close CORE SPRAY LOOP B 18 INJ SHUTOFF HV-152F005B.

EVALUATOR NOTE Min flow valve will already be open due to spurious initiation 6 Observes Core Spray Loop B minimum flow When flow is <635 gpm, Observe CORE SPRAY LOOP B MIN FLOW HV-152F031B OPENS.

7 Place LO RX PRESS PERM Switch HS-152498 to Verifies LO RX PRESS PERM Switch HS-NORM 152498 in NORM position

8 Stop CORE SPRAY PUMP 1P206B Turns CORE SPRAY PUMP 1P206B control switch to STOP and returns to AUTO.

9 Stop CORE SPRAY PUMP 1P206D Applicant turns CORE SPRAY PUMP 1P206D control switch to STOP and returns to AUTO

PERFORMANCE CHECKLIST 51.0P.1933.101Rev1 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action Standard Eva I Comments 10 Observes following indications: Observes following indications as applicable:

a. CORE SPRAY LOOP BIB INJ SHUTOFF HV-152F005B indicates CLOSED and whiter light EXTINGUISHED

b. CORE SPRAY LOOP B ACTUATED alarm CLEARED.

c. Core Spray Room Unit Coolers 1V211 B and D STOP indicated on Heating and Ventilation Panel 1C681.

EVALUATOR NOTE SteQs 2.4.13 and 2.4.14 are NIA. Not being aligned to the CST or SuQQression Pool.

2.4.13; If Core Spray suction is being aligned to the CST, Return to "Alignment and Operation of Core Spray System for Taking Suction From CST' section. N/A

If Core Spray suction is being aligned to the Suppression Pool, Return to" Re-alignment of Core Spray System From Taking Suction From CST' section. N/A

11 Place CORE SPRAY LOOP B MOV OL BYPS HS- After 2 minutes, Place CORE SPRAY LOOP E211S128 to NORM position B MOV OL BYPS HS-E211S12B to NORM position.

12 Clear TRO 3.8.2.1 Applicant notifies Unit Supervisor of need to enter TRO 3.8.2.1 EVALUATOR NOTE Roleplay as Unit Supervisor and acknowledge applicant request to clear TRO 3.8.2.1

PERFORMANCE CHECKLIST 51.0P.1933.101 Rev 1 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 Step Action Standard Eva I Comments 13 Observe following indications: Observe following indications:

a. CORE SPRAY LOOP B OUT OF SERVICE alarm CLEARS

b. CORE SPRAY LOOP B MOV'S IN TEST status light EXTINGUISHED

c. No CORE SPRAY STATUS DIV 2 status indication lights ILLUMINATED 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?

EXAM INEE TASK CONDITIONS The plant is operating at 100% power Core Spray Loop B has spuriously initiated The cause of the spurious initiation has been found and corrected Misoperation in AUTOMATIC MODE has been confirmed by at least two (2) independent indications Adequate core cooling is assured by at least two (2) independent indications Switch Collar Core Spray Loop B MAN INIT HS-E211S16B is NOT ARMED INITIATING CUE The Unit Supervisor has directed you to shutdown 'B' Core Spray Loop in accordance with OP-151-001, section 2.4.

EVALUATOR TASK CONDITIONS The plant is operating at 100% power Core Spray Loop B has spuriously initiated The cause of the spurious initiation has been found and corrected Misoperation in AUTOMATIC MODE has been confirmed by at least two (2) independent indications Adequate core cooling is assured by at least two (2) independent indications Switch Collar Core Spray Loop B MAN INIT HS-E211 S16B is NOT ARMED INITIATING CUE The Unit Supervisor has directed you to shutdown 'B' Core Spray Loop in accordance with OP-151-001, section 2.4.

51.0P.1933.101 Rev 1 04/23/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure OP-151-001 Rev 36 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.

51.0P.1933.101 Rev 1 04/23/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Evaluator cue sheet cue loose

3. JPM jpm loose

4. OP-151-001 (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Shutdown Cooling Temperature Control S/RO 49.0N.1869.151 3 04/23/2015 Simulator Applicability JPM Number Revision Date Setting 223002 K1.08 3.4/3.5 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/23/2015 Richard Bolduc 03/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

49.0N.1869.151 Rev 3 04/23/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM Revise for TQ procedures and conversion of NRC JPM template to SSES JPM 1

template 2 Revise for OP/ON revisions Revised to incorporate the new Off Normal (ON) procedures. Updated Simulator 3

set-up page with new IC number and .sen file, Incorporated validation comments.

49.0N.1869.151Rev3 04/23/2015 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-149-002, RHR Shutdown Cooling (Revision 67)

B. ON-SDC-101, Loss of Shutdown Cooling (Revision 1)

C. AOP-149-001, RHR Abnormal Operating Procedure (Revision 0)

3. TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.

Reactor coolant temperature is 170 °F.

Time to 200 °F is approximately 45 minutes.

No core alterations are in progress Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.

TRO 3.8.2.1 has been entered for SOC temperature control.

An operator has been assigned to perform a S0-100-011 during the cooldown.

4. INITIATING CUE Lower reactor coolant temperature to 140°F in accordance with OP-149-002, Attachment E, step 6.

5. TASK STANDARD Manipulate RHR to lower reactor coolant temperature. Restore SOC following a SOC isolation.

49.0N.1869.151Rev3 04/23/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to JPM Specific IC 388. If IC 388 is not available, prepare an IC as follows:

a. Reset the simulator to IC 272 'B' Loop of RHR in Shutdown Cooling

Place the simulator in RUN.

Open RHR F048B

Adjust RHR flow to 10,000 gpm and RHRSW flow to 9000 gpm.

b. Run scenario file LOC27 JPM E SETUP.SCN to lower ESW temperature. The scenario will take 5 min to complete.

00:00:00 IRF rfEN009002 f :45 00:00:01 IRF rfEN100005 f :45 00:00:02 set ypxfstctwbasin=100 00:00:03 set ypxfsttsprpond=100 00:05:02 set ypxfstctwbasin=1 00:05:03 set ypxfsttsprpond=1

c. Run scenario file LOC27 JPM E.SCN

{Key[1]} IMF cmfMV05_HV151F009 c:20

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 04/23/2015 Examinee <<LastName>>, <<FirstName>> 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 Identifies governing procedure and obtain Obtains controlled copy of OP-149-002 controlled copy. Att. E, SOC Temperature Control.

2 Ensure TRO 3.8.2.1 is entered. Confirms TRO 3.8.2.1 is entered per initial conditions 3 Places HS-E11-1S628 RHR LOOP B MOV OL Place keyswitch to TEST BYPS keyswitch to TEST EVALUATOR NOTE Due to RHR conditions (F0038 and F0478 open and RHRSW and RHR at maximum flow), the only option for lowering temperature is to throttle closed F0488)

4 Operates RHR B to lower reactor coolant Throttle Closed on HV-151-F0488 RHR HX temperature B SHELL SIDE BYPS EVALUATOR NOTE Candidate may not place HS-E11-1S628 RHR Loop B MOV OL BYP keyswitch to normal with temperature at 140F.

5 AFTER 2 minutes, Place HS-E 11-1 S628 RHR AFTER 2 minutes, place keyswitch to LOOP B MOV OL BYPS keyswitch to NORM NORM

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 5 Step Action Standard Eva I Comments FAULT STATEMENT HV-151-F009, SOC SUCTION 18 ISOLATION VALVE SPURIOUS CLOSURE OCCURS WHILE LOWERING REACTOR COOLANT TEMPERATURE BOOTH OPERATOR CUE After reactor coolant temperature begins to lower (indicated by RHR HX Inlet temperature) or when directed by the evaluator, depress Key 1 to initiate spurious isolation of F009 and cause a loss of SOC.

EVALUATOR NOTE Examinee will investigate isolation of HV-151-F009 6 Enters and obtains a copy of ON-SOC-101 for Enters ON-SOC-101 based on isolation of Loss of Shutdown Cooling for automatic isolation HV-151-F009 and loss of SOC flow.

of HV-151-F009.

EVALUATOR CUE If the applicant does not recognize to enter ON-SOC-101, ask, "What procedure will the SRO direct you to enter in this condition?" Then direct Entry for ON-SOC-101.

EVALUATOR CUE Once the examinee has determined that HV-151-F009 is closed, provide report as the US that "Electrical maintenance has determined that F009 experienced a spurious closure. The cause of the spurious closure has been found and corrected." If the examinee does not recognize that a quick recovery can be performed due to the F009 being closed, as the US direct the examinee to "Restore shutdown cooling in accordance with AOP-149-001 Attachment A."

7 Determines cause for the loss of RHR was due to Recognizes that Condition B of ON-SOC-spurious isolation of HV-151-F009. 101 is applicable to restore RHR LOOP B to shutdown cooling.

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 5 Step Action Standard Eva I Comments EVALUATOR NOTE Resetting PCIS and SOC is not critical for this JPM since isolation logic was not actuated 8 IF in Mode 4 AND RHR aligned PER OP 149 002 Attachment E is being performed by another (OPERATION OF SOC IN MODE 4 OR 5 section), operator THEN PERFORM Attachment E while continuing with the remaining Actions 9 Perform S0-100-011 S0-100-011 is being performed by another operator.

10 IF in Mode 4, THEN DETERMINE estimated time Attachment B is being performed by another to 200°F PER Attachment B. operator 11 ESTABLISH reactor coolant circulation using N/A ONE of the following alternate methods:

MAINTAIN water level ~ 45 inches. [C 2]

ENSURE Reactor Recirculation System in service. (OP 164 001) 12 IF SOC was lost due to Loss of RPS, N/A THEN PERFORM the following:

13 RESTORE a RHR Pump in the previously IF conditions permit restoring a RHR Pump in-service loop of RHR to SOC in the previously in-service loop of RHR to SOC, THEN PERFORM Quick Recovery of Previously lnservice Shutdown Cooling Loop. (AOP-149-001) 14 Enter LCO Unit Supervisor Enters LCO 15 Perform AOP-149-001, Attachment A Selects AOP-149-001, RHR Abnormal Operating Procedure, Attachment A for Quick Recovery of Previously In-service Shutdown Cooling Loop.

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 5 Step Action Standard Eva I Comments 16 Reset PCIS isolation logic Performs the following

Depress HS-B21-1S32 MN STM LINE DIV 1 ISO RESET.

Depress HS-B21-1S33 MN STM LINE DIV 2 ISO RESET.

17 Reset SOC isolation logic

Depress HS-E11-1S32A RHR LOOP A SHUTDOWN CLG RESET.

Depress HS-E11-1S32B RHR LOOP B SHUTDOWN CLG RESET.

18 Place MOV controls in TEST

Place HS-E11-1S62B, RHR LOOP B MOVS OL BYPS in TEST.

Place HS-B21-1S37A, AC MOV OL BYPS in TEST.

Place HS-B21-1S37B, DC MOV OL BYPS in TEST.

19 Verify valve alignment prepared for SOC

Ensure CLOSED HV-151-F015B .

restoration.

Ensure CLOSED HV-151-F049 RW OB Isolation.

Ensure CLOSED HV-151-F040 RW IB Isolation.

Ensure CLOSED HV-151-F007B RHR PUMPS B&D DISCHARGE MIN FLOW VLV TO SUPP POOL.

20 Determines that loop voiding is not suspected Marks step 7 N/A

21 Opens shutdown cooling suction isolation valve

Ensure Open HV-151-F008 OPEN F009. SHUTDOWN CLG SUCT OB ISO.

Ensure Open HV-151-F009 SHUTDOWN CLG SUCT IB ISO.

22 Lines up RHR injection valves for pump start.

Close HV-151-F017B RHR INJ FLOW CTL.

Open HV-151-F015B RHR INJ OB ISO .

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 5 of 5 Step Action Standard Eva I Comments

23 Starts an RHR pump Starts RHR PUMP 1P2028 or D.

24 Establishes approximately 5000 GPM of RHR Throttle OPEN HV-151-F0178 RHR INJ flow. FLOW CTL to promptly establish flow approximately 5,000 gpm.

EVALUATOR NOTE Candidate may choose not to perform the next step to allow for operation of valves for restoring cooling.

HV-151-F0078 was previously closed for the SOC lineup. The breaker for the valve is open.

25 Place MOV controls in NORM

Place HS E11 1S628, RHR LOOP 8 MOVS OL 8YPS in NORM.

Place HS 821 1S37A, AC MOV OL 8YPS in NORM.

Place HS 821 1S378, DC MOV OL 8YPS in NORM.

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?

EXAMINEE TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.

Reactor coolant temperature is 170 °F.

Time to 200 °F is approximately 45 minutes.

No core alterations are in progress Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.

TRO 3.8.2.1 has been entered for SOC temperature control.

An operator has been assigned to perform a S0-100-011 during the cooldown.

INITIATING CUE Lower reactor coolant temperature to 140°F in accordance with OP-149-002, Attachment E, step 6.

EVALUATOR TASK CONDITIONS Unit 1 is in MODE 4, 2 days into an outage.

Reactor coolant temperature is 170 °F.

Time to 200 °F is approximately 45 minutes.

No core alterations are in progress Section 2.22 (Operation of SOC in Mode 4 or 5) of OP-149-002 has NOT been performed.

TRO 3.8.2.1 has been entered for SOC temperature control.

An operator has been assigned to perform a S0-100-011 during the cooldown.

INITIATING CUE Lower reactor coolant temperature to 140°F in accordance with OP-149-002, Attachment E, step 6.

49.0N.1869.151Rev3 04/23/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure ON-SDC-101 Rev 1 Procedure OP-149-002 Rev 67 Procedure AOP-149-001 Rev 0 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.

49.0N.1869.151Rev3 04/23/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. OP-149-002 Attachment E exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

5. ON-SDC-101 (replacement) sim PC

6. AOP-149-001 (replacement) sim PC

SUSQUEHANNA NUCLEAR LLC I JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Swap RBCCW Pumps, Respond to a Loss of RBCCW S/RO 14.0P.1335.150 0 04/23/2015 Simulator Applicability JPM Number Revision Date Setting 295018 AK3.03 3.1/3.3 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/23/2015 Richard Bolduc 03/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> {<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

14.0P.1335.150 Rev 0 04/23/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM

14.0P.1335.150 Rev 0 04/23/2015 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-114-001, Reactor Building Closed Cooling Water System (Revision 24)

B. ON-RBCCW-101, Loss of Reactor Building Closed Cooling Water (Revision 0)

3. TASK CONDITIONS Unit 1 has Scrammed RBCCW Pump 1A is in service.

RBCCW Pump 1B is in standby.

The NPO has reported that the RBCCW Pump 1A is exhibiting signs of high vibrations

4. INITIATING CUE Place RBCCW Pump 1Bin service and secure RBCCW Pump 1A due to high vibrations.

In accordance with OP-114-001, section 2.2.

5. TASK STANDARD Unit 1 RBCCW Pump 1B will be placed in service. Following a loss of RBCCW, both Reactor Recirc Pumps will be manually tripped due to rising temperatures.

14.0P.1335.150 Rev O 04/23/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to JPM Specific IC 389. If IC 389 is not available, prepare an IC as follows:

a. Reset the simulator to any low power IC

Scram the reactor and take actions.

Ensure both recirc pumps are running

2. Run scenario file LOC27 JPM F.SCN or insert the following expert commands:

insmp rwvp113062 changemp rwvp113062 ,,,RBCCW PP A DISCH VLV POS insmp rwvp113068 changemp rwvp113068 ,,,RBCCW PPB DISCH VLV POS insmp rwpi11306a changemp rwpi11306a ,,,RBCCW PP 1A DSCH PR insmp rwpi11306b changemp rwpi11306b ,,,RBCCW PP 18 DSCH PR

{Key[1]} IRF rfRW114001 r:30 f:O

{Key[3]} IRF rfRW114001 r:30 f:100

{Key[3]} IMF cmfPM02_1P21 OB d:45

{Key[3]} IMF cmfTH02_TE14357A1A2 d:45 r:10:00 f:290

{Key[3]} IMF cmfTH02_TE143578182 d:45 r:10:00 f:290Ensure the following aet ET140P IMF cmfPM04_1P210A

PERFORMANCE CHECKLIST 14.0P.1335.150 Rev 0 04/23/2015 Examinee <<LastName>>, <<firstName>> 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-389, 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-114-001 Section 2.2 is Controlled copy of OP-114-001 obtained, select Section governing procedure and obtains 2.2.

controlled copy.

2 Starts RBCCW Pump 1B. Depress RBCCW PUMP 1P210B START push button.

3 Verifies RBCCW Pump 1B discharge Direct NPO to verify RBCCW Pump 1B discharge pressure 90-110 psig. pressure between 90-110 psig on local pressure gage Pl-113068.

EVALUATOR CUE Pump discharge pressure is 95 psig, steady.

4 Closes RBCCW Pump 1A discharge Direct NPO to slowly close RBCCW Pump 1A Dsch valve. 113062.

BOOTH OPERATOR CUE When directed, depress KEY 1 to close RBCCW Pump 1A discharge valve 113062. Notify evaluator when 113062 is fully closed.

EVALUATOR CUE When 113062 is reported closed by Booth Operator, notify candidate that Pump discharge valve is closed.

PERFORMANCE CHECKLIST 14.0P.1335.150 Rev 0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments

5 Stops RBCCW Pump 1A. Depress RBCCW PUMP 1P21 OA STOP push button.

6 Opens RBCCW Pump 1A discharge Direct NPO to slowly open RBCCW Pump 1A Dsch valve. 113062.

BOOTH OPERATOR CUE When directed, depress KEY 3 to open RBCCW Pump 1A discharge valve 113062 and initiate the fault.

Notify evaluator promptly after 113062 is fully open.

EVALUATOR CUE When 113062 is reported open by Booth Operator, promptly notify candidate that Pump discharge valve is open.

EVALUATOR NOTE Shortly after report of RBCCW Pump 1A discharge valve 113062 open, B pump will trip initiating the below described fault.

PERFORMANCE CHECKLIST 14.0P.1335.150 Rev 0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action I Standard I Eval Comments FAULT STATEMENT THE ALTERNATE PUMP (18) TRIPS AND PUMP 1A DOES NOT AUTO START-AFTER MANUALLY STARTING, PUMP 1A TRIPS.

6 Identifies trip of the running 1B Pump and failure of auto start of Responds to 1B Pump trip and identifies the 1A alternate pump. 1A alternate pump fails to auto start.

7 Starts RBCCW Pump 1A Depress RBCCW PUMP 1P210A START push button.

8 Identifies loss of RBCCW Flow Enters ON-RBCCW-101, Loss of RBCCW Condition A.

9 Ensure standby RBCCW pump is running N/A 10 Monitor Reactor Recirc Pump temperatures Monitor Reactor Recirc Pump Motor Bearing and Seal Cavity Temperatures on TRSH-B31-1 R601.

BACK PANEL - Recirc Tern~ Recorder 11 IF RBCCW Pump has tripped, then check tripped RBCCW Pump NIA breakers

1B216103

1B237093 12 Monitors Rx Recirc Pump Motor Bearing Temps Monitors Rx Recirc Pump Motor Bearing temperature(s) ~ 195°F OR Seal Cavity temperatures ~ 200°F

13 Trips both Rx Recirc Pumps TRIP BOTH Rx Recirc Pumps when Rx Recirc Pump Motor Bearing temperature(s) ~ 195°F OR Seal Cavity temperatures ~ 200°F EVALUATOR CUE Record JPM stop time:

PERFORMANCE CHECKLIST 14.0P.1335.150 Rev 0 04/23/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 Step I Action I Standard I Eval I 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?

EXAM INEE TASK CONDITIONS Unit 1 has Scrammed RBCCW Pump 1A is in service.

RBCCW Pump 1B is in standby.

The NPO has reported that the RBCCW Pump 1A is exhibiting signs of high vibrations INITIATING CUE Place RBCCW Pump 1Bin service and secure RBCCW Pump 1A due to high vibrations.

In accordance with OP-114-001, section 2.2.

EVALUATOR TASK CONDITIONS Unit 1 has Scrammed RBCCW Pump 1A is in service.

RBCCW Pump 1B is in standby.

The NPO has reported that the RBCCW Pump 1A is exhibiting signs of high vibrations INITIATING CUE Place RBCCW Pump 1Bin service and secure RBCCW Pump 1A due to high vibrations.

In accordance with OP-114-001, section 2.2.

14.0P.1335.150 Rev 0 04/23/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure OP-114-001 Rev 24 Procedure ON-RBCCW-101 Rev 0 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.

14.0P.1335.150 Rev 0 04/23/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Evaluator cue sheet cue loose

3. JPM jpm loose

4. ON-RBCCW-101 (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Restore Offgas System IAW ON-143-001 S/RO 72.0N.1786.151 0 01/08/2015 Simulator Applicability JPM Number Revision Date Setting 271000 A2.11 2.8/2.9 y N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/12/02015 Richard Bolduc 05/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 15 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

72.0N.1786.151 Rev 0 01/08/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM

72.0N.1786.151Rev0 01/08/2015 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 40)

B. OP-172-001, SJAE and OFFGAS System (Revision 68)

3. TASK CONDITIONS Unit 1 is operating in Mode 1 at approximately 62% power.

Steam Seal Evaporator is out of service Auxiliary Steam is supplying the Steam Seals Main Steam was supplying the SJAE when a spurious closure of HV-10721 occurred, causing an ARESD ON-143-001 has been entered The cause of the spurious isolation of HV-10721 has been corrected and the ARESD signal is clear.

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

72.0N.1786.151Rev0 01/08/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset the simulator to IC 13.

2. Ensure both Aux Boilers are in service

3. Swap steam seals from Main Steam to Aux Steam IAW OP-192-001

4. Insert the following expert commands; IMF cmfAV04_PV10701A f:O IMF cmfAV04_PV107018 f:4.0 IMF cmfAV04_PV10752 f:O

{Key[1]} IMF cmfAV04_PV10752 c:61 r:60 i:O f:42

5. Close HV-10721, SJAE Discharge Isolation SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

6. Reset the simulator to IC 390.

7. Verify ETs and Commands per the above

PERFORMANCE CHECKLIST 72.0N.1786.151Rev0 01/08/2015 Examinee <<LastName>>, <<FirstName>> 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 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 ON-143-001 is the governing procedure Obtains controlled copy of ON-143-001, and obtains controlled copy. selects step 3.6.7.

PERFORMANCE CHECKLIST 72.0N.1786.151Rev0 01/08/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 4 Step Action Standard Eva I Comments 2* IF 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.

FAULT STATEMENT STEAM PRESSURE WILL BE <110 PSIG ON Pl-10701, SJAE STM SUP PRESS 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 If asked, as the US direct the candidate to transfer steam supply to the alternate source

PERFORMANCE CHECKLIST 72.0N.1786.151Rev0 01/08/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 4 Step Action Standard Eva I Comments EVALUATOR NOTE Prerequisites of section 2. 7 are satisfied.

EVALUATOR CUE If asked by candidate, as Unit Supervisor, inform candidate that prerequisites are satisfied.

5 Identifies OP-172-001 is the governing procedure Obtains controlled copy of OP-172-001, and obtains controlled copy. selects step 2. 7 to transfer SJAE/Recombiner Steam Supply From Main to Aux.

6 Verifies Aux Steam Header Pressure At Panel OC653, Check greater than 200 psig on Pl 02118 Aux Boiler Header Press 7 IF steam seals are NOT being supplied by Aux N/A Boiler, THEN at Area 05 699', Throttle Open 121008 Su Stm Viv To SJAE and Sealing Stm to allow warm up of Aux Steam Line 8 IF steam seals are NOT being supplied by Aux N/A Boiler, THEN at Area 01 699' CDSR, Open 107077 Aux Stm Supply to SJAE ISO 9 Ensures Main Steam Supply Isolations are closed

Ensure HV-10701A SJAE Mn Stm Sup lso CLOSED

Ensure HV-10701 B SJAE Mn Stm Sup lso CLOSED 10 Observe the following CLOSED (due to low dilution

HV 10716 SJAE Suet lso steam flow)

HV 10717 SJAE Suet lso

HV 10718 SJAE Suet lso

HV 10719 SJAE Suet lso 11* Isolates Main Steam to the SJAE Close HV-10107 Mn Stm SJAE lso

PERFORMANCE CHECKLIST 72.0N.1786.151Rev0 01/08/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 4 12 Lineup Aux Steam to SJAE Open HV-10752 SJAE Aux Stm Sup lso

13 Open Aux Stm Supply to SJAE ISO. Dispatches NPO to Area 01-699' CDSR to SLOWLY Open 107077 Aux Stm Supply to SJAE ISO.

BOOTH OPERATOR CUE When NPO is dispatched to SLOWLY OPEN 107077 Aux Stm Supply to SJAE lso, INSERT KEY 1 14 Verify steam supply pressure Check steam supply pressure at 110 - 130 psig on Pl-10701 SJAE Stm Sup Press

15 Open SJAE suction isolation valves Open HV-10716, HV-10717, HV-10718 and HV-10719 SJAE Suet lso by depressing HS-10716 OPEN Pushbutton 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?

EXAM INEE TASK CONDITIONS Unit 1 is operating in Mode 1 at approximately 62% power.

Steam Seal Evaporator is out of service Auxiliary Steam is supplying the Steam Seals Main Steam was supplying the SJAE when a spurious closure of HV-10721 occurred, causing an ARESD ON-143-001 has been entered The cause of the spurious isolation of HV-10721 has been corrected and the ARESD signal is clear.

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

EVALUATOR TASK CONDITIONS Unit 1 is operating in Mode 1 at approximately 62% power.

Steam Seal Evaporator is out of service Auxiliary Steam is supplying the Steam Seals Main Steam was supplying the SJAE when a spurious closure of HV-10721 occurred, causing an ARESD ON-143-001 has been entered The cause of the spurious isolation of HV-10721 has been corrected and the ARESD signal is clear.

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

72.0N.1786.151 Rev 0 01/08/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure ON-143-001 Rev 40 Procedure OP-172-001 Rev 68 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.

Operator comments incorporated from validation. Key one added for field actions and typos corrected.

72.0N.1786.151 Rev O 01/08/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. ON-143- 001 (marked-upto step 3.6. 7) exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title APRM Gain Adjustment S/RO 78.0P.3677.101 4 02/18/2015 Simulator Applicability JPM Number Revision Date Setting 215005 A1.07 3.0/3.4 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 02/18/2015 Richard Bolduc 05/10/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Greg van den Berg 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 15 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments LOC26 NRCX

78.0P.3677.101 Rev 4 02/18/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM 1 Revise for TQ procedures, minor editorial corrections 2 NRC revised based on facility comments 3 Revised for format change from NRC format to SSES format 4 Minor editorial changes. Revised power level to accommodate JPM pairing.

78.0P.3677.101 Rev 4 02/18/2015 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-178-002, PRNMS (Revision 7)

3. TASK CONDITIONS APRM Channel 3 is reading approximately 60%.

Core thermal power from the OD-3 heat balance has been verified to to be 63%

APRM Channel 3 has already been bypassed by the PCO.

4. INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.

5. TASK STANDARD Successfully perform manual APRM GAF adjustments for APRM 3.

78.0P.3677.101 Rev 4 02/18/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS

1. Reset Simulator to any power IC and adjust reactor power to 63%.

Adjust APRM 3 GAF to indicate ~60%

Bypass APRM 3.

SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

1. Reset the simulator to IC 390.

2. Verify conditions above.

PERFORMANCE CHECKLIST 78.0P.3677.101 Rev 4 02/18/2015 Examinee <<LastName>>, <<FirstName>> 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-390, or configure the simulator per the Simulator Setup Instructions.

A replacement copy of OP-178-002 section 2.2 .

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-178-002, controlled copy. determines section 2.2.5 applies. Verifies prerequisites and precautions are met.

EVALUATOR NOTE Role-play as PCO or SRO to avoid using plant page system during the JPM 2 Establish communications with PCO Establishes communications using plant page.

EVALUATOR CUE State that all communications will be with examiner role playing as PCO or SRO to avoid using plant page system during the JPM EVALUATOR CUE When operator is confirming BYPASS LED status state, "Channel 13 BYPASSED LEDs for APRM 11, 12, and 14 are lit."

3 Verifies APRM 3 bypassed Confirms all four 2/4 voters, BYPASSED LEDs for bypassed APRM are illuminated

4 Adjust the display to the proper screen Press ETC button to display ENTER SET MODE

5 Accept the proper display screen Press ENTER SET MODE key

6 Enter the password Enter password "1234" and press ENT

PERFORMANCE CHECKLIST 78.0P.3677.101 Rev 4 02/18/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 3 Step Action Standard Eva I Comments

7 Confirm mode Confirm OPER SET mode indicated on APRM or ODA

8 Setup display for gain adjustment

Using the cursor keys, highlight the APRM GAIN

Press SET PARAMETERS key

Verify APRM indicates SET PARAMETERS: APRM GAIN

9 Adjust APRM 3 GAF to the target gain Performs the following IAW section 2.2.5:

Adjust the APRM GAIN DESIRED UNTIL PROJECTED FLUX(%) is+/- 2%

of calculated CTP using using (t j)

CURSOR keys to scroll

Press the ACCEPT key

10 Confirm APRM 3 target gain is selected

Confirm the APRM GAIN PRESENT changes to equal the APRM GAIN DESIRED

Confirm ACTUAL FLUX(%) is+/- 2% of calculated CTP 11 Exit the setup displays

Press EXIT key

Press EXIT SET MODE key

Press YES key 12 Confirms APRM 3 display indicates OPERATE Confirms APRM upper display section indicates OPERATE on top right corner of display 13 Ensures indications are within 2% of APRM Ensure reading on NMSB display and reading APRM ODA reading within 2% of desired APRM reading EVALUATOR NOTE When Applicant either calls the control room or is returning to the control room to verify indications, end the JPM.

PERFORMANCE CHECKLIST 78.0P.3677.101 Rev 4 02/18/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 3 Step I Action I Standard I Eval I 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?

EXAMINEE TASK CONDITIONS APRM Channel 3 is reading approximately 60%.

Core thermal power from the OD-3 heat balance has been verified to to be 63%

APRM Channel 3 has already been bypassed by the PCO.

INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.

EVALUATOR TASK CONDITIONS APRM Channel 3 is reading approximately 60%.

Core thermal power from the OD-3 heat balance has been verified to to be 63%

APRM Channel 3 has already been bypassed by the PCO.

INITIATING CUE Perform a manual APRM GAF adjustment of APRM 3 IAW OP-178-002 Section 2.2.5.

78.0P.3677.101 Rev 4 02/18/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure OP-178-002 Rev 7 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.

78.0P.3677.101 Rev 4 02/18/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. Evaluator cue sheet cue loose

3. JPM jpm loose

4. OP-178-002 Section 2.2 sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Venting Unit 2 Scram Air Header during ATWS S/RO OO.E0.1996.202 1 02/18/2015 Plant Applicability JPM Number Revision Date Setting 295037 EA1.05 3.9/4.0 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 02/18/2015 Greg van den Berg 05/13/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 15 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

OO.E0.1996.202Rev1 02/18/2015 Page 2 of 3 JPM REVISION

SUMMARY

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

OO.E0.1996.202 Rev 1 02/18/2015 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. E0-000-113, Level/Power Control, Attachment G (Revision 14)

3. TASK CONDITIONS Unit 2 has just received a reactor scram signal; however RPS has failed to actuate.

All control rods are withdrawn and power is ~ 100 percent.

Both channels of RPS are energized.

Manual initiation of ARI has failed to depressurize the Scram Air Header.

4. INITIATING CUE Vent the Unit 2 Scram Air Header to insert control rods. Notify Control Room just prior to venting scram air header.

5. TASK STANDARD Air supply valves to the Unit 2 scram air header simulated closed, with vent valve simulated uncapped and open.

PERFORMANCE CHECKLIST 00. E0.1996.202 Rev 1 02/18/2015 Examinee <<LastName>>, <<FirstName>> 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 plant. Obtain Shift Manager Authorization to proceed .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure as posted Applicant may use the local posted instructions instructions to vent the Unit 2 Scram Air Header or provided Hard Card (see attached).

2 Bypass the scram header block valves. Open ARI Solenoid Valve Bypass Valve 247021.

Undoes the locking mechanism

Turns handle to the left 90°

3 Isolate the Scram Air Header. Close SCRAM AIR SUPPLY Valves 247002A and 247002B.

Turns SCRAM AIR SUPPLY Valves 2470002A and 247002B CLOCKWISE to CLOSE.

PERFORMANCE CHECKLIST OO.E0.1996.202Rev1 02/18/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 2 Step Action Standard Eva I Comments

4 Vent off the Scram Air Header. Uncap and open SCRAM AIR HOR VENT Valve 247007.

Turns cap Counter Clockwise (Looking Up from floor to ceiling view) 5 Verify air is being vented. Check for air at discharge vent.

EVALUATOR CUE Inform applicant that the sound of air venting can be heard.

6 Notify Control Room that Air Header is vented. Contact Control Room by Radio or Page that air is venting from the 247007 Valve.

EVALUATOR CUE Inform applicant Control Room has been notified and all control rods have inserted.

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?

EXAMINEE TASK CONDITIONS Unit 2 has just received a reactor scram signal; however RPS has failed to actuate.

All control rods are withdrawn and power is -100 percent.

Both channels of RPS are energized.

Manual initiation of ARI has failed to depressurize the Scram Air Header INITIATING CUE Vent the Unit 2 Scram Air Header to insert control rods. Notify Control Room just prior to venting scram air header.

EVALUATOR TASK CONDITIONS Unit 2 has just received a reactor scram signal; however RPS has failed to actuate.

All control rods are withdrawn and power is -100 percent.

Both channels of RPS are energized.

Manual initiation of ARI has failed to depressurize the Scram Air Header INITIATING CUE Vent the Unit 2 Scram Air Header to insert control rods. Notify Control Room just prior to venting scram air header.

OO.E0.1996.202Rev1 02/18/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk (*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure E0-000-113 Rev 14 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.).

NIA 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.

OO.E0.1996.202 Rev 1 02/18/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. procedure (marked-up) exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

5. Procedure (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Maintaining RCIC Suction Supply With Loss of AC and DC Power (LOC 27 Unit 2)

S/RO 50.E0.2567 .003 1 04/18/2015 Plant Applicability JPM Number Revision Date Setting 217000 A2.16 3.4/3.5 N N NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg van den Berg 04/18/2015 Greg van den Berg 05/13/2015 Author Date Instructor Date Review Approval Manu Sivaraman 06/05/2015 Durand Adams 06/03/2015 Operations Management Date Nuclear Training Supervisor Date 25 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket_>>) <<Employee>>

Last, First Ml Employee Number Exam Date: -------

Exam Duration (Min) - - - - - -

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

50.E0.2567.003 Rev 1 04/18/2015 Page 2 of 3 JPM REVISION

SUMMARY

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

50.E0.2567.003 Rev 1 04/18/2015 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. ES-250(150)-003, RCIC Manual Injection With Loss of AC and DC Power (Revision 13)

3. TASK CONDITIONS A Station Blackout has been in progress for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

All 250V DC power was lost on both Units.

RCIC has been started on both Units per ES-250-003.

Unit 1 and 2 CST levels are low and cannot be crosstied to the RWST.

ES-250(150)-003 Attachment C is in progress on both Units (another operator is performing ES-150-003 for Unit 1 RCIC)

4. INITIATING CUE Realign Unit 2 RCIC suction to the Suppression Pool per ES-250-003.

5. TASK STANDARD Unit 2 RCIC suction aligned to the Suppression Pool and isolated from the CST per ES-250-003.

PERFORMANCE CHECKLIST 50.E0.2567.003 Rev 1 04/18/2015 Examinee <<LastName>>, <<FirstName>> 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 plant. Obtain Shift Manager Authorization to proceed .

Mark-up a copy of ES-250-003 complete through Step 4.4 .

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of ES-250-003.

controlled copy.

2 Verifies ES-250-003 Step 4.4 is governing Controlled copy of ES-250-003 obtained, procedure and obtains controlled copy. selects Step 4.4.

3 Verifies Attachment C in progress to supply cooling Per Task Conditions.

to Unit 2 RCIC.

4 Opens RCIC PUMP SUCTION CST SUPPLY VLV At 20254 (32-670'), places control paddle HV-249F010 breaker, 20254-041 for breaker 20254-041 to the OFF position.

EVALUATOR CUE Breaker 20254-041 is open.

5 Opens RCIC PUMP SUCTION SUPP POOL Places control paddle for breaker SUPPLY VLV HV-249F031 breaker, 20254-042 20254-042 to the OFF position.

EVALUATOR CUE Breaker 20254-042 is open.

PERFORMANCE CHECKLIST 50.E0.2567.003 Rev 1 04/18/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 2 Step Action Standard Eva I Comments

6 Opens HV-249F031, RCIC Pump Suction Supp Performs the following at HV-249F031, Pool Supply Viv RCIC PUMP SUCTION SUPP POOL SUPPLY VLV (33-645')

Depresses the MOV manual operation clutch lever

Rotates the MOV handwheel in the counter-clockwise direction until resistance is felt

7 Closes HV-249F010, RCIC Pump Suction CST Performs the following at HV-249F010, Supply Viv RCIC PUMP SUCTION CST SUPPLY VLV (33-645')

Depresses the MOV manual operation clutch lever

Rotates the MOV handwheel in the clockwise direction until resistance is felt 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?

EXAM I NEE TASK CONDITIONS A Station Blackout has been in progress for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

All 250V DC power was lost on both Units.

RCIC has been started on both Units per ES-250-003.

Unit 1 and 2 CST levels are low and cannot be crosstied to the RWST.

ES-250(150)-003 Attachment C is in progress on both Units (another operator is performing ES-150-003 for Unit 1 RCIC)

INITIATING CUE Realign Unit 2 RCIC suction to the Suppression Pool per ES-250-003.

EVALUATOR TASK CONDITIONS A Station Blackout has been in progress for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

All 250V DC power was lost on both Units.

RCIC has been started on both Units per ES-250-003.

Unit 1 and 2 CST levels are low and cannot be crosstied to the RWST.

ES-250(150)-003 Attachment C is in progress on both Units (another operator is performing ES-150-003 for Unit 1 RCIC)

INITIATING CUE Realign Unit 2 RCIC suction to the Suppression Pool per ES-250-003.

50.E0.2567.003 Rev 1 04/18/2015 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 G.v. 1. Task description and number, JPM description and number are identified.

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

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

G.v. 4. Initial setup conditions are identified.

G.v. 5. Initiating and terminating cues are properly identified.

G.v. 6. Task standards identified and verified by SME review.

G.v.

7. Critical steps meet the criteria for critical steps and are identified with an G.v. asterisk(*).

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

G.v. 9. Ensure performance time is accurate.

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

Procedure ES-250-003 Rev 13 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.

50.E0.2567.003 Rev 1 04/18/2015 Page 1 of 1 JPM ASS EMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. ES-250-003 (marked-up through step 4.4) exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

5. Procedure (replacement) sim PC

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Manual Emergency Shutdown of Diesel Generator 'A' from Panel OC521A S/RO 24.0P .1443.051 1 06/25/2015 Plant Applicability JPM Number Revision Date Setting 264000 A4.04 3.7/3.7 N y NUREG-1123 KIA Number KIA Importance Alternate Path Time Critical E/APE I Sys Prepared Validated Greg Schrad 06/25/2015 Greg Schrad 07/20/2015 Author Date Instructor Date Review Approval Greg van den Berg 07/20/2015 Operations Management Date Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name: <<LastName>>, <<FirstName>> (<<Docket >>) <<Employee>>

Last, First Ml Employee Number Exam Date: -------

Exam Duration (Min) ------

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments

24.0P.1443.051 Rev 1 06/25/2015 Page 2 of 3 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM Changed to new TQ format 1

Updated procedures to the latest revision

24.0P.1443.051 Rev 1 06/25/2015 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-300, Administration of 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-024-001 Diesel Generators (Rev. 76)

3. TASK CONDITIONS A. The Rx has experienced a small Loss of Coolant Accident.

B. Drywell pressure is 2.1 psig up slow.

C. All Emergency Diesel Generators (DG) have started in Emergency Mode, 1 minute ago.

D. DG 'A' output breaker failed to close and cannot be closed.

E. There is no Emergency Service Water (ESW) cooling being supplied to DG 'A'.

4. INITIATING CUE The Control Room directs a Manual Emergency Shutdown of Diesel Generator 'A' in accordance with OP-024-001, section 2.7.

5. TASK STANDARD DG 'A' is shutdown using the Overspeed Fuel Shutdown Valve and Fuel Quadrant Lever due to Emergency Stop pushbutton failing to stop DG 'A'.

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee <<LastName>>, <<FirstName>> Page 1 of 5 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

This is a time critical JPM

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 A DG bay .

Have a copy of OP-024-001, section 2.7 EVALUATOR NOTE The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

This JPM is Time Critical. Step 7 must be completed by 7 minutes after candidate acknowledges the Initiating Cue.

EVALUATOR CUE Record JPM start time:

1 Identifies governing procedure and obtain Obtains controlled copy of OP-024-001, controlled copy. Section 2.7.

2* If diesel generator running in Emergency Mode, Places 43CM switch clockwise to Local.

Place DG 'A' 43CM Control Mode Select Switch in Local.

EVALUATOR CUE 43CM switch in the Local position.

3 At Diesel Engine Control Panel OC521A, Depress Depresses the Emergency Stop SES Emergency Stop pushbutton. pushbutton.

EVALUATOR CUE Emergency Stop pushbutton is depressed and stayed depressed.

FAULT STATEMENT THE NEXT STEP HAS THE STUDENT OBSERVE THE DG STOPS. THE EVALUATOR WILL CUE THE STUDENT THAT THE DG CONTINUES TO RUN. THE STUDENT WILL TAKE FURTHER ACTIONS TO SHUTDOWN THE DG.

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee <<LastName>>, <<FirstName>> Page 2 of 5 Step Action Standard Eva I Comments 4 At Diesel Engine Control Panel OC521A, Observe Student monitors for DG shutdown.

following:

Student determines that DG is still running

a. Master Trip Circuit Tripped Green light and continues in procedure.

Illuminates

b. Running Idle light Extinguishes

c. At 280 rpm, DG 'A' Pre-Lube Pump OP532A Starts EVALUATOR CUE

a. Master Trip Circuit Tripped Green light - NOT LIT

b. Running Idle light - LIT

c. DG Engine speed - 600 rpm and stable 5 WARNING Evaluates if the area is safe Personnel safety must be considered before proceeding with this step. Do not perform if area is not safe.

EVALUATOR CUE Inform student that Maintenance is present to assist in the following step and the area is safe.

6 If the diesel engine fails to stop as expected, Obtain Pulls SX-03483A.

maintenance assistance and Perform the following:

a. Pull the black knob labeled SX-03483A, Overspeed Fuel Shutdown Viv Reset. This knob is located on top of engine on the right side by the overspeed governor.

EVALUATOR CUE SX-03483A is pulled to end of travel.

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee <<LastName>>, <<FirstName>> Page 3 of 5 Step Action Standard Eva I Comments

7 b. Pull the fuel quadrant lever down and hold until Pulls and holds the Fuel quadrant lever.

the engine comes to a complete stop. The fuel There is a pushbutton on top of the lever quadrant lever is located on the engine left side that needs to be depressed to allow above the turning gear motor. movement.

EVALUATOR CUE If Student depresses the pushbutton on the lever, provide this cue: Fuel quadrant lever is pulled down to end of travel and is being held in that position. The sound of the engine's speed is lowering. The engine has stopped.

If Student does not depress the pushbutton on the lever, provide this cue: Fuel quadrant lever did not move EVALUATOR CUE Record JPM step completion time:

This time must be s 7 minutes after the recorded start time.

8 c. When diesel generator comes to stop, reset Resets SX-03483A by pushing-in plunger SX-03483A by pushing-in the plunger EVALUATOR CUE SX-03483A is reset and pushed-in 9 When diesel generator comes to stop, Depress Depresses Emergency Stop Reset Emergency Stop Reset pushbutton pushbutton.

EVALUATOR CUE Emergency Stop Reset pushbutton is depressed and stays depressed.

10 Depress Reset pushbutton for Annunciator and Depresses Reset pushbutton.

System Reset to reset emergency trip.

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee <<LastName>>, <<FirstName>> Page 4 of 5 Step Action Standard Eva I Comments EVALUATOR CUE If Student asks if any Protective Relays are tripped on OC519A, inform student all relays on OC519A are as indicated.

Spring resistance is felt, the pushbutton "bottomed out" and returned to normal when released.

Red label next to Reset pushbutton states, "Protective Relay Seal-In Reset Pushbutton (OC519) must be Reset Prior to Ann & System Reset". It is not necessary to perform this if no relays are tripped.

11 Observe OG A Master Trip Circuit Reset Amber Observes OG A Master Trip Circuit Reset light Illuminates. Amber light Illuminated.

EVALUATOR CUE Amber light is lit.

12 Observe OG A Master Trip Circuit Tripped Green Observes OG A Master Trip Circuit Tripped light extinguishes. Green light extinguished.

EVALUATOR CUE Green light is not lit.

13 Comply with TS 3.8.1 for Unit 1 and Unit 2. Informs SRO of TS.

EVALUATOR CUE SRO has been informed and is complying.

14 Ensure auto initiation signal Reset. Inquires about OW pressure.

EVALUATOR CUE High OW pressure condition still present.

No further OG manipulations required.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee <<LastName>>, <<FirstName>> Page 5 of 5 Step I Action I Standard I Eval I Comments EVALUATOR NOTE That completes the JPM.

EVALUATOR:

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

EXAMINEE TASK CONDITIONS A. The Rx has experienced a small Loss of Coolant Accident.

B. Drywell pressure is 2.1 psig up slow.

C. All Emergency Diesel Generators (DG) have started in Emergency Mode, 1 minute ago.

D. DG 'A' output breaker failed to close and cannot be closed.

E. There is no Emergency Service Water (ESW) cooling being supplied to DG 'A'.

INITIATING CUE The Control Room directs a Manual Emergency Shutdown of Diesel Generator 'A' in accordance with OP-024-001, section 2.7.

EVALUATOR TASK CONDITIONS A. The Rx has experienced a small Loss of Coolant Accident.

B. Drywell pressure is 2.1 psig up slow.

C. All Emergency Diesel Generators (DG) have started in Emergency Mode, 1 minute ago.

D. DG 'A' output breaker failed to close and cannot be closed.

E. There is no Emergency Service Water (ESW) cooling being supplied to DG 'A'.

INITIATING CUE The Control Room directs a Manual Emergency Shutdown of Diesel Generator 'A' in accordance with OP-024-001, section 2. 7.

24.0P.1443.051 Rev 1 06/25/2015 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.

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

Procedure OP-024-001 Rev 76 Procedure Rev Procedure Rev

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.).

12. If the JPM cannot be performed as written, then revise as necessary and

revalidate.

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

24.0P.1443.051 Rev 1 06/25/2015 Page 1 of 1 JPM ASSEMBLY INSTRUCTIONS Seq Item Copier Program Binding

1. Examinee cue sheet cue loose

2. OP-024-001 section 2. 7 exam staple

3. Evaluator cue sheet cue loose

4. JPM jpm loose

SUSQUEHANNA NUCLEAR, LLC OPERATIONS TRAINING PROGRAM SCENARIO EXAMINATION GUIDE CONTROL ROD PATTERN ADJUSTMENT/ RFP LUBE OIL PUMP SWAP/ RFP VIBRATION/

LOSS OF RBCCW/ HYDRAULIC-BLOCK ATWS SCN# LOC28-NRC-01 Revision 1 04/14/2016 Examination Material TEAM SUSQUEHANNA,

LOC28-NRC-01 Lesson Information Title Control Rod Pattern Adjustment/ RFP lube oil pump swap/ RFP Vibration/ Loss of RBCCW/ Hydraulic-Block ATWS Vision ID Accredited *YES D NO Training ID LOC28-NRC-01 Revision 11 Date I 04/14/2016 Prerequisites Teaching Time 65 Minutes Approval CBT Approval1 N/A Date N/A Preparer Date Review (lnstructor/SME) Date Nuclear Engineering 1 N/A Date N/A Training Supervision Date Line Management Date 1

1f required, otherwise N/A This simulator scenario has been reviewed and satisfies management expectations for inclusion of OE, Department Fundamentals and HuP, error-reduction techniques and safety standards. Specific applications and/or opportunities for reinforcement of management expectations are noted in the scenario guide or Attachment(s) where applicable.

Copyrighted by Nuclear Training Group, SUSQUEHANNA NUCLEAR, LLC, 2016. All rights reserved, no part of this training material may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the Nuclear Training Group.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 2

LOC28-NRC-01 Revision History Revision Date Comments 0 03/17/2014 New exam Revised to new template format.

Changed event number 1 to the lube oil pump transfer.

Removed some RWCU malfunctions. Clarified the event going 1 04/14/2016 into the scram. Changed the reports to match procedures and actual guidance. Changed the scram from high RRP temperature to a RBCCW rupture. Event 3 is just a setup for Event 4 and actions are removed due to the fast nature of the RFP trip.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

3

LOC28-NRC-01 Table of Contents Scenario Overview ................................................................................................................................5 Objectives .............................................................................................................................................7 A. Terminal Objective ................................................................................................................7 B. Generic Performance Objectives ...........................................................................................7 C. Simulator Performance Objectives ........................................................................................ 8 D. Task List. ............................................................................................................................. 10 Scenario Attributes .............................................................................................................................12 A. Critical Tasks ....................................................................................................................... 12 B. Scenario Malfunctions ......................................................................................................... 13 C. Abnormal Events and Major Transients ............................................................................... 14 D. EOP and EOP Contingencies Used .................................................................................... 14 E. Technical Specifications ...................................................................................................... 15 References ..........................................................................................................................................16 Setup Instructions ..............................................................................................................................18 A. Required Materials ................................................,. ............................................................. 18 B. Simulator Initialization ..........................................'. .............................................................. 18 C. Simulator Preparation .......................................................................................................... 19 D. Document Training and Performance Feedback ................................................................. 19 E. Scenario Execution ............................................................................................................. 19 F. Simulator Files .................................................................................................................... 19 Event 1 - RFP 'A' Main Lube Oil Pump Swap ....................................................................................22 Event 2 - Control Rod Pattern Adjustment .......................................................................................23 Event 3 - 'B' RFP vibration .................................................................................................................25 Event 4 - 'B' RFP trip ..........................................................................................................................25 Event 5 - RBCCW TCV fails ................................................................................................................28 Event 6 - Complete loss of RBCCW ..................................................................................................30 Event 7 - Hydraulic block ATWS .......................................................................................................32 Event 8 - SLC pump trips ...................................................................................................................32 Event 9 - Wide Range level instrument fails .....................................................................................32 Event 10 - In-service RFP trips ..........................................................................................................37 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

4

LOC28-NRC-01 Scenario Overview The scenario begins with Unit 1 at 95 percent power, 500 days into the operating cycle. Preparations are set for performing a control rod pattern adjustment. HPCI is in day 2 of a planned 4-day system outage window. Diesel Generator E is substituted for DG A for a system outage window. The RFP lube oil conditioner was swapped from the RFP A reservoir to the B reservoir last shift. A severe thunderstorm watch is in effect for Luzerne County for the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The first task for the crew is to test the RFP A main lube oil pumps, and perform a pump swap in the process, per OP-145-003. NPOs will report the RFP lube oil conditioner is in-service on the RFP B reservoir once the lube oil pump swap is complete.

When the RFP main lube oil Pump swap is complete the crew will withdraw control rods in accordance with the Reactivity Maneuver Request provided by Reactor Engineering, then proceed to raise power with recirc flow. The pattern adjustment will raise reactor power approximately 3 percent.

When the reactivity maneuver has been completed, 'B' RFP will experience a rising vibration trend.

Vibration will quickly rise to the alarm setpoint and then to the RFP trip setpoint. The crew is not expected to be able to respond to vibration trip. The crew will respond per off-normal procedures to the RFP trip and recirc LIM2 runback. Control rod insertion may be performed due to margin to the MELLA rod-line. The Recirc loop 'A' drive flow inputs to APRM flow channels 'C' and 'D' (APRMs 2 and 3) will drift high during the runback, resulting in a RBM flow compare control rod withdrawal block. The inoperable flow-biased scram and rod-block functions of the two APRMs will require entry into TS 3.3.1.1 and TRO 3.1.3.

When the crew has lowered power below the MELLA rod-line, the RBCCW TCV will malfunction resulting in a loss of cooling to RBCCW. RBCCW temperature will quickly rise. The RBCCW TCV bypass valve will be stuck closed. The crew will be required to place RBCCW on ESW which bypasses the RBCCW TCVs and will restore cooling to RBCCW loads. Entry into TS 3.7.2 will be required for the loop of ESW made inoperable when aligned to the RBCCW HX.

Once the crew has placed ESW in-service to RBCCW the return valve HV11024A2 will fail closed after approximately 5 minutes, due to its solenoid failing, resulting in a total loss of RBCCW cooling. Recirc Pump A lower motor bearing temperature will rise rapidly on the second loss of cooling, requiring a reactor scram and tripping of the Recirc Pump. If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power-flow map will be entered and the reactor will automatically scram on OPRMs.

The reactor scram will result in a hydraulic-block ATWS. The crew will trip both Recirc Pumps and reduce level to the ATWS band to lower power. The crew will perform the ES to bypass RPS trips, allowing the scram to be reset to drain the SDV and scram again. The crew will be able to insert control rods using RMCS. The first SLC pump started will trip shortly after starting, requiring the second pump to be started. As reactor level is lowered one channel of Wide Range reactor level will fail, requiring the crew to diagnose the failure and raise FW flow to maintain reactor level within the ATWS band.

The in-service RFP will trip after the scram is reset. RCIC can be used to maintain reactor level as the standby RFP is placed in service.

The first attempt at draining the SDV and re-inserting a scram will result in limited control rod motion.

The crew should reset the scram and allow the SDV to drain again while continuing control rod insertion.

The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A' RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

5

LOC28-NRC-01 Objectives Mastery of the training content shall be demonstrated by individual and/or crew performance evaluation as specified in this training material and the applicable training program description, in accordance with training procedures.

A. Terminal Objective Perform all system operations required to maintain the plant operating safely, or place the plant in a safe condition if a plant shutdown is required During the specified mode of plant I system operation Without error and in accordance with site procedures and management expectations B. Generic Performance Objectives

1. For all activities, exhibit use of the Human Performance Tools, demonstrating the ability to:

Use HU tools to effectively control the plant during normal, abnormal, and emergency conditions Use of HU tools will be observable per the standards in HU-AD-003 (SRO) Take every opportunity to coach the team when HU standards are not being met and provide feedback to the team when the HU standards are being met

2. For all activities, exhibit proper use of procedures by:

Applying the correct procedure to operate equipment and respond to abnormalities Ensuring procedures are detailed enough to allow precise control of plant evolutions.

Demonstrating the ability to:

Apply the correct procedure to the situation Use place keeping for accurate implementation Identify any and all areas for procedure improvement Take ownership of and complete the improvement, whenever an area for procedure improvement is identified

3. Base actions and decisions with a bias toward conservative, safe operation of the plant, demonstrating the ability to:

Assure all plant evolutions and work are assessed for Radiological Safety, Industrial Safety, Nuclear Safety, Environmental Safety, or Corporate Safety Once a risk is determined, take appropriate actions to mitigate or minimize risk Request assistance for any activity which requires additional planning, special precautions, and management oversight to adequately manage the risks (SRO) Champion activities that are biased conservatively LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

6

LOC28-NRC-01

4. Demonstrate complete understanding of plant design and system interrelationships, demonstrating the ability to:

Work effectively as a team to interpret plant indications and determine an effective response Understand the bases for, and the plant response to, actions being taken

5. Maintain continuous awareness of critical parameters, demonstrating the ability to:

Validate parameters by observing multiple independent indications Relay parameter values with value, units, and trend; and include action being taken for an abnormal value or trend Notify supervision of any change to critical parameters (SRO) Assure critical parameters for operational conditions are understood by the team

6. Operate plant systems and equipment within design and operational limits, maintaining relevant parameters within assigned operating bands, demonstrating the ability to:

Anticipate the impact of component operation prior to its operation, and then verify that the expected effects occur during and following the operation Take manual actions (in accordance with procedure direction) when automatic actions do not occur Take prompt action to adjust system operating controls before assigned operating bands are exceeded Make reactivity and mode changes as directed by detailed operating procedures and approved reactivity plans C. Simulator Performance Objectives

1. Operational Actions and Annunciator Response Correctly identify plant annunciators and indications and perform appropriate remedial actions

2. System Operation, Controls and Instrumentation Accurately identify plant instrumentation and correctly interpret instrument readings to respond to normal, abnormal, and emergency conditions

3. Facility Design and Operating Characteristics Demonstrate the following:

An understanding of facility operating characteristics

The ability to safely control the operating characteristics of the facility within prescribed operating boundaries LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

7

LOC28-NRC-01

4. System Loss and Component Level Malfunctions Perform system control manipulations to obtain desired operating results and demonstrate the ability to correctly respond to malfunction/loss of components and the impact of the malfunction/loss on interfacing plant systems

5. Heat Removal Component Operation Safely operate the plant's heat removal components and demonstrate knowledge of the relationship between the heat removal systems and the operation of facility to prevent exceeding System, Structure, or Component (SSC) design limits which include:

Primary coolant systems

Emergency coolant systems

Decay heat removal systems

6. Auxiliary and Emergency Component Operations Safely operate the plant's auxiliary and emergency components I systems to include the controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment to control release of radioactivity within regulatory limits

7. Reactivity Management Demonstrate knowledge of how reactivity is affected by plant operation and ability to respond to the change in reactivity to protect the safety and integrity of the reactor core

8. Technical Specifications During plant operation with the plant or system in a condition requiring Technical Specification action Identify the deviation and any required actions I notifications

9. Emergency Plan (if required)

During plant operation in an emergency condition Recognize conditions covered by the Emergency Plan (SRO) Demonstrate the ability to:

Identify and Implement the appropriate Emergency Action Level

-use the applicable bases to support an Event Classification on the specified Emergency Action Level Recognize conditions covered by the Emergency Plan

(SRO) Demonstrate the ability to:

Identify and Implement the appropriate Emergency Action Level

Use the applicable bases to support an Event Classification on the specified Emergency Action Level LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 8

LOC28-NRC-01

10. Control Room Duties Demonstrate the knowledge and ability to assume the appropriate responsibilities (for the assigned position) associated with the safe operation of the facility

11. Control Room Team Work Demonstrate the ability to function within the Control Room team to comply with station procedures and limits of facility license and respond to plant events using appropriate human performance tools to support safe operation of the facility D. Task List Task Title ID Licensed Operator Apply Technical Specification (TS) And Technical Requirements Manual (TRM) Requirements S-C00-00-1185 Implement Reactivity Manipulations Standards and Communication Requirements S-C00-00-2784 Implement Appropriate Portions Of Operations Standards S-C00-00-1081 For System and Equipment Operation Implement Operations Standards For Error And Event S-ADM-00-1091 Prevention Implement Standards for Shift Operations S-C00-00-2780 Implement Appropriate Portions of Conduct of Operations S-C00-00-1015 Implement Appropriate Portions of Secondary Containment Integrity Control S-C00-00-1020 Implement EOP Cautions S-C00-00-2566 Implement Operations Directives S-C00-00-3130 Ensure Plant Operates IAW the Operating License, Technical Specifications (TS), and Technical S-C00-00-1183 Requirements Manual (TRM)

Implement HUMAN PERFORMANCE (HuP) - Standards for Error and Event Prevention S-EPP-00-3068 Reactor Operator Implement Withdraw Control Rod One Notch S-201002-01-005 Implement Test of Standby Main and Emergency Oil Pumps S-259001-01-100 Operate a Single Reactor Feed Pump in Manual S-259001-01-037 Perform Speed Adjustment of Reactor Recirc Pump During Normal Operation S-202001-01-008 Direct RBCCW Heat Exchanger Manual Transfer Of S-276000-01-003 Service Water And Emergency Service Water Inhibit ADS from actuating S-218000-01-006 Bypass the MSIV and CIG Interlocks S-239001-01-025 Inject Liquid Poison Using Pump 1P208A(B)/2P208A(B) S-211000-01-006 Perform the Required Actions to Maximize CRD Flow S-201001-01-044 Start an Individual Reactor Feed Pump Turbine following a Trip S-259001-01-045 Perform a Manual Startup of RCIC Using Turbine Trip and Throttling Valve S-217000-01-035 Perform Actions Required to Override RCIC Injection S-217000-01-060 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

9

LOC28-NRC-01 Task Title ID Perform HPCI System Override Injection S-206000-01-062 Direct the Actions for Unanticipated Reactivity Change S-201002-01-009 Direct Actions for Core Flux Oscillations S-215005-01-017 Direct Actions for Loss of RBCCW Flow S-208000-01-007 Direct the Actions for RPS and ARI Trip Bypass S-212000-01-038 Perform Required Actions for a Reactor Recirculation Pump Runback S-202002-01-022 Enter EOP RPV Control S-EOPRR-01-006 Enter Level/Power Control EO Procedure S-EOPRPV-01-004 Confirm Reactor Scram S-EOPRPV-01-002 Confirm Reactor Shutdown S-EOPRPV-01-003 Ensure All Isolations and Actuations Occur S-EOPRPV-01-005 Enter Primary Containment Control S-EOPPCC-01-002 Scram the Reactor S-EOPRR-01-005 Senior Reactor Operator Direct Entry into Loss of Reactor Recirculation Flow S-202001-02-004 Direct Required Actions for a Trip of Both Reactor Recirculation Pumps S-202001-02-009 Direct Entry into Unanticipated Reactivity Change S-201002-02-001 Direct Entry into Loss of Reactor Building Closed Cooling Water (RBCCW) S-208000-02-001 Direct and Coordinate Implementation of Level Power Control (ATWS) 000000-02-1154 Direct Performance of RPS and ARI Trip Bypass S-212000-02-002 Direct the Operation of a Single Reactor Feed Pump in Manual {ICS) S-259001-02-024 Direct a Reactor Feed Pump Turbine A(B)(C) Trip S-259001-02-035 Direct Speed Adjustment of Reactor Recirc Pump During Normal Operation S-202001-02-002 Direct Inhibiting the Automatic Depressurization System from Actuating S-218000-02-001 Direct Performance of the Required Actions to Maximize CRD Flow S-201001-02-007 Direct Start of an Individual Reactor Feed Pump Turbine Following a Trip S-259001-02-030 Direct Performance of Overriding RCIC Injection S-217000-02-010 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 10

LOC28-NRC-01 Scenario Attributes A. Critical Tasks

1. Inject SLC Early boron injection has the following benefits:

Safety Significance

Stop or prevent large magnitude Limit Cycle Oscillations which can lead to core damage.

Limit fuel damage from uneven flux patterns that could result from partial rod inserts.

Failure to inject Boron can result in Consequences for Failure

Cycle Oscillations which can lead to core damage .

to Perform Task

Fuel damage from uneven flux patterns that could result from partial rod inserts.

Indications/Cues for Event ATWS with initial reactor power level greater than 5% APRM power.

Requiring Critical Task Inject SLC by inserting key into keylock switch and turning to start Performance Criteria selected SLC pump, fire the Squib valves and close the Reactor Water

'

Cleanup isolation valve.

Successful SLC injection would be indicated by a lowering SLC tank level Performance Feedback and a corresponding power level decrease.

2. Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise Core damage due to unstable operation can be prevented or at least Safety Significance mitigated by promptly reducing Feedwater flow so that level is lowered below the Feedwater spargers.

A General Electric Company study (NED0-32047) indicates that the Consequences for Failure major threat to fuel integrity from ATWS is caused by large-amplitude to Perform Task power/flow instabilities. The power oscillations can become large enough to cause melting of fuel in high-power bundles.

Indications/Cues for Event ATWS with initial reactor power level greater than 5% APRM power.

Requiring Critical Task Lower reactor water level by manually controlling injection rate from Performance Criteria Feedwater, HPCI and/or RCIC.

Reducing vessel injection will result in Wide Range level indications lowering to -60 to -110 inches and will result in power level lowering as Performance Feedback indicated on the Average Power Range Monitors.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

11

LOC28-NRC-01

3. Insert Control Rods IAW E0-000-113 Safety Significance Control rod insertion initiates power reduction immediately.

Consequences for Failure Failure to insert control rods allows power to remain elevated with to Perform Task resultant power oscillations and potential core damage.

Indications/Cues for Event Exceeding a RPS scram setting with NO reactor scram signal, or Requiring Critical Task RPS/ARI fail to fully insert all control rods.

Insert Control Rods by one or more of the following methods:

Performance Criteria

Drive control rods after bypassing RWM

Reset and Scram again by performing ES-158-002 Bypass RPS logic trips Successful insertion of control rods will be indicated by:

Rod position full in indication for manual insertion of control rods Performance Feedback

Rod position showing control rod insertion after resetting scram, draining scram discharge volume and re-scram

Power level lowering as indicated on the Average Power Range Monitors B. Scenario Malfunctions Event Malfunction Operator Action in Response 1 Swap 'A' RFP main lube oil pumps N/A (OP-145-003) 2 N/A Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012) 3 'B' RFPT vibration rises and 'B' RFPT trips on mfFW145 0078 high vibration, Recirc LIM2 runback (ON-164-002) 4 cmfTR03_FTB31 APRM 2 and 3 'A' Recirc Loop drive flow fails 1N014C high during LIM2 run back (TS 3.3.1.1) 5 RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001), ESW cmfAV04 TV11028 loop declared inoperable when aligned to RBCCW {TS 3.7.2) 6 Complete loss of RBCCW, High RRP cmfAV01_HV11024A2 temperatures, Manual Scram 7 Hydraulic-block ATWS mfRD155 017 (E0-100-113, OP-145-005, ES-158-002)

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

12

LOC28-NRC-01 8 cmfPM03- 1P208A SLC pump trips after start, standby SLC pump cmfPM03- 1P208B successfully injects boron (OP-153-001) 9 Wide Range level instrument fails, RFP flow cmfTR01_LT14201A must be raised to maintain reactor level in ATWS band 10 In-service RFPT trips after first scram, RCIC mfFW148002 restored to maintain RPV level while standby RFPT placed in-service C. Abnormal Events and Major Transients Malfunction Description R Withdraw control rods to raise reactor power 3 percent. (OP-AD-338, G0-100-012)

N Swap 'A' RFP main lube oil pumps (OP-145-003)

AE1 RBCCW TCV fails, ESW placed in-service to restore RBCCW cooling (ON-114-001)

AE2 RBCCW ruputure ( ON-114-001 )

MT1 Hydraulic-block ATWS '

TS1 APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 run back (TS 3.3.1.1)

TS2 ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2)

SLC pump trips after start, standby SLC pump successfully injects boron (OP-153-MAE1 001)

Wide Range level instrument fails, RFP flow must be raised to maintain reactor level MAE2 in ATWS band In-service RFPT trips after first scram, RCIC restored to maintain RPV level while MAE3 standby RFPT placed in-service D. EOP and EOP Contingencies Used EOPs EOP Contingencies IZl E0-000-102, RPV Control D E0-000-102, Alternate Level Control IZl E0-000-103, Primary Containment Control D E0-000-102, Steam Cooling D E0-000-104, Secondary Containment Control D E0-000-112, Emergency Depressurization D E0-000-105, Radioactivity Release Control IZl E0-000-113, Power/Level Control D E0-000-114, RPV Flooding LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

13

LOC28-NRC-01 E. Technical Specifications

1. TS 3.3.1.1, Instrumentation Reactor Protection System (RPS)

2. TS 3.7.2, Plant Systems Emergency Service Water System

3. TRM 3.1.3, Reactivity Control Systems Control Rod Block Instrumentation LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 14

LOC28-NRC-01 References

1. OP-AD-001 Operations Standards for System and Equipment Operation

2. OP-AD-004 Operations Standards for Error and Event Prevention

3. OP-AD-300 Administration of Operations

4. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

5. OP-111-001 Service Water System

6. OP-145-001 RFP and RFP Lube Oil System

7. OP-145-005 Infrequent Manual RFP System Operations

8. OP-145-006 Feedwater HMI Operations

9. OP-153-001 Standby Liquid Control System

10. OP-156-001 Reactor Manual Control System RMCS

11. OP-183-001 Automatic Depressurization System and Safety Relief Valves

12. OP-184-001 Main Steam System

13. G0-100-012 Power Maneuvers

14. ON-SCRAM-101 Reactor Scram

15. ON-RBCCW-101 Loss of RBCCW

16. ON-PWR-101 Reactor Power

17. ON-RECIRC-101 Reactor Recirculation Malfunction

18. E0-000-102 RPV Control

19. E0-000-103 Primary Containment Control

20. E0-000-104 Secondary Containment Control

21. E0-000-112 Emergency Rapid Depressurization

22. E0-000-113 Power/Level Control

23. AR-101-A01 RWCU Filter Inlet Hi Temp lso

24. AR-101-A10 RFPT A Trip

25. AR-101-A16 RFPT B Trip

26. AR-102-F03 Recirc Pump A Seal Clg Water Lo Flow

27. AR-103-E06 APRM Flow Reference Off Normal

28. AR-104-H03 Rod Out Block

29. AR-106-C09 Gen Volt Reg Auto To Man Set Point Unbalanced

30. AR-110-A01 ADS Logic A Timer Initiated

31. AR-110-A02 ADS Logic B Timer Initiated LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 15

LOC28-NRC-01

32. AR-100-A03 ADS Logic C Timer Initiated

33. AR-100-A04 ADS Logic D Timer Initiated

34. AR-123-E05 RBCCW Header Hi Temp

35. LA-1295-001 RWCU System Panel 1C295

36. EP-PS-100 Emergency Director Control Room Emergency Plan Position Specific Instruction

37. EP-RM-004 EAL Classification Bases

38. ES-158-002 RPS and ARI Trip Bypass 39.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 16

LOC28-NRC-01 Setup Instructions A. Required Materials

1. US Turnover Sheet

a. Unit 1

1) -95% power for control rod pattern adjustment, 500 days on-line

2) HPCI in day 2 of 4-day system outage window for steam side maintenance. LCO 3.5.1 condition D has been entered for the outage.

3) 'E' EOG substituted for 'A' EOG for 'A' system outage window

4) RFP lube oil conditioner was swapped from RFP 'A' reservoir to 'B' reservoir last shift

5) Perform control rod pattern adjustment per RMR

6) Test 'A' RFP main lube oil pump 'B' and swap to main lube oil pump 'B'

b. Common and Unit 2

1) Unit 2 at rated power.

2) Severe thunderstorm watch is in effect for Luzerne County for the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

2. Supporting Documents

a. RMR (2 copies)

b. OP-145-003 (for the Normal Event)

B. Simulator Initialization

1. Reset to exam specific IC. If not available, setup IAW the following instructions

a. Reset to IC-20

b. Place the simulator in RUN

c. Reduce core power to 95% using RRPs. Match loop flows.

d. Isolate the HPCI steam supply by closing the F002 and F003 isolation valves.

e. Depressurize the HPCI steam supply line after F002 and F003 are closed by opening F054 valve. Close the F054 valve once the steam line is depressurized.

f. Run SCN file HPB_HPCIOOS.scn to tagout HPCI steam-side

g. Place the simulator in FREEZE

2. Run SCN file exam\LOC28-NRC-01.scn

3. Place the simulator in RUN LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

17

LOC28-NRC-01

4. Perform simulator activities

a. Place a status control tag on the HPCI Steam Supply Valves

b. Place protected equipment magnets around RCIC

c. Place the 'E' for 'A' EOG signs up

d. Ensure proper CRMs are inservice

e. Post the blue reactivity signs

5. Verify the simulator matches the following

a. 3 RFs and 1MF is in the list due to performing the HPCI setup MF RF OR ET CONDITIONS 8:8 4:4 0:0 8 15

6. Ensure FW Control is selected to LEFM

7. Reset ODAs and all Overhead, PICSY, HMI and RWM alarms

8. Ensure horns and annunciators are on

9. Ensure Overhead Lights Override is off C. Simulator Preparation

1. Ensure the EOL CRC Book is at the PCO Console D. Document Training and Performance Feedback

1. Record crew position assignments in G:\NTGOPS\LOR\REQUAL\lnfo Tracking\ (LOR)

2. Record crew position assignments perTQ-104 (ILO)

3. Complete simulator exam checklist E. Scenario Execution

1. Identify performance improvement actions that may be addressed during the scenario

2. Provide turnover to the crew using the US Turnover sheet

3. Direct the crew to walk down the Control Room panels

4. Inform the Shift Manager that the crew has the shift F. Simulator Files LOC28-NRC-01 changemp fx10FWCTRL_B21.0UT ,,%,FW MASTER LVL CTRL OUTPUT de Imp SCN rat_mp insmp fxlBRFP _B115.0UT changemp fxlBRFP _B115.0UT ,,%,RFP B DEMAND insmp ycpxftv03 changemp ycpxftv03 0,10,mils,RFP B VIBR insmp fxlBB_SM_Bl.OUT changemp fxlBB_SM_Bl.OUT ,,RPM,RFPT B SPEED insmp fx10FWCTRL_B21.0UT insmp fxlBRFP _B115.MA LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

18

LOC28-NRC-01 changemp fxlBRFP _B115.MA ,,bool,RFPT B AUTO/MAN ; RFP B vibration

{Key[l]} IMF mfFW145007B r:180 f:lO insmp rwtt11305 changemp rwtt11305 ,,,RBCCW HX OUTLET TEMP ; RBCCW HX TCV fails

{Key[3]} IMF cmfAV04_TV11028 r:lO f:O insmp swvsptv11028 changemp swvsptv11028 ,,,RBCCW HX TCV POS ; Adjust RBCCW cooling

{Key[4]} IMF cmfAV04_TV11028 d:15 r:30 f:5 insmp aoTRSHB311R601D.CurrValue changemp aoTRSHB311R601D.CurrValue 0,300,DEG F,RRP A LO ; RBCCW discharge header rupture GUIDE BRG TEMP(PT4) {Key[5]} IMF mfRW114001 f:20 insmp aoTRSHB311R6011.CurrValue ; Byp CRD pump suet filter changemp aoTRSHB311R6011.CurrValue 0,300,DEG F,RRPA #1 {Key[6]} IRF rfRD155028 d:120 f:lOO SEAL CAV TEMP

Close CRD chrg wtr isol F034 insmp cuteg331n019 {Key[7]} IRF rfRD155017 d: 120 f:O changemp cuteg331n019 ,,DEG F,RWCU NRHX INLET

ES-158-002 - ARI

0-G alarms suppressed SDR {Key[8]} IRF rfDC102129 f: OPEN d:120 IMF annAR106F15 f:ALARM_OFF {Key[8]} IRF rfDC102103 f:OPEN d:120 IMF annAR131A04 f:ALARM_OFF

ES-158-002 - Div 1 RPS

B CRM spurious alarm suppressed {Key[9]} IRF rfRP158039 f: BYPASS d:120 IMF annAR112G04 f:ALARM_OFF {Key[9]} IRF rfRP158040 f:BYPASS d:120

E DG subst for A ; ES-158-002 - Div 2 RPS I RF rfDG024001 f: A {Key[lO]} IRF rfRP158041 f:BYPASS d:120

{Key[lO]} IRF rfRP158042 f:BYPASS d:120

Recirc loop A xmitter offset initialization IMF cmfTR03_FTB311N014C f: O ; Re-open CRD chrg wtr isol F034 IMF cmfTR03_FTB311N014D f:O {Key[ll]} IRF rfRD155017 d:120 f:lOO

Hyd-block ATWS ; X-Tie CIG and I/A IMF mfRD155017 {Key[l2]} IRF rfPC125001 f: OPEN

CRD PCV binding ; HPCI OOSVC - isolate and depress steam-side first IMF cmfMV07 _PV146F003 f: Asls {Key[40]} SCN exam\HPB_HPCIOOS

Recirc loop A channel D flow xmitter malfunctions aet ETLOC28-NRC01-B HPB.HPCIOOS

HV-F002 BRKR OPEN (IB)

activate NRHX iso alarm on high temp IRF rfDB106236 f: OPEN aet ETLOC28-NRC01-C ;# HV-F003 BRKR OPEN (OB)

IRF rfDC188113 f:OPEN

align ESW to RBCCW HX ;# HPCI AOP BRK OPEN aet ETLOC28-NRC01-D IRF rfDC188128 f: OPEN

LOSS OF PWR TO HV-FlOO SOLENOID

Activates ETLOC28-NRC01-J IMF cmfAVOl_HV155F100 aet ETLOC28-NRC01-E

1st SLC pump trips ETLOC28-NRC01-B aet ETLOC28-NRC01-F fx1B_LIMITERS_B432.B001=1 aet ETLOC28-NRC01-G MMF cmfTR03_FTB311N014C r: 30 i:O f:21789 MMF cmfTR03_FTB311N014D r:30 i:O f:19876

Trips breaker for PV-146-F003 when operated aet ETLOC28-NRC01-H ETLOC28-NRC01-C

WR level A fails as-is cuteg331n019 > 145 aet ETLOC28-NRC01-I IMF annARlOlAOl f: ALARM_ON LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 19

LOC28-NRC-01 ETLOC28-NRC01-D ETLOC28-NRC01-G

SWITCH: RBCCW HX A SW-ESW CHANGEOVER ;SWITCH:SBLC MANUAL INITIATION diHS11024A.CurrValue =#OR.diHS11024A.EMERG =

diHSS14804.CurrValue #OR.diHSS14804.START_B IMF cmfAV04_HV11024Al f:O IMF cmfPM03_1P208B d:45 IMF cmfAV04_HV11024A2 f:O cet ETLOC28-NRC01-F IRF rfSW111032 f:O IMF cmfCV02_110050

+5 DMF cmfAV04_HV11024Al ETLOC28-NRC01-H DMF cmfAV04_HV11024A2 ;SWITCH:DRIVE WTR PRESS THTLG diHS14603.CurrValue =#OR.diHS14603.0PEN IMF cmfMVOl_PV146F003 ETLOC28-NRC01-E

SWITCH: MODE SWITCH diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN ETLOC28-NRC01-I aet ETLOC28-NRC01-J rrlwr < -50 IMF cmfTROl_LT14201A ETLOC28-NRC01-F

SWITCH: SBLC MANUAL INITIATION ETLOC28-NRC01-J diHSS14804.CurrValue =#OR.diHSS14804.START_A ;SWITCH:MODE SWITCH IMF cmfPM03_1P208A d:4S diHSC72AlS01.CurrValue != #OR.diHSC72AlS01.RUN & (

cet ETLOC28-NRC01-G rp_c721k14a = 1 I rp_c721k14b =1) & rp_c721kla =0 IMF mfFW148002 d:120 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

20

LOC28-NRC-01 Event 1 - RFP 'A' Main Lube Oil Pump Swap Instructor Activities Operator Activities Notes Booth Operator No additional actions required PCO Role Play D Identifies the following alarm windows:

As NPO dispatched to 'A' RFP main lube oil pumps for AR-120-803 and AR-101-H 10 pre-start checks, report D Dispatch NPO to perform pre-start Standing by for test and checks of RFPT 'A' main lube oil pump swap of 'A' RFP main lube oil pumps. D Depress and hold TEST pushbutton for RFPT A ALT MN L-0 PPS HS-11912A D Observes standby lube oil pump starts by appropriate Red light ILLUMINATED D Release TEST pushbutton HS-11912A D Depress RUN pushbutton for RFPT A MN L-0 PP 1P124B

'

D Places 1P124A in Standby D Performs above steps again to test the auto start function of the 'A' lube oil pump us D Directs PCO to test the 'A' RFP main lube oil pumps and perform a pump swap IAW OP-145-003 If the student asks, all prerequistes are completed so that the evolution may proceed.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

21

LOC28-NRC-01 Event 2 - Control Rod Pattern Adjustment Instructor Activities Operator Activities Notes Booth Operator When control rod withdrawal is complete, Enter the Control Room as Reactor Engineering and update the CRC book with the updated shutdown sequence sheets and current control rod pattern.

When the CRC book has been updated, Perform the third role play as the booth or on the floor Initiate Event 3 as soon as the reactivity maneuver is completed.

PCOM Role Play D Withdraws Control Rods 22-23, 38-39, As RE contacted for assistance, reply 38-23, and 22-39 from position 00 to Core Thermal limits are position 04 IAW OP-156-001 and within our predictions. You OP-AD-338 may proceed with the pattern adjustment. D Uses two finger operation to select the proper Control Rod by depressing the Role Play Control Rod Selection pushbuttons As SM contacted for approval to commence the reactivity D Verifies the correct Control Rod is manipulation, reply ' selected and in the proper position The Reactivity D Withdraws Control rods by depressing manipulation may proceed IAWtheRMR the "W/Draw Rod" pushbutton D When all 4 rods have been moved, Role Play verifies that the rods are in the proper As RE contact the Control position Room as stated in the booth operator section D Depress 'Rod Selct Clear' pushbutton Thermal Limits are sat per D Plots the power change on the step #4 of the RMR. We will bring the RMR for returning Power/Flow map to rated power with Recirc D Monitors diverse indications of reactor flow momentarily. The power IAW OP-AD-001 Att G updated CRC pages have been replaced. The PCOP maneuvering envelope is D Verifies control rods to be withdrawn still 90% to 100% power.

as directed by RMR IAW OP-AD-338 Role Play D IAW OP-AD-300, nulls Manual and As GCC, acknowledge all Automatic regulars using Man Volt Reg power change updates Adjust HC-10002 potentiometer, as required D Maintains Load Set -100 MWe above actual generator loads IAW G0-100-012 by depressing Load Selector

'Decrease' and 'Increase' pushbuttons, as required LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

22

LOC28-NRC-01 Event 2- Control Rod Pattern Adjustment Instructor Activities Operator Activities Notes us D Obtains permission from the Shift Manager prior to commencing reactivity manipulations D May, inform GCC of load change on Unit 1 D Conducts a Crew Update prior to commencing rod withdrawal D Directs Control Rod Withdrawal IAW OP-156-001, RMR, and G0-100-012 D Monitors control rod movement with independent copy of RMR The rod pattern adjustment should be completed before moving to Event 3. This will ensure that the rod-line is raised high enough to challenge the fv1ELLA boundary during the runback for the RFP Trip.

Instructor Cue Initiate Event 3 as soon as power has been raised 5% or on the Lead Examiner's direction. If llfl>>) the next event is started before the RE explaination for the maneuvering envelope, the crew may decide to only use RRPs.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

23

LOC28-NRC-01 Event 3 & 4 - 'B' RFP vibration/ 'B' RFP trip Instructor Activities Operator Activities Notes Booth Operator When power has been raised 5% or at the Lead Examiner's direction, Insert Key 1 to initiate high vibrations on

'B' RFP.

{Key[1]} IMF mfFW145007B r:180 f:10 'B' RFP vibration Monitor 'B' RFP vibration in Monitored Parameters.

Ensure Event Trigger ETLOC28-NRC01-B fires when a Recirc LIM2 is actuated by the 'B' RFP trip, to fail the APRM 2 drive flow input from Recirc Loop 'A'.

PCOM Role Play D Performs AR-101-A16 for 'B' RFP vibs As FUS/NPO dispatched to

'B' RFP, wait 2 minutes and D Reports Reactor Power, pressure, and report water level The 'B' RFP sounds out-of- D If directed, lowers 'B' RFP speed IAW balance and it feels like there are higher vibrations OP-145-006 by taking manual control around the pump. and lowering speed D If directed, lowers Core power IAW Role Play As FUS/NPO contacted for OP-164-002 by manually lowering

'B' RFP status post-trip, RRPs speed report D Observes AR-101-A12 and reports 'B'

'B' RFP is coasting down on the turning gear. I don't RFP Tripped see anything abnormal. D Plots position on Power/Flow map D Performs ON-PWR-101 to monitor Role Play OPRMs for instabilities As NPO dispatched to the Lower Relay Room to report D If directed, inserts control rods IAW the status of APRMS, wait 2 OP-156-001 and OP-AD-338 minutes and report No APRMs indicate any D Performs AR-104-H03 and AR-103-alarms. E06 for 'A' & 'B' RBM and APRM 2 D Directs NPO to investigate APRMs LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

24

LOC28-NRC-01 Event 3 & 4 - '8' RFP vibration/ 'B' RFP trip Instructor Activities Operator Activities Notes PCOP Role Play D IAW AR-101-A16, Checks alarm As WWM contacted for assistance with 'B' RFP condition and trend on RFPT Vibration vibrations, wait 5 minutes and XRSH-12728 and observes rise in 'B' report RFP vibration Engineering is looking at the vibration data but D May direct NPO to report conditions at doesn't have a specific the 'B' RFP recommendation at this time.

D Performs ON-RECIRC-101 and verifies a LIM2 runback occurred Role Play D Monitors Main Steam Line Radiation As WWM contacted for Monitor, RR-012-1 R603, and Offgas assistance with APRM flow reference abnormal alarm, Pretreatment Log Radiation Monitor, wait 5 minutes and report RR-012-1 R601 l&C reports that Recirc Loop 'A' recirc flow us transmitters B31-1N014C D If time allows, directs lowering 'B' RFP and 1N014D are indicating ~peed IAW AR-101-A16 by either

-20,000 gpm higher than the other two 'A' Recirc manual control of the 'B' RFP or Loop drive flow manual control of the RRPs transmitters. D Contacts WWM for assistance with the

'B' RFP D Directs Transient Actions IAW OP-AD-300 when 'B' RFP trips D [)irects entry into ON-RECIRC-101 and ON-LVL-101 D May direct control rod insertion to gain margin to MELLA rod-line IAW the Shutdown Control Rod Sequence package and ON-PWR-101 D Notifies Chemistry, RP, and RE of

>15% power change in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months IAW G0-100-012 D Contacts WWM for assistance with the APRM flow compare alarm LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

25

LOC28-N RC-01 Event 3 & 4 - 'B' RFP vibration/ '8' RFP trip Instructor Activities Operator Activities Notes us D Enters Tech Specs 3.3.1.1 Condition

'A' for B31N014C and B31N014D Recirc Flow Transmitter inoperable in functions 2.b and 2.f AND TRM 3.1.3 Conditions 'A' and 'B' for Function 1.b The scenario may proceed to Event 5 after 1O minutes have elapsed or once the crew has evaluated the power/flow map and made a determination as to whether control rod insertion is required.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 26

LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities Operator Activities Notes Booth Operator IAW Event 3 note, Insert KEY 3 to initiate a failure of the RBCCW HX TCV

{Key[3]} IMF cmfAV04_TV11028 r:10f:O RBCCW HX TCV fails Ensure Event Trigger ETLOC28-NRC01-C fires when RWCU NRHX inlet temperature reaches 145F to activate RWCU F/D inlet high temperature isolation alarm.

Monitor RRP bearing temperature on Monitored Parameters. After RWCU isolates, if required to prevent RRP bearing temperatures exceeding 195F, Insert KEY 4. Adjust the severity of malfunction cmfAV04_TV11028 in 1 % increments as necessary to slowly raise bearing temperatures toward the 195F limit without going over.

{Key[4]} IMF cmfAV04_TV11028 d:15 r:30 f:5 Ensure Event Trigger ETLOC28-NRC01-D fires when ESW is aligned to the RBCCW HX to complete the in-field valve alignments.

PCOM Role Play D Reports Reactor power, pressure, and As NPO dispatched to RBCCW, wait 2 minutes water level The RBCCW HX TCV is PCOP almost full closed. D Performs AR-123-E05 and checks Role Play RBCCW HX DSCH temp and As NPO directed to open the controller RBCCW HX TCV bypass, D Dispatches NPO to RBCCW 110062, wait 1 minutes The RBCCW bypass valve, pump/heat exchanger area 110062, would not move. I D Performs ON-RBCCW-101 to verify do not hear flow noise RRP temperatures, TCV-11028 through the valve.

operability, Bypass Valve 110062 Role Play operability, and swap RBCCW HX to As NPO directed to support ESW supply IAW OP-111-001 aligning 'A' ESW to 'A' D Aligns ESW to RBCCW HX 'A' IAW RBCCW HX, when asked to report local valve position OP-111-001 by starting ESW in one IAW OP-114-001 Step loop and depressing the RBCCW HX A 5.13.9b, report HV-11024A1 and HV- SW/ESW SUP HA 11024 pushbutton 11024A2 are open, HV-11024A3 is closed.

Role Play As NPO directed to RWCU filters, wait 2 minutes The RWCU filters are in hold LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

27

LOC28-NRC-01 Event 5 - RBCCW TCV failure Instructor Activities Operator Activities Notes us Role Play D Directs entry into ON-RBCCW-101 As NPO directed to close 11046 IAW step 5.13.9c, wait D Contacts WWM for assistance with the 1 minute RBCCWTCV 110046 is closed D Directs aligning ESW to the RBCCW Role Play HX IAW OP-111-001, Service Water As WWM contacted for System assistance with RBCCW HX D Declares ESW loop to be aligned TCV, wait 5 minutes l&C believes the positioner inoperable IAW OP-111-001 and is getting a close signal Enters TS 3.7.2 Condition C for 1 ESW from the controller. subsystem inoperable for reasons Additional investigation is required. other than Condition B

The RBCCW high temperature a'larm is received -3 minutes after the TCV malfunction is inserted.

A total loss of RBCCW occurs in the next event.

Once ESW has been aligned to RBCCW HX 'A', proceed to Event 5 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

28

LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes Booth Operator IAW Event 4 Note, Depress KEY 5 to insert a 20% rupture on the common discharge header of RBCCW

{Key[5]} IMF mfRW114001 f:20 RBCCW discharge header rupture Perform first role play after inserting Key 5 Ensure Event Trigger ETLOC28-NRC01-E fires when the mode switch is placed in SHUTDOWN to activate Event Trigger ETLOC28-NRC01-J PCOM Role Play D If directed, trips 'A' RRP by depressing As NPO at RBCCW HX, when Key 5 is inserted, MG SET A DRV MTR BKR HS-contact the control room 14001 A STOP PB There is a rupture on the D Inserts a manual scram by placing the common discharge header of RBCCW. It is too large Mode Switch to Shutdown to quantify. D Identifies more than 1 control rod >

position 00 Role Play As WWM contacted for D Reports A TWS assistance with RBCCW D Arms and Depresses the manual rupture, acknowledge Scram Pushbuttons request.

D Performs Scram Report PCOP Role Play D Performs AR-201-F03 for 'A' RRP by As NPO requested to isolate monitoring motor bearing and seal the rupture, report The rupture cannot be cavity temperatures and trips RRP isolated. when seal cavity exceeds 195F D Initiates ARI by arming and depressing ARI pushbuttons and collars during the ATWS us D Before RRP 'A' temperatures exceed 195F, either Trips the 'A' RRP and scrams the reactor on OPRMs or Manually scrams the reactor and trips the 'A' RRP D IAW ON-RBCCW-101, performs a manual scram of the Unit.

D Enters E0-000-102 and transitions to E0-000-113 LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

29

LOC28-NRC-01 Event 6 - Complete loss of RBCCW/ SCRAM Instructor Activities Operator Activities Notes If the reactor is not scrammed before the recirc pump is tripped, Region 1 of the power/flow map will be entered and the reactor will automatically scram on OPRMs.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 30

LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-F(G) fires when the first SLC pump is started, to trip the running pump due to a motor fault after a time delay.

Ensure Event Trigger ETLOC28-NRC01-H fires when the CRD PCV, PV-146-F003 is opened to trip the breaker.

When directed, Insert KEY 6 to bypass CRD pump suction filter. Monitor sim RF count and report when complete.

{Key[6]} IRF rfRD155028 d:120 f:100 Byp CRD pump suet filter When directed, Insert KEY 7 to close CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete

{Key[7]} IRF rfRD 155017 d:120 f:O Close CRD chrg wtr isol F034 Ensure Event Trigger ETLOC28-NRC01-l fires when RPV level falls below-50" to fail Wide range level transmitter 14201A Lowers RPV level to <-60" and maintains until E0-000-113 directs otherwise PCOM Role Play D If requested, reports reactor power>

As NPO dispatched to CRD PCV breaker 18227-024, wait 5%

2 minutes D Performs actions IAW ON-SCRAM-18227 breaker 24 is tripped 101, Inserts IRMs and SRMS on magnetics D Trips both RRPs Role Play D Verifies HPCI is overridden If directed to open CRD PCV D Takes manual control of RFPs and bypass valve 146-F004, wait valves, as required, to stop and 2 minutes CRD PCV bypass valve prevent injection until water level 146-F004 is stuck closed lowers to -60" and then starts injecting Role Play to control level in band As WWM contacted for D Ensures only 2 Condensate pumps are assistance, acknowledge and running take no action LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

31

LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities Operator Activities Notes PCOM D Injects SBLC IAW OP-153-001 by placing HS-14804 to 'A' or 'B' and then to the other pump when the first fails D Identifies Wide Range Level 'A' instrument channel failure. Maintains with 'B' Level indicator D Uses FW to maintain RPV water level within ATWS level band, initially -60" to

-110" PCOP D Ensures HV-144-F004 RWCU Inlet OB lso Closes D Inhibits ADS IAW OP-183-001 D If directed, Overrides RCIC by manually lowering flow until -2200

'

RPM D Bypasses MSIV and CIG interlocks IAW OP-184-001 by taking the 5 switches to BYPASS on 1C645 and 1C644 D Maximizes CRD by starting the standby pump, fully open CRD flow ..

controller in MANUAL, fully open Drive water pressure valve us D Enters E0-000-113 D Directs PCOP to inhibit ADS D Directs PCOM to perform the ATWS HC D Gives PCOM a RPV water level band of -60" to -11 O" LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

32

LOC28-NRC-01 Event 7, 8 & 9- Hydraulic-block ATWS Instructor Activities Operator Activities Notes us D Directs PCOP to bypass MSIV and CIG interlocks D Directs PCOP to maximize CRD to drift control rods D Directs PCOM to maintain reactor pressure 800-1050 psig using the main turbine D Contacts WWM for assistance with SBLC ES-158-002 actions are in Event 7A LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

33

LOC28-NRC-01 Event 7A- Control Rod Insertion Instructor Activities Operator Activities Notes Booth Operator When ES-158-002 is requested, Insert KEY 8. Monitor sim SCN count and when complete, perform the first role play and Key 9.

{Key[8]} IRF rfDC102129 f:OPEN d:120 ES-158-002 ARI with 2 min TD

{Key[8]} IRF rfDC102103 f:OPEN d:120 ES-158-002 ARI with 2 min TD When moving on to Div 1 RPS, Insert KEY 9. Monitor sim RF count and perform second role play when complete.

{Key[9]} IRF rfRP158039 f:BYPASS d:120 ES-158-002 Div 1 RPS

{Key[9]} IRF rfRP158040 f:BYPASS d:120 If requested to bypass DIV 2 RPS because the scram cannot be reset, Insert KEY 10. Monitor sim RF count and when complete perform fourth role-play.

{Key[10]} IRF rfRP158041 f:BYPASS d:120 ES-158-002 Div 2 RPS

{Key[10]} IRF rfRP158042 f:BYPASS d:120 IF requested, Insert KEY 11 to reopen CRD charging water isolation valve 146-F034. Monitor sim RF count and report when complete.

{Key[11]} IRF rfRD155017 d:120 f:100 Re-open CRD ch rg wtr isol F034 If directed to X-tie CIG and I/A, Wait 2 minutes, Insert KEY 12 to open 126172 and report when complete

{Key[12]} IRF rfPC125001 f:OPEN X-Tie CIG and I/A PCOM Role Play D Performs hard card for driving control As FUS performing ES-158-002 and ARI is bypassed rods ARI has been disabled. D Dispatch NPO to close charging water Proceeding to RPS Div 1. isolation valve 146F034 to attempt to Role Play restore drive water pressure As FUS performing ES-158- D Opens 146F034 when rods will not 002 and Div 1 RPS is insert bypassed RPS Div 1 has been D Resets Scram when directed bypassed, the scram can D Resets rod drift alarm by depressing be reset at this time. Let ROD DRIFT RESET pushbutton me know if the scram cannot be reset. D Reports when SDV hi-hi level alarm AR-103( 4 )-F02 clears LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 34

LOC28-NRC-01 Event 7A - Control Rod Insertion Instructor Activities Operator Activities Notes PCOM Role Play D When directed, inserts a manual scram As WWM contacted for assistance, acknowledge D Observes control rod motion by AR-request 104-H05, OD?, and 4-rod display D Resets the scram when directed a Role Play second time As FUS performing ES-158- PCOP 002 and Div 2 RPS is D Directs NPO to re-open charging water bypassed RPS Div 2 has been isolation valve 146F034 when scram is bypassed, the scram may reset be reset at this time, ES- us 158-002 section 5.3 is complete D Directs PCO to manually drive control rods D Directs FUS to perform ES-158-002 to defeat ARI and bypass RPS trips D Directs PCO to ensure charging water isolation valve 146F034 is open when the scram is reset D Directs PCOM to insert a manual scram when the SDV is drained D Directs the PCOM to reset the scram after the first attempt fails to fully insert all the control rods Critical Parameter The US should give a Critical Parameter to the PCOM to monitor SDV hi-hi level alarm AR-103( 4 )-F02 and inform the US when the alarm clears.

This scenario will terminate prior to all the control rods being inserted. The scenario should not be terminated until the scram has been reset twice.

The charging water isolation valve 146F034 must be open to be able to have an effective scram. If the student has closed it and does not reopen the valve, they may not be able to clear the alarms.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016

35

LOC28-NRC-01 Event 10 - RFP Trip Instructor Activities Operator Activities Notes Booth Operator Ensure Event Trigger ETLOC28-NRC01-J fires when the scram is reset. Trips the 'A' RFP after a time delay.

PCOM Role Play D Observes and reports AR-101-A10 for As NPO dispatched to 'A' RFP, wait 2 minutes 'A' RFP trip

'A' RFP is coasting down. I D Places the standby RFP in service by don't see any indication of opening the HV-10603C valve, why it tripped.

Manually raising speed on the 'C' RFP Role Play until level is steady, and placing 'C' As WWM contacted for RFP and valves in automatic assistance, acknowledge request PCOP D If directed, uses RCIC to restore level until a RFP is restored by raising speed on the speed controller until the desired injection rate is established us' D Directs PCO to place standby RFP in-service IAW OP-145-005 D Directs PCO to maintain RPV water level -60" to -11 O" using RCIC until Feedwater is restored D May direct using RCIC as the sole injection source if the plant can support D May direct RHR placed in Suppression Pool Cooling Instructor Activity - Termination

~ The scenario may be terminated when RPV water level is stable in the ATWS band, the 'A'

,

RFP has tripped, and the Scram has been reset twice OR at the lead evaluator's discretion.

LOC28-NRC-01 Rev 1 Examination Material 04/14/2016. 36

SUSQUEHANNA LEARNING CENTER TllAM SUSQUEHANNA.

(Jen-n*uJirtM t_:,.t*f'lfow*e SIMULATOR SCENARIO NR Instrument Failure I Loss of Aux Bus 11 B I Loss Of Scenario Title:

Vacuum I ATWS I Failure of CRD and SBLC Scenario Duration: 75 minutes Scenario Number: LOC27-N-03 Revision I Date: 0 I April 20, 2015 PC017 SRO License Course:

PC018 RO License

'{ ,',

,:,:( ,' >::"

,,

Rich Bolduc 04/20/2015 Prepared By:

Instructor Date Reviewed By: GreQ van den Berq 05/06/15 Operations Training Management Date Approved By: Manu Sivaraman 05/06/15 Operations Line Management Date

LOC27-N-03 Rev 0 04/20/2015 Page 2 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 3 of 30 I SCENARIO

SUMMARY

I The scenario begins with a reactor shutdown in progress in preparation for a turbine outage. Reactor power is approximately 23%. Unit 2 is at rated power.

After the crew takes the shift, reactor power is lowered to 20%. At 20% power the Auxiliary Susses are transferred from the Main Generator to Startup Bus 10. After the Auxiliary Susses have been transferred, a Narrow Range Level Instrument begins to fail by slowly drifting low. The crew will respond in accordance with ON-LVL-101 and remove the affected Narrow Range Level Instrument from service.

After actions for the Narrow Range Level Instrument failure are complete, a loss of Auxiliary Bus 11 B occurs. The crew responds to the loss of Auxiliary Bus 11 Bin accordance with ON-AUXBUS-101.

Technical Specifications will be addressed for single recirc loop operation.

After the crew restarts a 2nd condensate pump, an air leak in the Main Condenser develops that causes lowering condenser vacuum. Condenser back pressure will rise and enter the five-minute turbine operation region. This requires the crew to scram the reactor and to trip the turbine within 5 minutes of the low vacuum condition.

When the crew scrams reactor, a failure of RPS and ARI will result in an A TWS. The crew will respond in accordance with the LEVEL/POWER CONTROL EOP including initiation of Standby Liquid Control (SBLC) System, reducing reactor level, and use of alternate control rod insertion methods. SBLC will not inject due to failure of both SBLC pumps.

Attempts to drift control rods using elevated CRD cooling water pressure will not be successful due to a CRD pump trip and a CRD flow control valve failure. Individual control rod insertion can be performed once the CRD pump is started. Due to the symptoms of an electrical ATWS, the crew will prioritize depressurization of the scram air header and removal RPS fuses. After reactor level has been lowered into the prescribed band for the A TWS, a full scram will occur due to either depressurization of the scram air header or removal of RPS fuses.

The scenario is terminated after the crew has transitioned from the LEVEL/POWER CONTROL EOP to the RPV Control EOP and reactor level has been restored to the normal band.

LOC27-N-03 Rev 0 04/20/2015 Page 4 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 5 of 30 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-055 Operations Procedure Program

4. OP-AD-300 Administration of Operations

5. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

6. G0-100-004 Plant Shutdown to Minimum Power

7. OP-156-001 Reactor Manual Control System (RMCS)

8. OP-145-005 Infrequent Manual RFP System Operations

9. OP-103-001 13.8KV Electrical System

10. ON-AUXBUS-101 Loss of/Undervoltage Condition on 13 KV Bus 11A OR 11 B

11. ON-RECIRC-101 Reactor Recirculation Malfunction

12. ON-SCRAM-101 Reactor Scram

13. ON-LVL-101 RPV Level Control System Malfunction

14. ON-143-001 Main Condenser Vacuum and Offgas System off Normal Operation

15. ON-CRD-101 Control Rod Malfunction

16. E0-100-102 RPV Control

17. E0-000-113 Level Power Control

18. EP-RM-004 EAL Classification Levels

19. TS 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation

20. TS 3.4.1 Recirculation Loops Operating

LOC27-N-03 Rev 0 04/20/2015 Page 6 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 7 of 30 I CRITICAL TASKS I

Lowers RPV level to < -60" but > -179" Core damage due to unstable operation can be prevented or at least mitigated by promptly reducing feedwater flow so that level is lowered Safety Significance below the feedwater spargers.

A General Electric Company study (NED0-32047) indicates that the major threat to fuel integrity from A TWS is caused by large-amplitude power/flow Consequences for instabilities. The power oscillations can become large enough to cause Failure To Perform Task melting of fuel in high-power bundles.

Indications/Cues for Event Requiring Critical A TWS with initial reactor power level greater than 5% APRM power.

Task Stop and prevent all injection into the RPV except from RCIC, CRD and SBLC until less than -60". Maintain reactor level in a prescribed band Performance Criteria greater than -179 inches by manually controlling injection rate from Feedwater, HPCI and/or RCIC.

Lowering water level to less than -60" and maintaining it in a prescribed band will result in power level lowering as indicated on the Average Power Range Performance Feedback Monitors.

Inserts control rods IAW E0-100-113 Control rod insertion initiates power reduction immediately.

Safety Significance Failure to insert control rods allows power to remain elevated with resultant Consequences for power oscillations and potential core damage.

Failure To Perform Task Indications/Cues for Exceeding a RPS scram setting and RPS/ARI fail to insert control rods.

Event Requiring Critical Task Insert Control Rods by one or more of the following methods:

Drive control rods after bypassing RWM Performance Criteria 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 Performance Feedback indication for manual insertion of control rods, venting scram air header, or de-energizing RPS solenoids.

LOC27-N-03 Rev 0 04/20/2015 Page 8 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 9 of 30 I SCENARIO MALFUNCTIONS I

Event Description Crew Response Narrow Range Instrument Failure Remove the narrow range instrument from service 3

and determine Technical Specification impact.

Re-energize bus 11 B, respond to recirculation Loss of Auxiliary Bus 11 B pump and condensate pump trips. Restart a 4

condensate pump. Determine Technical Specification impact for single recirculation loco.

Loss of Vacuum Lower power. Scram the reactor and trip the 5 turbine within 5 minutes of entering the low vacuum region.

Scram the Reactor, initiation of SBLC, reducing ATWS due to RPS and ARI Failing 6 reactor level, and use of alternate control rod to Actuate insertion methods.

7 SBLC Fails to Inject Inject boron solution with RCIC CRD Pump Trip and Flow Control 8 Start CRD pump and swap flow control valves Valve Failure ABNORMAL EVENTS I MAJOR TRANSIENTS I TECH SPEC Malfunction Description R Lower Reactor Power by Inserting Control Rods N Transfer Auxiliary Susses AE1 Narrow Range Instrument Failure AE2 Loss of Auxiliary Bus 11 B AE3 Loss of Vacuum MT2 ATWS due to RPS and ARI Failing to Actuate TS1 Narrow Range Instrument Failure TS2 Loss of Auxiliary Bus 11 B

LOC27-N-03 Rev 0 04/20/2015 Page 10 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 11 of 30 I SCENARIO SPECIAL INSTRUCTIONS I

1. Simulator setup

a. Initialize to an exam-specific IC (IC-397). If an exam-specific IC is not available, then setup the simulator as follows:

i) Initialize to IC-263 (20% EOL shutdown).

ii) Place the simulator in RUN.

iii) Raise power to 23%

b. Run SCN file exam\LOC27-N03.scn

2. Verify the following malfunctions/overrides, event triggers and key assi ~ nments:

MF RF OR SCN ET COND 11 :11 1:1 4:4 0:0 4:0 21

3. Prepare the simulator for evaluation

a. Complete a simulator exam checklist, TQ-106-0315

b. Reset ODAs and all Overhead, PPC, HMI and RWM alarms

c. Ensure EOL control rod shutdown sequence is available and marked up to current control rod

d. Ensure the RWM is bypassed.

e. Markup G0-100-004 to step 5.25

4. Prepare a Turnover Sheet including the following:

a. Unit 1 i) A Reactor Shutdown is in progress in preparation for a turbine outage.

ii) Reactor power is approximately 23%.

iii) G0-100-004 is complete through step 5.25 iv) RBCCW Pump "A" is OOS and is not available.

v) The directions to the shift are to:

(1) - Reduce reactor power to 20%

(2) - Transfer the auxiliary busses to the startup transformer

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

LOC27-N-03 Rev 0 04/20/2015 Page 12 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 13 of 30 I SCENARIO FILES I

LOC27-N03.scn ;AUX BUS AUTO TRANSFER PERM TO OFF

Monitored parameters {Key[19]} IRF rfDS003002 f: OFF SCN rat_mp

NR Level C Drifts Low

SET UP FOR ELECTRICAL ATWS {Key[1]) IMF cmfTD04_PDTC321N004C r: 240 I:O f:-15 SCN exam¥LOC27-N03-A

Loss of Aux Bus B

DISABLE FUEL POOL COOLING ALARMS {Key[2]) IOR diHS00012B c: 2 f:TRP IMF annAR016H14 f:ALARM_OFF IMF annAR106A17 f:ALARM_OFF ;Loss of Vacuum

{Key[3]} IMF cmfMV07_HV10742A R:240 I:3 f:8

RBCCW A OOS {Key[3]} IMF cmfMV07_HV10742B R: 240 I:3 f:8 IRF rfDB106275 f :OPEN {Key[3]} IMF cmfMV07_HV10742C R:240 I :3 f:8

{Key[3]} IMF cmfMV07_HV10716 r:240 i :100 f:20

ARI Div 2 fai Is to actuate {Key[3]} IMF cmfMV07_HV10717 r: 240 i :100 f:20 IMF cmfRL01_63X114725D2 {Key[3]} IMF cmfMV07_HV10718 r:240 i :100 f:20 IMF cmfRL01_63X214725D2 {Key[3]} IMF cmfMV07_HV10719 r:240 i :100 f:20

CRD PCV Fai I when Mode Sw to SD ;OPEN CRD F047B aet ETLOC27-N03-1 {Key[4]} IRF rfRD155021 r: 60 f:100

ARI Div 1 power loss on init ; Vent SAH aet ETLOC27-N03-1A {Key[8]} SCN exam¥RDB_VSAH

DEL "B" SLC PP MALF &TRIGGER ; Restore SAH vent aet ETLOC27-N03-2 {Key[9]} SCN exam¥RDB_RSAH

DEL "A" SLC PP MALF &TRIGGER ; Close CRD 146F034 aet ETLOC27-N03-3 {Key [5]} IRF rfRD155017 d: 60 f: 0

OVERRIDE LIGHTS FOR VAC BREAKER AND OG !SOL VLVS ; Pul I Div 1 RPS Fuses IOR doHS10716_1 f: Asls {Key[6]} SCN exam¥RPB_ES158001A IOR doHS10716_2 f:Asls IOR doHS10716A_1 f:OFF ; Pul I Div 2 RPS Fuses IOR doHS10716A_2 f:ON {Key[7]} SCN exam¥RPB_ES158001B IMF annAR121F01 f:ALARM_OFF

Restore Div 2 RPS Fuses

{Key[16]) SCN exam¥RPB_ES158001BR

Restore Div 1 RPS Fuses

{Key[17]} SCN exam¥RPB_ES158001AR

Open GIG X-Tie Valves

{Key[12]} IRF rfPC125001 d:120 f:OPEN

Reset GIG

{Key[13]} SCN exam¥LOC27-N03-E

{Key[22]} IRF crfPM16_1P502B f:RESET

LOC27-N-03 Rev 0 04/20/2015 Page 14 of 30 LOC27-N03-A.scn LOC27-N03-2.et/scn IMF mfRP158003 ; RPS FAIL TO SCRAM ;SWITCH:SBLC MANUAL INITIATION IMF cmfRL03_63X114725D2 ; ARI DIV 2 INITIATION diHSS14804.CurrValue = #OR.diHSS14804.START_A

RELAR FAIL AS IS IMF cmfRL03_63X214725D2; ARI DIV 2 INITIATION RELAR cet ETLOC27-N03-3

FAIL AS IS IMF cmfPM03_1P208A IMF cmfPM03_1P208B d:60 LOC27-N03-E.scn LOC27-N03-3.et/scn IOR diHSM44131PB_Q f:RESET ;SWITCH:SBLC MANUAL INITIATION

+2 MOR diHSM44131PB_Q f:NORM diHSS14804.CurrValue = #OR.diHSS14804.START_B

+2 DOR diHSM44131PB_Q

+2 IOR di1C239RST_Q f:RESET cet ETETLOC27-N03-2

+2 MOR di1C239RST_Q f:NORMAL IMF cmfPM03_1P208B

+2 DOR di1C239RST_Q IMF cmfPM03_1P208A d:60 LOC27-N03-1.et/scn

;SWITCH: MODE SWITCH diHSC72A1S01.CurrValue = #OR.diHSC72A1S01.SHUTDN

FAIL CRD FLOW CONTROL VALVE CLOSED and Trip A CRD Pump IMF cmfAV04_FV146F002A f: O IMF cmfPM03_1P132A LOC27-N03-1 A.et/sen SWITCH:ARI DIV I MAN TRIP (NORM, INIT) diHS147103A1A.CurrValue !=#OR. diHS147103A1A.NORM

ARI DIV 1 LOGIC FUSE OUT IMF cmfFU01_1CB224AFU1

LOC27-N-03 Rev 0 04/20/2015 Page 15 of 30 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 0 Lower Reactor Power by Inserting Control Rods 2 10 Transfer Auxiliary Susses 3 15 Narrow Range Instrument Failure 4 25 Loss of Auxiliary Bus 11 B 5 45 Loss of Vacuum 6 55 A TWS due to RPS and ARI Failing to Actuate 7-8 65 SBLC Fails to Inject/ CRD Pump Trip and Flow Control Valve Failure NIA 75 Termination

LOC27-N-03 Rev 0 04/20/2015 Page 16 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 1 BRIEF DESCRIPTION Lower Reactor Power by Inserting Control Rods INSTRUCTOR ACTIVITY

1. None ROLE PLAY Role play any directed actions as required.

EVALUATOR NOTES

1. None.

LOC27-N-03 Rev 0 04/20/2015 Page 17 of 30 I SCENARIO EVENT FORM I

EVENT 1 BRIEF DESCRIPTION Lower Reactor Power by Inserting Control Rods POSITION TIME STUDENT ACTIVITIES PCOM Insert control rods per the shutdown control rod sequence using continuous insertion to full in accordance with OP-156-001 and OP-AD-338:

Manipulator SELECT control rod. (5.4.3.a)

Verifier CONFIRM correct control rod selected. (5.4.3.b)

Manipulator STATE intended move AND correct control rod number. (5.4.3.c)

Manipulator PLACE fingers adjacent to associated button(s) on reactor benchboard. (5.4.3.d)

Verifier CONFIRM the Manipulator is positioned adjacent to the correct directionalcontrol button(s). (5.4.3.e)

Verifier STATE intended move AND correct control rod number. (5.4.3.f)

Verifier STATES PROCEED. (5.4.3.g)

*Manipulator DEPRESS appropriate button(s) AND OBSERVES directional control lights on reactor benchboard prior to looking at control rod position indication. (5.4.3.h)

AND

Verifier OBSERVE control rod position indication on Standby Information Panel. (5.4.3.i)

Monitor diverse indications:

RPIS / IRMs I APRMs I

Reactor water level I Reactor pressure PCOP Provide verifier checks for control rod movement.

Monitors plant parameters, including CRD parameters us Direct PCOM to perform control rod insertion per the shutdown control rod sequence to 20% power Provide oversight for reactivity manipulation.

LOC27-N-03 Rev 0 04/20/2015 Page 18 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2 BRIEF DESCRIPTION Transfer Auxiliary Susses INSTRUCTOR ACTIVITY

1. None ROLE PLAY

2. As NPO, when requested to to take AUX BUS AUTO TRANSFER PERM TO OFF, wait 1 minute and depress KEY 19 and report completion to the control room.

{Key[19]} IRF rfDS003002 f:OFF Role play any directed actions as required.

EVALUATOR NOTES

1. None

LOC27-N-03 Rev 0 04/20/2015 Page 19 of 30 I SCENARIO EVENT FORM I

EVENT 2 BRIEF DESCRIPTION Transfer Auxiliary Susses POSITION TIME STUDENT ACTIVITIES PCOM Monitors plant parameters PCOP Transfers Auxiliary Susses Startup Bus 10 by performing the following:

Ensure TIE BUS TO BUS 10 BKR OA10303 is CLOSED.

Ensure TIE BUS OA106 ENERGIZED by Observing WHITE LIGHT ILLUMINATED on mimic bus on Panel OC653 OR by Checking TIE BUS OA 106 voltage on voltmeter Xl-00005 is nominally 14KV.

Ensure all synchroscope switches OFF on OC653.

Insert synchronizing key into TIE BUS TO BUS 11A SYNC SEL HS-00021A AND Place switch to ON.

Ensure voltages MATCHED by Observing Diesel Gen Bus Diff Volts XI-00036, < 600 volts OR Compare Aux Bus 11A voltage on voltmeter XI-00009A with TIE BUS OA 106 voltage on voltmeter Xl-00005.

Ensure sources IN PHASE by Observing synchroscope Xl-00037 is at 12 o'clock position+/- 5 minutes.

Close TIE BUS TO BUS 11A BKR 1A10104 by Placing switch to CLOSE AND Hold until BKR 1A 10104 indicates CLOSED.

Observe when switch spring returns to NORMAL, AUX XFMR 11 TO BUS 11A BKR 1A10101 automatically OPENS.

Reset breaker flag for AUX XFMR 11 TO BUS 11A BKR 1A10101 by Placing switch to OPEN.

Return TIE BUS TO BUS 11A SYNC SEL HS-00021A to OFF AND Remove synchronizing key.

Insert synchronizing key into TIE BUS TO BUS 11 B SYNC SEL HS-00021 B AND Place switch to ON.

Ensure voltages MATCHED by Observing Diesel Gen Bus Diff Volts, XI-00036, < 600 volts OR Compare Aux Bus 11 B voltage on voltmeter XI-00009B with TIE BUS OA 106 voltage on voltmeter Xl-00005.

Ensure sources IN PHASE by Observing synchroscope Xl-00037 is at 12 o'clock position +/- 5 minutes.

Close Tl E BUS TO BUS 11 B BKR 1A10204 by Placing switch to CLOSE AND Hold until BKR 1A10204 indicates CLOSED.

Observe when switch spring returns to NORMAL, AUX XFMR 11 TO BUS 11 B BKR 1A 10201 automatically OPENS.

Reset breaker flag for AUX XFMR 11 TO BUS 11 B BKR 1A10201 by Placing switch to OPEN.

Return TIE BUS TO BUS 11 B SYNC SEL HS-00021 B to OFF, AND Remove synchronizing key.

Store synchronizing key in TIE BKR SYNC SEL HS-00018 keylock switch.

At OA10303, Place Auto Transfer Permissive switch HS-101 to OFF us Direct PCOP to transfer Auxiliary Susses Startup Bus 10 IAW OP-103-001

LOC27-N-03 Rev 0 04/20/2015 Page 20 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 3 BRIEF DESCRIPTION Narrow Range Instrument Failure INSTRUCTOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 1 to initiate NR Level C Drifts Low.

{Key[1]} IMF cmfTD04_PDTC321N004C r:240 1:0 f:-15 ROLE PLAY As WWM (or equivalent) contacted for assistance to investigate NR Level C, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None

LOC27-N-03 Rev 0 04/20/2015 Page 21 of 30 I SCENARIO EVENT FORM I

EVENT 3 BRIEF DESCRIPTION Narrow Range Instrument Failure POSITION TIME STUDENT ACTIVITIES Recognize I report:

NR Level indications are drifting TEAM

Determines that NR Level C is malfunctioning .

When NR Level C deviates by greater than 10 inches. It is deselected by ICS.

Monitor plant parameters.

PCOM Executes ON-LVL-101 Section E:

EVALUATE all RPV Level Transmitter inputs:

NRLA (PT C32 1N004A)

NRLB/BB (PT C32 1N004B)

PCOP NRLC (PT C32 1N004C)

UPSETLVL/B (PDT C32 1N017)

Determines that NR Level C is malfunctioning.

PLACES NRLC in MAINTENANCE BYPASS IAW OP-131-003 Enters and direct actions for ON-LVL-101 Section E us Evaluates Technical Specifications and identifies a 7 day LCO for TS 3.3.2.2.A.

INOTES I

LOC27-N-03 Rev 0 04/20/2015 Page 22 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 4 BRIEF DESCRIPTION Loss of Auxiliary Bus 11 B OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 2 to initiate loss of Auxiliary Bus 11 B.

{Key[2]} IOR diHS00012B c:2 f:TRP

2. If the crew is going to restart Cond Pump B, as the NPO when requested to reset the lockout for condensate pump B, wait1 minute and depress KEY 22.

{Key[22]} IRF crfPM16_1P502B f:RESET ROLE PLAY

1. As NPO dispatched to Aux Bus 11 B, wait 2 minutes and report No bus lockout devices are tripped. The lockout for condensate pump B is tripped due to undervoltage from the loss of Aux Bus 11 B.

2. As WWM (or Electrical Maintenance) contacted for assistance with Aux Bus 11 B, wait 5 minutes and report Electrical reports Aux Bus 11 B has checked and has determined that it can be reenergized.

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None.

LOC27-N-03 Rev 0 04/20/2015 Page 23 of 30 I SCENARIO EVENT FORM I

EVENT 4 BRIEF DESCRIPTION Loss of Auxiliary Bus 11 B POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

Loss of Auxiliary Bus 11 B

Trip of Recirculation Pump B

Trip of Condensate Pump B

PCOM Monitor plant parameters.

Executes ON-RECIRC-101, Reactor Recirculation Malfunction Section B

DISPLAY Core Pressure Drop via PPC computer point NJP51 Core PL Press or if PPC unavailable via XR 14301 Point 5, Recirc: Core Plate DP.

DETERMINE actual core flow using Form GO 100 009 2 "Core Flow vs. Core Pressure Drop" curve.

PLOT position on Power/Flow Map .

Concurrently PERFORM G0-100-009.

PERFORM the following:

COMPLY with TRO 3.8.2.1.

PLACE RECIRC B MOV OL BYPS key switch HV-143-F031 B/F032B to TEST

ENSURE Recirc Pump Discharge Bypass valve HV-143-F032B is OPEN:

CLOSE Recirc Pump Discharge Valve HV-143-F031 B

WITHIN 5 minutes, OPEN Recirc Pump Discharge Valve HV-143-F031 B WHEN 2 minutes have elapsed THEN PLACE RECIRC B MOV OL BYPS key switch HV-143-F031B/F032B to NORM.

NOTIFY Shift Supervision to evaluate exiting TRO 3.8.2.1.

LOC27-N-03 Rev 0 04/20/2015 Page 24 of 30

POSITION TIME STUDENT ACTIVITIES PCOP Executes ON-AUXBUS-101 Loss of/Undervoltage Condition on 13 KV Bus 11A OR 11B:

Directs NPO to check for protective relaying and lockouts on Auxiliary Bus 11 B

When directed to restore Auxiliary Bus 11 B, re-energizes Auxiliary Bus 11 B IAW OP-103-001 Closes Breaker 1A10204 to energize Auxiliary Bus 11 B by performing the following:

Ensure TIE BUS OA106 ENERGIZED by Observing WHITE LIGHT ILLUMINATED on mimic bus on Panel OC653 OR by Checking Tl E BUS OA 106 voltage on voltmeter Xl-00005 is nominally 14KV.

Ensure all synchroscope switches OFF on OC653 .

Insert key AND Place TIE BUS TO BUS 11 B SYNC SEL HS-00021 B keyswitch to ON.

Close TIE BUS TO BUS 11 B BKR 1A 10204 by Placing switch to CLOSE.

Observe TIE BUS TO BUS 11 B BKR 1A10204 CLOSES

Return TIE BUS TO BUS 11 B SYNC SEL HS-00021 B to OFF AND Remove key.

Observe UNIT AUX BUS 11 B WHITE LIGHT ILLUMINATED on Panel OC653.

Check AUX BUS 11 B voltage on voltmeter Xl-00009B is nominally 14KV.

Starts a 2nd condensate pump IAW OP-144-001 as follows:

Check Open the selected COND PP SUCT HV-10501

Depress the selected CONDENSATE PUMP START pushbutton

Observe the selected COND PP B(D) DSCH HV -10502 STARTS OPENING within five (5) seconds after Condensate Pump 1P102B(D) starts us Enter ON-AUXBUS-101 Loss of/Undervoltage Condition on 13 KV Bus 11A OR 11 B Directs PCOP to perform ON-AUXBUS-101 Enters ON-REC IRC-101, Reactor Recirculation Malfunction Directs PCOM to perform ON-RECIRC-101 Determine Technical Specification 3.4.1 Condition B applicable for single recirculation loop operations.

When report received that Auxiliary Bus 11 B has been cleared by electrical maintenance to re-energize, directs the PCOP to re-energize Auxiliary Bus 11 B.

When Auxiliary Bus 11 B is reenergized, directs PCOP to start a 2nd condensate pump IAW OP-144-001.

JOTES I

LOC27-N-03 Rev 0 04/20/2015 Page 25 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-03 Rev 0 04/20/2015 Page 26 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 5 BRIEF DESCRIPTION Loss of Vacuum OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 3 to initiate loss of vacuum.

{Key[3]} IMF cmfMV07_HV10742A R:2401:3 f:8

{Key[3]} IMF cmfMV07 _HV107428R:2401:3 f:8

{Key[3]} IMF cmfMV07_HV10742C R:240 1:3 f:8

{Key[3]} IMF cmfMV07_HV10716 r:240 i:100 f:20

{Key[3]} IMF cmfMV07_HV10717 r:240 i:100 f:20

{Key[3]} IMF cmfMV07_HV10718 r:240 i:100 f:20

{Key[3]} IMF cmfMV07_HV10719 r:240 i:100 f:20 ROLE PLAY As NPO dispatched to investigate main condenser vacuum breakers, wait 2 minutes and report:

"The main condenser vacuum breakers appear to be stuck partially open. There does not appear to be 1 ny way to close them "

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None.

LOC27-N-03 Rev 0 04/20/2015 Page 27 of 30 I SCENARIO EVENT FORM I

EVENT 5 BRIEF DESCRIPTION Loss of Vacuum POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

lowering condenser vacuum

main condenser vacuum breakers partially open PCOM Recognizes/reports lowering Main Condenser Vacuum.

Recognizes/reports AR-105-B02, CONDENSER HI PRESSURE.

Reduces reactor power by inserting control rods.

Scrams the reactor and trip the turbine when directed.

PCOP Performs ON-143-001, Main Condenser Vacuum and Offgas System Off-Normal Operation.

Performs Section 3.9 of ON-143-001 for air in leakage Brings up VAC display (backpressure limits) on PPC Monitors and reports backpressure trend Checks Vacuum Breaker position indication and recognizes vacuum breakers are partially open.

At 1C668, Attempts to Close by depressing CLOSE pushbutton HV-10742 A, B, C Cdsr Vac Bkr.

Directs NPO to investigate stuck open vacuum breakers.

Reports when back pressure has entered the Max 5 Minutes of Operation region of the back pressure limit graph.

us Enters ON-143-001, Main Condenser Vacuum and Offgas System Off-Normal Operation.

Directs PCOP to execute ON-143-001 Directs PCOM to lower power by inserting control rods.

Assigns a critical parameter for main condenser vacuum.

When report received that the Max 5 Minutes of Operation region of the back pressure limit graph has been entered, directs the PCOM to scram the reactor and trip the turbine (within 5 minutes of entering Max 5 Minutes region.)

LOC27-N-03 Rev 0 04/20/2015 Page 28 of 30 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENTS 6 BRIEF DESCRIPTION ATWS due to RPS and ARI Failing to Actuate OPERATOR ACTIVITY

1. Ensure Event Trigger ETLOC27-N03-1A initiates when Div 1 of ARI is initiated to cause a logic power failure.

2. Ensure Event Trigger ETLOC27-N03-2 and ETLOC27-N03-2 initiates with SLC Pump A(B) is started to trip the pump immediately, and the standby pump after 1 minutes.

3. When RPV level has been stabilized below -60 inches, and 5 minutes have elapsed since the request for maintenance assistance, perform the Role Play for venting the scram air header.

Depress KEY 8 to vent the scram air header when directed.

{Key[8]} SCN exam\RDB_VSAH

4. When directed, depress KEY 9 to restore from venting the scram air header

{Key[9]} SCN exam\RDB_RSAH ROLE PLAY As NPO sent to investigate CRD PCV, wait 2 minutes and report There is a burnt smell coming from the motor of HV-146-F003 but it looks normal.

f directed to manually operate the PCV, wait 2 minutes and report I can't get the handwheel to move more than 3 turns.

If directed to place the B FCV in-service, depress KEY 4 to place B FCV in-service, wait 2 minutes and report B FCV has been lined up and is ready to be placed in service As WWM directed to investigate the CRD Pump trip, wait 10 minutes and report The A CRD Pump motor has an internal fault and will have to be replaced.

As WWM directed to investigate the A(B) SLC Pump trip, wait 5 minutes and report The A SLC Pump shaft is frozen. I don't know how long it will take to fix. The B SLC pump has an electrical fault and will need to be repaired.

As NPO dispatched to vent the scram air header, wait 2 minutes and report The cap on the Scram Air Header vent line will not come off. I need help from Maintenance.

When directed by Instructor Activity 4, as NPO dispatched to vent the scram air header contact the Control Room and report Maintenance has removed the cap from 147007. We're ready to vent the Unit 1 scram air header.

As FUS contacted to perform ES-158-001, acknowledge the request and take no further action. If contacted for status, report that the Unit 2 TB NPO was dispatched. If the Control Room attempts to contact the Unit 2 TB NPO, do not reply.

Role play any other directed actions as required.

EVALUATOR NOTES Recommended termination point is after the crew has transitioned from the LEVEL/POWER CONTROL

op to the RPV Control EOP and reactor level is being restored to the normal band.

LOC27-N-03 Rev 0 04/20/2015 Page 29 of 30 I SCENARIO EVENT FORM I

EVENTS 6 BRIEF DESCRIPTION ATWS due to RPS and ARI Failing to Actuate POSITION TIME STUDENT ACTIVITIES

TEAM Inserts control rods IAW E0-000-113 Lowers RPV level to < -60" but > -179" PCOM Stops and prevents injection from feedwater.

Establishes injection with feedwater, to maintain -60 to -110.

Attempts to drive control rods per E0-100-113, observes CRD Pump trip.

After the CRD pump B has been started and drive water pressure established, manually inserts control rods in accordance with EO-000-113, sheets 2 Observes all control rods fully inserted when scram air header vented PCOP Initiates ARI and determines that one division has lost power and that the other division has failed to initiate.

Initiates standby liquid control. When selected pump trips, starts the other pump and observes that it also trips.

Inhibits ADS and overrides MSIV isolation Stops and prevents injection from HPCI.

Starts the B CRD pump and recognizes that the FCV is failed closed.

Operates the CRD pressure control valve to obtain sufficient drive pressure for manually driving rods but insufficient for drifting rods.

Directs the NPO to vent the scram air header.

Directs the FUS to pull RPS fuses IAW ES-158-001.

us Enters E0-000-102 and transitions to E0-000-113 for level power control.

Directs PCOP to stop and preventing injection from systems with the exception of CRD, SLC, and RCIC Directs PCOM to stop and preventing injection from feedwater Directs PCOM to maintain reactor level between -60 and -110 When scram air header is vented and all control rods are inserted, transitions to E0-000-102.

Denotes Critical Task

LOC27-N-03 Rev 0 04/20/2015 Page 30 of 30 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

SUSQUEHANNA LEARNING CENTER

._SUSQ~,~.~~~!;!~*

- SIMULATOR SCENARIO APRM Failure / Inadvertent HPCI Initiation I Fault on Bus Scenario Title: 1A201 I Main Steam Leak I LOOP I EOG Failures I HPCI and RCIC Failures Scenario Duration: 75 minutes Scenario Number: LOC27-N-04 Revision I Date: 0 I April 20, 2015 PC017 SRO License Course:

PC018 RO License

' ',, "

' '

Prepared By: Rich Bolduc 04/20/2015 Instructor Date Reviewed By: Greg van den Berg 05/06/15 Operations Training Management Date Approved By: Manu Sivaraman 05/06/15 Operations Line Management Date

LOC27-N-04 Rev 0 04/20/2015 Page 2 of 39 I THIS PAGE 15 INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 3 of 39 I SCENARIO

SUMMARY

I The scenario begins with Unit 1 at approximately 97% power following control rod exercising.

The first activity for the crew will be to raise Reactor power by raising recirculation flow to 100% power.

During the power ascension, an APRM fails upscale and causes a control rod block. The crew will bypass the APRM to clear the rod block. The SRO will review the Technical Specification impact of the failed APRM.

After Technical Specifications have been addressed for the failed APRM, HPCI will inadvertently initiate due to a momentary, spurious start signal. The crew will secure HPCI to prevent uncontrolled injection to the Reactor. The SRO will declare HPCI inoperable and determine the Technical Specification impact.

A report will be received that the HPCI spurious initiation signal to have seen has been corrected and that HPCI can be shut down and placed in a standby lineup. The BOP will shut down HPCI in accordance with the operating procedure and place the system in a standby lineup.

After HPCI has been shut down, an electrical fault will develop on ESS Bus 1A (1A201). This results in the loss of Core Spray pump A, RHR pump A, and RHR loop A Containment Spray ability. The crew will respond per ON-4KV-101, Loss of 4KV Bus, and multiple other off-normal procedures. The crew will cross-tie Instrument Air to Containment Instrument Gas, place RPS Bus A on the alternate supply, reset a half scram and half isolation, and start the 1B CRD pump. The SRO will determine the Technical Specification impact.

Next, a leak will develop from the Main Steam lines into the Turbine Building. The crew will lower Reactor power as time allows and manually scram the Reactor. An MSIV isolation signal will be received on high temperature, however Main Steam Line D will fail to isolate. The crew will manually isolate Main Steam Line D by closing at least one of the two MS IVs.

Once the MSIVs are closed, a loss of all off-site power will occur. Emergency Diesel Generator A is unable to supply its bus due to the earlier fault on 1A201. Emergency Diesel Generator C will start, but then trip. Emergency Diesel Generators B and D will fail to automatically start, but be available to manually start. This will result in momentary Station Blackout conditions until the crew manually starts Emergency Diesel Generator Band/or D. The crew will take actions per ON-LOOP-101, Unit 1 Loss of All Offsite Power.

Reactor water level control will be complicated by failures of HPCI and RCIC. HPCI and RCIC will fail to automatically start. Additionally, the manual initiation pushbuttons for HPCI and RCIC will fail to function correctly. The crew will be able to manually start RCIC and/or HPCI to restore and maintain Reactor water level and assist in controlling Reactor pressure. Reactor pressure control will be complicated by closure of the MS IVs. SRVs will initially be required to control Reactor pressure. The scenario may be terminated when all control rods are inserted, the Main Steam Lines are isolated, at least one ESS Bus is re-energized, Reactor water level is being controlled above -161", and Reactor pressure is being controlled below 1087 psig.

LOC27-N-04 Rev 0 04/20/2015 Page 4 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 5 of 39 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-055 Operations Procedure Program

4. OP-AD-300 Administration of Operations

5. OP-AD-338 Reactivity Manipulations Standards and Communication Requirements

6. G0-100-002 Plant Startup, Heatup and Power Operation

7. OP-156-001 Reactor Manual Control System (RMCS)

8. OP-145-001 RFP and RFP Lube Oil System

9. AR-103-A06 APRM Upscale or INOP Trip

10. AR-103-806 APRM Upscale

11. ON-4KV-101 Loss of 4KV Bus

12. AR-114-E02 HPCI Pump Dsch Lo Flow

13. ON-PWR-101 Reactor Power

14. ON-RPR-101 Rapid Power Reduction

15. ON-SCRAM-101 Reactor Scram

16. E0-000-102 RPV Control

17. ON-LOOP-101 Unit 1 Loss of All Offsite Power

18. EP-RM-004 EAL Classification Levels

19. TS 3.3.1.1 Reactor Protection System (RPS) Instrumentation

20. TS 3.5.1 ECCS - Operating

21. TS 3.8.7 Distribution Systems - Operating

22. TS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling

23. TS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray

LOC27-N-04 Rev 0 04/20/2015 Page 6 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 7 of 39 I CRITICAL TASKS I

Manually isolate a Main Steam Line break.

High energy leakage into the Turbine Building impacts the ability to safely operate the plant. Action is taken to isolate systems that are discharging into the Turbine Building to terminate possible sources of radioactivity release.

Safety Significance Minimizing radioactive release to the Turbine Building also helps accomplish the objective of precluding a radioactive release outside Turbine Building under conditions where Turbine Building integrity cannot be maintained.

Consequences for Failure to take actions to mitigate the energy released to the Turbine Failure To Perform Task Building directly affects the radiation dose to the General Public.

Simplex Fire Detection alarms; room area temperature annunciation; Indications/Cues for feedback from plant personnel.

Event Requiring Critical High radiation annunciation for affected areas/rooms.

Task Other indication of steam line break: lowering steam supply pressure, depressurization of the RPV; level transient on RPV.

Performance Criteria Manually close at least one MSIV in each Main Steam line.

Initiating an isolation of the affected system results in Control Room/PPC indications of lowering area temperatures and radiation levels. Successful Performance Feedback isolation is indicated on Control Room panel by full closed light indication for operated valves.

Restore power to an ESS Bus by manually starting an emergency diesel generator.

Manually starting an emergency diesel generator and re-energizing an ESS Safety Significance bus removes the plant from a Station Blackout.

Continued Station Blackout conditions will lead to a significant challenge to Consequences for fuel cladding, the Reactor coolant system, and the Primary Containment.

Failure To Perform Task Fission product release to the environment is highly likely during a prolonged Station Blackout.

Indications/Cues for AC electrical power is lost to all plant components. No emergency diesel Event Requiring Critical generator is running.

Task Performance Criteria Manually start an emergency diesel generator and re-energize an ESS bus.

Emergency diesel generator speed and electrical output rise. AC power is Performance Feedback restored to multiple plant components.

LOC27-N-04 Rev 0 04/20/2015 Page 8 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 9 of 39 I SCENARIO MALFUNCTIONS I

Event Description Crew Response Bypass APRM; determine Technical Specification 2 APRM Fails Upscale impact Secure HPCI; determine Technical Specification 3 Inadvertent HPCI Initiation impact Cross-tie IA to CIG; restore RPS bus A; reset half Electrical Fault on ESS Bus 1A 5 scram and isolations; start CRD pump B; (1A201) determine Technical Specification impact Main Steam Leak into Turbine 6 Scram the Reactor Building 7 MSIVs Fail to Automatically Close Close MSIVs Respond to multiple equipment losses, including 8 Loss of Offsite Power Feedwater/Condensate EOG C Fails to Start, EDGs B and 9 Start EDG(s) to exit Station Blackout D Fail to Auto-Start HPCI and RCIC Fail to Auto-Initiate 10 and Manual Initiation Pushbuttons Perform manual start of RCIC and/or HPCI Fail ABNORMAL EVENTS I MAJOR TRANSIENTS I TECH SPEC Malfunction Description R Raise Reactor Power with Recirc Flow N Shutdown HPCI and Place in a Standby Lineup AE1 Electrical Fault on ESS Bus 1A (1A201)

AE2 Inadvertent HPCI Initiation MT1 Main Steam Leak into Turbine Building MT2 Loss of Offsite Power TS1 APRM Fails Upscale TS2 Inadvertent HPCI Initiation

LOC27-N-04 Rev 0 04/20/2015 Page 10 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 11 of 39 I SCENARIO SPECIAL INSTRUCTIONS I

1. Simulator setup

a. Initialize to an exam-specific IC (IC-400). If an exam-specific IC is not available, then setup the simulator as follows:

i) Initialize to IC-21. (100% power MOL) ii) Place the simulator in RUN.

iii) Reduce power with Recirc to 97%.

iv) Insert .13 leak on SRV P v) Allow SRV tailpipe temperature to stabilize at 235°

b. Run SCN file exam\LOC27-N04.scn

c. Open trend files rat.tnd.

2. reri::he flllow::: marnct~:s/ol~i:~:evr tri::ra alnd~~~N~sirnments*

3. Prepare the simulator for evaluation

a. Complete a simulator exam checklist, TQ-106-0315

b. Reset ODAs and all Overhead, PPC, HMI and RWM alarms

4. Prepare a Turnover Sheet including the following:

a. Unit 1 i) Reactor power 97% following deep rod exercising.

ii) SRV P is leaking. Tailpipe temperature is approximately 235°F

b. Common i) Unit 2 is at rated power

c. Directions to the shift is to raise power to 100% using recirculation flow per the RMR.

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

LOC27-N-04 Rev 0 04/20/2015 Page 12 of 39 I THIS PAGE 15 INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 13 of 39 I SCENARIO FILES I

LOC27-N04.scn LOC27-N04-M P .sen SCN rat_mp SCN exam\LOC27-N04-MP LOC27-N04-1.et/scn

SWITCH: MAIN STEAM LINE 0 ISOLATION

APRM 1 Fails Upscale diHS141230.CurrValue = #OR.diHS141230.CLS

{Key[l]} IMF mfNM178007A f:12S dmf cmfAV06_HV141F0220

Electrical Fault on ESS Bus lA (1A201)

{Key[2]} IMF cmfEB01_1A201 LOC27-N04-2.et/scn

SWITCH: MAIN STEAM LINE 0 ISOLATION

Xtie IA to CIG diHS141290.CurrValue = #OR.diHS141290.CLS

{Key[12]} !RF rfPC125001 f:OPEN dmf cmfAV06_HV141F0280

Inadvertent HPCI Initiation

{Key[3]} IMF mfHP152004 c:10 LOC27-N04-3.et/scn

Main Steam Leak into Turbine Building ;SWITCH: OG B START BLACK PB

{Key[4]} IMF mfMS183008 r:10:00 f:0.25 diHS00051B.CurrValue = #OR.diHS00051B.RESET

0 MSIVs Fail to Automatically Close OMF mfOG024001B IMF cmfAV06_HV141F0280 f: Asls IMF cmfAV06_HV141F0220 f:Asls LOC27-N04-4.et/scn aet LOC27-N04-1 ;SWITCH:OG 0 START BLACK PB aet LOC27-N04-2 diHS000510.CurrValue = #OR.diHS000510.RESET

O MSIVs Leak to cause slight inventory loss OMF mfOG024001D IMF cmfAV05_HV141F0220 f: S IMF cmfAV05_HV141F0280 f:S LOC27-N04-5.et/scn

Loss of Offsite Power ;LIGHT: MAIN STEAM LINE 0 ISOLATION

EOG C Fails to Start, EOGs B and 0 Fail to (doHS141230_2.CurrValue =

Auto-Start #OR.doHS141230_2.0FF)&&(doHS141290 2.CurrValue aet LOC27-N04-5 = #OR.doHS141290_2.0FF) -

EOG B and O will start with control room PB IMF mfOS003007 d: 30 aet LOC27-N04-3 IMF mfOS003008 d:30 aet LOC27-N04-4 IMF mfOG024008C d:45 IMF mfOG024001B d:30

RCIC and HPCI Fail to Auto-Initiate, IMF mfOG0240010 d: 30 Initiation PBS Fail to ARM IMF annAR015C13 f:ALARM OFF d:30 IMF mfRC150001 IMF annAR015E13 f:ALARM=OFF d:30

{Key[4]} IMF mfHP152002 IMF annAR016C03 f:ALARM_OFF d:30

!OR diHS15012CB f:NORM IMF annAR016E03 f:ALARM_OFF d:30

!OR diHSS15677B f:NORM

LOC27-N-04 Rev 0 04/20/2015 Page 14 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04Rev 0 04/20/2015 Page 15 of 39 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 0 Raise Reactor Power with Recirc Flow 2 10 APRM Fails Upscale 3 15 Inadvertent HPCI Initiation 4 25 Shutdown HPCI and Place in a Standby Lineup 5 40 Electrical Fault on ESS Bus 1A (1A201) 6-7 55 Main Steam Leak into Turbine Building, MSIVs Fail to Automatically Close Loss of Offsite Power, EOG C Fails to Start, EDGs Band D Fail to Auto-Start, 8-10 65 HPCI and RCIC Fail to Auto-Initiate and Manual Initiation Pushbuttons Fail N/A 75 Termination

LOC27-N-04 Rev 0 04/20/2015 Page 16 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 1 BRIEF DESCRIPTION Raise Reactor Power with Recirc Flow INSTRUCTOR ACTIVITY

1. None ROLE PLAY

1. If RxEng contacted for assistance, report Core thermal limits are within our predictions. You may proceed with power ascension.

2. If RxEng contacted for how fast to raise power, report Raise power 1 percent power per minute.

3. As Shift Manager contacted for approval to commence the reactivity manipulation, report The reactivity manipulation may proceed.

Role play any directed actions as required.

EVALUATOR NOTES

1. None.

LOC27-N-04Rev 0 04/20/2015 Page 17 of 39 I SCENARIO EVENT FORM I

EVENT 1 BRIEF DESCRIPTION Raise Reactor Power with Recirc Flow POSITION TIME STUDENT ACTIVITIES PCOM Raises reactor power with recirc flow in accordance with OP-AD-338 ATT. K Per G0-100-012, plots power change on power/flow map Depresses 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)

Monitors diverse indications of reactor power (APRMs, heat balance, Main Generator output) per OP-AD-001 Attachment G Reports power/pressure/level to US following reactivity manipulation PCOP Verifier confirms the correct RRP, Direction, Intended Manipulation as directed by OP-AD-338 us Contacts RE for assistance with raising reactor power using recirc flow Obtains permission from Shift Manager prior to commencing reactivity manipulation Performs Reactivity Brief to raise Reactor power to 100% using recirc flow Performs crew update for commencing reactivity manipulations Directs PCOM to raise reactor power using recirc flow in accordance with RE and OP-AD-338 Directs PCOP to provide peer check to PCOM during power ascension Conducts Crew Update after recirc flow manipulation is complete

LOC27-N-04 Rev 0 04/20/2015 Page 18 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2 BRIEF DESCRIPTION APRM Fails Upscale INSTRUCTOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 1 to initiate event.

{Key[1]} IMF mfNM178007A f:125 ROLE PLAY As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None

LOC27-N-04Rev 0 04/20/2015 Page 19 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2 BRIEF DESCRIPTION APRM Fails Upscale INSTRUCTOR ACTIVITY

2. When directed by Lead Examiner, depress KEY 1 to initiate event.

{Key[1]} IMF mfNM178007A f:125 ROLE PLAY As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

2. None

LOC27-N-04 Rev 0 04/20/2015 Page 20 of 39

SCENARIO EVENT FORM I

EVENT 2 BRIEF DESCRIPTION APRM Fails Upscale POSITION TIME STUDENT ACTIVITIES Recognize I report:

Annunciator AR-103-A06, APRM UPSCALE OR INOP TRIP

Annunciator AR-103-B06, APRM UPSCALE

Annunciator AR-103-C04, RBM UPSCALE OR INOP ROD TEAM BLOCK

Annunciator AR-104-H03, ROD OUT BLOCK

APRM 1 indicates upscale .

Other Reactor power indications indicate normal values .

Execute ARs.

Determine APRM 1 has failed upscale.

PCOM Bypass APRM 1 by moving APRM BYPASS joystick up to CH 1 position.

Monitor plant parameters.

PCOP Ensure execution of ARs.

Determine Technical Specification 3.3.1.1 only requires 3 APRMs, us which allows bypassing of APRM 1.

Direct bypass of APRM 1.

INOTES I

LOC27-N-04Rev 0 04/20/2015 Page 21 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 3 BRIEF DESCRIPTION Inadvertent HPCI Initiation OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 3 to initiate event.

{Key[3]} IMF mfHP152004 c:10 ROLE PLAY As NPO dispatched to investigate HPCI, wait 2 minutes and report:

"There are no abnormal indications in the HPCI room."

If asked as l&C or WWM to investigate the HPCI spurious start, wait 3 minutes, then report:

"HPCI started due to a spurious initiation signal. Recommend shutting down HPCI and placing in a standby lineup. Operations management has concurred with this recommendation" Role play any other directed actions as required.

EVALUATOR NOTES None

LOC27-N-04 Rev 0 04/20/2015 Page 22 of 39 I

I SCENARIO EVENT FORM EVENT 3 BRIEF DESCRIPTION Inadvertent HPCI Initiation POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

AR-114-E02, HPCI PUMP DSCH LO FLOW .

HPCI initiation .

Reactor water level rises (if HPCI injects) .

Reactor power rises (if HPCI injects) .

Drywell pressure and Reactor water level are SAT and HPCI injection is not required.

PCOM Monitor Reactor power and water level.

May reduce Recirculation flow to restore Reactor power.

Perform ON-PWR-101 actions as directed.

PCOP Override HPCI injection:

Ensure HPCI AUXILIARY PUMP 1P213 switch placed to START.

Place HPCI TURBINE FLOW CONTROL FC-E41-1R600 in MANUAL.

Reduce demand to stop HPCI flow .

Will likely maintain HPCI running on min flow during troubleshooting efforts, but may shutdown HPCI per OP-152-001 section 2.10.

us Direct overriding HPCI injection.

Direct action to lower Reactor power, if necessary.

Enter ON-PWR-101.

Declare HPCI inoperable.

Determine Technical Specification 3.5.1 Condition D must be entered (verify RCIC operable immediately, restore HPCI within 14 days.

Determine Technical Specification 3.5.1 Condition E must be entered (due to inop CS A - restore CS A or HPCI within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

LOC27-N-04Rev 0 04/20/2015 Page 23 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 4 BRIEF DESCRIPTION Shutdown HPCI and Place in a Standby Lineup OPERATOR ACTIVITY None ROLE PLAY Role play any other directed actions as required.

EVALUATOR NOTES

LOC27-N-04 Rev 0 04/20/2015 Page 24 of 39

SCENARIO EVENT FORM I

EVENT 4 BRIEF DESCRIPTION Shutdown HPCI and Place in a Standby Lineup POSITION TIME STUDENT ACTIVITIES PCOM Monitor plant parameters during shutdown of HPCI PCOP Shuts down HPCI in accordance with OP-152-001 Section 2.10:

Depress HS-E41-1S17 to RESET Initiation Signal.

Ensure HPCI AUXILIARY OIL PUMP 1P213 switch placed to START.

Ensure following overload bypass switches placed to TEST.

Place HPCI TURBINE FLOW CONTROLLER FC-E41-1R600 in MANUAL.

Manually Reduce HPCI Pump flow (speed) with HPCI TURBINE FLOW CONTROL FC-E41-1 R600 to reduce Turbine speed to

-2200 rpm.

Open HPCI Room Floor Drain Valve 161119.

Check Closed HPCI TEST LINE TO CST isolation valves.

Depress and Maintain HPCI TURB TRIP HS-E41-1S19 pushbutton DEPRESSED.

Ensure HPCI INJECTION HV-155-F006 CLOSES.

Ensure HPCllNJECTION HV-155-F006 CLOSES.

Observe HPCI AUXILIARY OIL PUMP 1P213 STARTS as HPCI Turbine coasts down.

WHEN HPCI TURBINE STEAM SUPPLY HV-155-F001 indicates Fully Closed Release HPCI TURB TRIP pushbutton.

Ensure HPCI STM LINE ORN TO CDSR IB ISO HV-155-F028 OPENS.

Ensure HPCI STM LINE ORN TO CDSR OB ISO HV-155-F029 OPENS.

Ensure HPCI BARO CDSR COND PP DSCH ORN HV-156-F026 Ensure HPCI ROOM UNIT COOLER 1V209A(B) STOPS.

Ensure HPCI L-0 CLG WTR HV-156-F059 CLOSED.

Reset HPCI TURBINE FLOW CONTROL FC-E41-1R600 to 5100 gpm and in AUTO.

AFTER 2 minutes, return overload bypass switches to NORM us Direct PCOP to shutdown HPCI in accordance with OP-152-001.

LOC27-N-04Rev 0 04/20/2015 Page 25 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 5 BRIEF DESCRIPTION Electrical Fault on ESS Bus 1A (1A201)

OPERATOR ACTIVITY

1. After HPCI shutdown and when directed by Lead Examiner, depress KEY 2 to initiate event.

{Key[2]} IMF cmfEB01_1A201

2. When dispatched as NPO to crosstie lntrument Air to CIG, wait 2 minutes, then depress KEY 12:

{Key[12]} IRF rfPC125001 f:OPEN ROLE PLAY If dispatched as NPO to investigate ESS Bus 1A, wait 2 minutes, then report, "The normal supply breaker to ESS Bus 1A tripped on overcurrent."

When dispatched as NPO to crosstie Instrument Air to CIG, wait 2 minutes, then depress KEY 12 as described above and report:

"Instrument Air has been cross-tied to CIG."

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. Recommend moving to the next event once RPS is on the alternate supply, the half scram is reset, RBCW is restored, CRD is restored, and the Technical Specification call is made.

LOC27-N-04 Rev 0 04/20/2015 Page 26 of 39 I

SCENARIO EVENT FORM I

EVENT 4 BRIEF DESCRIPTION Electrical Fault on ESS Bus 1A (1A201)

POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

Annunciator AR-015-A08, 4KV BUS 1A (1A201) LO VOLT/PROT CKT TROUBLE

Annunciator AR-015-D08, 4KV BUS 1A BUS LOCKOUT RELAY TRIP

Annunciator AR-015-D10, DG A SUPPLY BKR TO BUS 1A/2A TRIP

Annunciators AR-109-B02(B09), CORE SPRAY (RHR)

LOOP A OUT OF SERVICE

Half scram .

Loss of ESS Bus 1A PCOM Monitor plant parameters.

Once RPS A is placed on alternate supply, reset half scram by momentarily positioning REACTOR SCRAM RESET HS-C72A-1S05 to GROUP 1/4 position AND THEN to GROUP 2/3 position.

PCOP Execute ON-4KV-101, Loss of 4KV Bus:

Reference Attachment D for automatic actions .

Perform Attachment C.

Crosstie Instrument Air to CIG 90# header in accordance with ON-125-001, Loss of CIG:

0 Dispatch NPO to perform OP-125-001, Containment Instrument Gas System, section 2.8.

Ensure ESW in service to provide cooling to diesel generator in accordance with OP-054-001, ESW System:

0 Start at least one ESW pump.

LOC27-N-04Rev 0 04/20/2015 Page 27 of 39 POSITION TIME STUDENT ACTIVITIES PCOP (cont.)

Start CRD pump B in accordance with ON-CRD-101, Control Rod Malfunction:

0 Close CRD Flow Control Valve FV 146 F002A(B) as follows:

Place CRD Flow Controller FC-C12-1R600 in MANUAL.

Set CRD Flow Controller FC-C 12-1 R600 to 0% DEMAND SIGNAL.

Verify CRD Flow Control Valve FV-146-F002A(B) CLOSED.

0 Start standby CRD Pump 1P132B by placing control switch to RUN position.

0 With CRD Pump 1P132B in operation, Establish system flow - 63 gpm using CRD Flow Controller FC-C12-1 R600.

0 Place CRD Flow Controller FC-C12-1R600 in AUTO.

Transfer RPS bus A to alternate supply and Restore containment isolation in accordance with ON-RPS-101, Loss of RPS:

0 Ensure ALTERNATE A FEED White indicating light ILLUMINATED.

0 Ensure RPS M G SET TRANSFER SWITCH HS-C72B-S1 in NORM position.

0 Place RPS M G SET TRANSFER SWITCH HS-C72B-S1 in ALT A position.

0 Reset the Main Steam Line Rad Monitors at Panel 1C606.

0 Coordinates with ATC to reset A RPS half scram by momentarily positioning REACTOR SCRAM RESET HS-C72A-1 SOS to GROUP 1/4 position AND THEN to GROUP 2/3 position.

0 Depress MN STM LINE DIV 1 ISO RESET HS-B21-1S32.

0 Depress MN STM LINE DIV 2 ISO RESET HS-B21-1S33.

0 Recover from RBCW isolation:

Ensure RRP A CLG WTR OB ISO VALVES HV-18791A1&A2 CLOSED.

Ensure RRP B CLG WTR IB ISO VALVES HV-18792A1&A2 CLOSED.

Depress HV-18791A1&A2 ISOLATION RESET.

Depress HV-18792A1&A2 ISOLATION RESET.

Ensure RRP A CLG WTR OB ISO VALVES HV-18791A1&A2 OPEN.

Ensure RRP B CLG WTR IB ISO VALVES HV-18792A1&A2 OPEN.

Ensure Automatic Actions occurred in accordance with Attachment D.

LOC27-N-04 Rev 0 04/20/2015 Page 28 of 39

POSITION TIME STUDENT ACTIVITIES us Enter ON-4KV-101, Loss of 4KV Bus.

Enter ON-125-001, Loss of Containment Instrument Gas.

Enter ON-CRD-101, Control Rod Malfunction.

Enter ON-RPS-101, Loss of RPS.

Determine Technical Specification 3.8.7 Condition A Required Action 1 is applicable for loss of ESS Bus 1A (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore).

May reference Technical Specifications 3.5.1, 3.6.2.3, and 3.6.2.4.

I NOTES I

LOC27-N-04Rev 0 04/20/2015 Page 29 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04 Rev 0 04/20/2015 Page 30 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENTS 6-7 BRIEF DESCRIPTION Main Steam Leak into Turbine Building, MSIVs Fail to Automatically Close OPERATOR ACTIVITY

1. When directed by Lead Examiner, depress KEY 4 to initiate event, then make first Role Play below.

{Key[4]} IMF mfMS183008 r:10:00 f:0.25

2. When the crew attempts to manually close MSIV(s) in D MSL, ensure the following trigger(s) activate(s) to allow the MSIV(s) to close.

aet LOC27-N04-1 / aet LOC27-N04-2 ROLE PLAY Upon event initiation, call the crew as an NPO in the Turbine Building and report:

"There is a lot of steam in the Turbine Building. It appears to be coming from the vicinity of the Main Steam Tunnel."

If dispatched as NPO to investigate abnormal conditions in the Turbine Building, wait 2 minutes, then report:

"There was elevated temperature and a lot of steam as soon as I got into the Turbine Building. I have exited the building." (if after MSIVs closed, instead report steam seems to be clearing)

If dispatched as NPO/Security to check TB blowout panels, wait 2 minutes, then report:

"No Turbine Building blowout panels have ruptured."

Role play any other directed actions as required.

EVALUATOR NOTES

1. MSIVs may be closed based on Operator standards to backup automatic actions that fail or on guidance in E0-000-102, RPV Control, step RC/L-1.

2. A small amount of leak-by will occur on the D MSL MSIVs even after closure. This is programmed to cause a small Reactor coolant inventory loss, which achieves the desired Reactor water level response to ensure the crew must inject with HPCI and/or RCIC later in the scenario.

3. When both D MSL MSIVs are closed, an automatic event trigger will cause the loss of offsite power that leads to the next event. If desired by Lead Examiner to facilitate scenario completion, this automatic event trigger may be manually forced.

LOC27-N-04Rev 0 04/20/2015 Page 31 of 39 I SCENARIO EVENT FORM I

EVENTS 6-7 BRIEF DESCRIPTION Main Steam Leak into Turbine Building, MSIVs Fail to Automatically Close POSITION TIME STUDENT ACTIVITIES

TEAM Manually isolate a Steam Line break.

TEAM Recognize I report:

Notification of steam in Turbine Building

Rising temperature in Main Steam Tunnel in Turbine Building

Annunciator AR-111-F02, STEAM TUNNEL TURBINE AREA HI TEMP

Annunciators AR-111 (112)-B02, STEAM TUNNEL LOGIC A/C (B/D) HI TEMP

Annunciators AR-111 (112)-B03, MS STM LINE LEAK DETECTION HI TEMP

Annunciators AR-111-D01 (E01 ), MSIV LOGIC A/C (BID)

ISO INITIATED

Failure of Inboard and Outboard MSIVs on Main Steam Line D to close.

PCOM As time I power level permits, perform ON-RPR-101, Rapid Power Reduction:

INSERT Control Rods, as necessary

NOTIFY GCC that the Unit is coming Off Line .

Place the Mode Switch in SHUTDOWN.

Execute scram actions of ON-SCRAM-101, Reactor Scram:

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 .

Check status of MSIVs .

Control Reactor water level between +13" and +54" (+20" to +45" preferred band) using Condensate/Feedwater (prior to LOOP, as time allows), CRD, HPCI and/or RCIC.

May initiate Reactor cooldown.

LOC27-N-04 Rev 0 04/20/2015 Page 32 of 39

POSITION TIME STUDENT ACTIVITIES PCOP Recognize I report D MSIVs fail to close.

Manually close D MSIVs (HV-141-F022D and F028D).

us Enter ON-SCRAM-101, Reactor Scram.

As time/power level allows, direct power reduction for ON-RPR-101, Rapid Power Reduction by initiating #2 Recirc Speed Limiter.

As time allow, directs manual Reactor scram.

May enter E0-000-102, RPV Control, on low Reactor water level and/or high Reactor pressure, as applicable.

Direct closure of MSIVs and Main Steam Line drains.

As time permits, direct Reactor water level controlled +13" to +54"

(+20" to +45" preferred band) using HPCI, RCIC, CRD, SLC, and/or Condensate/Feedwater (while available prior to LOOP).

As time permits, direct Reactor pressure controlled 800-1050 psig using SRVs.

Direct evacuation of the Turbine Building.

I

Denotes Critical Task

LOC27-N-04Rev 0 04/20/2015 Page 33 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

LOC27-N-04 Rev 0 04/20/2015 Page 34 of 39 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENTS 8-10 Loss of Offsite Power, EOG C Fails to Start, EOGs B and 0 Fail to Auto-Start, BRIEF DESCRIPTION HPCI and RCIC Fail to Auto-Initiate and Manual Initiation Pushbuttons Fail OPERATOR ACTIVITY

1. When the crew closes the 0 MSL MSIVs, ensure the following trigger activates to initiate the event (may be manually forced if directed by Lead Examiner).

aet LOC27-N04-5

2. When the crew attempts to manually start EOG Band/or 0, ensure the following trigger(s) activate(s) to allow the EOG(s) to start.

aet LOC27-N04-3 / aet LOC27-N04-4 ROLE PLAY If directed as NPO to check EOG C, wait 2 minutes, then report, "EOG C tripped on overspeed and there appears to be extensive damage to the governor and generator."

If directed as NPO to check EOG 8(0), wait 2 minutes, then report, "EOG B{D) looks fine. It appears that EOG B{D) is in a normal standby condition."

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES

1. The crew may start B and/or 0 EOGs before pulling out procedures due to failed automatic action.

In this case, entry into E0-100-030 may be avoided.

2. Numerous recovery actions are included above for completeness. However, based on the expected progression of the scenario, the crew will not complete all of these recovery actions.

3. Recommended termination criteria:

All control rods inserted.

Main Steam Lines isolated.

At least one ESS bus re-energized.

Reactor water level controlled in assigned band above -161 ".

Reactor pressure controlled below 1087 psig.

LOC27-N-04Rev 0 04/20/2015 Page 35 of 39 I SCENARIO EVENT FORM I

EVENTS 8-10 Loss of Offsite Power, EOG C Fails to Start, EDGs Band D Fail to Auto-Start, BRIEF DESCRIPTION HPCI and RCIC Fail to Auto-Initiate and Manual Initiation Pushbuttons Fail POSITION TIME STUDENT ACTIVITIES

TEAM Restore power to an ESS Bus by manually starting an emergency diesel generator.

TEAM Recognize I report:

Multiple annunciators, including:

0 AR-015-A01, START-UP XFMR 10 TROUBLE 0 AR-015-A02, AUX XFMR 11 TROUBLE 0 AR-015-A07, START-UP XFMR 20 TROUBLE

EOG C starts and then trips .

EDGs B & D do not start .

No cooling to EOG A requiring securing EOG which will result in a loss of all AC power (Station Blackout).

HPCI and RCIC fail to automatically start .

PCOM/PCOP May execute E0-100-030, Unit 1 Response to Station Blackout:

Manually Attempt to Start all Diesel Generators OG501A(B)(C)(D), as follows:

0 At OC653, Place DIG A(B)(C)(D) GOV MODE SEL HS-00055A(B)(C)(D) in ISOCH.

0 To start diesel at OC653, Depress DG A(B)(C)(D)

START HS-00051A(B)(C)(D) pushbutton.

For each Diesel Generator that starts:

0 Observe auto closure of DG A(B)(C)(D) Unit 1 and Unit 2 bus supply breakers.

0 IF any breaker does not auto close and Associated Bus is NOT LOCKED OUT:

Ensure all SYNC SEL switches for bus supply breakers in OFF.

Place DG A(B)(C)(D) SYNC SEL HS-00039A(40A)(41A)(42A) to ON.

Close DG A(B)(C)(D) supply breaker, 1A201-04 (1A202-04) (1A203-04) (1A204-04)

Return DG A(B)(C)(D) SYNC SEL HS-00039A(40A) (41A) (42A) to OFF.

0 Observe ESW PUMP OP504A(B)(C)(D) STARTS in approximately 40(40)(44)(48) seconds.

LOC27-N-04 Rev 0 04/20/2015 Page 36 of 39

POSITION TIME STUDENT ACTIVITIES PCOM/PCOP

For each Diesel Generator that fails to start:

(cont.) 0 Maintain Control Mode Select Switch in Local until directed otherwise, AND 0 Depress Local Emerg Stop for A D Diesel Generators.

Exit this procedure and Enter E0-000-031, if any Diesel Generator is reliably energizing a Unit 1 ESS Bus.

May manually initiate RCIC per OP-150-001 using either manual pushbutton method or component-by-component startup:

If attempts RCIC start using manual pushbutton, recognize I report RCIC initiation pushbutton fails.

Starting RCIC Com12onent-by-Com12onent

Place RCIC TURBINE FLOW CONTROL FC-E51-1 R600 in MANUAL and set for MINIMUM SPEED.

Start RCIC BARO CDSR VACUUM PP 1P219 .

Open RCIC L 0 COOLER WTR SUPPLY HV-150-F046 .

Open STEAM TO RCIC TURBINE HV-150-F045 .

Observe RCIC Turbine accelerate .

When RCIC Pump discharge pressure > 190 psig with flow <

75 gpm, Observe MIN FLOW TO SUPP POOL FV-149-F019 OPENS.

Using RCIC TURBINE FLOW CONTROL FC-E51-1R600, Raise RCIC pump discharge pressure within 50 psig of reactor pressure.

Open RCIC INJECTION HV-149-F013 .

Using RCIC TURBINE FLOW CONTROL FC-E51-1R600, Establish desired flow.

Ensure MIN FLOW TO SUPP POOL FV-149-F019 CLOSES.

When desired flow established:

0 Null RCIC TURBINE FLOW CONTROL FC-E51-1R600.

0 Place RCIC TURBINE FLOW CONTROL FC-E51-1R600 in AUTO.

I

LOC2 t -1'11-\..1-.. ,_

04/20/2015 Page 37 of 39 POSITION TIME STUDENT ACTIVITIES PCOM/PCOP (cont.) As time permits, execute E0-000-031, Station Power Restoration:

Perform section 2.2 .

IF ESSW pumphouse ventilation NOT in service, Perform OP-128-001 Section 2.2 to provide cooling within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Perform following to cool containment:

0 Suppression pool cooling per Step 2.5.

0 Drywell cooling when all ESS busses energized per Step 2.6.

Load diesel generator to extent practical based on priority loading of EOPs OR Attachment A or B of this procedure in accordance with OP-024-001, Diesel Generator.

As time permits, execute ON-LOOP-101, Unit 1 Loss of All Offsite Power:

Ensure proper Diesel Generator operation in accordance with OP-024-001.

IF Diesel Generator A, B or C fail to start, Perform Attachment A to ensure 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months capacity of 250V DC batteries 10650 and 10660.

Ensure ESW Pumps OP504A, B, C, D operating in accordance with OP-054-001 after Diesel Generators start and re-energize Emergency Busses.

On direction of Shift Supervision, Transfer following systems cooling water supply from Service Water to Emergency Service Water in accordance with OP-111-001:

0 Restore Reactor Building Closed Cooling Water in accordance with ON-RBCCW-101 Loss of RBCCW.

Restore Instrument Air System in accordance with ON-118-001 Loss of Instrument Air.

Restore RPS in accordance with ON-RPS-101 Loss of RPl

Check shift of Drywell Cooling from Reactor Building Chille Water to Reactor Building Closed Cooling Water:

RBCCW Supply Viv FV-187710 OPEN .

RBCCW Return Viv FV-18771C OPEN .

Chilled Water Supply Viv to Drywell Coolers FV-187718 CLOSE.

Chilled Water Return Viv from Drywell Coolers FV-1877 CLOSE.

IF desired, Align control switch for Drywell Cooling Wati Control Valves to the RBCCW position at panel 1C279

Ensure following Drywell Cooler Isolation Valves OPEr

A Clrs Clg Wtr OB Isa Valves HV-18781A1&A2 .

A Clrs Gig Wtr 18 lso Valves HV-1878281&82 .

B Clrs Clg Wtr 18 Isa Valves HV-18782A1&A2 .

8 Clrs Clg Wtr OB lso Valves HV-1878181&B2 .

LOC27-N-04 Rev 0 04/20/2015 Page 38 of 39

.

"' POSITION TIME STUDENT ACTIVITIES

"" PCOM/PCOP

Ensure Containment Instrument Gas Isolation valves OPEN:

(cont.)

Instr Gas Cmp OB Suet lso SV-12605 .

Instr Gas to Contn lso SV-12651 .

Restart Control Rod Drive System by starting CRD Pump in accordance with ON-CRD-101, Control Rod Malfunction.

Restore affected systems to desired status in accordance with ON-RPS-001 Loss of RPS.

us Enter ON-LOOP-101, Unit 1 Response to Loss of All Offsite Power.

Direct start of EOG B and/or D.

Direct Reactor water level controlled +13" to +54" (+20" to +45" preferred band) using RCIC and/or HPCI.

Note: UNUSUAL EVENT on EAL FU1 or MU1

LOC27-N-04Rev 0 04/20/2015 Page 39 of 39 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

ML17013A457

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search