Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML15275A365
Person / Time
Site:	Susquehanna
Issue date:	08/11/2015
From:	; Talen Energy
To:	Todd Fish; Operations Branch I
Shared Package
ML15063A453	List: ML15223A033; ML15244A311; ML15244A312; ML15244A314; ML15244A316; ML15244A320; ML15275A362; ML15275A363; ML15275A364; ML15275A365;
References
	TAC U01916
	Download: ML15275A365 (285)
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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

~/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:

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

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

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

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

OO.G0.1178.101 Reva 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.G0.1178.101 Rev 0 4/24/2015 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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 2100 and 2200 exceeds 100°F, actual LiT=104°F

Determines Steam Dome cooldown rate between 2115 and 2215 exceeds 100°F, actual LiT=103°F Evaluator Note:

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

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.G0.1178.101 Rev 0 4/24/2015 Examinee Page 2 of 3 Step Action Standard Eva I Comments 4 Additional calculation and 15 minute cooldown rate Candidate should identify:

excursions

Recirc Loop A i1T °F:

0 2100-2115 i1T=27.0 0 2115-2130 i1T=23.2 0 2130-2145 i1T=23.1 0 2145-2200 i1T=27.3

Recirc Loop A i1T 60 Minute:

0 2100-2200 i1T=100.6

Recirc Loop B i1T °F:

0 2100-2115 i1T=25.3 0 2115-2130 i1T=25.0 0 2130-2145 i1T=23.2 0 2145-2200 i1T=24.2 0 2200-2215 i1T=23.1 0 2330-2345 i1T=23.3

Bottom Head Drain i1T °F:

0 2100-2115 i1T=23.0 0 2115-2130 i1T=27.0 0 2130-2145 i1T=22.0 0 2145-2200 i1T=28.0 0 2330-2345 i1T=24.0

Rx Steam Dome i1T °F:

0 2100-2115 i1T=25.0 0 2115-2130 i1T=26.0 0 2130-2145 i1T=25.0 0 2145-2200 i1T=28.0 0 2200-2215 i1T=24.0 0 2245-2300 i1T=25.0

Rx Steam Dome i1T 60 Minute:

0 2100-2200 i1T=104.0 0 2115-2215 i1T=103.0 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.G0.1178.101 Rev 0 4/24/2015 Examinee Page 3 of 3 Step Action Standard Eva I Comments

5 SR 3.4.10 violation Notifies evaluator that SR 3.4.10 and TS 3.4.10 are applicable for cooldown rate

>100°F/hr EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

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

CONFIDENTIAL Examination Material

EXAM 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 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

CONFIDENTIAL Examination Material

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 S0-100-011for1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

CONFIDENTIAL Examination Material

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:

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

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

OO.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 CONFIDENTIAL Examination Material

OO.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. NU REG 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)

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 00.AD.1032.001 Rev 3 08/05/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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:

N DAP-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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.1032.001Rev3 08/05/2014 Examinee 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.1032.001 Rev 3 08/05/2014 Examinee Page 3 of 3 Step I Action IStandard I Eval I Comments EVALUATOR:

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

CONFIDENTIAL Examination Material

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 grading criteria.

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

JPM Answer Sheet for Examinee Use 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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Review Failed Surveillance Test and Determine Required Action S/RO 51.80.1944.151 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:

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

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

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

51.S0.1944.151 Rev 1 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.S0.1944.151 Rev 1 03/27/2015 Examinee 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.S0.1944.151Rev1 03/27/2015 Examinee 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.S0.1944.151 Rev 1 03/27/2015 Examinee 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?

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.3274.202 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:

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

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

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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.3274.202 Rev 1 03/27/2015 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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. 1and2, 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?

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

PROPOSED BLOCKING CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

PROPOSED BLOCKING KEY DO NOT GIVE TO CANDIDATE Component Position Taq 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

..J. *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 VLV OPEN No tag/Pink tag

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

CONFIDENTIAL Examination Material

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)

Examinee Name:

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

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

OO.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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.3274.201 Rev 1 03/27/2015 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.AD.3274.201 Rev 1 03/27/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAM I NEE 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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

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:

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

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

OO.EP.1132.185 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" CONFIDENTIAL Examination Material

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).

CONFIDENTIAL Examination Material

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

4. 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.

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

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee 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).

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.185 Rev 2 08/08/2014 Examinee 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?

CONFIDENTIAL Examination Material

EXAMINEE 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.

CONFIDENTIAL Examination Material

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 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 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.

CONFIDENTIAL Examination Material

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Emergency Plan communications S/RO 00.EP .1135.001 1 04/24/2015 Simulator Applicability JPM Number Revision Date Setting Generic 2.4.39 3.9/3.8 N y 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 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 15 Validation Time (min)

Examinee Name:

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

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

OO.EP.1135.001Rev1 04/24/2015 Page 2 of 4 JPM REVISION

SUMMARY

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

OO.EP.1135.001Rev1 04/24/2015 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. EP-PS-126, CR E-Plan Communicator (Revision 35)

3. TASK CONDITIONS Review Event Notification Report

4. INITIATING CUE A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

Complete the Emergency Notification Report and communicate it to the offsite agencies.

This is a time critical JPM

5. TASK STANDARD The applicant should obtain appropriate Brief Non-Technical Description (BNTD) sticker and verbally communicate the ENR form to the offsite agencies by utilizing backup telephone numbers within the required 15 minute time frame. The last offsite agency must answer within the 15 minute timeframe.

CONFIDENTIAL Examination Material

OO.AD.3274.201 Rev 1 0312712015 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) NIA loose

5. E-4 (C or 17x22" landscape) NIA loose

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

7. Evaluator cue sheet cue loose

8. JPM jpm loose

9. Procedure (replacement) sim PC CONFIDENTIAL Examination Material

OO.EP.1135.001Rev1 04/24/2015 Page 4 of 4 SIMULATOR SETUP INSTRUCTIONS This JPM requires the use of the E-Plan communications conference lines and phones.

These are located on the STA desk in the simulator. The simulator is not required to be in run to support this JPM. The candidate has access to all of the pertinent data required to complete the task without the aid of the simulator.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1135.001 Rev 1 04/24/2015 Examinee Page 1 of 5 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the simulator due to location of the E-Plan communications equipment. Simulator setup I not required. See Simulator Setup Instructions for further explanation.

Mark-up a copy of EP-PS-001, Attachment I, and Emergency Notification Report (attached) .

Fill in the declaration time as two minutes prior to the current time EVALUATOR NOTE Sign the ENR form under approved section on bottom and fill in the current time as the time approved. (when applicant starts the Admin JPM)

Remind Simulator Booth Operator to NOT answer any of the Notification calls: All communications will be with the evaluator per the evaluator cues.

EVALUATOR CUE Record JPM start time: **TIME CRITICAL**

1 Identifies governing procedure and obtain Obtains controlled copy of EP-PS-126 and controlled copy. ENR form (to be provided).

EVALUATOR NOTE Acting as the Emergency Director *ED), provide the candidate with the marked-up ENR Form. If candidate asks to review the form with the ED, notify candidate that ED is not available, continue with the notifications with ENR.

2 Obtain and review Event Notification Report (ENR) Candidate reviews ENR report form with the Shift Manager/ED EVALUATOR NOTE Pre-printed labels containing the Brief Non-technical Descriptions of the EALs are located in a marked folder in the STA desk drawer.

3 If the Shift Manger has not already done so,

Obtains label for General Emergency obtain a label containing the Brief Non-technical containing the brief Non-technical Descriptions of the EALs and affix the Descriptions of the EALs and description to the ENR form in the space on the

Affix the description to the ENR form in form. the space provided on the form.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1135.001Rev1 04/24/2015 Examinee Page 2 of 5 Step Action Standard Eva I Comments EVALUATOR NOTE The Simulator Booth Operator will not answer the "191" call.

4 Within 15 minutes of declaration, transmit the Using the purple colored phone button, dial ENR form to the offsite agencies (Dialing 191 "191" to transmit the ENR form to the will simultaneously connect the listed agencies following:

in a conference call.) (Dialing 191 will simultaneously connect the listed agencies in a conference call.)

EVALUATOR NOTE The Simulator Booth Operator will not answer the "196" call.

5 The "191" function does not work, attempt to use Using the "196" to transmit the ENR form to conference line "196" the following:

(Dialing 196 will simultaneously connect the listed agencies in a conference call.)

EVALUATOR NOTE The Simulator Booth Operator will not answer the calls. Evaluator will role play as the individual agencies (PEMA, LCEMA, CC EMA) when the backup numbers are dialed.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1135.001Rev1 04/24/2015 Examinee Page 4 of 5 Step Action Standard Eva I Comments

7 Verbally communicate the ENR form to the When the first agency answers the phone, offsite agencies communicates ENR form verbally to the offsite agencies.

Identifies His/her Name.

Call back number

Declaration Time

Event Classification (GE)

Unit-1

"The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel. The unit has been shut down prior to the event and remains shut down. Protective actions will be recommended for the public".

"The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel. The unit has been shut down prior to the event and remains shut down. Protective actions will be recommended for the public".

There is an airborne radiological release in progress due to the event.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1135.001Rev1 04/24/2015 Examinee Page 5 of 5 Step I Action I Standard Eva I Comments EVALUATOR CUE If required(requested by applicant), repeat back applicant message to complete 3 way communication.

Understand that U1 Declared a GE at (T-2min).

"The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel. The unit has been shut down prior to the event and remains shut down. Protective actions will be recommended for the public".

There is an airborne radiological release in progress due to the event.

Your call back# is 570-759-4915 EVALUATOR NOTE Once the applicant has successfully communicated the event to the LAST offsite agency, you may END the JPM.

EVALUATOR CUE Record JPM stop time:

EVALUATOR CUE That completes the JPM.

EVALUATOR NOTE That completes the JPM.

EVALUATOR:

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

CONFIDENTIAL Examination Material

EXAMINEE TASK CONDITIONS Review Event Notification Report INITIATING CUE A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

Complete the Emergency Notification Report and communicate it to the offsite agencies.

This is a time critical JPM CONFIDENTIAL Examination Material

EVALUATOR TASK CONDITIONS Review Event Notification Report INITIATING CUE A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

Complete the Emergency Notification Report and communicate it to the offsite agencies.

This is a time critical JPM CONFIDENTIAL Examination Material

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:

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

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

OO.EP.1132.180 Rev 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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.EP.1132.180 Rev 2 12/04/2014 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

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

EVALUATOR NOTE This is a TIME CRITICAL JPM.

EVALUATOR CUE Record JPM start time:

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

2 Refers to classification matrix. Selects the correct Table.

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

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

5 Documents and communicates the Emergency Announces the following:

Classification.

I am assuming duties of the Emergency Director

[Event] declared based on [EAL summary]

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

CONFIDENTIAL Examination Material

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

8 Initiates an ENR form. Performs the following:

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

Records CR-1 as the control#

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

9 Completes Line 3 of the ENR Performs the following:

*Places checkmark in the correct event box

Places checkmark in the correct unit box

Records declaration time and date

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

Records EAL in Classification Description

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

PERFORMANCE CHECKLIST OO.EP.1132.180 Rev 2 12/04/2014 Examinee Page 3 of 3 Step Action Standard Eva I Comments 11 Completes Line 5 of the ENR Performs the following:

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

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

Records wind direction, wind speed .

Places checkmark in THIS IS A DRILL box

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

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

Communicator.

Provides the approved ENR to the Emergency Plan Communicator.

Reviews the ENR with the Communicator

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

EVALUATOR:

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

CONFIDENTIAL Examination Material

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:

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

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

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.

CONFIDENTIAL Examination Material

55.0N.1998.151Rev2 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, step 5.2 ..

CONFIDENTIAL Examination Material

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 ETEVALSSON1998151 aet ETEVALSSON1998151A sen exam\EVALSSON1998151-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 ETs and Commands per the above CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.101Rev2 04/28/2015 Examinee 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.101Rev2 04/28/2015 Examinee 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.101Rev2 04/28/2015 Examinee Page 3of10 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee 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.

CONFIDENTIAL Examination Material

PERFOklVIANCE CHECKLIST 55.0N.1998.1::>1Rev2 04/28/2015 Examinee 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.101Rev2 04/28/2015 Examinee 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.1!:>1Rev2 04/28/2015 Examinee 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 02-23 INDICATED on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.1!:>1Rev2 04/28/2015 Examinee Page 8 of 10 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 ET550N1998151 fires when control rod 02-27 is at position 46 to drift the control rod in.

Ensure Event Trigger ET550N1998151A 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 1O EVALUATOR CUE Respond per procedure.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 55.0N.1998.151Rev2 04/28/2015 Examinee 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-C 12-1 R600, indicates -63 gpm Cooling Water Flow.

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

CONFIDENTIAL Examination Material

PERFOkMANCE CHECKLIST 55.0N.1998.fo1Rev2 04/28/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAM I NEE 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.

CONFIDENTIAL Examination Material

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.

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

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

CONFIDENTIAL Examination Material

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 W, Awtfifr1 i)L ~ !rt I()tJ, )-

Date dV' '~&:

Instructor

~Li9 lt ~

Date Review Approval 0

~.<

Oat d::Tr~ Supervisor

~/;;~po1~

Date 25 Validation Time (min)

Examinee Name:

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

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

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

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

44.0P.4652.151 Rev 0 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.

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

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

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

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

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

2. REFERENCES A 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)

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 44.0P.4652.151Rev0 06/20/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the simulator. Reset to exam-specific IC-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 LIC-C32-1 R602 is in Manual with a controller output of 0%.

CONFIDENTIAL Examination Material

PERFOt<MANCE CHECKLIST 44.0P.4652.1o1 Rev 0 06/20/2015 Examinee 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).

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 44.0P.4652.101 Rev 0 06/20/2015 Examinee 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."

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 44.0P.4652.151 Rev 0 06/20/2015 Examinee 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 NIA 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?

CONFIDENTIAL Examination Material

EXAMINEE 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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

SUSQUEHANNA NUCLEAR, LLC JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET Task Title Quarterly Turbine Valve Cycling S/RO 93.80.2467.101 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:

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

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

93.S0.2467.101Rev0 04/23/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

93.S0.2467.101 Rev O 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.

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 Main Turbine tripped by candidate upon sustained vibration >10 mils after releasing CV test pushbutton CONFIDENTIAL Examination Material

93.S0.2467.101Rev0 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 93.S0.2467.1U1Rev0 04/23/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

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

Mark-up a copy of S0-193-001 complete through Step 5.3 .

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 S0-193-001, 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 93.S0.2467.101Rev0 04/23/2015 Examinee Page 2 of 4 Step Action Standard Eva I Comments EVALUATOR NOTE The following step is not critical if the test is performed at power levels <85%.

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 VIS/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 NIA; 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 93.S0.2467.1U1Rev0 04/23/2015 Examinee Page 3 of 4 Step Action Standard Eva I Comments EVALUATOR CUE l&C reports test box installed and continuity reading indicates CVTS is OPEN 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-1 S05 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 93.S0.2467.101 Rev 0 04/23/2015 Examinee Page 4 of 4 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?

CONFIDENTIAL Examination Material

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

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.

CONFIDENTIAL Examination Material

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

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.

CONFIDENTIAL Examination Material

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:

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

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

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

SUMMARY

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

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

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 B. Place the Manual Initiation Pushbutton collar back to disarm once Core Spray B has been initiated.

SIMULATOR SETUP INSTRUCTIONS FOR LOC 27 NRC EXAM

3. Reset the simulator to IC 392.

4. Verify conditions above.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.0P.1933.101Rev1 04/23/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the simulator. Reset to exam-specific IC-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 B Initiation signal Applicant:

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

b. Observe Core Spray Loop B INIT SIG RESET HS-E211S17B 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 B MOV OL BYPS HS- Applicant acquires key from below bench E211S128 to TEST position board, inserts key and turns CORE SPRAY LOOP B MOV OL BYPS HS-E211S128 to TEST position CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.0P.1933.101Rev1 04/23/2015 Examinee 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 BIB 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 1P2060 Applicant turns CORE SPRAY PUMP 1P2060 control switch to STOP and returns to AUTO CONFIDENTIAL Examination Material

PERFOklVIANCE CHECKLIST 51.0P.1933.1u1Rev1 04/23/2015 Examinee Page 3 of 4 Step Action Standard Eva I Comments 10 Observes following indications: Observes following indications as applicable:

a. CORE SPRAY LOOP 818 INJ SHUTOFF HV-152F0058 indicates CLOSED and whiter light EXTINGUISHED

b. CORE SPRAY LOOP 8 ACTUATED alarm CLEARED.

c. Core Spray Room Unit Coolers 1V2118 and D STOP indicated on Heating and Ventilation Panel 1C681.

EVALUATOR NOTE Ste12s 2.4.13 and 2.4.14 are NIA. Not being aligned to the CST or Su1212ression 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 8 MOV OL 8YPS HS- After 2 minutes, Place CORE SPRAY LOOP E211S128 to NORM position 8 MOV OL 8YPS HS-E211S128 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 51.0P.1933.1 U1 Rev 1 04/23/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAMINEE 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-E211S168 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.

CONFIDENTIAL Examination Material

EVALUATOR TASK CONDITIONS The plant is operating at 100% power Core Spray Loop 8 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-E211S168 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.

CONFIDENTIAL Examination Material

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:

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

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

49.0N.1869.151Rev3 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.

CONFIDENTIAL Examination Material

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.

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

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

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

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

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

2. REFERENCES A. OP-149-002, RHR Shutdown Cooling (Revision 67)

8. 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.

CONFIDENTIAL Examination Material

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=l00 00:05:02 set ypxfstctwbasin=l 00:05:03 set ypxfsttsprpond=l

c. Run scenario file LOC27 JPM E.SCN

{Key[l]} IMF cmfMV05 HV151F009 c:20 CONFIDENTIAL Examination Material

PERFOt<MANCE CHECKLIST 49.0N.1869.10*1Rev3 04/23/2015 Examinee Page 1 of 5 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

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

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

EVALUATOR CUE Record JPM start time:

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

1 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-E 11-1 S62B RHR LOOP B MOV OL Place keyswitch to TEST BYPS keyswitch to TEST EVALUATOR NOTE Due to RHR conditions (F003B and F047B open and RHRSW and RHR at maximum flow), the only option for lowering temperature is to throttle closed F048B)

4 Operates RHR B to lower reactor coolant Throttle Closed on HV-151-F048B RHR HX temperature B SHELL SIDE BYPS EVALUATOR NOTE Candidate may not place HS-E11-1S62B RHR Loop A MOV OL BYP keyswitch to operate with temperature at 140F.

5 AFTER 2 minutes, Place HS-E11-1S62B RHR AFTER 2 minutes, place keyswitch to LOOP B MOV OL BYPS keyswitch to OPERATE OPERATE CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.101Rev3 04/23/2015 Examinee Page 2 of 5 Step Action Standard Eva I Comments FAULT STATEMENT HV-151-F009, SOC SUCTION OB 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.151Rev3 0412312015 Examinee 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 NIA 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, NIA 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.101Rev3 04/23/2015 Examinee Page 4 of 5 Step Action Standard Eva I Comments 16 Reset PCIS isolation logic Performs the following

Depress HS-B21-1 S32 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-E 11-1 S32B 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-B21-1 S37B, 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 NIA

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 49.0N.1869.151 Rev 3 04/23/2015 Examinee Page 5 of 5 Step Action Standard Eva I Comments

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 .

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-FOO?B was previously closed forthe SOC lineup. The breakerforthe valve is open.

25 Place MOV controls in NORM

Place HS E11 1S628, RHR LOOP B MOVS OL BYPS in NORM.

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

Place HS 821 1S37B, DC MOV OL BYPS 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?

CONFIDENTIAL Examination Material

EXAM I NEE 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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

SUSQUEHANNA NUCLEAR , LLC 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:

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

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

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

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

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 1B in service and secure RBCCW Pump 1A due to high vibrations.

In accordance with OP-144-001, 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.

CONFIDENTIAL Examination Material

14.0P.1335.150 Rev 0 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 rwpi 11306b ,, ,RBCCW PP 1B 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 14.0P.1335.100 Rev 0 04/23/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the simulator. Reset to exam-specific IC-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.

CONFIDENTIAL Examination Material

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

5 Stops RBCCW Pump 1A. Depress RBCCW PUMP 1P210A 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.

CONFIDENTIAL Examination Material

PERFOt<MANCE CHECKLIST 14.0P.1335.100 Rev 0 0412312015 Examinee Page 3 of 4 Step Action J Standard J Eval Comments FAULT STATEMENT THE ALTERNATE PUMP (1 B) 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 NIA 10 Monitor Reactor Recirc Pump temperatures Monitor Reactor Recirc Pump Motor Bearing and Seal Cavity Temperatures on TRSH-B31-1R601.

BACK PANEL - Recirc Tem12 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:

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 14.0P.1335.100 Rev 0 04/23/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAM I NEE 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-144-001, section 2.2.

CONFIDENTIAL Examination Material

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 1B in service and secure RBCCW Pump 1A due to high vibrations.

In accordance with OP-144-001, section 2.2.

CONFIDENTIAL Examination Material

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:

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

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

72.0N.1786.151 Rev O 01/08/2015 Page 2 of 4 JPM REVISION

SUMMARY

Revision Description/Purpose of Revision 0 NewJPM CONFIDENTIAL Examination Material

72.0N.1786.151 Rev 0 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 CONFIDENTIAL Examination Material

72.0N.1786.151 Rev 0 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_PV10701B 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 CONFIDENTIAL Examination Material

PERFOt<MANCE CHECKLIST 72.0N.1786.1o1 Rev 0 01/08/2015 Examinee Page 1 of 4 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

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

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

EVALUATOR 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 72.0N.1786.101Rev0 01/08/2015 Examinee 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 107018 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 72.0N.1786.151Rev0 01/08/2015 Examinee 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 NIA 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 NIA 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 CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 72.0N.1786.101 Reva 01/08/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAMINEE 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 CONFIDENTIAL Examination Material

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 ARE SD signal is clear.

INITIATING CUE Restore the Offgas System IAW ON-143-001, step 3.6.7 CONFIDENTIAL Examination Material

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 05110/2015 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:

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

Evaluation Result: D Satisfactory D Unsatisfactory Evaluator Name Signature Comments CONFIDENTIAL Examination Material LOC26 NRC X

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 78.0P.3677.1 U1 Rev 4 02/18/2015 Examinee Page 1 of 3 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the simulator. Reset to exam-specific IC-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 5 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."

6 Verifies APRM 3 bypassed Confirms all four 2/4 voters, BYPASSED LEDs for bypassed APRM are illuminated

7 Adjust the display to the proper screen Press ETC button to display ENTER SET MODE

8 Accept the proper display screen Press ENTER SET MODE key

9 Enter the password Enter password "1234" and press ENT CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 78.0P.3677.1U1 Rev 4 02/18/2015 Examinee Page 2 of 3 Step Action Standard Eva I Comments

10 Select proper indication to change Using the cursor keys, highlight the APRM GAIN

11 Setup display for gain adjustment

Press SET PARAMETERS key

Verify APRM indicates SET PARAMETERS: APRM GAIN

12 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 Ui)

CURSOR keys to scroll

Press the ACCEPT key

13 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 14 Exit the setup displays

Press EXIT key

Press EXIT SET MODE key

Press YES key 15 Confirms APRM 3 display indicates OPERATE Confirms APRM upper display section indicates OPERATE on top right corner of display 16 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.

EVALUATOR CUE Record JPM stop time:

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 78.0P.3677.101 Rev4 02/18/2015 Examinee Page 3 of 3 Step I Action I Standard I Eval I Comments EVALUATOR CUE That completes the JPM.

EVALUATOR:

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

CONFIDENTIAL Examination Material

EXAM INEE 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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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:

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

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

OO.E0.1996.202 Rev 1 02/18/2015 Page 2 of 3 JPM REVISION

SUMMARY

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

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.E0.1996.202Rev1 02/18/2015 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST OO.E0.1996.202Rev1 02/18/2015 Examinee 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?

CONFIDENTIAL Examination Material

EXAM I NEE 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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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:

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

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

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 CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.E0.2567.0uJ Rev 1 04/18/2015 Examinee Page 1 of 2 Step Action Standard Eva I Comments EVALUATOR INSTRUCTIONS

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

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

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

This JPM must be performed in the plant. Obtain Shift Manager Authorization to proceed .

Mark-up a copy of ES-250-003 complete through Step 4.3 .

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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 50.E0.2567.0u.:l Rev 1 04/18/2015 Examinee 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 VL V (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?

CONFIDENTIAL Examination Material

EXAM INEE 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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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/2 va1idat}ra ttk£

-~yr-~'a~~-~ &ko-1{)_()/~

Author Date Instructor Date Approval 7 /J-0 la-(),~

OperIOilSi\ianagement date Date 20 Validation Time (min)

Examinee Name:

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

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

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 Manu Sivaraman Greg van den Berg 07/20/2015 Operations Management Nuclear Training Supervisor Date 20 Validation Time (min)

Examinee Name:

Last, First Ml Employee Number Exam Date: -------

Exam Duration (Min) - - - - - - -

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

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 CONFIDENTIAL Examination Material

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'.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee 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.

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee 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 DG A Master Trip Circuit Reset Amber Observes DG A Master Trip Circuit Reset light Illuminates. Amber light Illuminated.

EVALUATOR CUE Amber light is lit.

12 Observe DG A Master Trip Circuit Tripped Green Observes DG 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 DW pressure.

EVALUATOR CUE High DW pressure condition still present.

No further DG manipulations required.

EVALUATOR CUE Record JPM stop time:

CONFIDENTIAL Examination Material

PERFORMANCE CHECKLIST 24.0P.1443.051 Rev 1 06/25/2015 Examinee Page 5 of 5

)

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?

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

SUSQUEHANNA LEARNING CENTER

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SIMULATOR SCENARIO Uncoupled Control Rod I Control Rod Drop I Fuel Failure Scenario

Title:

Max Safe Rad in Two Areas/ Emergency Depressurization Scenario Duration: 75 minutes Scenario Number: LOC27-N-02 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 CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 2 of 34 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 3 of 34 I SCENARIO

SUMMARY

I The scenario begins with a reactor startup in progress following a refueling outage. Reactor power is approximately 3%. Unit 2 is at rated power.

After the crew takes the shift, the steam jet air injectors are placed in service and mechanical vacuum pump is secured. After the steam jet air injectors are in-service, control rods are withdrawn in preparation for placing the mode switch in RUN.

While withdrawing control rods, an uncoupled rod is discovered. An attempt to re-couple the rod in accordance with ON-CRD-101 is unsuccessful. When the crew prepares to fully insert the mechanism for the uncoupled control rod, a critical fault of Rod Worth Minimizer (RWM) occurs blocking all control rod motion. Technical Specifications are addressed for the uncoupled control rod and RWM.

While the crew is preparing to bypass the RWM, the blade for the uncoupled control rod drops causing a reactor power spike exceeding the IRM/APRM auto scram setpoints. The reactor fails to scram requiring the crew to manually scram the reactor.

The power spike from the control rod drop causes a fuel failure. Main steam line high radiation will require the crew to close MSIVs and steam line drains in accordance with ON-179-001.

Following the scram, the Scram Discharge Volume (SDV) vent and drain valves fail to close. When the SDIV vent and drain valves fail to close, due to the fuel failure, radioactive steam will be released to the reactor building causing a high radiation condition requiring secondary containment control EOP actions. Attempts to reset RPS to isolate the reactor coolant leak will be unsuccessful.

After initial actions for the steam leak from the SDIV are initiated, a pipe break in the Reactor Water Cleanup system will occur causing area high temperatures and high radiation levels. The Reactor Water Cleanup (RWCU) will fail to auto isolate. When an attempt is made to manually isolate RWCU, the isolation valves will bind in mid-position and fail to close. The loss of coolant from RWCU break will require additional makeup from available injection systems.

The high radiation from the SDIV steam leak combined with the high radiation in the RWCU area will exceed maximum safe radiation levels into areas requiring emergency depressurization in accordance with the Secondary Containment Control EOP.

The scenario is terminated following emergency depressurization when reactor level and pressure have been stabilized.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 4 of 34 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 5 of 34 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. AR-104-H06 Rod Overtravel

9. ON-CRD-101 Control Rod Malfunction

10. ON-SCRAM-101 Reactor Scram

11. ON-179-001 Increasing Offgas I MSL Rad Levels

12. AR-101-F01 RWCU HI FLOW ISOLATION

13. AR-101-A04 RWCU SYSTEM PRE-ISOLATION HI TEMP/HI DIFF TEMP

14. AR-101-A02 RWCU LEAK DET ISO LOGIC A HI TEMP

15. AR-101-A03 RWCU LEAK DET ISO LOGIC B HI TEMP

16. E0-000-102 RPV Control

17. E0-000-104 Secondary Containment Control

18. E0-000-112 Emergency Depressurization

19. EP-RM-004 EAL Classification Levels

20. TS 3.1.3.c Control Rod Coupling

21. TS 3.3.2.1.c Bypassing Rod Worth Minimizer CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 6 of 34 I THIS PAGE IS INTENTIONALLY LEFT BLANK I

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 7 of 34 I CRITICAL TASKS I

Recognize a failure to scram condition and initiate a manual scram within 60 seconds from the time that a neutron monitoring RPS setpoint is exceeded.

Control rod insertion initiates power reduction immediately Safety Significance Failure to insert control rods allows power to remain elevated with the Consequences for potential for core damage.

Failure To Perform Task Indications/Cues for Exceeding a RPS scram setting and RPS fails to fully insert all control rods.

Event Requiring Critical Task Initiate a manual scram within 60 seconds from the time that an RPS scram Performance Criteria setting is exceeded.

Successful insertion of control rods will be indicated by rod position full in Performance Feedback indication following manual initiation of a scram.

Perform Emergency Depressurization when Two Secondary Containment areas exceed maximum safe radiation levels with a Primary System discharging into Secondary Containment.

Action is taken to isolate systems that are discharging into secondary containment to terminate possible sources of radioactivity release.

Minimizing radioactive release to secondary containment also helps accomplish the objective of precluding a radioactive release outside Safety Significance secondary containment under conditions where secondary containment integrity cannot be maintained. Previous containment control actions have not, for whatever reason, mitigated the event and now potentially large areas of the secondary containment have been challenged.

The criteria of "2 or more areas" identifies the increase in radiation trend as a wide spread problem which may pose a direct and immediate threat to Consequences for secondary containment integrity, equipment located in the secondary Failure To Perform Task containment, or continued safe operation of the plant.

Indications/Cues for Plant Process Computer formats indicating radiation values greater than Event Requiring Critical Max Safer values.

Task Perform a Emergency Depressurization per E0-000-112 when two or more RB areas exceed max safe radiation per E0-000-104 Table 9 (10 R/hr for Performance Criteria all areas)

Initiating an emergency depressurization causes Reactor pressure to lower which lowers the driving force of any primary system breach.

Performance Feedback Verify ADS valves are open using light red light indication, acoustic monitoring and lowering Reactor pressure and rising reactor water level.

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CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 9 of 34 I SCENARIO MALFUNCTIONS I

Event Description Crew Response Inserts control rod to attempt to re-couple the rod IAW ON-CRD-101. The control rod does not re-3 Uncoupled Control Rod couple. The SRO will address Technical Specifications for the uncoupled control rod.

Bypass the RWM. The SRO will address Technical 4 Rod Worth Minimizer Failure Specifications for the inoperative RWM.

Reactor power spike exceeds the IRM/APRM auto 5 Control Rod Drop scram setpoints. The reactor fails to scram requiring the ATC to insert a manual scram.

6 Fuel Failure Scram the Reactor SDIV Vent and Drain Valves Fail to Mitigate leak by taking actions for Secondary 7

Close Containment Control Reactor Water Cleanup Pipe Break 8 Attempt manual isolation of RWCU Without Auto Isolation Perform Emergency Depressurization when Two Reactor Water Cleanup Isolation 9 Secondary Containment areas exceed maximum Valves Fail to Close safe radiation levels ABNORMAL EVENTS I MAJOR TRANSIENTS I TECH SPEC Malfunction Description N Place Off Gas in Service R Raise Reactor Power by Withdrawing Control Rods AE1 Uncoupled Control Rod AE2 Rod Worth Minimizer Failure MT SDIV Vent and Drain Valves Fail to Close TS1 Uncoupled Control Rod TS2 Rod Worth Minimizer Failure CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 11 of 34 I SCENARIO SPECIAL INSTRUCTIONS I

1. Simulator setup

a. Initialize to an exam-specific IC (IC-394). If an exam-specific IC is not available, then setup the simulator as follows:

i) Initialize to IC-12.

ii) Place the simulator in RUN.

iii) Insert steps 317 and 318 iv) Run SCN file exam\LOC27-N02.scn v) Withdraw CRDMs from step 317 to above step 332, but before withdrawing rod 14-07 (blades are stuck and uncoupled) vi) Perform actions to prepare for transferring from MVP to OG OP-172-001 2.1.22

b. Run SCN file exam\LOC27-N02.scn

2. Verify the following malfunctions/overrides, event triaaers and key assig nments:

MF RF OR SCN ET COND 53:53 2:2 1:1 0:0 3:0 6

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 startup control rod sequence is available and marked up to current control rod

d. Ensure the RWM is initialized and the rod block annunciator is clear.

e. Ensure two copies of the control rod pull sheet are available.

f. Fill out an S0-156-007 for current rod pattern

g. Fill out an OP-172-001to2.1.22

4. Prepare a Turnover Sheet including the following:

a. Unit 1 i) A Reactor Startup is in progress following a refueling outage.

ii) The Reactor Mode Switch is in Startup.

iii) Reactor power is approximately 3% with the IRMs on Range 9.

iv) Reactor Pressure is 940 psig with 1/4 bypass valve open.

v) G0-100-002 is complete to step 5.59.2 vi) Main condenser back pressure has lowered to allow placing Off Gas in service.

vii) The Off Gas system is prepared for placing SJAE in-service.

viii) The directions to the shift are to:

(1) - Place Off Gas in service IAW OP-172-001 starting at step 2.1.22.

(2) - Secure the Mechanical Vacuum Pump (3) - Continue the reactor startup

b. Common (1) Unit 2 is at rated power

5. Document training participation and feedback

a. Ensure all present have signed Security Agreements per NUREG-1021 and TQ-104-0306

b. Show the crew that the Evaluators and Booth Operators are qualified

c. Complete an Operator Fundamental Score Card CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 13 of 34 LOC27-N02.scn

Monitored parameters SCN rat_mp LOC27-N-02 SETUP.sen SCN exam\LOC27-N02-MP ;Reset to IC 12 SCN exam\LOC27-N02-MP1 ;Insert steps 317 and 318

RUN seen then withdraw mechs from step 317 to

RWCU F001/F004 auto-isol failure and valve 332 binding IMF mfRD1550061851 f: Asis IMF cmfMV09_HV144F001 f:80 IMF mfRD1550071851 IMF cmfMV09_HV144F004 f :80 IMF mfRD1550064251 f:Asis IMF cmfMV06_HV144F004 IMF mfRD1550074251 IMF cmfMV06_HV144F001 IMF mfRD1550064211 f:Asis IMF mfRD1550074211

RWCU F100/F102/Fl06 valve binding IMF mfRD1550061811 f: Asis IMF cmfMV09_HV144F100 f :80 IMF mf RD1550071811 IMF cmfMV09_HV144F102 f:80 IMF mfRD1550061407 f:Asis IMF cmfMV09_HV144F106 f:80 IMF mfRD1550071407 IMF mfRD1550064655 f:Asis

DISABLE FUEL POOL COOLING ALARMS IMF mfRD1550074655 IMF annAR016H14 f: ALARM_OFF IMF mfRD1550064607 f:Asis IMF annAR106Al7 f:ALARM_OFF IMF mfRD1550074607 IMF mfRD1550061455 f:Asis

{Key[l]} sen exam\LOC27-N02-INOP RWM IMF mfRD1550071455 IMF mfRD1550060647 f:Asis

{Key[2]} sen exam\LOC27-N02-Delete Stuck Rods IMF mfRD1550070647

{Key[2]} sen exam\LOC27-N02-NM Spike IMF mfRD1550065415 f:Asis IMF mfRD1550075415

Bypass AUTO Scram IMF mfRD1550065447 f: Asis IRF rfRP158039 f:BYPASS IMF mfRD1550075447 IRF rfRP158040 f:BYPASS IMF mfRD1550060615 f:Asis IMF mfRD1550070615

Restore Auto scram when MS in SD IMF mfRD1550060227 f: Asis AET ETLOC27-N02-1 IMF mfRD1550070227 IMF mfRD1550065835 f:Asis

Initiates Fuel Failure and SDV rad from leak IMF mfRD1550075835 when MS in SD IMF mfRD1550062603 f: Asis aet ETLOC27-N02-2 IMF mfRD1550072603 IMF mfRD1550063459 f:Asis

MSL rads lower after isolation IMF mfRD1550073459 aet ETLOC27-N02-3 LOC27-N-02-A.scn

SDV drain valves stuck open IMF mfRR179003 f: 10 IMF mfRD155018 IMF cmfTR02_RIT13705 r:480 f:1000 IMF cmfTR02_RIT13706 d:20 r:480 f:1000

RPS reset HS failed IMF cmfTR02_RIT13750 d: 440 r:480 f:13.32 IOR diHSC72AlS05 f:NORM IMF cmfTR02_RIT13751 d:460 r:480 f:12.24

Initiate RWCU Leak AND Rads +120 IMF mfRM179004A r: 60 f:12048

{Key[3]} sen exam\LOC27-N02-B IMF mfRM179004B r:60 f:13589 IMF mfRM179004C r:60 f:11048

Local evacuation IMF mfRM179004D r: 60 f:12048

{Key[10]} SCN exam\LOCAL_EVAC_ALARM

+60 MMF mfRM179004A r:300 f:14048

ADS keylock switches MMF mfRM179004B r: 300 f:15589

{Key[ll]} SCN exam\ADB_ADSKEYS MMF mfRM179004C r:300 f:12048 MMF mfRM179004D r:300 f:14048 LOC27-N-02-B.scn IMF cmfTR02_RIT13708 r:60 f:100 IMF cmfTR02_RIT13752 d:60 r:240 f:lS IMF mfCU161007 r:270 f:50 CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 14 of 34

'.OC27-N-02-Delete Stuck Rods.sen !RF rfRP158039 f:NORM

~F mfRM179004D r:300 f:14048 !RF rfRP158040 f:NORM DMF mfRD1550061407 DMF mfRD1550060647 ETLOC27-N02-2 et/sen DMF mfRD1550060615 ;SWITCH:MODE SWITCH DMF mfRD1550060227 diHSC72AlS01.CurrValue =

DMF mfRD1550061455 #OR.diHSC72AlS01.SHUTDNSCN exam\LOC27-N02-A DMF mfRD1550061811 ;RAISE CRD RADS DMF mfRD1550061851 DMF mfRD1550062603 ETLOC27-N02-3 et/sen DMF mfRD1550063459 ;SWITCH:MAIN STEAM LINE A ISOLATION DMF mfRD1550064211 diHS14123A.CurrValue = #OR.diHS14123A.CLS DMF mfRD1550064251 abort exam\LOC27-N02-A DMF mfRD1550064607 MMF mfRM179004A r:30 f:1204 DMF mfRD1550064655 MMF mfRM179004B r:30 f:1358 DMF mfRD1550065415 MMF mfRM179004C r:30 f:1104 DMF mfRD1550065447 MMF mfRM179004D r:30 f:1204 DMF mfRD1550065835 LOC27-N-02-INOP RWM.scn

!OR diHSC12J600NM c:l f:BYPASS

!OR diHSC12J600Sl f:OFF LOC27-N-02-NM Spike.sen IMF mfNM178004A c:2 r:2 f:125 IMF mfNM178004B c:2 r:2 f:125 IMF mfNM178004C c:2 r:2 f:125 IMF mfNM178004D c:2 r:2 f:125 IMF mfNM178004E c:2 r:2 f:125 MF mfNM178004F c:2 r:2 f:125

_MF mfNM178004G c:2 r:2 f:125 IMF mfNM178004H c:2 r:2 f:125 IMF mfNM178007A c:2 r:l f:21 IMF mfNM178007B c:2 r:l f:21 IMF mfNM178007C c:2 r:l f:21 IMF mfNM178007D c:2 r:l f:21 IMF mfNM178002A c:2 r:l f:2000 IMF mfNM178002B c:2 r:l f:2000 IMF mfNM178002C c:2 r:l f:2000 IMF mfNM178002D c:2 r:l f:2000 ETLOC27-N02-1 et/sen

SWITCH: MODE SWITCH TO SD diHSC72AlS01.CurrValue =

OR.diHSC72AlS01.SHUTDN CONFIDENTIAL Examination Material

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LOC27-N-02 Rev 0 04/20/2015 Page 16 of 34 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 NIA 0 Crew assumes shift 1 5 Place Off Gas in Service 2 10 Raise Reactor Power by Withdrawing Control Rods 3-4 20 Uncoupled Control Rod/ Rod Worth Minimizer Failure 5 40 Control Rod Drop 6 45 Fuel Failure 7 50 SDIV Vent and Drain Valves Fail to Close Reactor Water Cleanup Pipe Break Without Auto Isolation/ Isolation Valves 8-9 65 Fail to Close NIA 75 Termination CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 17 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 1 BRIEF DESCRIPTION Place Off Gas in Service INSTRUCTOR ACTIVITY

1. None ROLE PLAY

1. When requested to perform the below local operations for placing off gas in service, wait 2 minutes and report, "The local operations for placing off gas in service are complete."

Place TIC-16937 Offgas Reb Inlet Temp Ctlr in AUTO SET AT 270°F.

Place TV-16937 Preheater Steam Bleed Control to AUTO.

Using PIC-16984 Motive Stm Jet In Offgas Press in MANUAL, Adjust PV-16984 Motive Stm Jet In Offgas to- -4.8 psig on PIC-16984.

WHEN, Motive Stm Jet In Offgas Press stable at- -4.8 psig on PIC-16984, THEN Place PIC-16984 in AUTO SET AT -4.8 psig.

Role play any directed actions as required.

EVALUATOR NOTES

1. None CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 18 of 34 I

SCENARIO EVENT FORM I

EVENT 1 BRIEF DESCRIPTION Place Off Gas in Service POSITION TIME STUDENT ACTIVITIES PCOP Places Off Gas in service in accordance with OP-172-001 as follows:

Place steam jet air ejector in service as follows:

Ensure Unit 1 Recombiner offgas isolation signal not present by observing Unit 1 Offgas Permissive White Light ILLUMINATED.

At Control Panel 1 C668:

Open HV-10722 SJAE Sup Pri Eject Isa .

Check pressure on Pl-10701 SJAE Stm Sup Press 110-130 psig.

At 1C668 Control Panel, Depress HS-10716 SJAE Suet Isa Pushbutton to Open HV-10716, HV-10717, HV-10718 and HV-10719.

Check SJAE flow stable on Fl-10724 SJAE Cdsr Flow .

WHEN offgas Rec inlet temp stable at- 270°F or above on TIC-16937 Offgas Reb Inlet Temp Ctlr, THEN have the NPO:

Place TIC-16937 Offgas Reb Inlet Temp Ctlr in AUTO SET AT 270°F.

Place TV-16937 Preheater Steam Bleed Control to AUTO .

Using PIC-16984 Motive Stm Jet In Offgas Press in MANUAL,

Adjust PV-16984 Motive Stm Jet In Offgas to- -4.8 psig on PIC-16984.

WHEN, Motive Stm Jet In Offgas Press stable at- -4.8 psig on PIC-16984, THEN Place PIC-16984 in AUTO SET AT -

4.8 psig.

WHEN SJAE operation stable, THEN Close HV-16904 Offgas Recycle.

Check main condenser vacuum IMPROVING (absolute pressure going down).

Shut Down Mechanical Vacuum Pump 1P105 in accordance with OP-143-001 as follows:

Depress 1P105 Vacuum Pump STOP pushbutton.

Observe following automatic actions occur:

HV-10731 Vac Pump Suet CLOSES .

1P138 Seal Wtr Pump STOPS .

1P141 Seal Wtr Cir Chw PP STOPS .

1 P1 05 Vacuum Pump STOPS .

Close HV-10734A and HV-107348 Vac PP Suet Isa by I depressing common CLOSE pushbutton.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 19 of 34 PCOM Monitors plant parameters.

us Direct PCOP to place Off Gas in service in accordance with OP-172-001 , starting at step 2.1.22 and secure the Mechanical Vacuum Pump INOTES I CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 20 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 2 BRIEF DESCRIPTION Raise Reactor Power by Withdrawing Control Rods INSTRUCTOR ACTIVITY

1. None ROLE PLAY Role play any directed actions as required.

EVALUATOR NOTES

1. None.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 21 of 34 I SCENARIO EVENT FORM I

EVENT 2 BRIEF DESCRIPTION Raise Reactor Power by Withdrawing Control Rods POSITION TIME STUDENT ACTIVITIES PCOM Withdraw control rods per the startup control rod sequence steps 333 to 336 from position 00 to 12 one notch at a time 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 I 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 withdrawals per the startup control rod sequence and G0-100-002.

Provide oversight for reactivity manipulation.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 22 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 3-4 BRIEF DESCRIPTION Uncoupled Control Rod/ Rod Worth Minimizer Failure INSTRUCTOR ACTIVITY

1. Just prior to the PCOM fully inserting rod 14-07, depress KEY 1 to initiate the RWM failure.

{Key[1]} sen exam\LOC27-N02-INOP RWM ROLE PLAY As WWM (or equivalent) contacted for assistance for the uncoupled control rod, acknowledge request.

As RE (or equivalent) contacted for guidance for fully inserting the uncoupled control rod report:

I concur with fully inserting rod 14-07 As WWM or Computer Group contacted for assistance for failure of the RWM wait 3 minutes and report:

The RWM has an unrecoverable software fault. Repair of the RWM is estimated to be greater than one day.

Role play any other directed actions as required.

EVALUATOR NOTES

1. None CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 23 of 34 I SCENARIO EVENT FORM I

EVENT 3-4 BRIEF DESCRIPTION Uncoupled Control Rod/ Rod Worth Minimizer Failure POSITION TIME STUDENT ACTIVITIES Recognize I report:

TEAM

Control rod 14-07 is determined to be uncoupled when it is fully withdrawn When control rod 14-07 reaches full out, recognizes and reports that the control Rod is uncoupled and refers to AR-104-H06 Rod Overtravel.

Takes action per OP-CRD-101 to re-couple the rod:

a. INSERT control rod to Position 46.

b. WITHDRAW control rod to Position 48.

c. Concurrently DEPRESS and HOLD the following pushbuttons:

W/DRAWROD

CONT W/DRAW ROD When control rod 14-07 is withdrawn from position 46, recognizes and reports that the control Rod is still uncoupled.

PCOM When preparing to fully insert the control Rod, recognizes and reports that an RWM failure is causing an insert and withdraw block.

Bypasses the RWM IAW OP-131-001 as follows:

Insert key into Normal/Bypass keylock

Turn fully clockwise to BYPASS position.

Observe status of following RWM indicator lights:

Manual Bypass indicator light ILLUMINATED.

Insert Error digital display window BLANK.

Withdraw Error digital display window BLANK.

Latched GRP digital display window BLANK.

RWM and Program section of lnop/Reset indicator light ILLUMINATED.

PCOP Monitor plant parameters.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 24 of 34

POSITION TIME STUDENT ACTIVITIES Enters ON-CRD-101 for the uncoupled control rod.

Directs PCOM to recouple rod 14-07 IAW ON-CRD-101.

When the control rod fails to recouple, determines Technical Specification 3.1.3.c requires fully inserting the control rod.

Directs PCOM to fully insert control Rod 14-07 and carry out the additional actions directed by ON-CRD-101 for an uncoupled control us Rod.

When the report is received that the RWM has an unrecoverable software fault, determines Technical Specification 3.3.2.1.c allows bypassing the RWM.

Directs PCOM to bypass the RWM IAW OP-131-001.

'NOTES I CONFIDENTIAL Examination Material

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LOC27-N-02 Rev 0 04/20/2015 Page 26 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 5 BRIEF DESCRIPTION Control Rod Drop INSTRUCTOR ACTIVITY

1. After the RWM is bypassed, and prior to inserting control rods 14-07, depress KEY 2 to initiate the control rod drop.

{Key[2]} sen exam\LOC27-N02-Delete Stuck Rods

{Key[2]} sen exam\LOC27-N02-NM Spike ROLE PLAY As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 27 of 34 I SCENARIO EVENT FORM I

EVENT 5 BRIEF DESCRIPTION Control Rod Drop POSITION TIME STUDENT ACTIVITIES TEAM

Recognize a failure to scram condition and initiate a manual scram within 60 seconds from the time that a neutron monitoring RPS setpoint is exceeded. (Critical task)

Recognizes that all IRM's momentarily pegged upscale and that APRM's exceeded 20% power.

Recognizes that the Neutron Monitoring Trip alarm was received without a scram signal occurring.

PCOM As soon as it is determined that the reactor failed to scram, announces ATWS and takes the mode switch to SHUTDOWN.

Carries out PCOM actions IAW ON-SCRAM-101.

Verify control rods fully insert Insert IRMs and SRMs Verify scram discharge volume vent and drain valves are closed PCOP Carries out PCOP actions IAW ON-SCRAM-101

Verify expected isolations and initiations have occurred

Monitor for abnormal conditions us As soon as it is determined that the reactor failed to scram, directs that a manual scram be initiated by taking the mode switch to shutdown.

Enters and directs actions be carried out for ON-SCRAM-101.

Enters E0-000-102, RPV control, due to the failure to scram.

Assign reactor level band of +20" to +45" with feedwater .

Assigns a reactor pressure band of 800 psig to 1050 psig using bypass valves.

Directs that isolations and initiations be verified .

INOTES I CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 28 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENT 6 BRIEF DESCRIPTION Fuel Failure INSTRUCTOR ACTIVITY

1. When the mode switch is taken to SHUTDOWN, verify that the following event triggers fire:

aet ETLOC27-N02-2 (to initiate a fuel failure and SDV rad) aet ETLOC27-N02-1 (Restore Auto scram when MS in SD)

2. When the MS IVs are isolated for the fuel failure, verify that the following event trigger fires:

aet ETLOC27-N02-3 (lowers MSL after isolation)

3. When requested as Unit 2 PCO to perform evacuation, depress KEY 10 to sound the local evacuation alarm and then perform OP-009-004 Attachment A for a local evacuation as requested by the crew.

{Key[10]} SCN exam\LOCAL_EVAC_ALARM Local evacuation 10LE PLAY As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

EVALUATOR NOTES none CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 29 of 34 I SCENARIO EVENT FORM I

EVENT 6 BRIEF DESCRIPTION Fuel Failure POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

Rising reactor building radiation levels

Rising containment, MSL, and Off Gas rad levels PCOM Recognizes SDV vent and drain valves fail to isolate.

Reports when MSL Rad Hi-Hi alarm received.

PCOP Closes MSIVs and drains when directed After MSIVs are closed controls reactor pressure and level using SRVs and RCIC/HPCI for reactor level control.

us Enters E0-000-104 on high RB rad levels Enters ON-179-001, Increasing Off Gas MSL Rad Levels due to fuel failure symptoms.

Directs scram reset to stop release from SDV Directs evacuation of the Unit 1 Reactor Building Directs that MSIVs and drains be closed when MSL Rad Hi-Hi alarm received IAW ON-179-001.

Directs transitioning to SRVs for pressure control and RCIC/HPCI for reactor level control.

Note: SITE AREA EMERGENCY on EAL FS1, RCS 2.c POTENTIAL LOSS, PC 3.c LOSS CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 30 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENTS 7 BRIEF DESCRIPTION SDIV Vent and Drain Valves Fail to Close INSTRUCTOR ACTIVITY ROLE PLAY If dispatched as NPO to investigate abnormal conditions in the Reactor Building, wait 2 minutes, then report:

There was elevated temperature and a lot of steam in the vicinity of the CRD HCU's. I have exited the building.

If dispatched as NPO/Security to check RB blowout panels, wait 2 minutes, then report:

"No, Reactor Building blowout panels have ruptured."

As WWM (or equivalent) contacted for assistance, acknowledge request.

Role play any other directed actions as required.

~VALUATOR NOTES

1. None.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 31 of 34 I SCENARIO EVENT FORM I

EVENTS 7 BRIEF DESCRIPTION SDIV Vent and Drain Valves Fail to Close POSITION TIME STUDENT ACTIVITIES TEAM Recognize I report:

CRD N&S Areas exceed Max Safe levels, rad levels rising in additional areas PCOM Reports SDV drain valves failed to isolate Attempts to reset RPS and observes scram cannot be reset PCOP Monitors Reactor Building radiation levels Starts area coolers for E0-000-104 Initiates a reactor cool down with SRV's.

us Direct actions for E0-000-104, secondary containment control.

Directs PCOP to start area coolers Recognizes that a primary system is discharging into secondary containment.

Directs a reactor cooldown, not to exceed 100° per hour Note: SITE AREA EMERGENCY on EAL FS1, RCS 2.c POTENTIAL LOSS, PC 3.c LOSS CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 32 of 34 INSTRUCTOR ACTIVITIES I ROLE PLAY I NOTES EVENTS 8-9 BRIEF DESCRIPTION Reactor Water Cleanup Pipe Break Without Auto Isolation/ Isolation Valves Fail to Close INSTRUCTOR ACTIVITY

1. When directed by the lead examiner, depress KEY 3 to initiate the RWCU pipe break.

{Key[3]} sen exam\LOC27-N02-B ROLE PLAY As NPO directed to investigate RWCU isolation valves, wait 5 minutes and report:

(locally at valve) The motor operators are hot.

(Locally at MCC) Everything looks normal As WWM (or equivalent) contacted for assistance, acknowledge request and take no action.

Role play any other directed actions as required.

EVALUATOR NOTES Termination criteria:

Recommend terminating the scenario after emergency depressurization has been initiated, and reactor level is stabilized with either low pressure ECCS or condensate.

CONFIDENTIAL Examination Material

LOC27-N-02 Rev 0 04/20/2015 Page 33 of 34 I SCENARIO EVENT FORM I

EVENTS 8-9 BRIEF DESCRIPTION Reactor Water Cleanup Pipe Break Without Auto Isolation/ Isolation Valves Fail to Close POSITION TIME STUDENT ACTIVITIES

TEAM Perform Emergency Depressurization when Two Secondary Containment areas exceed maximum safe radiation levels with a Primary System discharging into Secondary Containment.

TEAM Recognize I report:

Rising RWCU area temperatures and radiation levels

RWCU fails to isolate from isolation signal PCOM/PCOP Attempts to manually isolate RWCU Recognizes isolation valve dual indication and diagnoses that RWCU has not isolated.

Reports when RWCU area exceeds 10 R per hour Opens 6 ADS/SRVs Maintains RPV level > -161" using available injection systems Places both loops of RHR in Suppression Pool cooling per OP-149-005 us When it is determined that a RWCU pipe break occurred or when report received that RWCU failed to isolate:

Directs manual isolation of reactor water cleanup

Assigns a critical parameter to monitor RWCU greater than 10 R per hour (max safe)

When it is determined that RWCU will not manually isolate, contacts the WWM for assistance.

Declares rad levels exceed Max Safe in 2 areas

Enters E0-000-112, verifies Suppression Pool level >5' and directs an Emergency Depressurization by opening 6 ADS/SRVs

Directs maintaining RPV level +20" to +45" using available injection systems

Enters E0-000-103 on high Suppression Pool temperature

Directs maximizing Suppression Pool cooling

Denotes Critical Task CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

SUSQUEHANNA LEARNING CENTER

~

---sus~;~.~e~~~*

SIMULATOR SCENARIO NR Instrument Failure I Loss of Aux Bus 11 B I Loss Of Scenario

Title:

Vacuum I A TWS 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 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 CONFIDENTIAL Examination Material

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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 B in 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 A TWS, 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.

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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 CONFIDENTIAL Examination Material

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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 ATWS 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.

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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 sinqle recirculation loop.

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 CONFIDENTIAL Examination Material

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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% BOL 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 MOL 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 CONFIDENTIAL Examination Material

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LOC27-N-03 Rev 0 04/20/2015 Page 13 of 30 I SCENARIO FILES

AUX BUS AUTO TRANSFER PERM TO OFF I

LOC27-N03.scn

Monitored parameters {Key[19)} IRF rfDS003002 f: OFF SCN rat_mp

NR Level C Drifts Low

SET UP FOR ELECTRICAL ATWS {Key[l)} IMF cmfTD04_PDTC321N004C r: 240 I:0 f:-

SCN exam\LOC27-N03-A 15

DISABLE FUEL POOL COOLING ALARMS ;Loss of Aux Bus B IMF annAR016H14 f: ALARM_OFF {Key[2]} IOR diHS00012B c:2 f:TRP IMF annAR106A17 f:ALARM_OFF

Loss of Vacuum

RBCCW A OOS {Key[3]} IMF cmfMV07_HV10742A R: 240 1:3 f:8 IRF rfDB106275 f:OPEN {Key[3]} IMF cmfMV07_HV10742B R:240 1:3 f:8

{Key[3]} IMF cmfMV07_HV10742C R:240 I:3 f:8

ARI Div 2 fails to actuate {Key[3]} IMF cmfMV07_HV10716 r: 240 i:100 f:20 IMF cmfRL01_63X114725D2 {Key[3]} IMF cmfMV07_HV10717 r:240 i:100 f:20 IMF cmfRL01_63X214725D2 {Key[3]} IMF cmfMV07_HV10718 r:240 i:100 f:20

{Key[3]} IMF cmfMV07_HV10719 r:240 i:100 f:20

CRD PCV Fail when Mode Sw to SD aet ETLOC27-N03-1 ;OPEN CRD F047B

{Key[4)} IRF rfRD155021 r:60 f:100

ARI Div 1 power loss on init aet ETLOC27-N03-1A ; Vent SAH

{Key[8]} SCN exam\RDB_VSAH

DEL "B" SLC PP MALF & TRIGGER aet ETLOC27-N03-2 ; Restore SAH vent

{Key[9)} SCN exam\RDB_RSAH

DEL "A" SLC PP MALF & TRIGGER aet ETLOC27-N03-3 ; Close CRD 146F034

{Key[S)} IRF rfRD155017 d:60 f:0

OVERRIDE LIGHTS FOR VAC BREAKER AND OG !SOL VLVS ; Pull Div 1 RPS Fuses IOR doHS10716_1 f: Asls {Key[6)} SCN exam\RPB_ES158001A IOR doHS10716_2 f:Asls IOR doHS10716A_l f:OFF ; Pull 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 CIG X-Tie Valves

{Key[12]} IRF rfPC125001 d:120 f:OPEN

Reset CIG

{Key[13)} SCN exam\LOC27-N03-E

{Key[22)} IRF crfPM16_1P502B f:RESET LOC27-N03-A.scn IMF mf RP158003 RPS FAIL TO SCRAM CONFIDENTIAL Examination Material

LOC27-N-03 Rev 0 04/20/2015 Page 14 of 30 IMF cmfRL03_63X114725D2 ARI DIV 2 INITIATION LOC27-N03-2.et/scn RELAR FAIL AS IS ;SWITCH:SBLC MANUAL INITIATION

~MF cmfRL03_63X214725D2; ARI DIV 2 INITIATION diHSS14804.CurrValue = #OR.diHSS14804.START_A RELAR ;FAIL AS IS cet ETLOC27-N03-3 LOC27-N03-E.scn IMF cmf PM03_1P208A IMF cmfPM03_1P208B d:60

!OR diHSM44131PB_Q f:RESET

+2 MOR diHSM44131PB_Q f:NORM LOC27-N03-3.et/scn

+2 DOR diHSM44131PB_Q ;SWITCH:SBLC MANUAL INITIATION

+2 !OR di1C239RST_Q f:RESET diHSS14804.CurrValue = #OR.diHSS14804.START_B

+2 MOR di1C239RST_Q f :NORMAL

+2 DOR di1C239RST_Q cet ETETLOC27-N03-2 IMF cmf PM03_1P208B LOC27-N03-1.et/scn IMF cmfPM03_1P208A d:60

;SWITCH: MODE SWITCH diHSC72AlS01.CurrValue

OR.diHSC72AlS01.SHUTDN

FAIL CRD FLOW CONTROL VALVE CLOSED and Trip A CRD Pump IMF cmfAV04_FV146F002A f: 0 IMF cmf PM03_1P132A LOC27-N03-1 A.et/sen

SWITCH: ARI DIV I MAN TRIP (NORM,INIT) diHS147103AlA.CurrValue !=

OR.diHS147103AlA.NORM

ARI DIV 1 LOGIC FUSE OUT MF cmfFU01_1CB224AFU1 CONFIDENTIAL Examination Material

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 N/A 75 Termination CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

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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 CONFIDENTIAL Examination Material

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 1A 10101 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 BAND 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 TIE BUS TO BUS 11 B BKR 1A 10204 by Placing switch to CLOSE AND Hold until BKR 1A 10204 indicates CLOSED.

Observe when switch spring returns to NORMAL, AUX XFMR 11 TO BUS 11 B BKR 1A10201 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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

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 1N0048)

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.

'NOTES I CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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 8

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/F0328 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-F0318 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.

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LOC27-N-03 Rev 0 04/20/2015 Page 24 of 30 I

POSITION TIME STUDENT ACTIVITIES PCOP Executes ON-AUXBUS-101 Loss of/Undervoltage Condition on 13 KV Bus 11 A OR 11 B:

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 TIE 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 Tl E 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 11 A OR 11 B Directs PCOP to perform ON-AUXBUS-101 Enters ON-RECIRC-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 CONFIDENTIAL Examination Material

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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_HV10742B R:240 1:3 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

'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.

CONFIDENTIAL Examination Material

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.)

CONFIDENTIAL Examination Material

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.

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LOC27-N-03 Rev 0 04/20/2015 Page 29 of 30 I SCENARIO EVENT FORM I

EVENTS 6 BRIEF DESCRIPTION A TWS due to RPS and ARI Failing to Actuate POSITION TIME STUDENT ACTIVITIES

TEAM Inserts control rods IAW E0-000-113 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 Sht 2, 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 CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

SUSQUEHANNA LEARNING CENTER

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SIMULATOR SCENARIO APRM Failure / Inadvertent HPCI Initiation I Fault on Bus Scenario

Title:

1A201 /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 BerQ 05/06/15 Operations Training Management Date Approved By: Manu Sivaraman 05/06/15 Operations Line Management Date CONFIDENTIAL Examination Material

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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.

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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.TS3.3.1.1 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 CONFIDENTIAL Examination Material

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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/PPG 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.

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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 CONFIDENTIAL Examination Material

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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. r*i::he f111ow~:: marn?:s/ol"~i~::evlt tri::rs ind~~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 rod exercising.

ii) SRV Pis 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.

5. Document training participation and feedback

a. Ensure all present have signed Security Agreements per NUREG-1021 and TQ-104-0306

b. Show the crew that the Evaluators and Booth Operators are qualified

c. Complete an Operator Fundamental Score Card CONFIDENTIAL Examination Material

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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 D ISOLATION

APRM 1 Fails Upscale diHS14123D.CurrValue = #OR.diHS14123D.CLS

{Key[l]} IMF mfNM178007A f:125 dmf cmfAV06_HV141F022D

Electrical Fault on ESS Bus lA (1A201)

{Key[2]} IMF cmfEB01_1A201 LOC27-N04-2.et/scn

SWITCH: MAIN STEAM LINE D ISOLATION

Xtie IA to CIG diHS14129D.CurrValue = #OR.diHS14129D.CLS

{Key[12]} IRF rfPC125001 f:OPEN dmf cmfAV06_HV141F028D

Inadvertent HPCI Initiation

{Key[3]} IMF mfHP152004 c:10 LOC27-N04-3.et/scn

Main Steam Leak into Turbine Building ;SWITCH: DG B START BLACK PB

{Key[4]} IMF mfMS183008 r:10:00 f:0.25 diHS00051B.CurrValue = #OR.diHS00051B.RESET

D MSIVs Fail to Automatically Close DMF mfDG024001B IMF cmfAV06_HV141F028D f: Asis IMF cmfAV06_HV141F022D f:Asis LOC27-N04-4.et/scn aet LOC27-N04-1 ;SWITCH:DG D START BLACK PB aet LOC27-N04-2 diHS00051D.CurrValue = #OR.diHS00051D.RESET

D MSIVs Leak to cause slight inventory loss DMF mfDG024001D IMF cmfAV05_HV141F022D f: S IMF cmfAV05_HV141F028D f:S LOC27-N04-5.et/scn

Loss of Offsite Power ;LIGHT: MAIN STEAM LINE D ISOLATION

EDG C Fails to Start, EDGs B and D Fail to (doHS14123D_2.CurrValue =

Auto-Start #OR.doHS14123D_2.0FF)&&(doHS14129D 2.CurrValue aet LOC27-N04-5 = #OR.doHS14129D_2.0FF) -

EDG B and D will start with control room PB IMF mfDS003007 d: 30 aet LOC27-N04-3 IMF mfDS003008 d:30 aet LOC27-N04-4 IMF mfDG024008C d:45 IMF mfDG024001B d:30

RCIC and HPCI Fail to Auto-Initiate, IMF mfDG024001D d: 30 Initiation PBs Fail to ARM IMF annAR015C13 f:ALARM_OFF d:30 IMF mf RC150001 IMF annAR015E13 f:ALARM_OFF d:30

{Key[4]} IMF mfHP152002 IMF annAR016C03 f:ALARM_OFF d:30 IOR diHS15012CB f:NORM IMF annAR016E03 f:ALARM_OFF d:30 IOR diHSS15677B f:NORM CONFIDENTIAL Examination Material

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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 CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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-338ATT. 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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

LOC27-N-04 Rev 0 04/20/2015 Page 20 of 39 I

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.

I NOTES I CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

LOC27-N-04 Rev 0 04/20/2015 Page 22 of 39 SCENARIO EVENT FORM I

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 .

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

LOC27-N-04 Rev 0 04/20/2015 Page 24 of 39 I

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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.

CONFIDENTIAL Examination Material

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-C 12-1 R600 in MANUAL.

Set CRD Flow Controller FC-C12-1R600 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.

CONFIDENTIAL Examination Material

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 CONFIDENTIAL Examination Material

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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.

CONFIDENTIAL Examination Material

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 (B/D)

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.

CONFIDENTIAL Examination Material

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

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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 Band 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 O 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 I 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 O 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.

CONFIDENTIAL Examination Material

LOC27-N-04Rev 0 04/20/2015 Page 35 of 39 I SCENARIO EVENT FORM I

EVENTS 8-10 Loss of Offsite Power, EDG 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

EDG C starts and then trips .

EDGs B & D do not start .

No cooling to EDG A requiring securing EDG which will result in a loss of all AC power (Station Blackout).

HPCI and RCIC fail to automatically start .

PCOM I 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-00051 A{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.

CONFIDENTIAL Examination Material

LOC27-N-04 Rev 0 04/20/2015 Page 36 of 39

POSITION TIME STUDENT ACTIVITIES PCOM I 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-E51-1R600 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 CONFIDENTIAL Examination Material

LOC27-N-04Rev 0 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 1D650 and 1D660.

Ensure ESW Pumps OP504A, B, C, D operating in accordance with OP-054-001 after Diesel Generators start and re-energize Emergency Susses.

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 RPS

Check shift of Drywell Cooling from Reactor Building Chilled Water to Reactor Building Closed Cooling Water:

RBCCW Supply Viv FV-18771 D OPEN .

RBCCW Return Viv FV-18771 C OPEN .

Chilled Water Supply Viv to Drywell Coolers FV-18771 B CLOSE.

Chilled Water Return Viv from Drywell Coolers FV-18771A CLOSE.

IF desired, Align control switch for Drywell Cooling Water Control Valves to the RBCCW position at panel 1C279.

Ensure following Drywell Cooler Isolation Valves OPEN:

A Clrs Clg Wtr OB lso Valves HV-18781A1&A2 .

A Clrs Clg Wtr IB lso Valves HV-1878281 &82 .

B Clrs Clg Wtr IB lso Valves HV-18782A1&A2 .

B Clrs Clg Wtr OB lso Valves HV-1878181&82 .

CONFIDENTIAL Examination Material

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 Band/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 SU1 .1 for LOOP CONFIDENTIAL Examination Material

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CONFIDENTIAL Examination Material

v t e Letter Sequence Other
TAC:U01916, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML15275A362, ML15275A363, ML15275A364, ML15275A365
MONTHYEAR2015-07-30 [Table View]

ML15275A365

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