Text

2014-12 Draft Operating Test
	ML15007A172
Person / Time
Site:	River Bend
Issue date:	12/12/2014
From:	Vincent Gaddy; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML15007A172 (263)
	v • d • e

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A1) Determine the amount of Decay Heat in the Core Conduct of Operations R, D per OSP-0041 KA 2.1.20 (4.6) Ability to interpret and execute procedure steps (A2) Determine corrected Fuel Zone Level Indication Conduct of Operations R, D KA 2.1.23 (4.3) Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(A3) Use plant drawings to determine effect(s) of fuse R, N removal Equipment Control KA 2.2.15 (3.9) Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.

Radiation Control (A4) Determine Containment Water Level During Containment Flooding Emergency Procedures/Plan R, M KA 2.4.21 (4.0) Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

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

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

NRC RO ADMIN JPMS A1 - This task will have the applicant calculate core decay heat using the charts from Attachments 1 and 6 of OSP-0041.

A2 - This task will have the applicant plot RPV level using a set of correction curves and then determine is adequate core cooling is assured.

A3 - The applicant will use plant drawings to determine the effects of removing a fuse to support a maintenance activity. Three effects are asked for: (1) the fail position of an exhaust filter damper; (2) any other components that are affected and the associated effect; and (3) identification of any alarms or indications that would be seen in the Control Room.

A4 - This task will have the applicant use given data and a procedure to determine the water level in the containment. This data will be further used to determine correlated water level in the RPV. The task is being performed because of a plant emergency that required entry into the Severe Accident Procedures (SAPs).

JPM A4 was re-selected due to validation comments about the original JPM not being an RO task in our plant.

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A5) Determine stay time for a hot environment Conduct of Operations R, M KA 2.1.26 (3.4) Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen, and hydrogen).

R, M (A6) Determine Actions for Reactor Water Chemistry Conduct of Operations KA 2.1.34 (3.5) Knowledge of primary and secondary plant chemistry limits.

R, N (A7) Determine Secondary Containment Operability Equipment Control KA 2.2.12 (4.1) Knowledge of surveillance procedures.

(A8) Determine required actions upon Radioactive Radiation Control R, D Effluent Monitor Failure KA 2.3.11 (4.3) Ability to control radiation releases.

(A9) Determine PAR Emergency Procedures/Plan R, M KA 2.4.44 (4.4) Knowledge of emergency plan protective action recommendations.

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

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

NRC SRO ADMIN JPMs A5 - This task will have the applicant determine the type of work demand and the maximum stay time for an evolution involving two nuclear equipment operators.

Use of EN-IS-108, Working in Hot Environments will be required A6 - This task will require an SRO to review data and AOP-0058 to determine actions after a report from the Chemistry Department. In part, the SRO is determining if the Mode Switch can be taken to RUN.

A7 - This task will require the SRO to use Daily Logs and given data to determine corrected annulus pressure and secondary containment operability.

A8 - The applicant reviews given plant and environmental conditions, as well as the TRM to determine potential actions for allowing a radiological effluent discharge.

A9 - The applicant reviews given plant and environmental conditions to determine a Protective Action Recommendation. This is a TIME CRITICAL JPM.

RJPM-NRC-D14-A1 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine the Amount of Decay Heat in the Core OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: August 28, 2014 Reviewed: Steve Carter Date: October 1, 2014 (Operations Representative)

Approved: Joey Clark Date: October 17, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A1 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant determined decay heat in the core in accordance with the answer key; the applicant further determined that the capacity of SPC/ADHR is INSUFFUCIENT.

Synopsis: This task will have the applicant calculate core decay heat using Attachments 1 and 6 of OSP-0041.

The applicant will conclude that SPC/ADHR does not meet acceptability requirements.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

After operating 396 days at 100% power, the plant scrammed at 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on November 25, 2014. It is now 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on November 26, 2014. RHR B is operating in SDC and the designated Alternate Decay Heat Removal Method is SPC/ADHR. The following conditions exist:

Reactor coolant Temperature 164F Service Water Temperature 83F Service Water Flow 2500 gpm RHR A is inoperable due to an electrical bus fault All other plant equipment is operable and available.

3) Initiating Cues:

The CRS has directed you to (1) determine the amount of decay heat in the core by completing OSP-0041, Alternate Decay Heat Removal Attachment 1, and (2) determine if SPC/ADHR will have sufficient capacity to remain in Mode 4, if RHR-B becomes inoperable.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A1 Rev 0 Page 2 of 7

RJPM-NRC-D14-A1 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine the amount of Decay Heat 301001005003 G 2.1.20 4.6 in the Core per OSP-0041

REFERENCES:

APPLICABLE OBJECTIVES OSP-0041, Alternate Decay Heat Removal, Rev 306 REQUIRED MATERIALS:

OSP-0041, Alternate Decay Heat Removal, Rev 306 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant determined decay heat in the core in accordance with the answer key; the applicant further determined that the capacity of SPC/ADHR is INSUFFUCIENT.

RJPM-NRC-D14-A1 Rev 0 Page 3 of 7

RJPM-NRC-D14-A1 Rev. 0 PERFORMANCE:

START TIME:

OSP-0041, Alternate Decay Heat Removal Attachment 1

1. Procedure Step: 1. Time Since Reactor Shutdown Record current date and time ___

Record date and time of Reactor shutdown ___

Determine length of time since Reactor shutdown ___ Hours Standard Applicant determined the reactor has been shutdown for 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Cue Notes Results SAT UNSAT 2.

Procedure Step: 2. Reactor Core Decay Heat from Attachment 6 or Incore Fuels Group

__________ 106 BTU/HR Standard Applicant determined the core decay heat to be 75 x 106 Btu/hr. (+/-3)

Cue If asked: The Incore Fuels Group is unavailable due to Thanksgiving Holiday Notes Applicant will use the graph from Attachment 6 to perform this step.

Results SAT UNSAT RJPM-NRC-D14-A1 Rev 0 Page 4 of 7

RJPM-NRC-D14-A1 Rev. 0 3.

Procedure Step: 3. Compare Reactor Core Decay Heat value from Step 2 of this attachment to the systems heat removal capacities below and determine the alternate Shutdown Cooling Methods.

Standard Applicant concluded that the capacity of SPC/ADHR is 70.86 MBtu/Hr and is insufficient compared to the 75 MBtu/Hr of core decay heat.

The applicant marked the answer sheet INSUFFUCIENT.

Cue Notes Applicant will use the SPC/ADHR system and the 200F Rx Coolant temperature to make this determination.

Results SAT UNSAT Terminating Cue: Applicant determined decay heat in the core in accordance with the answer key; the applicant further determined that the capacity of SPC/ADHR is INSUFFUCIENT.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A1 Rev 0 Page 5 of 7

RJPM-NRC-D14-A1 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A1 Rev 0 Page 6 of 7

RJPM-NRC-D14-A1 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

After operating 396 days at 100% power, the plant scrammed at 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on November 25, 2014. It is now 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on November 26, 2014. RHR B is operating in SDC and the designated Alternate Decay Heat Removal Method is SPC/ADHR. The following conditions exist:

Reactor coolant Temperature 164F Service Water Temperature 83F Service Water Flow 2500 gpm RHR A is inoperable due to an electrical bus fault All other plant equipment is operable and available.

Initiating Cues:

The CRS has directed you to (1) determine the amount of decay heat in the core by completing OSP-0041, Alternate Decay Heat Removal Attachment 1, and (2) determine if SPC/ADHR will have sufficient capacity to remain in Mode 4, if RHR-B becomes inoperable.

Applicant Answer Sheet:

Decay Heat at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on Friday November 26 _______________

SPC/ADHR capacity is SUFFICIENT / INSUFFICIENT (circle one)

RJPM-NRC-D14-A1 Rev 0 Page 7 of 7

RJPM-NRC-D14-A2 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Corrected Fuel Zone Level Indication and Adequate Core Cooling OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 6 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: August 28, 2014 Reviewed: Steve Carter Date: October 1, 2014 (Operations Representative)

Approved: Joey Clark Date: October 17, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A2 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant determined that RPV water level is below TAF and that adequate core cooling is assured.

Synopsis: This task will have the applicant plot RPV level using a correction curve.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to use the Fuel Zone Correction Curve of SOP-0001, Attachment 1 to determine whether RPV level is above or below the top of active fuel and to determine whether or not adequate core cooling is assured.

3) Initial Conditions:

The plant has experienced a LOCA.

Fuel Zone Indication is reading -185 inches RPV pressure is reading 300 psig LPCS is injecting at 2500 gpm

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A2 Rev 0 Page 2 of 7

RJPM-NRC-D14-A2 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine corrected fuel zone level 200009005005 G 2.1.25 3.9 indication and determine whether or not adequate core cooling exits

REFERENCES:

APPLICABLE OBJECTIVES SOP-0001, Nuclear Boiler Instrumentation, Rev 19 RLP-STM-0051, Obj 5 RLP-HLO-0511, Intro to EOPs and SAPs RLP-HLO-0305, Obj 4 RLP-HLO-0511, Obj 4 REQUIRED MATERIALS: of SOP-0001, Nuclear Boiler Instrumentation SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant determined that RPV water level is below TAF and that adequate core cooling is assured.

RJPM-NRC-D14-A2 Rev 0 Page 3 of 7

RJPM-NRC-D14-A2 Rev. 0 PERFORMANCE:

START TIME:

1.

Procedure Step: 1. Use Attachment 3, Fuel Zone Correction Curve, of SOP-0001, Nuclear Boiler Instrumentation to determine actual RPV level.

Standard Applicant used Attachment 3 of SOP-0001 (handout) and determined that RPV level is below TAF.

Cue Notes The intersection of -185 and 300 psig is just below the curve for TAF.

Results SAT UNSAT 2.

Procedure Step: 2. Use Attachment 3, Fuel Zone Correction Curve, of SOP-0001, Nuclear Boiler Instrumentation to determine if adequate core cooling is assured Standard Applicant used Attachment 3 of SOP-0001 (handout) and determined that Adequate Core Cooling is assured.

Cue Notes The intersection of -185 and 300 psig is just below the curve for TAF and above the Minimum Steam Cooling RPV Water Level (MSCRWL)

Results SAT UNSAT Terminating Cue: Applicant determined that RPV water level is below TAF and that adequate core cooling is assured.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A2 Rev 0 Page 4 of 7

RJPM-NRC-D14-A2 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A2 Rev 0 Page 5 of 7

RJPM-NRC-D14-A2 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

The plant has experienced a LOCA.

Fuel Zone Indication is reading -185 inches RPV pressure is reading 300 psig LPCS is injecting at 2500 gpm Initiating Cues:

The CRS has directed you to use the Fuel Zone Correction Curve of SOP-0001, Attachment 1 to determine whether RPV level is above or below the top of active fuel and to determine whether or not adequate core cooling is assured Answer Sheet:

RPV Water Level is ABOVE / BELOW the Top of Active Fuel (circle one)

Adequate Core Cooling IS / IS NOT assured. (circle one)

RJPM-NRC-D14-A2 Rev 0 Page 6 of 7

RJPM-NRC-D14-A2 Rev 0 River Bend Station Initial License Exam Page 7 of 7

RJPM-NRC-D14-A3 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Use Plant Drawings to Determine Effect of Fuse Removal OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 25 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform Plant X Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 7, 2014 Reviewed: Steve Carter Date: October 1, 2014 (Operations Representative)

Approved: Joey Clark Date: October 17, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A3 Rev. 0 EXAMINER INFO SHEET Task Standard: The applicant determined the effects of removing fuse F1 in Panel P852 in accordance with the attached key.

Synopsis: The applicant will use plant drawings to determine the effects of removing a fuse to support a maintenance activity.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

Given the appropriate drawings, the CRS has directed you to determine the following:

1. The fail position of HVF-AOD 20B, Fuel Building Exhaust Filter 2B Inlet Isolation Damper, when the fuse is removed.

2. Any other component(s) positions that are affected by the fuse removal and the associated affect.

3. Identify any control room alarms, status lights and / or component indication affected. (Alarm # is sufficient)

3) Initial Conditions:

Mechanical Maintenance has a Work Order to work on the Fuel Building Exhaust Filter 2B Inlet Isolation Damper, HVF-AOD 20B. The 2B Filtration Unit has been tagged out and Electricians are ready to remove the 5 amp Fuse F1 in Panel P852 to de-energize the damper for work to begin.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A3 Rev 0 Page 2 of 7

RJPM-NRC-D14-A3 Rev. 0 ANSWER KEY Initiating Cues:

Given the appropriate drawings, the CRS has directed you to determine the following:

1. The fail position of HVF-AOD 20B, Fuel Building Exhaust Filter 2B Inlet Isolation Damper, when the fuse is removed.

2. Any other component(s) positions that are affected by the fuse removal and the associated affect.

3. Identify any control room alarms, status lights and / or component indication affected. (Alarm # is sufficient)

Write answers below:

(Critical Task)

1. HVF-AOD 20B fails OPEN (Critical Task is for all of the three listed below)

2. HVF-AOD 31B fails OPEN HVF-AOD 3B fails CLOSED HVF-AOD33 fails CLOSED (Critical Task is for any one of the three listed below)

3. ALARM number 0464 on H13-P863 Status Light for FB Vent Dampers Loss of Lights for all 4 valves above RJPM-NRC-D14-A3 Rev 0 Page 3 of 7

RJPM-NRC-D14-A3 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Use Plant Drawings to Determine 300246003001 G 2.2.15 3.9 Effect of Fuse Removal 299003001001

REFERENCES:

APPLICABLE OBJECTIVES ESK-07HVF03 RLP-HLO-542-1, Obj 5, 6, 7 ESK-07HVF04 ESK-10ANN23 ESK-07SCC22 REQUIRED MATERIALS:

ESK-07HVF03 ESK-07HVF04 ESK-10ANN23 ESK-07SCC22 SIMULATOR CONDITIONS & SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup but pictures/diagrams must be developed for the applicants use.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: The applicant determined the effects of removing fuse F1 in Panel P852 in accordance with the attached key.

RJPM-NRC-D14-A3 Rev 0 Page 4 of 7

RJPM-NRC-D14-A3 Rev. 0 PERFORMANCE:

START TIME:

1. *Procedure Step: Determine fail position of HVF-AOD 20B, Fuel Building Exhaust Filter 2B Inlet Isolation Damper.

Standard Applicant determined the fail position in accordance with the attached key.

Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT

2. *Procedure Step: Determine other component positions affected by removal of fuse F1.

Standard Applicant determined the position(s) of other components affected in accordance with the attached key.

Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT

3. *Procedure Step: Determine Main Control Room indications and alarms caused by removal of fuse F1.

Standard Applicant determined the MCR indications and alarms in accordance with the attached key.

Cue Notes Provide applicant with attachments as necessary Results SAT UNSAT Terminating Cue: The applicant determined the effects of removing fuse F1 in Panel P852 in accordance with the attached key.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A3 Rev 0 Page 5 of 7

RJPM-NRC-D14-A3 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A3 Rev 0 Page 6 of 7

RJPM-NRC-D14-A3 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

Mechanical Maintenance has a Work Order to work on the Fuel Building Exhaust Filter 2B Inlet Isolation Damper, HVF-AOD 20B. The 2B Filtration Unit has been tagged out and Electricians are ready to remove the 5 amp Fuse F1 in Panel P852 to de-energize the damper for work to begin.

Initiating Cues:

Given the appropriate drawings, the CRS has directed you to determine the following:

1. The fail position of HVF-AOD 20B, Fuel Building Exhaust Filter 2B Inlet Isolation Damper, when the fuse is removed.

2. Any other component(s) positions that are affected by the fuse removal and the associated affect.

3. Identify any control room alarms, status lights and / or component indication affected. (Alarm # is sufficient)

Write answers below:

1.

2.

3.

RJPM-NRC-D14-A3 Rev 0 Page 7 of 7

RJPM-NRC-D14-A4 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Containment Water Level During Containment Flooding OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 8 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform Plant X Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: August 28, 2014 Reviewed: Steve Carter Date: October 1, 2014 (Operations Representative)

Approved: Joey Clark Date: October 17, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 6

RJPM-NRC-D14-A4 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant determined the Primary Containment Water Level and correlated RPV water level in accordance with the key.

Synopsis: This task will have the applicant use given data and a procedure to determine the water level in the containment. This data will be further used to determine correlated water level in the RPV. The task is being performed because of a plant emergency that required entry into the Severe Accident Procedures (SAPs).

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

The CRS has directed you to determine Containment water level AND a correlated RPV water level using step 3.3 of EOP-0005 Enclosure 23, Containment Water Level Determination.

3) Initiating Cues:

Containment Flooding is in progress in accordance with SAP-1; It has been determined that the vessel has been breached.

Suppression Pool level indication on panel H13-P808 is pegged upscale.

The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

Div II CMS-PI17B indicates 7.5 psig

E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig

E51-F031 RCIC PUMP SUP PL SUCTION VALVE is open

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A4 Rev 0 Page 2 of 6

RJPM-NRC-D14-A4 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine Containment Water Level 200063005001 G 2.4.21 4.0 During Containment Flooding

REFERENCES:

APPLICABLE OBJECTIVES EOP-00055, Encl 23, Containment Water RLP-HLO-0516, Obj 1 Level Determination, Rev 314 REQUIRED MATERIALS:

EOP Enclosure 23, Rev 314 Calculator SIMULATOR CONDITIONS & SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup.

2. The RWP needs to be altered before giving it to applicants.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant determined the Primary Containment Water Level and correlated RPV water level in accordance with the key.

RJPM-NRC-D14-A4 Rev 0 Page 3 of 6

RJPM-NRC-D14-A4 Rev. 0 PERFORMANCE:

START TIME:

1.

Procedure Step: 3.3 Determine Containment Water Level.

Standard Applicant determined water level of containment using graph figure 8 to be 55 feet. (+/- one half foot)

Applicant determined water level of containment using the calculation given to be 54.6 feet. (+/- one half foot)

Cue If applicant did not already perform calculation, as the CRS, request that the applicant confirm his finding on the graph using the calculation.

Notes Results SAT UNSAT 2.

Procedure Step: Determine correlated RPV water level.

Standard Applicant determined the correlated RPV water level using Table 1 to be

-246 inches. (acceptable range is -253 to -246)

Cue Notes Results SAT UNSAT Terminating Cue: Applicant determined the Primary Containment Water Level and correlated RPV water level in accordance with the key.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A4 Rev 0 Page 4 of 6

RJPM-NRC-D14-A4 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A4 Rev 0 Page 5 of 6

RJPM-NRC-D14-A4 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

The CRS has directed you to determine Containment water level AND a correlated RPV water level using EOP-0005 Enclosure 23, Containment Water Level Determination.

Initiating Cues:

Containment Flooding is in progress in accordance with SAP-1.

Suppression Pool level indication on panel H13-P808 is pegged upscale.

The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

Div II CMS-PI17B indicates 7.5 psig

E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig

E51-F031 RCIC PUMP SUP PL SUCTION VALVE is open Answer Sheet:

Determine containment water level:

Answer:

Determine correlated RPV Water Level:

Answer:

RJPM-NRC-D14-A4 Rev 0 Page 6 of 6

RJPM-NRC-D14-A5 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Stay Time for a Hot Environment OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 20 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 7, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A5 Rev. 0 EXAMINER INFO SHEET Task Standard: Determination of the work demand classification and the stay time is in accordance with the attached key.

Synopsis: This task will have the applicant determine the type of work demand and the maximum stay time for an evolution involving two nuclear equipment operators. Use of EN-IS-108, Working in Hot Environments will be required.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

Complete the appropriate sections of Attachment 9.1, Heat Stress Survey Form, of EN-IS-108, Working in Hot Environments; disregard Recovery Time.

3) Initial Conditions:

The plant is in Mode 5; refueling is in progress.

Two Nuclear Equipment Operators are required to re-align two valves for the Fuel Pool Cooling and Cleanup System located in a room above the RB-162.

Both valves are infrequently operated but are considered easy to operate. The valves are in a C-Zone and require donning single anti-contamination clothing.

The dry bulb temperature is 95°F.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A5 Rev 0 Page 2 of 7

RJPM-NRC-D14-A5 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine Stay Time for a Hot 300076003001 G 2.1.26 3.6 Environment

REFERENCES:

APPLICABLE OBJECTIVES EN-IS-108, Working in Hot Environments, Rev 10 REQUIRED MATERIALS:

EN-IS-108, Rev 10 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Determination of the work demand classification and the stay time is in accordance with the attached key.

RJPM-NRC-D14-A5 Rev 0 Page 3 of 7

RJPM-NRC-D14-A5 Rev. 0 PERFORMANCE:

START TIME:

1. Procedure Step: 5.3 [1] Prior to performing work, the group supervisor shall determine whether heat stress conditions may be a factor:

Standard Applicant reviews precautions and limitations and the general requirements of EN-IS-108.

Cue Notes Results SAT UNSAT 2.

Procedure Step: 5.3 [2] From Attachment 9.2

Select the appropriate work demand category from the table titled Work Demand Standard Applicant selected the MODERATE Work Demand in accordance with Attachment 9.2.

Cue Notes The activity for Manual valve alignment - easy is listed under Moderate Work Demand.

Results SAT UNSAT

3. Procedure Step: 5.3 [2] From Attachment 9.2

Select the appropriate clothing ensemble from the table titled Typical Clothing Ensembles Standard Applicant selected SC (Single coveralls) in accordance with Attachment 9.2.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-A5 Rev 0 Page 4 of 7

RJPM-NRC-D14-A5 Rev. 0

4. Procedure Step: 5.3 [2] From Attachment 9.2

Determine if heat stress may be a factor by reviewing the table titled Heat Stress Threshold Values Standard NA Cue Notes Applicant determined that the Heat Stress Threshold is a factor in accordance with Attachment 9.2 by comparing the given condition of 95F dry bulb temperature and the threshold temperature of 90F.

Applicant will proceed to step 5.3 [3].

5. Procedure Step: 5.3 [3] If the dry bulb temperature is greater than, or expected to be greater than those listed, heat stress may be a factor; obtain a WBGT or reference historical temperature readings.

Standard Applicant requested wet bulb temperature.

Cue When asked, report that the wet bulb temperature is 102F Notes Results SAT UNSAT PROCEDURE NOTE Attachment 9.1, Heat Stress Survey Form is not required if the stay time associated with the temperature is listed as No Limit (NL) 6.

Procedure Step: 5.3 [4] If the WBGT temperature obtained falls within the chart on Attachment 9.4, then a Heat Stress Survey Form, Attachment 9.1, shall be completed.

Standard Applicant completes Attachment 9.1 using step 5.3 [5], bullets 1, 2, and 3.

Applicant determines max stay time to be 25 minutes in accordance with attachment 9.4.

Cue Notes Intersection of 102F and Single PCs with a Work Demand of MOD.

Results SAT UNSAT Terminating Cue: Determination of the work demand classification and the stay time is in accordance with the attached key.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A5 Rev 0 Page 5 of 7

RJPM-NRC-D14-A5 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A5 Rev 0 Page 6 of 7

RJPM-NRC-D14-A5 Rev. 0 OPERATOR CUE SHEET Initiating Cues:

Complete the appropriate sections of Attachment 9.1, Heat Stress Survey Form, of EN-IS-108, Working in Hot Environments; disregard Recovery Time.

Initial Conditions:

The plant is in Mode 5; refueling is in progress.

Two Nuclear Equipment Operators are required to re-align two valves for the Fuel Pool Cooling and Cleanup System located in a room above the RB-162.

Both valves are infrequently operated but are considered easy to operate. The valves are in a C-Zone and require donning single anti-contamination clothing.

The dry bulb temperature is 95°F.

RJPM-NRC-D14-A5 Rev 0 Page 7 of 7

RJPM-NRC-D14-A6 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Actions for Reactor Water Chemistry OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 22 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 8, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A6 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant determines that the plant startup may continue.

Synopsis: This task will require an SRO to review given data and AOP-0058 to determine actions after a report from the Chemistry Department.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

A Plant Startup is in progress; currently in Mode 2.

Reactor power is 9% and RPV pressure is 950 psig.

Preparations are being made for taking the Mode Switch to RUN.

Chemistry has been contacted to verify water quality per GOP-0001, Plant Startup, Step 7 of Section E, 600 PSIG to RUN.

3) Initiating Cues:

The Chemistry Manager has just completed the required sampling of Reactor Water, Feedwater, Condensate, and CRD Water. Review the Chemistry data and determine the course of action for plant startup.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A6 Rev 0 Page 2 of 7

RJPM-NRC-D14-A6 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine Actions for Reactor Water 400084004001 G 2.1.34 3.5 Chemistry

REFERENCES:

APPLICABLE OBJECTIVES AOP-0058, Abnormal Chemistry, Rev 8 REQUIRED MATERIALS:

AOP-0058, Abnormal Chemistry, Rev 8 TR 3.4.13 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant determines that the plant startup may continue.

RJPM-NRC-D14-A6 Rev 0 Page 3 of 7

RJPM-NRC-D14-A6 Rev. 0 PERFORMANCE:

START TIME:

1. *Procedure Step: 1. Determine the course of action for plant startup.

Standard Applicant determined that the plant startup may continue.

Cue If asked, as Chemistry Management report that the Hotwell conductivity is due to startup.

Notes Note 1 from Attachment 1 of AOP-0058 states that Elevated Hotwell Conductivity is expected following a plant startup. Consult with Chemistry Management prior to entering AOP-0058 due to Hotwell Conductivity while Reactor startup is in progress.

Results SAT UNSAT Terminating Cue: Applicant determines that the plant startup may continue.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A6 Rev 0 Page 4 of 7

RJPM-NRC-D14-A6 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A6 Rev 0 Page 5 of 7

RJPM-NRC-D14-A6 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

A Plant Startup is in progress; currently in Mode 2.

Reactor power is 9% and RPV pressure is 950 psig.

Preparations are being made for taking the Mode Switch to RUN.

Chemistry has been contacted to verify water quality per GOP-0001, Plant Startup, Step 7 of Section E, 600 PSIG to RUN.

Initiating Cues:

The Chemistry Manager has just completed the required sampling of Reactor Water, Feedwater, Condensate, and CRD Water. Review the Chemistry data on the attached form and determine the course of action for plant startup.

Answer Below The Startup may continue YES NO (circle one)

Course of Action (if any):

RJPM-NRC-D14-A6 Rev 0 Page 6 of 7

RJPM-NRC-D14-A6 Rev 0 Reactor Water Conductivity 0.25 µS/cm pH 7.3 S.U.

Chloride 1 ppb Sulfate 0.3 µg/L Feedwater Conductivity 0.061 µS/cm Total Iron 0.92 ppb Total Copper 0.12 ppb Condensate Hotwell Conductivity 0.25 µS/cm Control Rod Drive Conductivity 0.10 µS/cm River Bend Station Initial License Exam Page 7 of 7

RJPM-NRC-D14-A7 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Secondary Containment Operability OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 8, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 6

RJPM-NRC-D14-A7 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant reviewed the reported condition and the daily logs and determined that annulus pressure is not acceptable Synopsis: This task will have the applicant determine operability.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

The plant is mode 1, 100% power.

Annunciator H13-P863-72A-A01, ANNULUS PRESSURE HIGH is in Alarm, with an Annulus Pressure of -2.4 inches WC.

An operator was dispatched and reported that Aux Building Pressure is reading

-0.34 in WC.

3) Initiating Cues:

You are the CRS. Determine if the Annulus Pressure is acceptable.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A7 Rev 0 Page 2 of 6

RJPM-NRC-D14-A7 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine Secondary Containment 300095003001 G 2.2.12 4.1 Operability

REFERENCES:

APPLICABLE OBJECTIVES STP-000-0001, Daily Operating Logs, Rev 78 ARP-863-72A-A01, Rev 16 REQUIRED MATERIALS:

Marked up copy of STP-000-0001, Daily Operating Logs, Rev 78 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant reviewed the prepared tagout and determined that it is annulus pressure is not acceptable.

RJPM-NRC-D14-A7 Rev 0 Page 3 of 6

RJPM-NRC-D14-A7 Rev. 0 PERFORMANCE:

START TIME:

1. Procedure Step: Determine corrected annulus pressure.

Standard Applicant used data provided to determine corrected annulus pressure to be

-2.74 inches WC.

Cue Notes Calculation per STP-000-0001 step 92.

Results SAT UNSAT

2. *Procedure Step: Determine is Annulus Pressure is acceptable.

Standard Applicant used Attachment 3 of STP-000-0001 to determine that annulus pressure is in the unacceptable region.

Cue Notes Results SAT UNSAT Terminating Cue: Applicant reviewed the prepared tagout and determined that it is annulus pressure is not acceptable.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A7 Rev 0 Page 4 of 6

RJPM-NRC-D14-A7 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A7 Rev 0 Page 5 of 6

RJPM-NRC-D14-A7 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

The plant is mode 1, 100% power.

Annunciator H13-P863-72A-A01, ANNULUS PRESSURE HIGH is in Alarm, with an Annulus Pressure of -2.4 inches WC.

An operator was dispatched and reported that Aux Building Pressure is reading

-0.34 in WC.

Initiating Cues:

You are the CRS. Determine if the Annulus Pressure is acceptable.

Answer Below:

RJPM-NRC-D14-A7 Rev 0 Page 6 of 6

RJPM-NRC-D14-A8 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine Required Actions upon Radioactive Effluent Monitor Failure OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 8, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-A8 Rev. 0 EXAMINER INFO SHEET Task Standard: Applicant determined the effects of RMS-RE107 failure and the required actions to complete the radiological discharge in accordance with the key.

Synopsis: The applicant reviews given plant and environmental conditions, as well as the TRM to determine potential actions for allowing a radiological effluent discharge.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

Preparations for discharging Recovery Sample Tank TK4A utilizing LWS-P4A Recovery Sample Tank Pump are under way.

The Aux Control Room Operator reports that RCVY SAMPLE PROCESS RADIATION HIGH/MONITOR INOP is in Alarm (LWS-PNL187-4-C4). The RMS-RE107 Sample pump is tripped and hot to the touch.

3) Initiating Cues:

As the CRS, determine the impact on the current liquid radwaste discharge preparations and what actions, if any, will be required to perform the discharge.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A8 Rev 0 Page 2 of 7

RJPM-NRC-D14-A8 Rev. 0 ANSWER KEY Initial Conditions:

Preparations for discharging Recovery Sample Tank TK4A utilizing LWS-P4A Recovery Sample Tank Pump are under way.

The Aux Control Room Operator reports that RCVY SAMPLE PROCESS RADIATION HIGH/MONITOR INOP is in Alarm (LWS-PNL187-4-C4). The RMS-RE107 Sample pump is tripped and hot to the touch.

Initiating Cues:

As the CRS, determine the impact on the current liquid radwaste discharge preparations and what actions, if any, will be required to perform the discharge.

Answer Below:

RMS-RE107 is Operable / Inoperable (circle one)

What actions (if any) are required to continue with the liquid radiological release?

The discharge cannot be performed utilizing the RMS-RE107 Liquid Radwaste Effluent Radiation Monitor because sample flow must be 1 gpm.

The discharge may, however, continue by talking the actions of TRM 3.3.11.2 Action D:

Condition D.1 Perform a second independent set of samples and analyses per Table 3.11.1.1-1 prior to release AND Condition D.2 Perform verification of release rate calculation and discharge line valving by a second qualified member of the technical staff prior to release AND Condition D.3 Restore the channel to OPERABLE within 14 days RJPM-NRC-D14-A8 Rev 0 Page 3 of 7

RJPM-NRC-D14-A8 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine Required Actions upon 300169003002 G 2.3.11 4.3 Radioactive Effluent Monitor Failure

REFERENCES:

APPLICABLE OBJECTIVES TRM 3.3.11.2 TRM 3.11.1.1 LWS-PNL187-4-C4, Alarm Response REQUIRED MATERIALS:

TRM 3.3.11.2 TRM 3.11.1.1 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup 2.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Applicant determined the effects of RMS-RE107 failure and the required actions to complete the radiological discharge in accordance with the key.

RJPM-NRC-D14-A8 Rev 0 Page 4 of 7

RJPM-NRC-D14-A8 Rev. 0 PERFORMANCE:

START TIME:

1. Procedure Step: 1 Determine the impact of RMS-RE107 sample pump trip.

Standard Applicant determined that RMS-RE107 is INOPERABLE.

Cue Notes TR 3.3.11.2; Table 3.11.1.1-1 Results SAT UNSAT

2. *Procedure Step: 2 Determine what actions (if any) are required to continue with the liquid radiological release.

Standard Applicant determined that the radiological discharge could be allowed by taking the actions of Conditions D.1 and D.2 of TR 3.3.11.2.

Cue Notes See answer key.

Results SAT UNSAT Terminating Cue: Applicant determined the effects of RMS-RE107 failure and the required actions to complete the radiological discharge in accordance with the key.

This completes this JPM.

RJPM-NRC-D14-A8 Rev 0 Page 5 of 7

RJPM-NRC-D14-A8 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A8 Rev 0 Page 6 of 7

RJPM-NRC-D14-A8 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

Preparations for discharging Recovery Sample Tank TK4A utilizing LWS-P4A Recovery Sample Tank Pump are under way.

The Aux Control Room Operator reports that RCVY SAMPLE PROCESS RADIATION HIGH/MONITOR INOP is in Alarm (LWS-PNL187-4-C4). The RMS-RE107 Sample pump is tripped and hot to the touch.

Initiating Cues:

As the CRS, determine the impact on the current liquid radwaste discharge preparations and what actions, if any, will be required to perform the discharge.

Answer Below:

RMS-RE107 is Operable / Inoperable (circle one)

What actions (if any) are required to continue with the liquid radiological release?

RJPM-NRC-D14-A8 Rev 0 Page 7 of 7

RJPM-NRC-D14-A9 Rev 0 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Determine PAR OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): 15 Actual Time (min):

PERFORMANCE TIME: Average Time (min): NA Actual Time (min): NA JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Classroom Prepared: Dave Bergstrom Date: September 8, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 8

RJPM-NRC-D14-A9 Rev. 0 EXAMINER INFO SHEET This is a Time Critical JPM Task Standard: Applicant completed the PAR Block number and the Notification of General Emergency Short Form in accordance with the attached key within 15 minutes.

Synopsis: The applicant reviews given plant and environmental conditions to determine a Protective Action Recommendation. This is a TIME CRITICAL JPM.

NOTE: This JPM is Administrative and will be performed in a classroom.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

3) Initial Conditions:

Use the following conditions:

A General Emergency has just been declared due to Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mR TEDE or 5000 mR thyroid CDE for the actual or projected duration of the release (AG1).

The plant has experienced a loss of offsite power.

A release is in progress following a large break LOCA inside containment.

Minimum Protective Action Recommendations were issued.

Due to Hydrogen Concentration and Containment Pressure, Emergency Containment Venting is now required.

2) Initiating Cues:

As the acting Emergency Director, you have just been handed updated dose projections and meteorological information.

Review the updated data and, if necessary, alter the Protective Action Recommendations and complete a Notification of General Emergency short form.

This is a TIME CRITICAL JPM.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-A9 Rev 0 Page 2 of 8

RJPM-NRC-D14-A9 Rev. 0 ANSWER KEY PAR BLOCK # _________5____________

Notification of General Emergency Time/Date: Current time / date Message:

This is River Bend Station A General Emergency was declared at Declaration on Declaration for time date AG 1-2 VALID reading on one or more radiation monitors in Table R1 that exceeds or is expected to exceed GENERAL EMERGENCY reading for greater than or equal to 15 minutes Wind from __350 Deg__ At___3.1___ MPH No Release PAR Reference Scenario No.: 27 Release BELOW federally approved operating limits Release ABOVE federally approved operating limits Authorized by: Applicant Name

Title:

Emergency Director RJPM-NRC-D14-A9 Rev 0 Page 3 of 8

RJPM-NRC-D14-A9 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Determine PAR 301016005003 G 2.4.44

4.4 REFERENCES

APPLICABLE OBJECTIVES EIP-2-007, Rev 25 DOSEPAR2, Obj 13 EIP-2-006, Rev 41 REQUIRED MATERIALS:

EIP-2-007, Rev 25 EIP-2-006, Rev 41 SIMULATOR CONDITIONS &/or SETUP:

1. This is a classroom/Admin JPM - There is no simulator setup

2. This task is TIME CRITICAL CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD:

Applicant completed the PAR Block number and the Notification of General Emergency Short Form in accordance with the attached key within 15 minutes.

RJPM-NRC-D14-A9 Rev 0 Page 4 of 8

RJPM-NRC-D14-A9 Rev. 0 PERFORMANCE:

START TIME: This task is TIME CRITICAL

1. *Procedure Step: 1 Complete the PAR BLOCK using given data.

Standard Applicant completed PAR Block in accordance with the attached key.

Cue Notes The applicant will use the provided cue sheet to gather readings.

Results SAT UNSAT

2. *Procedure Step: 2 Complete the short form using given data.

Standard Applicant completed short form in accordance with the attached key.

Cue Notes The applicant will use the pictures provided to gather readings.

Results SAT UNSAT Terminating Cue: Applicant completed the PAR Block number and the Notification of General Emergency Short Form in accordance with the attached key within 15 minutes.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-A9 Rev 0 Page 5 of 8

RJPM-NRC-D14-A9 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-A9 Rev 0 Page 6 of 8

RJPM-NRC-D14-A9 Rev. 0 OPERATOR CUE SHEET Initial Conditions:

A General Emergency has just been declared due to Offsite dose resulting from an actual or imminent release of gaseous radioactivity (AG1).

The plant has experienced a loss of offsite power.

A release is in progress following a large break LOCA inside containment.

Minimum Protective Action Recommendations were issued.

Due to Hydrogen Concentration and Containment Pressure, Emergency Containment Venting is now required.

Initiating Cues:

As the acting Emergency Director, you have just been handed updated dose projections and meteorological information.

Review the updated data and, if necessary, alter the Protective Action Recommendations and complete a Notification of General Emergency short form.

This is a TIME CRITICAL JPM.

DOSE ASSESSMENT for Emergency Containment Venting DOSE RATE CALCULATIONS TEDE Dose (REM): CDE Dose (REM) Thyroid:

Site Boundary 1.51E2 Site Boundary 2.02E3 2 Miles 2.66E1 2 Miles 4.06E2 5 Miles 6.09E0 5 Miles 9.44E1 10 Miles 1.88E0 10 Miles 2.55E1 Meteorological Data Wind Speed 3.1 mph Wind Direction 350 deg.

Delta T -0.7oF Stability Class D RJPM-NRC-D14-A9 Rev 0 Page 7 of 8

RJPM-NRC-D14-A9 Rev. 0 OPERATOR ANSWER SHEET PAR BLOCK # ________________________

Notification of General Emergency Time/Date: Current time / date Message:

This is River Bend Station A General Emergency was declared at Declaration on Declaration for time date Wind from________ Deg. At__________ MPH No Release PAR Reference Scenario No.:

Release BELOW federally approved operating limits Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC-D14-A9 Rev 0 Page 8 of 8

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (S1) Pull Rods to Achieve Criticality - w/ trip of CRD pumps S,A,E,L,N 1

b. (S2) Shutdown RCIC using SOP- w/ Drain Trap Level High S,A,N 2

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4) Reduce SDC to only RHR-A - w/ overload pre-trip alarm S,A,L,N 4

e. (S5) Stop Cont High Volume Purge - w/Decay Heat Fan trip S,A,N,EN 9

f. (S6) Place Suppression Pool Cooling System in Service (SOP-140) S,D 5

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2) Bypass Control Rod in RACS (STP-500-0705) C,D 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2) Supply Fire Protection Water for CB via SSW (SOP-37, sect 5.3) E,N 8

k. (P3) Transfer Div 1 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.7)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5 (C)ontrol room (D)irect from bank 9/8/45 (E)mergency or abnormal in-plant 1/1/13 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/1/14 (N)ew or (M)odified from bank including 1(A) 2/2/17 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/1/11 (S)imulator

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (S1)

b. (S2) Shutdown RCIC using SOP- w/ Drain Trap Level High S,A,N 2

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4) Reduce SDC to only RHR-A - w/ overload pre-trip alarm S,A,L,N 4

e. (S5) Stop Cont High Volume Purge - w/Decay Heat Fan trip S,A,D,E,EN 9

f. (S6) Place Suppression Pool Cooling System in Service (SOP-140) S,D 5

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2) Bypass Control Rod in RACS (STP-500-0705) C,D 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2) Supply Fire Protection Water for CB via SSW (SOP-37, sect 5.3) E,N 8

k. (P3) Transfer Div 1 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.7)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 4 (C)ontrol room (D)irect from bank 9/8/45 (E)mergency or abnormal in-plant 1/1/15 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/1/13 (N)ew or (M)odified from bank including 1(A) 2/2/15 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/1/11 (S)imulator

NRC S1 - The applicant is directed to withdraw control rods to achieve criticality.

Before criticality is reached however, at the evaluators discretion, a CRD pump trip occurs. As an alternate path, the standby CRD pump is started but also trips. The operator will be required to place the mode switch in SHUTDOWN after receiving an accumulator fault associated with a withdrawn control rod and RPV pressure less than 600 psig.

S2 - This is a replacement JPM for Starting the Condenser Air Removal Pumps.

A complete loss of high pressure feed has occurred. Direction will be given to initiate Div 2 ECCS using the hard card. Pump C will undergo a trip after start. Because of plant conditions, and direction in the Alarm Response Procedure, the applicant will restart RHR-C.

S3 - This JPM was adjusted to perform the evolution at a higher power so that there would be less low power JPMs.

The applicant is directed to perform pressure regulator adjustments to minimize Recirc Pump seal thrust reversal IAW GOP-0001. The reactor is at 70% power during a plant startup. The applicant will perform a calculation and then make an adjustment to the EHC System Pressure Setpoint.

S4 - This is a replacement JPM for placing the Turbine on the turning gear.

The reactor has scrammed; Pressure control is required and the applicant is directed to perform enclosure 29, RWCU Blowdown Mode. This task will have the applicant perform a valve lineup and begin to discharge from the RPV to the Main Condenser. As an alternate path the applicant will be unable to complete the lineup to the main condenser and will have to decide to choose to discharge to Radwaste instead of the main condenser.

S5 - This JPM was adjusted to allow the evolution at higher power so there would be less low power JPMs. (Containment purge instead of drywell purge.)

The plant has experienced a high containment pressure. This task will have the applicant attempt to perform a containment low volume purge using SOP-0059, but due to a failure of the exhaust fan, the applicant will be required to perform a high volume purge instead.

S6 - This JPM was adjusted to allow the evolution at higher power so there would be less low power JPMs.

The plant is performing a startup per GOP-0001. This task has the applicant start the Suppression Pool Cooling and Cleanup System using SOP-0140, Suppression Pool Cleanup and Alternate Decay Heat Removal section 5.2.

NRC C1 - This task will remove DC loads from the station batteries in order to reduce heat load in the control room. Without operator action, during a station blackout, Control Room temperatures can reach greater than 120F in less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C2 - This task will have the applicant bypass a control rod to allow movement of the rod without position indication.

P1 - This task will have the applicant simulate venting the scram air header during an ATWS.

P2 - This task will have the applicant align the Standby Service Water System to the Fire Protection Water System Hose Racks. This would be performed provide water for firefighting via manual hose streams in the Control Building.

P3 - During a station blackout event, or in the event a battery charger becomes inoperable, power must be supplied to the Div 1 ENB bus. This task will align the backup battery charger to the ENB-SWG01A bus using SOP-0049, 125 VDC. An Alternate Path is taken when the normal manual transfer button is depressed: the transfer does not occur electrically and must therefore be performed manually.

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 12/8/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: ______________

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (S1)

b. (S2)

c. (S3) Adjust Pressure Regulator to Minimize Recirc Pump Seal S,M 3 Thrust Reversal (GOP-0001)

d. (S4)

e. (S5) Stop Cont High Volume Purge - w/Decay Heat Fan trip S,A,D,E,EN 9

f. (S6)

g. (C1) Shed DC Loads for Station Blackout (AOP-50, Attach 3) C,D,E,L 6

h. (C2)

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Vent Scram Air Header (Encl 11) R,D,E,EN 1

j. (P2)

k. (P3) Transfer Div 1 125 VDC to Backup Charger A,E,L,N 6 (AOP-14, Sect 5.3 and SOP-49, Sect 5.7)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 2 (C)ontrol room (D)irect from bank 9/8/43 (E)mergency or abnormal in-plant 1/1/14 (EN)gineered safety feature - / - / 1 (control room system) 2 (L)ow-Power / Shutdown 1/1/12 (N)ew or (M)odified from bank including 1(A) 2/2/12 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1/1/11 (S)imulator

RJPM-NRC-D14-C1 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Shed DC Loads for Station Blackout OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): 30 Actual Time (min):

PERFORMANCE TIME: Average Time (min): 10 Actual Time (min): NA JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform Plant X Simulate Simulator X Control Room Prepared: Dave Bergstrom Date: September 9, 2013 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 12

RJPM-NRC-D14-C1 Rev. 0 EXAMINER INFO SHEET Task Standard: Non-essential loads have been removed per AOP-0050, Attachment 3.

Synopsis: This task will remove DC loads from the station batteries in order to reduce heat load in the control room. Without operator action, during a station blackout, Control Room temperatures can reach greater than 120F in less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

NOTE:

If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

A station blackout has occurred. Restoration time is unknown.

3) Initiating Cues:

The CRS has directed you to shed DC loads in accordance with Attachment 3 of AOP-0050, Station Blackout.

This is a time critical JPM.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-C1 Rev 0 Page 2 of 12

RJPM-NRC-D14-C1 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Shed DC Loads for Station Blackout 400067004001 263000 A4.01 3.3 / 3.5 295003 AA1.04 3.6 /

3.7 REFERENCES

APPLICABLE OBJECTIVES AOP-0050, Station Blackout, Rev 49 RLP-HLO-0541, Obj 3, 7 REQUIRED MATERIALS: SAFETY FUNCTION:

AOP-0050, Rev 49 Attach 3 __9__

SIMULATOR CONDITIONS & SETUP:

1. NA - This is a Control Room JPM.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Non-essential loads have been removed per AOP-0050, Attachment 3.

RJPM-NRC-D14-C1 Rev 0 Page 3 of 12

RJPM-NRC-D14-C1 Rev. 0 PERFORMANCE:

START TIME:

PROCEDURE NOTE Performance of this procedure disables EHC Turbine Control and the Plant Process Computer.

The following disconnects are located on the Control Room south wall.

1. *Procedure Step: 1 Open the following disconnects on panel VBN-PNL01B1:

Disconnect 1, H13-P821, TURBINE GEN, EHC SYSTEM CABINET

Disconnect 3, H13-P869/P870, SST-AR40, 89, 194, 195, MSS-FR31, GMC-CR106

Disconnect 12, H13-P601, SPC MUX &, TEMP RECORDER E12-R601 Standard Applicant located and moved the three breaker handles to the OFF position.

Cue Notes Results SAT UNSAT PROCEDURE CAUTION Loads necessary for operation during a station blackout are powered from VBN-PNL02, Disconnects 19, 21, 23, 25, and 26.

Do not open VBN-PNL02, Disconnects 19, 21, 23, 25, and 26.

2. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 1, H13-P721D, ERIS NETWORK, COMMUNICATION EQUIPMENT Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 4 of 12

RJPM-NRC-D14-C1 Rev. 0

3. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 2, C91-P608, PMS Computer, CMS/PPX Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

4. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 3, C91-P600, PMS Computer, Central System Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

5. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 4, C91-P603, PMS Computer Large Core Storage Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

6. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 5, C91-P612, PMS Computer Display, Generator Cabinet Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 5 of 12

RJPM-NRC-D14-C1 Rev. 0

7. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 6, C91-P620, PMS Computer, BOP/NSSS Digital Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

8. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 7, C91-P625, PMS Computer, BOP/NSSS Digital Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

9. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 8, C91-P621, PMS Computer BOP, Digital Unit &

SPC-BNK1 Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

10. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 9, C91-P624, PMS Computer, BOP Digital Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 6 of 12

RJPM-NRC-D14-C1 Rev. 0

11. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 10, C91-P622, PMS Computer, BOP Digital Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

12. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 11, C91-P623, PMS Computer, BOP Digital Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

13. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 12, C91-P630/P631, PMS Computer, Printers Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

14. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 13, C91-P613, PMS Computer, NSSS Analog Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 7 of 12

RJPM-NRC-D14-C1 Rev. 0

15. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 14, C95-P604, Unit Operator Table, ERIS Terminals Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

16. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 15, C91-P616, PMS Computer, BOP Analog Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

17. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 16, C91-P615, PMS Computer, BOP Analog Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

18. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 17, C91-P614, PMS Computer, BOP Analog Unit Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 8 of 12

RJPM-NRC-D14-C1 Rev. 0

19. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 18, C91-P642, PMS Computer Results, Central Console Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

20. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 20, C91-P632/P633, PMS Computer, Printers Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Note: this is the first disconnect not in order - procedure skips disconnect 19 Results SAT UNSAT

21. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 22, C91-P650, PMS Computer BOP, Digital Unit &

SWC-BNK4 Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

22. *Procedure Step: 2 Open the following disconnects on panel VBN-PNL02:

Disconnect 24, H13-P954, Loose Parts Monitor, &

H13-P808/83A/F07, F08 Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C1 Rev 0 Page 9 of 12

RJPM-NRC-D14-C1 Rev. 0

23. *Procedure Step: 3 Open the following disconnects on panel VBN-PNL01A1:

Disconnect 17, H13-P808, SPI-REC102 & SWC, Harris Panel Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

24. *Procedure Step: 3 Open the following disconnects on panel VBN-PNL01A1:

Disconnect 21, C91-P642 C91-PM5 & PM5A, Core Monitor, System Recept Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Results SAT UNSAT

25. Procedure Step: 3 Open the following disconnects on panel VBN-PNL01A1:

Disconnect 22, C91-P631 C91-PM6 & PM6A, Core Monitor, System Recept Standard Applicant located and moved the breaker handle to the OFF position.

Cue Notes Reminder - This is a TIME CRITICAL Task.

Results SAT UNSAT Terminating Cue: Non-essential loads have been removed per AOP-0050, Attachment 3.

This completes this JPM.

STOP TIME: (Check time against the Time Critical Limit)

RJPM-NRC-D14-C1 Rev 0 Page 10 of 12

RJPM-NRC-D14-C1 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-C1 Rev 0 Page 11 of 12

RJPM-NRC-D14-C1 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

A station blackout has occurred. Restoration time is unknown.

INITIATING CUE:

The CRS has directed you to shed DC loads in accordance with Attachment 3 of AOP-0050, Station Blackout.

This is a time critical JPM.

RJPM-NRC-D14-C1 Rev 0 Page 12 of 12

RJPM-NRC-D14-C2 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Bypass a Control Rod in RACS (STP-500-0705)

OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform Plant X Simulate Simulator X Control Room Prepared: Dave Bergstrom Date: September 10, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 12

RJPM-NRC-D14-C2 Rev. 0 EXAMINER INFO SHEET Task Standard: Control Rod 16-25 has been bypassed in the RACS Cabinets.

Synopsis: This task will bypass a control rod to allow movement of the rod without position indication.

NOTE:

If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initial Conditions:

The plant is performing a startup. Thermal power is less than 10% of rated. Control rod 16-25 is in the correct position when both position reed switches fail. In order to clear the rod block and continue rod movement Rod 16-25 will have to be bypassed in RACS.

3) Initiating Cues:

In order to meet Technical Specification 3.1.3 requirements, the CRS directs you to bypass control rod 16-25 in accordance with STP-500-0705, Bypassing Control Rods in RACS.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-C2 Rev 0 Page 2 of 12

RJPM-NRC-D14-C2 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Bypass a Control Rod in RACS 214003004001 201005 K6.02 3.2 / 3.3 201005 A2.02 2.8 /

3.2 REFERENCES

APPLICABLE OBJECTIVES STP-500-0705, Bypassing Control Rods in RACS, RLP-STM-0503, Obj 18, 21 Rev 16 SOP-0071, Rod Control & Information System, Rev 29 REQUIRED MATERIALS: SAFETY FUNCTION:

Marked up copy of STP-500-0705, Rev 16 __7__

Completed section 6 with exception of applicant signing as second performer in Sect 6.2.

SOP-0071, Rev 29 SIMULATOR CONDITIONS & SETUP:

1. NA - This is a Control Room JPM.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Control Rod 16-25 has been bypassed in the RACS Cabinets.

RJPM-NRC-D14-C2 Rev 0 Page 3 of 12

RJPM-NRC-D14-C2 Rev. 0 PERFORMANCE:

START TIME:

Procedure Step: 4 Required Equipment 4.1 Key Number 1161, located on the Reactor Operator key ring in the Unit Operator desk, will be needed to access the Rod Bypass file.

Standard NA Cue Say, You have the key.

Notes The key is not needed; all controls can be viewed without the key.

Procedure Step: 6 Prerequisites 6.2 Each performer indicates that they have read and understand this procedure by completing the following:

Standard NA - Applicant should sign in section 6.2 Cue Notes Procedure Step: 7.1 Perform Attachment 2, Control Rods to be Bypassed for each Control Rod to be bypassed.

Standard NA Cue Notes This step is a placekeeper.

RJPM-NRC-D14-C2 Rev 0 Page 4 of 12

RJPM-NRC-D14-C2 Rev. 0 Attachment 2, Control Rods to be Bypassed Procedure Step: 1.1 Perform the matrix below for each control rod to be bypassed.

Standard NA Cue Notes This step is a placekeeper.

1. Procedure Step: Matrix Column 1 Row 1 Record the Control Rod being Bypasses.

Standard Applicant recorded rod 16-25 on Attachment 2 Matrix (p.2 of 2).

Cue Notes Results SAT UNSAT

2. Procedure Step: Matrix Column 1 Row 2 Step 1.2 complete 1.2 Prior to control rod movement, verify the movement of the control rod is per one of the following authorized movements

Rod movement per LCOs 3.1.3 bypassing of an inoperable control rod or 3.1.6 Action !.1 or B.1, movement to restore BPWS.

Standard Applicant identified first bullet of step 1.2 as applicable (from initiating cues), and initialed step.

Cue Notes Results SAT UNSAT

3. Procedure Step: Matrix Column 1 Row 3 Step 1.2 Ind. Verified Standard NA Cue As independent reviewer, inform the applicant that step 1.2 is verified.

Notes RJPM-NRC-D14-C2 Rev 0 Page 5 of 12

RJPM-NRC-D14-C2 Rev. 0

4. Procedure Step: Matrix Column 1 Row 4 Perform Attachment 3 Standard Applicant transitions to Attachment 3.

Cue Notes Results SAT UNSAT Attachment 3 PROCEDURE NOTE Technical Specifications requires verification of movement of bypassed control rods by two licensed operators or other Qualified members of the technical staff prior to and during movement. Steps 1.1 through 1.2 satisfy Tech Specs prior to rod motion and the remainder of this attachment satisfies Tech Specs during rod motion.

All Independent Verifications shall be completed prior to performing the next step.

5. Procedure Step: 1.1 Using the approved Reactivity Control Plan, record the control rod to be moved in step 1.6 through step 1.7, of this attachment.

Standard Applicant records control rod 16-25 in blanks on steps 1.6 and 1.7.

Applicant initials Step 1.1 as complete.

Cue As the concurrent verifier, inform applicant that step 1.7 is verified.

Notes Results SAT UNSAT RJPM-NRC-D14-C2 Rev 0 Page 6 of 12

RJPM-NRC-D14-C2 Rev. 0

6. Procedure Step: 1.2 Using Attachment 1, Control Rod number to Binary Code, determine binary code for selected Control Rod and record below.

Standard Applicant used attachment 1 (page 2 of 5) to identify the binary code for control rod 16-25 and recorded the following data in step 1.2 of Attachment 3 X4 = 0 X3 = 0 X2 = 1 X1 = 1 X0 = 0 Y4 = 0 Y3 = 1 Y2 = 0 Y1 = 0 Y0 = 0 Applicant initials Step 1.2 as complete.

Applicant request Independent Verifier. {Cue}

Cue As the independent verifier, inform applicant that step 1.2 is verified.

Notes Results SAT UNSAT NOTE The following switches are positioned to enter the Control Rod Binary Address. When the switch is in the RIGHT position, a 1 is input to the Address Register. When the switch is in the LEFT position, a 0 is input to the Address Register.

If a Control Rod Block exists for the bypassed control rod, once the selected control rod is bypassed, Annunciator, P680-07A-C01, CONTROL ROD WITHDRAWAL BLOCK should clear.

Steps 1.3 and 1.4 may be performed concurrently.

Key Number 1161, located on the Reactor Operator key ring in the Unit Operator desk, will be needed to access the Rod Bypass file.

All Independent Verifications must be performed by a second licensed operator or other technically qualified member of the Technical Staff.

RJPM-NRC-D14-C2 Rev 0 Page 7 of 12

RJPM-NRC-D14-C2 Rev. 0 7.

Procedure Step: 1.3 On H13-P651, Rod Bypass File A3, enter the address obtained in step 1.2 into the Bypass Cards Ident Select Switches of one bypass card.

Standard Operator simulated placing the switches in their proper positions on Panel H13-P651.

X4 = 0 (LEFT)

X3 = 0 (LEFT)

X2 = 1 (RIGHT)

X1 = 1 (RIGHT)

X0 = 0 (LEFT)

Y4 = 0 (LEFT)

Y3 = 1 (RIGHT)

Y2 = 0 (LEFT)

Y1 = 0 (LEFT)

Y0 = 0 (LEFT)

Applicant initialed step 1.3 of Attachment 3 Cue If requested, acknowledge whatever binary code sequence the applicant gives as simulated input.

Notes Any row of switches will work.

Results SAT UNSAT 8.

Procedure Step: 1.3.1 Place the BYPASS SWITCH in the BYPASSED Position on the effected card.

Standard Applicant placed the bypass switch in the BYPASS position.

Applicant initials step 1.3.1 of Attachment 3.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-C2 Rev 0 Page 8 of 12

RJPM-NRC-D14-C2 Rev. 0

9. Procedure Step: 1.3.2 Check that the BYPASSED LED comes on.

Standard Applicant located/identified and verified the bypass LED lit. {Cue}

Applicant initials step 1.3.2 of Attachment 3.

Cue Inform or represent to the applicant that the LED light is lit.

Notes The LED is immediately below the Bypass/Enable Switch and would be readily visible when lit.

Results SAT UNSAT 10.

Procedure Step: 1.4 H13-P652, Rod Bypass File A3, enter the address obtained in Step 1.2 into the Bypass Cards Ident Select Switches of one bypass card.

Standard Operator simulated placing the switches in their proper positions on Panel H13-P652.

X4 = 0 (LEFT)

X3 = 0 (LEFT)

X2 = 1 (RIGHT)

X1 = 1 (RIGHT)

X0 = 0 (LEFT)

Y4 = 0 (LEFT)

Y3 = 1 (RIGHT)

Y2 = 0 (LEFT)

Y1 = 0 (LEFT)

Y0 = 0 (LEFT)

Applicant initialed step 1.3 of Attachment 3 Cue If requested, acknowledge whatever binary code sequence the applicant gives as simulated input.

Notes Any row of switches will work.

Results SAT UNSAT RJPM-NRC-D14-C2 Rev 0 Page 9 of 12

RJPM-NRC-D14-C2 Rev. 0

11. Procedure Step: 1.4.1 Place the BYPASS SWITCH in the BYPASSED Position on the effected card.

Standard Applicant placed the bypass switch in the BYPASS position.

Applicant initials step 1.4.1 of Attachment 3.

Cue Notes Results SAT UNSAT

12. Procedure Step: 1.4.2 Check that the BYPASSED LED comes on.

Standard Applicant located/identified and verified the bypass LED lit. {Cue}

Applicant initials step 1.3.2 of Attachment 3.

Cue Inform or represent to the applicant that the LED light is lit.

Notes Results SAT UNSAT

13. Procedure Step: 1.5 Check that the POSITION BYP. LED comes on for Control Rod 16-25.

Standard NA Cue IF the applicant has given the proper codes for both RACS bypass file A3 cards, THEN inform the applicant that the POSITION BYP LED is ON for control rod 16-25.

IF the applicant has not given the proper codes for both RACS bypass file A3 cards, THEN inform the applicant that the POSITION BYP LED is not ON for control rod 16-25.

Notes Terminating Cue: Control Rod 16-25 has been bypassed in the RACS Cabinets.

This completes this JPM.

Cue:

STOP TIME:

RJPM-NRC-D14-C2 Rev 0 Page 10 of 12

RJPM-NRC-D14-C2 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-C2 Rev 0 Page 11 of 12

RJPM-NRC-D14-C2 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

The plant is performing a startup. Thermal power is less than 10% of rated. Control rod 16-25 is in the correct position when both position reed switches fail. In order to clear the rod block and continue rod movement Rod 16-25 will have to be bypassed in RACS.

INITIATING CUE:

In order to meet Technical Specification 3.1.3 requirements, the CRS directs you to bypass control rod 16-25 in accordance with STP-500-0705, Bypassing Control Rods in RACS.

RJPM-NRC-D14-C2 Rev 0 Page 12 of 12

RJPM-NRC-D14-P1 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Vent Scram Air Header per EOP-5, Enclosure 11 OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 17 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Dave Bergstrom Date: September 11, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-P1 Rev. 0 EXAMINER INFO SHEET Task Standard: Scram air header vented in accordance with EOP-0005, Enclosure 11 Synopsis: This task will have the applicant simulate venting the scram air header.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to perform EOP-0005, Enclosure 11, Venting Scram Air Header in order to insert control rods.

3) Initial Conditions:

An ATWS has occurred. Power is greater than 10%.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-P1 Rev 0 Page 2 of 7

RJPM-NRC-D14-P1 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Vent Scram Air Header per EOP-5, 201001005001 295037 EA1.05 3.9 / 4.0 Enclosure 11

REFERENCES:

APPLICABLE OBJECTIVES EOP-0005, Encl 11, Venting Scram Air Header RLP-HLO-0516, Obj 1 Rev 314 REQUIRED MATERIALS: SAFETY FUNCTION:

EOP-0005, Rev 314, Enclosure 11 __1__

SIMULATOR CONDITIONS & SETUP:

1. NA - This is an In Plant JPM.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Scram air header vented in accordance with EOP-0005, Enclosure 11.

RJPM-NRC-D14-P1 Rev 0 Page 3 of 7

RJPM-NRC-D14-P1 Rev. 0 PERFORMANCE:

START TIME:

1. Procedure Step: 3.1 OBTAIN EOP-0005 ENCL 11 tool kit from Control Room Emergency Locker.

Standard NA Cue Inform the applicant that he has the toolkit.

Notes 2.

Procedure Step: 3.2 CLOSE C11-VF095 INSTR AIR SUPPLY TO SCRAM PILOT VALVES ISOL (Containment EL 114 ft AZ 195, to right of backup scram valves).

Standard Applicant located/identified and simulated closing C11-VF095 by turning the handwheel fully counter clockwise.

Cue Inform the applicant that the handwheel is fully counter-clockwise.

Notes Results SAT UNSAT 3.

Procedure Step: 3.3 Remove test connection cap downstream of C11-PT-N052-V2 PILOT AIR HEADER PRESSURE TRANSMITTER TEST VALVE (above and left of backup scram valve)

Standard Applicant simulated using a crescent wrench to remove the test connection cap by rotating in a counter-clockwise direction.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-P1 Rev 0 Page 4 of 7

RJPM-NRC-D14-P1 Rev. 0 4.

Procedure Step: 3.4 OPEN C11-PT-N052-V2 PILOT AIR HEADER PRESSURE TRANSMITTER TEST VALVE Standard Applicant simulated opening the test valve by turning the handwheel in a counter-clockwise direction.

Cue Notes Results SAT UNSAT Terminating Cue: Scram air header vented in accordance with EOP-0005, Enclosure 11 This completes this JPM.

STOP TIME:

RJPM-NRC-D14-P1 Rev 0 Page 5 of 7

RJPM-NRC-D14-P1 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-P1 Rev 0 Page 6 of 7

RJPM-NRC-D14-P1 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

An ATWS has occurred. Power is greater than 10%.

INITIATING CUE:

The CRS has directed you to perform EOP-0005, Enclosure 11, Venting Scram Air Header in order to insert control rods.

RJPM-NRC-D14-P1 Rev 0 Page 7 of 7

RJPM-NRC-D14-P2 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Align Div 1 Standby Service Water to Fire Protection Water Supply OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 13 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Dave Bergstrom Date: September 11, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 7

RJPM-NRC-D14-P2 Rev. 0 EXAMINER INFO SHEET Task Standard: Div 1 SSW is lined up to supply the Fire Protection Water System.

Synopsis: This task will align the Standby Service Water System to the Fire Protection Water System Hose Racks.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to align Div 1 SSW to Control Building Fire Water in accordance with Section 5.3 of SOP-0037, Fire Protection Water System.

3) Initial Conditions:

The Div 1 Standby Service Water System has been initiated in the Main Control Room.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-P2 Rev 0 Page 2 of 7

RJPM-NRC-D14-P2 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Align Div 1 Standby Service Water to 400067004001 264000 K6.01 3.8 / 3.9 Fire Protection Water Supply 295003 AA1.02 4.2 /

4.3 REFERENCES

APPLICABLE OBJECTIVES SOP-0037, Fire Protection Water, Rev 35 RLP-STM-0250, Obj 11 REQUIRED MATERIALS: SAFETY FUNCTION:

SOP-0037, Fire Protection Water, Rev 35 __6__

SIMULATOR CONDITIONS & SETUP:

1. NA - This is an In Plant JPM.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Div 1 SSW is lined up to supply the Fire Protection Water System.

RJPM-NRC-D14-P2 Rev 0 Page 3 of 7

RJPM-NRC-D14-P2 Rev. 0 PERFORMANCE:

START TIME:

SOP-0037, Fire Protection Water System Section 5.3, Fire Protection Water Supply via Standby Service Water PROCEDURE CAUTION The cross connections described in this section will provide water for fire fighting via manual hose streams in the Control, Fuel, Auxiliary, and Reactor Buildings only. Water will not be available for any automatic water suppression systems.

Procedure Step: 5.3.1 Manually initiate Standby Service Water in accordance with SOP-0042, Standby Service Water System.

Standard NA Cue Notes This step is a place keeper; the initial conditions stated that SSW was initiated.

5.3.2 IF it is desired to supply fire protection hose racks in the Control or Diesel Buildings (including B tunnel), THEN perform the following at the Control Building Fire Protection Valve Header - 98 Elevation SW corner of Control Building:

1. Procedure Step: 1. Verify at least one division of standby Service Water is operating Div 1 Div 2 Standard Applicant verified (through initial conditions) that Div 1 SSW was operating.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-P2 Rev 0 Page 4 of 7

RJPM-NRC-D14-P2 Rev. 0 2.

Procedure Step: 2. IF Division 1 SSW is used, THEN perform the following:

1) Close FPW-V793, CB HOSE RACKS ISOLATION VALVE.

Standard Applicant located/identified and simulated closing FPW-V793 by turning the handwheel fully clockwise.

Cue Notes Results SAT UNSAT

3. *Procedure Step: 2. IF Division 1 SSW is used, THEN perform the following:

2) Unseal/Open SWP-V962, SVCE WTR SUPPLY TO FIRE PROTECTION IN CONTROL BLDG ISOL VLV.

Standard Applicant located/identified and simulated unsealing and opening SWP-V962 by turning the handwheel fully counter-clockwise.

Cue Notes Results SAT UNSAT

4. *Procedure Step: 2. IF Division 1 SSW is used, THEN perform the following:

3) Open FPW-V819, SWP BACKUP TO CB HOSE RACKS ISOLATION VALVE.

Standard Applicant located/identified and simulated opening FPW-V819 by turning the handwheel fully counter-clockwise.

Cue Notes Results SAT UNSAT Terminating Cue: Div 1 SSW is lined up to supply the Fire Protection Water System.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-P2 Rev 0 Page 5 of 7

RJPM-NRC-D14-P2 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-P2 Rev 0 Page 6 of 7

RJPM-NRC-D14-P2 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

The Div 1 Standby Service Water System has been initiated in the Main Control Room.

INITIATING CUE:

The CRS has directed you to align Div 1 SSW to Control Building Fire Water in accordance with Section 5.3 of SOP-0037, Fire Protection Water System.

RJPM-NRC-D14-P2 Rev 0 Page 7 of 7

RJPM-NRC-D14-P3 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Transfer ENB-SWG01A, 125 VDC STBY SWGR to Backup Charger OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant X Simulate Simulator Control Room Prepared: Dave Bergstrom Date: September 11, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 14

RJPM-NRC-D14-P3 Rev. 0 EXAMINER INFO SHEET Task Standard: ENB-SWG 01A is being supplied power from the backup battery charger.

Synopsis: During a station blackout event, or in the event of a battery charger becomes inoperable, power must be supplied to the Div 1 ENB bus. This task will align the backup battery charger to the ENB-SWG01A bus using SOP-0049, 125 VDC. An Alternate Path is taken when the normal manual transfer button is depressed: the transfer does not occur electrically and must therefore be performed manually.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to transfer ENB-SWG01A, 125 VDC Standby Switchgear to the backup charger per Section 5.7 of SOP-0049.

3) Initial Conditions:

The battery charger for ENB-SWG01A, 125 VDC Standby Switchgear is inoperable.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-P3 Rev 0 Page 2 of 14

RJPM-NRC-D14-P3 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Transfer ENB-SWG01A, 125 VDC 400039004001 263000 A4.01 3.3 / 3.5 STBY SWGR to Backup Charger.

REFERENCES:

APPLICABLE OBJECTIVES AOP-0014, Loss of 125 VDC, Rev 23 RLP-STM-0305, Obj 5,6 SOP-0049, 125 VDC, Rev 29 REQUIRED MATERIALS: SAFETY FUNCTION:

SOP-0049, 125 VDC, Rev 29 __6__

{print pp. 1-35}

SIMULATOR CONDITIONS & SETUP:

1. NA - This is an In Plant JPM.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: ENB-SWG 01A is being supplied power from the backup battery charger.

RJPM-NRC-D14-P3 Rev 0 Page 3 of 14

RJPM-NRC-D14-P3 Rev. 0 PERFORMANCE:

START TIME:

SOP-0049, 125 VDC 5.7, Transferring ENB-SWG 01A, 125 VDC STBY SWGR to Backup Charger PROCEDURE NOTE The following actions will render the Div 1 Battery Charger inoperable per TS 3.8.4 and 3.8.5. The Backup Charger can be used to meet the operability requirements of Tech Spec 3.8.4 for up to 7 days in Modes 1, 2, and 3.

Only one 125 VDC Switchgear can be placed on Backup Switchgear/Charger at a time.

1. Procedure Step: 5.7.1 Verify that the battery is connected to the battery bus by verifying the battery supply breaker at the 125 VDC switchgear is closed.

Standard Applicant located/identified and verified that the supply breaker is closed.

Cue Notes Results SAT UNSAT

2. Procedure Step: 5.7.2 On BYS-CHGR1D, 125 VDC Backup Battery Charger perform the following:

1. Verify open AC POWER breaker.

Standard Applicant located/identified and verified the AC power breaker open.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-P3 Rev 0 Page 4 of 14

RJPM-NRC-D14-P3 Rev. 0

3. Procedure Step: 5.7.2 On BYS-CHGR1D, 125 VDC Backup Battery Charger perform the following:

2. Verify open DC POWER breakers.

Standard Applicant located/identified and verified the DC power breaker open.

Cue Notes Results SAT UNSAT

4. Procedure Step: 5.7.3 Verify no ACB is inserted into circuit breaker compartments on BYS-SWG01D, 125 VDC BACKUP CHARGER SWGR, per Attachment 1H, Electrical Lineup - BYS-CHGR1D and BYS-SWG01D.

Standard Applicant located/identified and verified that no breakers were installed except BYS-SWG01D in accordance with Attachment H. (next page)

Cue Notes Attachment H is on the next page of this JPM Results SAT UNSAT RJPM-NRC-D14-P3 Rev 0 Page 5 of 14

RJPM-NRC-D14-P3 Rev. 0 RJPM-NRC-D14-P3 Rev 0 Page 6 of 14

RJPM-NRC-D14-P3 Rev. 0 Procedure Step: 5.7.4 IF the Station Blackout Diesel Generator will be used to supply the Backup Battery Charger per SOP-0054, Station Blackout Diesel Generator, THEN perform the following:

Standard NA Cue Notes This step is NA - applicant will move on to step 5.7.5.

5.7.5 IF the normal supply, NJS-SWG1U, 480 VAC Normal Switchgear will be used to supply the Backup Battery Charger, THEN perform the following:

5. *Procedure Step: 1. On NJS-SWG1U, 480 VAC Normal Switchgear, rack in and close NJS-ACB 453, BYS-CHGR1D 125 VDC BAT CHGR Supply Breaker per OSP-0052, Breaker Racking and 13.8 KV To 480 VAC Transformer Disconnect Operations.

Standard Applicant simulated racking in and closing NJS-ACB 453.

Cue Notes Results SAT UNSAT

6. Procedure Step: 2. On BYS-TRS4, XFR SW FOR SBO POWER CONNECTION located at Normal Switchgear Building 123 ft el, align BYS-SWG 01D, 125 VDC BACKUP CHARGER SWGR to the normal supply as follows:

1) Push the NORMAL MANUAL TRANSFER Button.

Standard Applicant located/identified and depressed the Normal Manual Transfer pushbutton.

Cue Notes Results SAT UNSAT PROCEDURE NOTE If the panel door is locked, key # C420A on the Operators key ring can be used to unlock the door.

RJPM-NRC-D14-P3 Rev 0 Page 7 of 14

RJPM-NRC-D14-P3 Rev. 0 ALTERNATE PATH:

7. Procedure Step: 2) Open the panel door and verify the transfer mechanism is pointing to NORMAL position.

Standard Applicant opened the door and looked at the transfer mechanism.

{cue}

Cue The mechanism arrow is pointing down.

Notes The graphic below is from inside the panel.

Arrow pointing up means normal; arrow pointing down means emergency Results SAT UNSAT

8. Procedure Step: 3) IF BYS-TRS4, did NOT transfer electrically, THEN transfer by hand using the directions provided inside the switch panel.

Standard Applicant transitions to the directions found inside the panel.

Cue Notes The next page of this JPM has close-up pictures of the transfer mechanism Results SAT UNSAT Inside panel BYS-TRS4:

RJPM-NRC-D14-P3 Rev 0 Page 8 of 14

RJPM-NRC-D14-P3 Rev. 0 Inside BYS-TRS4 :

RJPM-NRC-D14-P3 Rev 0 Page 9 of 14

RJPM-NRC-D14-P3 Rev. 0

9. *Procedure Step: Manually transfer BYS-TRS4 to Normal Supply using the directions inside the cabinet Standard Applicant manually transferred BYS-TRS4 to NORMAL by turning handle counter-clockwise until arrow points to NORMAL.

Cue Notes Results SAT UNSAT SOP-0049, Section 5.7 5.7.6 On BYS-SWG 01D, 125 VDC BACKUP CHARGER SWGR, perform the following:

PROCEDURE NOTE The breaker lifting bracket and the hoist operating handle will be located in one of the following electrical storage lockers: 98 ft Normal Switchgear Building, 98 ft Control Building, or 116 ft Control Building.

The breaker hoist may possibly be secured in place with a retaining bolt and/or large tie wraps that will have to be removed to allow operation.

10. *Procedure Step: 1. Remove the ACB from Storage Compartment A, and insert it into ACB605, ENB-SWG 01A CONT BLDG breaker compartment.

Standard Applicant simulated moving the ACB from the storage compartment to the ENB-SWG 01B compartment.

Cue Notes Results SAT UNSAT

11. *Procedure Step: 2. Rack in and close ACB605, ENB-SWG01A CONT BLDG Breaker.

Standard Applicant simulated racking in and closing ACB605.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-P3 Rev 0 Page 10 of 14

RJPM-NRC-D14-P3 Rev. 0

12. *Procedure Step: 5.7.7 On ENB-CHGR1A, Div 1 125 VDC Standby Battery Charger, perform the following:

1. Open the AC POWER Breaker

2. Open the DC POWER Breaker Standard Applicant simulated opening both the AC and DC power breakers on ENB-CHGR 1A.

Cue Notes Results SAT UNSAT

13. *Procedure Step: 5.7.8 On ENB-SWG01A, 125 VDC STBY SWGR, perform the following:

1. Open and rack out ACB560, ENB-CHGR1A BAT CHARGER 300A CONTROL BLDG Breaker.

Standard Applicant simulated opening and racking out ACB 560.

Cue Notes Results SAT UNSAT

14. *Procedure Step: 5.7.8 On ENB-SWG01A, 125 VDC STBY SWGR, perform the following:

2. Remove ACB560, ENB-CHGR1A BAT CHARGER 300A CONTROL BLDG Breaker from its compartment, and insert it into ACB563, BYS-CHGR1D BACKUP CHARGER SWGR breaker compartment.

Standard Applicant simulated moving ACB560 to the ACB563 compartment.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-P3 Rev 0 Page 11 of 14

RJPM-NRC-D14-P3 Rev. 0

15. *Procedure Step: 5.7.8 On ENB-SWG01A, 125 VDC STBY SWGR, perform the following:

3. Rack in and close ACB563, BYS-CHGR1D BACKUP CHARGER SWGR Breaker.

Standard Applicant simulated racking in and closing ACB563.

Cue Notes Results SAT UNSAT

16. *Procedure Step: 5.7.9 On BYS-CHGR1D, 125 VDC Backup Battery Charger, perform the following:

1. Close the DC POWER Breaker

2. Close the AC POWER Breaker Standard Applicant simulated closing both the DC and AC power breakers on BYS-CHGR 1D.

Cue Notes Results SAT UNSAT Terminating Cue: ENB-SWG 01A is being supplied power from the backup battery charger.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-P3 Rev 0 Page 12 of 14

RJPM-NRC-D14-P3 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-P3 Rev 0 Page 13 of 14

RJPM-NRC-D14-P3 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

The battery charger for ENB-SWG01A, 125 VDC Standby Switchgear is inoperable.

INITIATING CUE:

The CRS has directed you to transfer ENB-SWG01A, 125 VDC Standby Switchgear to the backup charger per Section 5.7 of SOP-0049.

RJPM-NRC-D14-P3 Rev 0 Page 14 of 14

RJPM-NRC-D14-S1 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Pull Control Rods to Achieve Criticality, with a Trip of CRD Pump OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 21, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 13

RJPM-NRC-D14-S1 Rev. 1 EXAMINER INFO SHEET Task Standard: Reactor Mode switch is placed in Shutdown after receiving one accumulator fault for a withdrawn control rod.

Synopsis: The applicant is directed to withdraw control rods to achieve criticality. Before criticality is reached however, at the evaluators discretion, a CRD pump trip occurs. As an alternate path, the standby CRD pump is started but also trips.

The operator will be required to place the mode switch in SHUTDOWN after receiving an accumulator fault associated with a withdrawn control rod and RPV pressure less than 600 psig.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to withdraw control rods to achieve criticality and raise reactor power to the point of adding heat IAW RCP-014-20, beginning at step 39.

3) Initial Conditions:

A plant startup is in progress following a refueling outage.

GOP-0001 is completed up to step C.11 Control Rod withdrawal is in progress.

RCP-RBS-014-20 is completed through step 38.

Estimated criticality is step 40.

A Reactor Engineer is verifying Control Rods per the movement plan.

SRM initial count rate was 80 cpm.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-S1 Rev 1 Page 2 of 13

RJPM-NRC-D14-S1 Rev. 1 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Pull Control Rods to Achieve 201020001001 201005 A3.04 3.3 / 3.3 Criticality, with a Trip of CRD Pump 201006001001 201005 A4.01 3.7 / 3.7 201001 A2.01 3.2 / 3.3 295022 AK2.02 3.1 / 3.1 295022 AA1.01 3.1 /

3.2 REFERENCES

APPLICABLE OBJECTIVES RMP-RBS-018-02 RLP-STM-0500, Obj 8, 10, 11, 18 SOP-0071, Rev 29 OSP-0022, Sect 4.10 and Attach 1, Rev 72 ARP-601-22-A01, G02, Rev 16 ARP-680-07-C03, Rev 34 Tech Spec 3.1.5 REQUIRED MATERIALS: SAFETY FUNCTION:

RMP-RBS-018-02 __1__

All other procedures are available in the simulator SIMULATOR CONDITIONS & SETUP:

1. IC # 255

2. Required Power: Shutdown, De-pressurized, Startup RMP in progress.

3. Event T1: Trigger set up for a clogged CRD suction filter/ trip of CRD Pump A.

(to be fired at the evaluators discretion)

4. Event T2: CRD-P1B trip.

(set to automatically trip 45 seconds after starting pump)

5. Shutdown Cooling secured. Begin from Base IC #217 CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Reactor Mode switch is placed in Shutdown after receiving one accumulator fault for a withdrawn control rod.

RJPM-NRC-D14-S1 Rev 1 Page 3 of 13

RJPM-NRC-D14-S1 Rev. 1 PERFORMANCE:

START TIME:

SOP-0071 Section 5.1, Performing Control Rod Notch Movement PROCEDURE NOTE Section 5.1 is designated as Reference Use.

If problems with indications or stall flows greater than 4 gpm occur during rod movement, Attachment 8, Control Rod Deficiency Report should be completed.

Main Steam Line Radiation Monitor (MSLRM) indication will gradually lower over a one to two month period following On-Line NobleChem application. During this time period, power changes and rod movements are expected to result in MSLRM indication fluctuations.

1.

Procedure Step: 5.1.1. Notch Control Rod Withdrawal

1. At H13-P680, on the Rod Select Module, select the rod to be moved.

Standard Applicant selected the correct control rod per RCP-14-020, step 39 by depressing the two rod select numbers simultaneously. (rod 44-09)

Cue As the Peer Checker, verify that the intended control rod is selected.

Notes The selected rod will show rod position on the Rod Display Module.

OSP-0022, Operations General Administrative Guidelines, Attachment 1 would normally be used with the ATC, a Peer Checker, and a Reactivity SRO stationed at P680. See next page for a copy of this procedure.

Results SAT UNSAT RJPM-NRC-D14-S1 Rev 1 Page 4 of 13

RJPM-NRC-D14-S1 Rev. 1 RJPM-NRC-D14-S1 Rev 1 Page 5 of 13

RJPM-NRC-D14-S1 Rev. 1

2. Procedure Step: 5.1.1. Notch Control Rod Withdrawal

2. Depress SELECTED GROUP button to check positions of control rods within group are correct prior to movement.

Standard Applicant depressed and held the SELECTED GROUP button.

Applicant compared the control rods in the group on the Rod Display Module to the RMP for correct rods and correct rod positions.

Applicant then releases the SELECTED GROUP button.

Cue As the Peer Checker, verify the positions of the rods in the selected group prior to applicant withdrawing the rod.

Notes Results SAT UNSAT

3. Procedure Step: 5.1.1. Notch Control Rod Withdrawal

3. Check that a Rod Withdrawal Block or Inhibit does not exist.

Standard Applicant verified the lack of Control Rod Block and Inhibit by (1) observing extinguished inhibit lights on the Pattern Control section of the Operator Control Module (2) observing extinguished Withdraw Block light on the Rod Motion section of the Operator Control Module (3) observing extinguished Withdraw Block light on the vertical section of insert 7 on P680 (C01)

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S1 Rev 1 Page 6 of 13

RJPM-NRC-D14-S1 Rev. 1 4.

Procedure Step: 5.1.1. Notch Control Rod Withdrawal

4. On H13-P680, depress and hold C11-S334, WITHDRAW Pushbutton until the IN indicator is lit or the start of rod motion is observed.

Standard Applicant removed the cover for the withdraw button.

Applicant stated intent of withdrawing control rod 44-49 one notch from position 04 to position 06 Applicant depressed the WITHDRAW Pushbutton.

Applicant released the WITHDRAW Pushbutton when rod motion was observed.

Cue As Peer Checker, verify the intended action of withdrawing the correct rod one notch from position 04 to position 06.

Notes The peer checking is from OSP-0022 (copy on previous page of JPM)

Results SAT UNSAT

5. Procedure Step: 5.1.1. Notch Control Rod Withdrawal

5. Check that the new rod notch position displayed is the next highest even number.

Standard Applicant verified intended position of control rod just moved.

Applicant replaced cover on the WITHDRAW pushbutton.

Applicant observed plant response to control rod movement.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S1 Rev 1 Page 7 of 13

RJPM-NRC-D14-S1 Rev. 1

6. Procedure Step: 5.1.1. Notch Control Rod Withdrawal

1. At H13-P680, on the Rod Select Module, select the rod to be moved.

Standard Applicant will repeat JPM steps 1 through 5 as necessary/desired.

Cue Notes The applicant may be allowed to move as many rods as the evaluator would like to see. The reactor will be critical at approximately step 40 of the RMP the applicant is using.

The evaluator will may request Trigger 1 at ANY POINT following step 5, when ready for the CRD malfunction.

Results SAT UNSAT ALTERNATE PATH:

ARP-601-22A-G02, CRD Pump Suction Filter High D/P ARP-601-22A-B01, CRD Pump A Overload Pre-Trip Warning ARP-601-22A-A01, CRD Pump A Auto Trip PROCEDURE NOTE With no CRD Pumps running, the Reactor Recirc Pump seal purge supply is lost.

Procedure Step: Applicant transitions to ARP-601-22A-A01, CRD Pump A Auto Trip Standard NA Cue Explain to the applicant that the peer checker Reactor Operator (RO) will monitor the core while the applicant addresses the alarm.

Notes The first two alarms come in just prior to the Alarm/Trip of the CRD Pump, The Auto Trip Alarm requires Operator Actions.

The applicant will refer to ARP-601-22A-A01, CRD Pump Trip and perform the operator actions The dedicated reactivity reactor operator would not normally be the one to address the alarm in this situation; but for this JPM, he will be relieved by the peer checker.

RJPM-NRC-D14-S1 Rev 1 Page 8 of 13

RJPM-NRC-D14-S1 Rev. 1

7. Procedure Step: 1. Start the standby CRD Pump as follows:

a. Start Standby CRD Pump Aux Oil Pump C11-C001BP Standard Applicant started the B - CRD Aux Oil Pump.

Cue Notes Turning the start switch (spring return) will start the aux oil pump, indicated by a red light on, green light off.

There is a also a white control power light above the CRD pump breaker that will energize as part of the starting logic. (checked in step 1d)

Results SAT UNSAT

8. Procedure Step: 1. Start the standby CRD Pump as follows:

b. Place Flow Controller C11-R600 to MANUAL.

Standard Applicant moved the lever from A (Auto) to M (Manual) (right-to-left) at the bottom of the Flow Controller.

Cue Notes Results SAT UNSAT

9. Procedure Step: 1. Start the standby CRD Pump as follows:

c. Close C11-R600, CRD Hydraulics Flow Controller C11-F002A/B Standard Applicant depressed and held the manual close button on the Flow Controller until the flow controller indicated closed, then released the button.

Cue Notes The Flow Controller is closed when 0% is indicated on the dial immediately above the Open/Close pushbuttons.

Results SAT UNSAT RJPM-NRC-D14-S1 Rev 1 Page 9 of 13

RJPM-NRC-D14-S1 Rev. 1

10. Procedure Step: 1. Start the standby CRD Pump as follows:

d. Verify White Control Power Light on for CRD Pump to be started.

Standard Applicant verified control power light is on.

Cue Notes There is an oil pressure switch in the start logic of the CRD pump that will energize the white light and allow the pump to be started. This light came on very shortly after turning on the Aux Oil Pump in step 1a.

Results SAT UNSAT

11. Procedure Step: 1. Start the standby CRD Pump as follows:

e. Start Standby Pump C11-C001B, CRD Pump B.

f. Verify amps return to normal of less than 45 amps.

Standard Applicant rotated the breaker switch for the B CRD pump in a clockwise direction and allowed the switch to spring return to mid-position.

Applicant located and verified the motor amps for CRD pump B return to less than 45 amps.

Cue Notes Results SAT UNSAT Evaluator NOTE:

While no CRD pumps are running, control rod accumulator pressures are lowering. There is an alarm associated with low accumulator pressure: P680-07-C03, Accumulator Trouble. The ARP currently being used, ARP-601-22A-A01 has actions to take for these conditions (accumulator fault on a withdrawn control rod and reactor pressure less than 600 psig). The applicant may or may not reference the ARP for the accumulator fault, ARP-680-07-C03, but will perform the action anyway (to determine which rod is alarming).

During validation, the first accumulator fault occurred after approximately __minutes.

CRD Pump B trips 30 seconds after starting.

RJPM-NRC-D14-S1 Rev 1 Page 10 of 13

RJPM-NRC-D14-S1 Rev. 1 CRD Pump B trips

12. Procedure Step: 1. Start the standby CRD Pump as follows:

g. WHEN system flow drops below 45 gpm as indicated on C11-R606, CRD HYDR FLOW, THEN slowly throttle open Flow Controller C11-R600 to achieve 45 gpm.

Standard Applicant recognizes and reports CRD Pump B trip.

Applicant transitions to Operator Actions step 2 of ARP-601-22A-A01.

Cue Notes Results SAT UNSAT

13. Procedure Step: 2. If neither CRD Pump can be restarted, THEN perform the following:

a. IF reactor pressure is less than 600 psig AND one or more control rod accumulator faults exist for withdrawn control rod(s) which can not be inserted, THEN immediately place the reactor mode switch to SHUTDOWN per LCO 3.1.5 Condition D.

Standard When one accumulator faults exist on a withdrawn control rod, the applicant placed the mode switch to SHUTDOWN.

Cue Notes Results SAT UNSAT Terminating Cue: Reactor Mode switch is placed in Shutdown after receiving one accumulator fault for a withdrawn control rod.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-S1 Rev 1 Page 11 of 13

RJPM-NRC-D14-S1 Rev. 1 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S1 Rev 1 Page 12 of 13

RJPM-NRC-D14-S1 Rev. 1 OPERATOR CUE SHEET INITIAL CONDITIONS:

A plant startup is in progress following a refueling outage.

GOP-0001 is completed up to step C.11 Control Rod withdrawal is in progress.

RCP-RBS-014-20 is completed through step 38.

Estimated criticality is step 40.

A Reactor Engineer is verifying Control Rods per the movement plan.

SRM initial count rate was 80 cpm.

INITIATING CUE:

The CRS has directed you to withdraw control rods to achieve criticality and raise reactor power to the point of adding heat IAW RCP-014-20, beginning at step 39.

RJPM-NRC-D14-S1 Rev 1 Page 13 of 13

RJPM-NRC-D14-S2 Rev 1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Shutdown RCIC using SOP - w/ Drain Trap Level High OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 5 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 4, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 11

RJPM-NRC-D14-S2 Rev. 1 EXAMINER INFO SHEET Task Standard: RCIC secured, in a standby lineup with the Gland Seal Compressor running.

Synopsis: RCIC is running and will be placed into a standby condition by the applicant. Near the end of the procedure, an Annunciator comes in that causes the operator to respond. The direction in the Alarm Response Procedure will have the applicant restart the Gland Seal Compressor.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to secure RCIC using the SOP and place it in a Standby Lineup.

3) Initial Conditions:

RCIC has just completed a post-maintenance test and is ready to be placed into a standby condition.

RCIC is currently running in a CST to CST lineup.

Containment Low Volume Purge is in progress.

RHR-A is in Suppression Pool Cooling mode of operation

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-S2 Rev 1 Page 2 of 11

RJPM-NRC-D14-S2 Rev. 1 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Shutdown RCIC using SOP - w/ Drain 217018001001 217000 A4.03 3.4 / 3.3 Trap Level High 217000 A4.10 3.6 / 3.5 Reason for Revision

REFERENCES:

APPLICABLE OBJECTIVES SOP-0035, Rev 47 RLP-STM-0209, Obj 5,10 ARP-601-21-A02, Rev 312, RCIC Turbine Exhaust Drain Trap Level High REQUIRED MATERIALS: SAFETY FUNCTION:

Simulator Copy of SOP and ARP __2__

SIMULATOR CONDITIONS & SETUP:

1. IC # 257

2. Rx Power: any

3. RCIC running in a CST to CST lineup

4. Cont Low Vol Purge and Supp Pool Cooling running

5. T1: Malfunction for initiating the alternate path (p601_21a:a02)

6. Event 1: zdi5(561) = 1 event triggered by the RCIC Gland Seal Compr. switch to STOP with a delay of 12 seconds CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: RCIC secured, in a standby lineup with the Gland Seal Compressor running.

RJPM-NRC-D14-S2 Rev 1 Page 3 of 11

RJPM-NRC-D14-S2 Rev. 1 PERFORMANCE:

START TIME:

SOP-35, Section 6.1, RCIC System Shutdown

1. *Procedure Step: 6.1.1 Depress E51-S17, RCIC Turbine Trip pushbutton.

Standard Applicant depressed the RCIC Trip Pushbutton.

Cue Notes Results SAT UNSAT

2. Procedure Step: 6.1.2 Verify E51-MOVC002, RCIC Trip & Throttle Valve Position indicates closed.

Standard Applicant verified the Trip/Throttle Valve closed as indicated by the green light on and the red light off.

Cue Notes Results SAT UNSAT

3. Procedure Step: 6.1.3 Verify RCIC speed lowering as indicated on E51-C002-1, RCIC TURB SPEED.

Standard Applicant verified RCIC speed lowering as indicated on E51-C002-1.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S2 Rev 1 Page 4 of 11

RJPM-NRC-D14-S2 Rev. 1

4. Procedure Step: 6.1.4 Reset any RCIC Initiation signals as follows:

1. Verify E51-C002C, Gland Seal Compressor control switch in START

2. Depress the RCIC Initiation Reset pushbutton

3. Verify RCIC Initiation Reset white light is off.

Standard Applicant verified the Gland Seal Compressor Switch in Start as indicated by the switch being in the AUTO position and the red flag showing.

Applicant depressed the RCIC Initiation Reset pushbutton.

Applicant verified the white initiation reset light off.

Cue Notes Results SAT UNSAT

5. *Procedure Step: 6.1.5 Close E51-F045, RCIC Steam Supply Turbine Stop Valve and verify the following:

E51-F025, RCIC STM SPLY DR POT Up Stream ISOL Valve is open.

E51-F026, RCIC STM SUPLY DR POT Dn Stream ISOL Valve is open.

E51-F004, RCIC Turb Exh DR POT Up Stream ISOL Valve is open.

E51-F005, RCIC Turb Exh DR POT Dn Stream ISOL Valve is open.

Standard Applicant closed the F045 valve by rotating handswitch and verified it closed as indicated by the green light on and the red light off.

Applicant verified the four indicated isolation valves are open as indicated by the green lights on and the red lights off.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S2 Rev 1 Page 5 of 11

RJPM-NRC-D14-S2 Rev. 1

6. Procedure Step: 6.1.6 Verify E51-F013, RCIC Inject Isol Valve is closed Standard Applicant verified the valve closed as indicated by the green light on and the red light off.

Cue Notes Results SAT UNSAT

7. Procedure Step: 6.1.7 Verify E51-F022, RCIC Test Bypass Vlv to CST is closed Standard Applicant closed the test bypass valve by rotating and holding the handswitch to close until the green light was on and the red light off.

Cue Notes Results SAT UNSAT

8. Procedure Step: 6.1.8 Verify E51-F059, RCIC Test Return Vlv to CST is closed Standard Applicant closed the test return valve by rotating the handswitch to close and observing the green light on and the red light off.

Cue Notes Results SAT UNSAT

9. Procedure Step: 6.1.9 Verify E51-F019, RCIC Min Flow Vlv to Suppression Pool is closed Standard Applicant verified the min flow valve closed as indicated by the green light on and the red light off.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S2 Rev 1 Page 6 of 11

RJPM-NRC-D14-S2 Rev. 1

10. Procedure Step: 6.1.10 Close E51-C002, RCIC Trip & Throttle Valve Operator.

Standard Applicant rotated the Trip/Throttle switch to CLOSE and held it there until the valve closes as indicated by the green light on and the red light off.

Cue Notes This is a spring return throttle valve switch Results SAT UNSAT

11. Procedure Step: 6.1.11 IF a RCIC isolation signal is not present, THEN open E51-C002, and verify RCIC Trip & Throttle Valve Position red light is on.

Standard Applicant rotated the Trip/Throttle switch to OPEN and held it there until the valve opened as indicated by the red light on and the green light off.

Cue Notes Results SAT UNSAT

12. Procedure Step: 6.1.12 Verify E51-R600, RCIC Pump Flow Flow Controller HVYC002 in AUTO and set to 600 gpm.

Standard Applicant adjusted the tape set on E51-R600 to set it to 600 gpm.

Cue Notes The flow controller is set for 400 gpm when the JPM begins.

Results SAT UNSAT RJPM-NRC-D14-S2 Rev 1 Page 7 of 11

RJPM-NRC-D14-S2 Rev. 1

13. Procedure Step: 6.1.13 WHEN RCIC has been secured for 15 to 30 minutes, THEN add oil as necessary to re-establish level just below the maximum level indication.

Standard {cue 1}

Applicant contacted the building operator to perform step 6.1.13.

{cue 2}

Cue {1} time compression: it has been 30 minutes.

{2} as building operator, accept direction to add oil and report back that oil levels are satisfactory.

Notes Results SAT UNSAT

14. Procedure Step: 6.1.14 WHEN 30 minutes have elapsed, THEN stop E51-C002C, Gland Seal Compressor Standard Applicant rotated the compressor breaker switch to STOP.

Cue Notes Previous cue told the applicant that 30 minutes have passed.

When applicant rotates switch to STOP, a malfunction will automatically be inserted that causes a turbine exhaust drain trap high level.

Results SAT UNSAT ALTERNATE PATH:

Procedure Step: ALARM: ARP-601-21A-A02, RCIC Turbine Exhaust Drain Trap Level High Standard Applicant transitions to ARP Cue Notes RJPM-NRC-D14-S2 Rev 1 Page 8 of 11

RJPM-NRC-D14-S2 Rev. 1

15. Procedure Step: 1. Verify Automatic Actions occur.

Standard Applicant verified that automatic actions occurred by checking E51-F005, RCIC Turb Exh DR POT Dn Stream ISOL Valve is open as indicated by the red light on and the green light off, AND E51-F045, RCIC Steam Supply Turbine Stop Valve is closed as indicated by the the green light on and the red light off.

Cue If called, as work control/maintenance/I&C, accept the direction to investigate Notes Results SAT UNSAT

16. Procedure Step: 2. Verify E51-F004, RCIC Turb Exh DR POT Up Stream ISOL Valve is open.

Standard Applicant verified that E51-F004, RCIC Turb Exh DR POT Up Stream ISOL Valve is open as indicated by the red light on and the green light off.

Cue Notes Results SAT UNSAT

17. *Procedure Step: 3. Start E51-C002C, Gland Seal Compressor and run for at least 20 minutes after alarm clears.

Standard Applicant starts the Gland Seal Compressor by rotating the breaker switch to the start position and verifying the red light on and the green light off.

Cue Notes Results SAT UNSAT Terminating Cue: RCIC secured, in a standby lineup with the Gland Seal Compressor running.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-S2 Rev 1 Page 9 of 11

RJPM-NRC-D14-S2 Rev. 1 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S2 Rev 1 Page 10 of 11

RJPM-NRC-D14-S2 Rev. 1 OPERATOR CUE SHEET INITIAL CONDITIONS:

RCIC has just completed a post-maintenance test and is ready to be placed into a standby condition.

RCIC is currently running in a CST to CST lineup.

Containment Low Volume Purge is in progress.

RHR-A is in Suppression Pool Cooling mode of operation INITIATING CUE:

The CRS has directed you to secure RCIC using the SOP and place it in a Standby Lineup.

RJPM-NRC-D14-S2 Rev 1 Page 11 of 11

RJPM-NRC-D14-S3 Rev 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Adjust Pressure Regulator to Minimize Thrust Reversal OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 10 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 5, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 6

RJPM-NRC-D14-S3 Rev. 0 EXAMINER INFO SHEET Task Standard: Pressure Set has been adjusted to between 999 and 1005 psig.

Synopsis: The reactor is at 70% power during a plant startup. This task will have the applicant perform a calculation and then make an adjustment to the EHC System Pressure Setpoint.

Precaution 3.25 of the GOP gives insight as to why this procedure is done when power is between approx. 55% and 70% and then restored. (Steps G34 and G44 respectively)

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM.

When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to perform pressure regulator adjustments to minimize Recirc Pump seal thrust reversal IAW GOP-0001, Plant Startup, Step G.44.

3) Initial Conditions:

The reactor is at 70% power during a plant startup.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-S3 Rev 0 Page 2 of 6

RJPM-NRC-D14-S3 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Adjust Pressure Regulator to Minimize 245013001001 241000 K4.01 3.8 / 3.8 Recirc Pump Seal Thrust Reversal A1.14 3.4 /

3.4 REFERENCES

APPLICABLE OBJECTIVES GOP-0001, Rev 82 (Step G.44/Attach 9) RLP-STM-0509 EHC, Obj 7, 9 REQUIRED MATERIALS: SAFETY FUNCTION:

Marked up copy of GOP-0001 (Sim Copy) __3__

SIMULATOR CONDITIONS & SETUP:

1. IC # 257 run with S2

2. Required Power: IAW GOP-1, approximately 70% power with Core Flow >70%

3. ERIS operating with computer points available for performing Attachment 9

4. Mark up a copy of GOP-0001, up to step G.44 for the students use in the simulator.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Pressure Set has been adjusted to between 999 and 1005 psig.

RJPM-NRC-D14-S3 Rev 0 Page 3 of 6

RJPM-NRC-D14-S3 Rev. 0 PERFORMANCE:

START TIME:

GOP-0001, Plant Startup, Attachment 9

2. IF returning the pressure set to the Nominal Press, THEN perform the following:

1. Procedure Step: 2.1 Determine the nominal pressure for the current reactor power (CTP %

Rated), using the Reactor Pressure Set Adjustment graph on the next page of this Attachment Standard Applicant determined the nominal pressure to be 1013 psig (+/- 3 psig).

Cue Notes Results SAT UNSAT Procedure Note:

Pressure Set may need to be adjusted within the bounds of the graphs as st necessary to insure that the 1 admission main turbine control valves, MSS-HVYCV1, 2, and 3 are full open. (lowering pressure set opens valves)

If computer points C33EA028 and C33EA200 are not available, pressure set may be adjusted using computer point B21EA044 provided that the accuracy of the point is validated by comparison against temperature points C33NA007 and C33NA008 using the relationship between saturated pressure and temperature.

2.

Procedure Step: 2.2 On H13-P680, using the PRESSURE SETPOINT, INCREASE pushbuttons, adjust pressure set point to the pressure determined in step 2.1 using the higher of the two ERIS points C33EA200 or C33EA028 OR B21EA044 Standard Applicant depressed Pressure Set Increase / Decrease Pushbuttons to adjust Pressure Setpoint to the nominal pressure using computer point.

Cue Notes Computer points must be used. Higher ERIS point when validated was C33EA028 (which was equal to the B21EA044)

Results SAT UNSAT Terminating Cue: Pressure Set has been adjusted to 1013 psig (+/- 3 psig).

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-S3 Rev 0 Page 4 of 6

RJPM-NRC-D14-S3 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S3 Rev 0 Page 5 of 6

RJPM-NRC-D14-S3 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

The reactor is at 70% power during a plant startup.

INITIATING CUE:

The CRS has directed you to perform pressure regulator adjustments to minimize Recirc Pump seal thrust reversal IAW GOP-0001, Plant Startup, Step G.44.

RJPM-NRC-D14-S3 Rev 0 Page 6 of 6

RJPM-NRC-D14-S4 Rev 1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Reduce SDC to only RHR-A - w/ overload pre-trip alarm OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS*: (Circle one)

SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 4, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 9

RJPM-NRC-D14-S4 Rev. 1 EXAMINER INFO SHEET Task Standard: RHR-B is secured from SDC and RHR-A motor amps restored to normal.

Synopsis: With the plant shutdown and two loops of Shutdown Cooling in service, the applicant is tasked with securing RHR-B loop of SDC. When the applicant reaches a particular step, an automatic trigger will cause a malfunction that makes the motor amps of the RHR-A pump to rise and an alarm to be activated. The applicant will then need to refer to the ARP for that alarm and take action to reduce the motor amps.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to secure RHR-B from Shutdown Cooling and to place RHR-B in standby per SOP-0031 beginning at step 5.6.11.

3) Initial Conditions:

RHR-A and RHR-B are in SDC.

4) Solicit and answer any questions the operator may have.

RJPM-NRC-D14-S4 Rev 1 Page 2 of 9

RJPM-NRC-D14-S4 Rev. 1 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Reduce SDC to only RHR-A - 205022001001 205000 A1.07 2.2 / 2.1 w/ overload pre-trip alarm 205000 A3.03 3.5 / 3.3 205000 A4.09 3.1 / 3.1 Reason for Revision

REFERENCES:

APPLICABLE OBJECTIVES SOP-0031, RHR, Rev 321 RLP-STM-0204, Obj 8, 10 ARP-601-20A-A04 REQUIRED MATERIALS: SAFETY FUNCTION:

Simulator Copy SOP-31 and ARP __2__

SIMULATOR CONDITIONS & SETUP:

1. IC # 247

2. Rx Power: Shutdown with RHR-A & B in SDC lineup

3. T1: malfunction p601_20a:a_4 fail on, delay 18 sec override AO_E12-C002A 109 amps, ramp 16 seconds

4. Event 1: FWS-7B Open switch zdi6(216) = 1

5. T2: malfunction p601_20a:a_4 fail on, delete 5 seconds override AO_E12-C002A 91 amps, ramp 18 seconds

6. Event 2: rhfrhr(1) < 622 represents RHR Loop Flow of approx. 4500 gpm CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: RHR-B is secured from SDC and RHR-A motor amps restored to normal.

RJPM-NRC-D14-S4 Rev 1 Page 3 of 9

RJPM-NRC-D14-S4 Rev. 1 PERFORMANCE:

START TIME:

SOP-0031, RHR Section 5.6, Shifting Divisions of Shutdown Cooling (Both Loops Operating) 5.6.11 Secure RHR A(B) from SDC as follows:

1. Procedure Step: 1. Simultaneously perform the following while maintaining flow between 1500 gpm and 2000 gpm to prevent automatic opening of E12-F064A(B),

RHR PUMP A(B) MIN FLOW TO SUP PL:

Throttle closed E12-F003B, RHR B HX OUTLET VALVE

Throttle open E12-F0048B, RHR B HX BYPASS VALVE Standard Applicant simultaneously closed the HX Outlet valve while opening the HX Bypass valve until the HX outlet valve was fully closed as indicated by the green light on and the red light off.

Cue Notes Results SAT UNSAT

2. *Procedure Step: 2. WHEN E12-F003B is full closed, THEN stop E12-C002B, RHR PUMP B Standard Applicant rotated the RHR-B pump breaker switch counter-clockwise and observed the green light on and the red light off.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S4 Rev 1 Page 4 of 9

RJPM-NRC-D14-S4 Rev. 1

3. *Procedure Step: 3. Close the following:

E12-F006B, RHR PUMP B SDC SUCTION VALVE Standard Applicant closed the valve by rotating the handswitch to the close position and observing the green light on and the red light off.

Cue Notes Results SAT UNSAT

4. *Procedure Step: 3. Close the following:

E12-F053B, RHR PUMP B SDC INJECTION VALVE Standard Applicant closed the valve by rotating the handswitch to the close position and observing the green light on and the red light off.

Cue Notes Results SAT UNSAT

5. Procedure Step: 3. Close the following:

E12-F048B, RHR B HX BYPASS VALVE Standard Applicant closed the valve by rotating the handswitch to the close position and observing the green light on and the red light off.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S4 Rev 1 Page 5 of 9

RJPM-NRC-D14-S4 Rev. 1

6. Procedure Step: 3. Close the following:

IF FWS-MOV7B, B FW OUTBD ISOL is closed, THEN open FWS-MOV7B Standard Applicant opened the valve by depressing the OPEN pushbutton and observing the red light on and the green light off.

Cue Notes The malfunction is automatically triggered 12 seconds after the Open pushbutton is depressed.

Results SAT UNSAT ALTERNATE PATH:

Applicant transitions to ARP-601-20A-A04, RHR Pump A Overload Pre-Trip Warning 3 Procedure Step: 1. Verify the following:

RHR Pump A discharge flow is less than 5950 gpm.

E12-F064A, RHR Pump A Min Flow to Supp Pool is closed Standard Applicant reports the alarm to the CRS.

{cue}

Applicant located the meter and observed that pump flow is less than 5950.

Applicant verified the min flow valve closed by observing the green light on and the red light off.

Cue As the CRS, accept the report of the pre-trip warning on RHR-A.

Notes Results SAT UNSAT RJPM-NRC-D14-S4 Rev 1 Page 6 of 9

RJPM-NRC-D14-S4 Rev. 1 4 *Procedure Step: 2. Reduce pump motor amps by throttling closed any of the following valves:

E12-F003A, RHR A HX OUTLET VALVE

E12-F048A, RHR A HX BYPASS VALVE Standard Applicant closed either the F003 or the F048 valves, by intermittently rotating the control switch counterclockwise and observing RHR A Loop Flow.

Cue Notes Motor amps will reduce when flow in the RHR-A loop is reduced to 4500 gpm Results SAT UNSAT Terminating Cue: RHR-B is secured from SDC and RHR-A motor amps restored to normal.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-S4 Rev 1 Page 7 of 9

RJPM-NRC-D14-S4 Rev. 1 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S4 Rev 1 Page 8 of 9

RJPM-NRC-D14-S4 Rev. 1 OPERATOR CUE SHEET INITIAL CONDITIONS:

RHR-A and RHR-B are in SDC.

INITIATING CUE:

The CRS has directed you to secure RHR-B from Shutdown Cooling and to place RHR-B in standby per SOP-0031 beginning at step 5.6.11.

RJPM-NRC-D14-S4 Rev 1 Page 9 of 9

RJPM-NRC-D14-S5 Rev. 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Secure from Containment High Volume Purge -w/ trip of Decay Heat Fan OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS*: (Circle one) SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 19, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 11

RJPM-NRC-D14-S5 Rev. 0 EXAMINER INFO SHEET TASK Containment High Volume Purge is secured and Standby Gas Treatment is in STANDARD: service following response to a trip of the Decay Heat Removal Fan.

SYNOPSIS: The plant had experienced elevated containment radiation levels and placed containment high volume purge in service. The cause has been remedied and the elevated rad levels have been reduced. This task will have the applicant secure containment high volume purge using SOP-0059, but due to a failure of the decay heat removal fan, the applicant will be required to re-start the Standby Gas Treatment Train.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to secure from containment high volume purge using SOP-0059, Containment HVAC System, starting at step 5.5.8.

3) Initial Conditions:

A containment radiation levels have been reduced by performing a high volume purge on containment per SOP-0059, Containment HVAC System.

RJPM-NRC-D14-S5 Rev 0 Page 2 of 11

RJPM-NRC-D14-S5 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Secure from Containment High 222023001001 295034 EA1.03 4.0 / 3.9 Volume Purge

-w/ trip of Decay Heat Fan

REFERENCES:

APPLICABLE OBJECTIVES:

SOP-0059, Containment HVAC, Rev 034 RLP-STM-0403 Objective 2, 12 ARP-863-73A-C03, Rev 8 SOP-0043, Standby Gas Treatment, Rev 17 REQUIRED MATERIALS: SAFETY FUNCTION:

Simulator copies of: __9__

SOP-0059 ARP-863-73A-C03 SOP-0043 SIMULATOR CONDITIONS & SETUP:

1. IC # 255

2. Required Power: no requirement Run concurrently with S4

3. High Volume purge in progress

4. T1 is to trip the decay heat fan with a delay of 5 seconds a) Malf: p863_73a:c_3 fail on Over: LO_GTS-FN2A stop LO_GTS-FN2A-G off LO_GTS-B3-A on Malf: p863_73a:d_6 on

5. Event 1: zdi2(458) = 1 (HVR-AOD 162 switch to close)

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: Containment High Volume Purge is secured and Standby Gas Treatment is in service following response to a trip of the Decay Heat Removal Fan.

RJPM-NRC-D14-S5 Rev 0 Page 3 of 11

RJPM-NRC-D14-S5 Rev. 0 PERFORMANCE:

START TIME:

SOP-0059, Section 5.5, Containment High Volume Purge.

1. Procedure Step: 5.5.8. WHEN Containment Purge is no longer required, THEN place HVR-FN8, HIGH VOL CONTMT/DW PURGE to STOP and verify HVR-AOD 244, HIGH VOL FAN DISCH closes.

Standard Applicant stopped Fan 8 by rotating the switch counterclockwise to STOP and observing the green light on and red light off.

Applicant verified HVR-AOD 244 damper closed by observing the green light on and red light off.

Cue Notes Results SAT UNSAT

2. Procedure Step: 5.5.9. Depress the GTS-FN1A, SGT EXH FAN A STOP Pushbutton and verify the following dampers close:

GTS-AOD1A, SGT FILTER A SUCT ISOL

GTS-AOD3A, SGT EXH FAN A DISCH Standard Applicant stopped Standby Gas Train A by depressing the STOP pushbutton and observing the green light on and red light off.

Applicant verified AOD 1A and 3A dampers closed by observing the green light on and red light off.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S5 Rev 0 Page 4 of 11

RJPM-NRC-D14-S5 Rev. 0

3. Procedure Step: 5.5.10. Verify proper Filter Train Decay Heat Removal operation by observing the following:

GTS-FN2A, SGT A DECAY HEAT REMOVAL running.

GTS-AOD4A, DECAY HEAT REMOVAL INTK is open.

Standard Applicant verified the Decay Heat Removal fan running by observing the red lights on and green lights off.

Applicant verified the intake damper open by observing the red lights on and green lights off.

Cue Notes Results SAT UNSAT

4. Procedure Step: 5.5.11. Close the following dampers and valves:

HVR-AOV165, CONTMT SPLY OUTBD ISOL

HVR-AOV123, CONTMT SPLY INBD ISOL

HVR-AOD124, CONTMT PURGE SPLY ISOL Standard Applicant closed the two valves and the one damper by locating and turning each switch to close and observing the green lights on and red lights off for each.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S5 Rev 0 Page 5 of 11

RJPM-NRC-D14-S5 Rev. 0

5. Procedure Step: 5.5.11. Close the following dampers and valves:

HVR-AOD127, CONTMT PURGE RTN ISOL

HVR-AOV128, CONTMT RTN INBD ISOL

HVR-AOV166, CONTMT RTN OUTBD ISOL Standard Applicant closed the 2 valves and one damper by locating and turning each switch to open and observing the green lights on and red lights off for each.

Cue Notes Results SAT UNSAT PROCEDURE NOTE HVR-AOD245(AOD162) is interlocked with the containment return valve, HVR-AOV128(AOV166). The control switch for the purge to SGT dampers must be taken to CLOSE to reset the logic, even when the damper is already closed.

6. Procedure Step: 5.5.12. Reset the logic by momentarily placing the control switches in CLOSE and then to the Mid position:

HVR-AOD245, CONTMT PURGE TO SGT

HVR-AOD162, CONTMT PURGE TO SGT Standard Applicant turned the control switch for AOD 245 to STOP and then back to mid position.

Applicant turned the control switch for AOD 162 to STOP and then back to mid position.

Cue Notes Placing AOD 162 to stop will automatically initiate the malfunction.

Results SAT UNSAT RJPM-NRC-D14-S5 Rev 0 Page 6 of 11

RJPM-NRC-D14-S5 Rev. 0 ALTERNATE PATH:

ANNUNCIATOR, P863-73A-C03 alarms.

Procedure Step: Respond to ANNUNCIATOR, P863-73A-C03, Div 1 SGT DECAY HEAT REMOVAL SYS INOPERATIVE.

1. IF GTS-AOD4A fails closed, THEN verify GTS-FN2A is stopped Standard Applicant recognizes, reports, and responds to the alarm:

Applicant recognizes that GTS-FN2A has neither green nor red lights lit.

Applicant dispatches operator to investigate.

Cue As CRS, accept report of fan trip.

Notes

7. Procedure Step: 2. IF SGT A Decay Heat Removal System was operating, THEN monitor temperature locally on GTS-TIS14A, local indication or ERIS Point GTSTY357.

Standard {cue}

Applicant contacts the building operator for local temperature indication of the charcoal bed.

Cue When the applicant enters the computer point, tell the applicant that the ERIS point reading is bad data.

When called, as the building operator, report that local temperature is reading 88 degrees.

Notes Results SAT UNSAT

8. Procedure Step: 3. IF temperature continues to increase, THEN start the A SGT Train per SOP-0043, Standby Gas Treatment System.

Standard {cue}

Applicant recognizes rising trend on charcoal bed temperature and transitions to SOP-0043.

Cue When called, as the building operator, report that local temperature is reading 90 degrees.

Notes Results SAT UNSAT RJPM-NRC-D14-S5 Rev 0 Page 7 of 11

RJPM-NRC-D14-S5 Rev. 0 SOP-0043, Section 4.1 Manual Startup Procedure Step: 4.1.1 IF Standby Gas will be started for testing 4.1.2 IF both Standby Gas trains will be operated simultaneously Standard NA Notes This is a place keeper

9. *Procedure Step: 4.1.3 Select one of the following areas for the GTS System to draw air and open the respective dampers:

1. Aux Building/Containment Annulus

HVR-AOD18A, AUX BLDG to GTS ISOLATION

HVR-AOD22A, ANNULUS MIXING OUT DMPR to GTS

2. Outside Air Supply

HVR-AOD263, SGT UPSTREAM SPLY ISOL

HVR-AOD264, SGT DNSTREAM SPLY ISOL Standard Applicant opened the two selected dampers by turning each switch to open and observing the red lights on and green lights off for each.

Cue As CRS, if asked, tell the applicant to use outside air.

Notes Results SAT UNSAT PROCEDURE NOTE The Standby Gas Treatment Exhaust Fan does not receive a start signal until after the suction damper is full open, therefore, the start switch must remain depressed until GTS-AOD1A, SGT FILTER A SUCT ISOL is full open.

10. *Procedure Step: 4.1.4 Start GTS-FN1A, SGT EXH FAN A by depressing the START Pushbutton and verify the following:

1. GTS-AOD1A, SGT FILTER A SUCT ISOL opens

2. GTS-FN1A, SGT EXH FAN A starts

3. GTS-AOD3A, SGT EXH FAN A DISCH opens Standard Applicant depressed and held the Start pushbutton until the AOD1A damper was full open and observed the red lights on and green lights off for each.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S5 Rev 0 Page 8 of 11

RJPM-NRC-D14-S5 Rev. 0

11. Procedure Step: 4.1.5 IF Standby Gas Treatment is aligned with suction form the Aux Building/Annulus, THEN verify open GTS-AOD22A, SGT FILTER A RECIRC to facilitate personnel access.

Standard Applicant verified the two dampers open by locating and observing the red lights on and green lights off for each damper.

Cue Notes Either JPM step 11 or 12 will be performed, not both.

Use this JPM step if applicant did not request the CRS to select the suction source and the applicant chose the Aux Bldg/Annulus.

Results SAT UNSAT 12.

Procedure Step: 4.1.5 IF Standby Gas Treatment is aligned with suction form the Aux Building/Annulus, THEN verify open GTS-AOD22A, SGT FILTER A RECIRC to facilitate personnel access.

Standard Applicant verified the two dampers open by locating and observing the red lights on and green lights off for each damper.

Cue Notes Either JPM step 11 or 12 will be performed, not both.

Use this JPM step if applicant chose the Outside air suction source.

Results SAT UNSAT Terminating Cue Containment High Volume Purge is secured and Standby Gas Treatment is in service following response to a trip of the Decay Heat Removal Fan.

STOP TIME:

RJPM-NRC-D14-S5 Rev 0 Page 9 of 11

RJPM-NRC-D14-S5 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S5 Rev 0 Page 10 of 11

RJPM-NRC-D14-S5 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

A containment pressure alarm has come in and containment pressure is currently 0.26 psig.

INITIATING CUE:

The CRS has directed you to perform a low volume purge on containment per SOP-0059, Containment HVAC System, Section 5.6.

RJPM-NRC-D14-S5 Rev 0 Page 11 of 11

RJPM-NRC-D14-S6 Rev. 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO ALTERNATE PATH TITLE: Start the Suppression Pool Cooling and Cleanup System OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): NA Actual Time (min): NA PERFORMANCE TIME: Average Time (min): Actual Time (min):

JPM RESULTS*: (Circle one) SAT UNSAT Refer to Grading Instructions at end of JPM EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: September 20, 2014 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

Approved: Joey Clark Date: October 18, 2014 (Facility Reviewer)

River Bend Station Initial License Exam Page 1 of 10

RJPM-NRC-D14-S6 Rev. 0 EXAMINER INFO SHEET TASK The Suppression Pool Cooling and Cleanup System has been started up using STANDARD: SOP-0140, section 5.2.

SYNOPSIS: The plant is performing a startup per GOP-0001. The reactor is at 50% power.

This task has the applicant start the Suppression Pool Cooling and Cleanup System using SOP-0140, Suppression Pool Cleanup and Alternate Decay Heat Removal section 5.2.

NOTE: If in the Plant or the Control Room, Caution the operator NOT to MANIPULATE the controls, but to make clear what they would do if this were not a simulated situation.

1) Read to the operator:

I will provide the initial conditions and initiating cues to you. I may also provide cues during the performance and ask follow-up questions at the conclusion of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied.

Inform me when you have completed the task.

2) Initiating Cues:

The CRS has directed you to start the Suppression Pool Cooling and Cleanup System using pump A in accordance with SOP-0140 Section 5.2.

3) Initial Conditions:

The plant is in Mode 1, operating at 50% power while performing a plant startup.

SPC/ADHR was secured after a loss of RPS bus using section 7.1 of SOP-0140, Suppression Pool Cleanup and Alternate Decay Heat Removal.

Suppression Pool Cooling is not required; the SPC Demin will be placed in service at a later time.

RJPM-NRC-D14-S6 Rev 0 Page 2 of 10

RJPM-NRC-D14-S6 Rev. 0 DATA SHEET TASK

Title:

Task Number K&A SYSTEM: K&A RATING:

Start the Suppression Pool Cooling 220004001001 209002 A2.14 3.0 / 3.3 and Cleanup System 209001 A2.10 3.1 /

3.4 REFERENCES

APPLICABLE OBJECTIVES:

SOP-0140, Rev 28, Section 5.2 RLP-STM-0656 Objective 7, 11 REQUIRED MATERIALS: SAFETY FUNCTION:

SOP-0059, Rev 034, Section 5.14 __5__

(Simulator copy)

SIMULATOR CONDITIONS & SETUP:

1. IC # 257 (Performed with S3)

2. Required Power: Any (this JPM set up for 50% power) 3.

CRITICAL ELEMENTS: Items marked with an

are Critical Steps and are required to be performed. Failure to successfully complete a Critical Step requires the JPM to be evaluated as Unsatisfactory.

TASK STANDARD: The Suppression Pool Cooling and Cleanup System has been started up using SOP-0140, section 5.2.

RJPM-NRC-D14-S6 Rev 0 Page 3 of 10

RJPM-NRC-D14-S6 Rev. 0 PERFORMANCE:

START TIME:

PROCEDURE NOTE:

The instrumentation and controls in this section are located at H13-P601 unless otherwise noted.

1. Procedure Step: 5.2.1 Notify Radiation Protection that system startup is in progress.

Standard NA Cue As the Rad Protection Department, accept report .

Notes

2. Procedure Step: 5.2.2 Verify E12-F105, RHR PUMP C SUP PL SUCTION VALVE is open Standard Applicant located/identified and verified the suppression pool suction valve for RHR-P1C open by checking the RED indicating light ON and GREEN indicating light OFF.

Cue Notes Results SAT UNSAT

3. Procedure Step: 5.2.3 Verify the following keyswitches are in NORMAL:

Standard NA Cue When asked, report that the back panel switches are in NORMAL.

Notes

4. Procedure Step: 5.2.4 IF the plant is in Mode 4, 5, or the reactor is defueled Standard NA Cue Notes This step is NA RJPM-NRC-D14-S6 Rev 0 Page 4 of 10

RJPM-NRC-D14-S6 Rev. 0

5. Procedure Step: 5.2.5 At AB, 95 el, Crescent Area, close RHS-V3022, RHR C TEST RETURN TO SP MANUAL ISOL VLV.

5.2.6 At AB, 70 ft el, Racquetball Room, perform the following:

Standard NA Cue As operator, report that steps 5.2.5 and 5.2.6 are complete.

Notes PROCEDURE CAUTION:

Maximum SPC-E1, SPC HEAT EXCHANGER service water flow is 2250 gpm.

6. Procedure Step: 5.2.7 IF Suppression Pool Cooling is required Standard NA Cue Notes This step is NA in accordance with the Initial Conditions.

PROCEDURE NOTE:

If SPC was filled to CNS pressure per section 5.1, opening RHS-AOV62, and RHS-AOV63 can cause momentary P618-E12-ESN653C gross fail annunciation on H13-P601, Insert 17.

7.

Procedure Step: 5.2.8 Open the following valves:

1. RHS-AOV63, SPC SUCTION VALVE

2. RHS-AOV62, SPC SUCTION VALVE

3. RHS-AOV64, SPC DISCH VALVE Standard Applicant located/identified and opened RHS-AOV63, RHS-AOV62, and RHS-AOV64 by placing their respective control switches in the OPEN position and by checking the RED indicating lights ON and GREEN indicating lights OFF.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S6 Rev 0 Page 5 of 10

RJPM-NRC-D14-S6 Rev. 0 8.

Procedure Step: 5.2.9 Open E12-MOV F021, RHR PUMP C TEST RTN TO SUP PL Standard Applicant located/identified and opened E12-MOV F021 by placing the control switch in the OPEN position and checking the GREEN indicating light OFF and the RED indicating light ON.

Cue Notes Results SAT UNSAT

9. Procedure Step: 5.2.10 At RW, 136 ft el, SPC-PNL200, open the following valves:

5.2.11 WHEN at least 5 seconds have elapsed, THEN close the valves:

Standard NA Cue As operator, report that steps 5.2.10 and 5.2.11 are complete.

Notes

10. Procedure Step: 5.2.12 IF Annunciator P601-20A-F02, SPC SYSTEM NOT FULL, alarms Standard NA Cue Notes This step is NA: The Alarm did not come in during validation.

11. Procedure Step: 5.2.13 IF SPC-P1A, SPC Pump A had auto tripped, THEN reset the trip as follows:

Standard NA Cue Notes According to the initial conditions, the system was secured in accordance with procedure.

12.

Procedure Step: 5.2.14 Start SPC-P1A, SPC PUMP A Standard Applicant located/identified and turned the control switch for SPC Pump A and checked the GREEN indicating light OFF and the RED indicating light ON.

Cue Notes Results SAT UNSAT RJPM-NRC-D14-S6 Rev 0 Page 6 of 10

RJPM-NRC-D14-S6 Rev. 0

13. Procedure Step: 5.2.15 Check open SPC-AOV25, SPC PUMP MINIMUM FLOW VALVE, as indicated by flow indication on SPC-FI 32, SPC Total Flow Standard Applicant located/identified and verified flow on SPC-FI 32.

Cue Notes This meter is located on the vertical section of the insert to the right of the SPC controls (Insert 17)

Results SAT UNSAT 14.

Procedure Step: 5.2.16 Throttle open SPC-AOV20, SPC FILTER DEMIN BYPASS VALVE to greater than 1500 gpm and less than or equal to 2250 gpm as indicated on SPC-FI 32, SPC TOTAL FLOW.

Standard Applicant located/identified and throttled open SPC-AOV20 by placing the control switch in the OPEN position until flow indicated between 1500 and 2250 gpm.

Cue Notes This is a spring return throttle type controller.

Results SAT UNSAT RJPM-NRC-D14-S6 Rev 0 Page 7 of 10

RJPM-NRC-D14-S6 Rev. 0

15. Procedure Step: 5.2.17 WHEN SPC-AOV25 closes, as indicated by a drop in flow on SPC-FI 32, SPC TOTAL FLOW, THEN adjust SPC-AOV20 to obtain system flow greater than 1500 gpm and less than or equal to 2250 gpm as indicated on SPC-FI 32, SPC TOTAL FLOW.

Standard After waiting for the flow indication to drop, the applicant located/identified and throttled open SPC-AOV20 by placing the control switch in the OPEN position until flow indicated between 1500 and 2250 gpm.

Cue Notes The SPC Min Flow Valve closes after about one minute; this will drop flow, but not out of the band if the applicant had flow toward the top of the directed band.

Results SAT UNSAT Terminating Cue: The Suppression Pool Cooling and Cleanup System has been started up using SOP-0140, section 5.2.

This completes this JPM.

STOP TIME:

RJPM-NRC-D14-S6 Rev 0 Page 8 of 10

RJPM-NRC-D14-S6 Rev. 0 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable.

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant RJPM-NRC-D14-S6 Rev 0 Page 9 of 10

RJPM-NRC-D14-S6 Rev. 0 OPERATOR CUE SHEET INITIAL CONDITIONS:

The plant is in Mode 1, operating at 50% power while performing a plant startup.

SPC/ADHR was secured after a loss of RPS bus using section 7.1 of SOP-0140, Suppression Pool Cleanup and Alternate Decay Heat Removal.

Suppression Pool Cooling is not required; the SPC Demin will be placed in service at a later time.

INITIATING CUE:

The CRS has directed you to start the Suppression Pool Cooling and Cleanup System using pump A in accordance with SOP-0140 Section 5.2.

RJPM-NRC-D14-S6 Rev 0 Page 10 of 10

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-1 IC No.: 251 Examiners: ________________ Operators: _____________________________

Initial Conditions: 84% reactor power B21-SRV51C is leaking - resulting in slowly rising suppression pool level ADS-SRV Leaking Alarm is in CWS-P1D tagged out for motor rewind Turnover Shift priorities: 1) Plant Shutdown in-progress due to leaking SRV; Reactor Engineering directs perform Step 2 of the RMP and then contact RE further guidance. 2) Perform SOP-0031, Section 4.8, Suppression Pool Reject to Radwaste Event Malf. Event Event No. No. Type* Description 0 MSS007K NA SRV 51C is leaking (Initial Condition) 1 NA R (ATC) Insert Control Rods per RMP step 2 (Reactivity Manipulation)

CRDM2025 C (SRO, ATC) Control Rod Accumulator Fault (Tech Spec) 2 NA N (SRO, BOP) Perform SOP-0031 Section 4.8, Suppression Pool Reject to Radwaste 3 RHR010A C (SRO, BOP) RHR A Pump Shaft Shear (Tech Spec) 4 FWS017A I (SRO, ATC) Steam Line Flow Transmitter A fails downscale (AOP-0006) 5 NA N (SRO,ATC) Perform SOP-0009 Section 6.3, Three Element to Single Element Control Transfer 6 ED003D C (SRO, ATC) Loss of NNS-SWG2A (AOP-0005) 7 CRDM2017 M (ALL) Reactor scram with turbine trip due to loss of vacuum CRDM3641 ATWS - 3 Control Rods CRDM4425 8 MSS005K C (SRO, BOP) Safety Relief Valve 51C fails open (AOP-0035) 9 RHS- C (BOP) RHS-AOV64 Fails to isolate. (AOP-0003)

AOV64P

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7) Accum Fault, RHR A Shear, MSL A Flow XMT, Loss NNS-SWG2A, SRV open, ATWS, RHS-AOV64 failure Malfunctions after EOP entry (1-2) (2) SRV open, failure to isolate Abnormal Events (2-4) (4), AOP-0006, AOP-0005, AOP-0035, AOP-0003 Major Transients (1-2) (1) Reactor scram with turbine trip due to loss of vacuum / 3 Control Rod ATWS EOPs entered (1-2) (2) EOP-0001/ EOP-0001A

December 2014 NRC Exam EOP contingencies (0-2) (1) Enter EOP-0001A Critical Tasks (2-3) (2) SRV closed; All control rods inserted General Scenario Outline Event 0 - The crew takes the shift with a plant shutdown (84%) in progress due to a leaking SRV. CWS-P1D is tagged out for motor rewind.

Event 1 - The team reduces reactor power with control rods per Step 2 of the shutdown reactivity maneuvering plan, which lowers reactor power to 80%. Following movement of the last control rod an accumulator fault occurs due to high moisture resulting in TRM 3.1.5.1 entry Event 2 - The team now starts RHR A in suppression pool cooling mode and begins reject of suppression pool to the radioactive waste system Event 3 - During establishment of suppression pool reject the shaft shears on RHR pump A requiring entry into Tech Spec 3.5.1 and 3.6.2.3. The system lineup is secured Event4 - The team next combats a failure of the A steam flow transmitter for the feedwater level control system. Manual control is established to stabilize and restore RPV water level per abnormal operating procedures.

Event5 - Following failure of the steam flow transmitter Single Element Control is established by the team to allow for automatic RPV level control Event6 - Next a loss of circulating water switchgear occurs, resulting in a loss of most of the condenser cooling pumps requiring entry into abnormal operating procedures for a loss of condenser vacuum and the plant to be shutdown (Scrammed).

Event 7 - Following taking the mode switch to shutdown three control rods fail to insert resulting in a low power (0%)

ATWS condition. EOP-0001A is entered and action taken to insert the control rods (Critical task to insert all control rods prior exceeding heat capacity temperature limit)

Event 8 - Also following plant shutdown the leaking safety relief valve opens fully resulting in an uncontrolled RPV pressure drop, actions are taken per abnormal operating procedures and the SRV is successfully closed.

(Critical task to close the SRV prior to exceeding the Heat Capacity Temperature Limit)

Event 9 - The final event is a failure of secondary containment isolation valve for the suppression pool cleanup system to isolate on the low RPV water level received (as expected) during plant shutdown.

Number: *RSMS-NRC_DEC14-1 RIVER Revision: 00 BEND STATION Page 1 of 20 Approximate Time: 1 Hour(s)

SIMULATOR SCENARIO Record Type: *Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

RHR A pump shaft shear, Steam Flow Transmitter failure, Loss NNS-SWG2A, 3 Rod out ATWS, SRV fails open REASON FOR REVISION:

NRC December 2014 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-2014 Preparer KCN Date Dave Bergstrom 0257 09-30-2014 Technical Review (SME) KCN Date Steve Carter 0358 10-01-2014 Operations Representative KCN Date Joey Clark 0260 10-18-2014 Facility Reviewer KCN Date

Indexing Information

I. DESCRIPTION OF SCENARIO This scenario begins with the plant at 84% power with CWS-P1D tagged out and leaking SRV.

Events for this scenario:

Reduce power with control rods

Perform SOP-0031 Section 4.8, Suppression Pool Reject to Radwaste

RHR A Pump Shaft Shear (Tech Spec)

Steam Line Flow Transmitter A fails low (AOP-0006)

Loss of NNS-SWG2A (AOP-0005)

Rx Scram on Low Vacuum

3 rod out ATWS

SRV 51C fails open following turbine trip

RHS-AOV64 fails to isolate on level 3 II. TERMINAL OBJECTIVES

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

RSMS-NRC_DEC14-1 Page 2 OF 20

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC #251 Power:

84%

Core:

Xenon equilibrium Equipment OOS:

CWS-P1D STPs Due:

None LCOs:

None Evolutions in progress:

High Suppression Pool Level due to leaking SRV RHR A SPC and Reject to Radwaste required Problem/Lit annunciators:

ADS-SRV Leaking (601-19A-B09)

RSMS-NRC_DEC14-1 Page 3 OF 20

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Actions Check Boards for Malfunctions Equip Tags MSS007K, SRV, 1B21*F051C LEAKS CRDM2017, STUCK, CONTROL ROD Check procedures and 2017 FAILURES hard cards for marks CRDM3641, STUCK, CONTROL ROD Check Gauges/Meters 3641 FAILURES for marks. CRDM4425, STUCK, CONTROL ROD 4425 FAILURES Make marked-up RHS-AOV64P, 100, RHS-AOV64 SPC copies of STPs SUCTION ISOL VALVE POSITION available. T2 CRDM2025, ACCUMFLTS, CONTROL ROD 2025 FAILURES Check that the Shutdown Plan is T3 RHR010A, RHR PUMP A SHEARED appropriate for this SHAFT scenario. T4 FWS017A, 0, STEAM FLOW XMITTER, C33-N003A FAILURE Check power <3090 T6 ED003D, NNS-SWG2A BUS FAULT MWth (4160 VAC)

T7 CRDM2017, STUCK, DELETE Bring up Insight - 00:00:01, CONTROL ROD 3641 FAILURES T7 CRDM3641, STUCK, DELETE 00:00:01, CONTROL ROD 4041 FAILURES T7CRDM4425, STUCK, DELETE 00:00:01, CONTROL ROD 4045 RSMS-NRC_DEC14-1 Page 4 OF 20

Event Number MFS-OR-REM-SCH Expected Operator Actions FAILURES T8 MSS005K, Delay 00:02:00, SRV 1B21*F051C FAILS OPEN Remote Functions T29 MSS012 OPERATE SRV B SOLENOID SWITCHES T30 MSS009, OUT, MAIN STEAM DIV 1 SRV F051C FUSE T30 MSS016, OUT, MAIN STEAM DIV 2 SRV F051C FUSE T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

T12 EOP012B, JUMPRD, EOP-5 ENCL 12 (ARI SIGNALS)

T14 EOP014, JUMPRD, EOP-5 ENCL 14 (RC&IS INTERLOCKS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T24 EOP024, JUMPRD, EOP-5 ENCL 24 (MSIV & MSL DRAIN LEVEL 1)

T28 CRDM2025, ACCUMFLTS, Delay 00:05:00, Delete 00:00:01, CONTROL ROD 2025 FAILURES T26 ECCS004, OUT, RHR A PUMP BREAKER RSMS-NRC_DEC14-1 Page 5 OF 20

Event Number MFS-OR-REM-SCH Expected Operator Actions T27 ECCS003, OUT, LPCS PUMP BREAKER Overrides NONE Event Triggers NONE Event 0 RUN CREW: Board walk down / Turnover.

RSMS-NRC_DEC14-1 Page 6 OF 20

Event 1 As console operator following completion SRO

Direct the ATC to perform RMP Step 2 to lower of movement of control rod 2025 insert reactor power.

Lower Reactor Power T2 CRDM2025, ACCUMFLTS,

Acknowledge accumulator trouble on control rod with Control Rods CONTROL ROD 2025 FAILURES 2025 and direct performance of ARP actions Event initiated by

Reference Technical Specifications TR 3.1.5.1 crew from turnover ROLE PLAY: As reactor engineer

Condition A Verify the affected accumulator sheet. Perform EN- acknowledge completion of RMP Step 2 pressure >= 1540psig once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

RE-215 RMP control and state that you will be performing monitor cases while they reject UO

Accept the direction to perform to perform RMP rod insertion step Step 2 to lower reactor power.

suppression pool water.

Perform RMP Step 2 control rod insertion.

Utilize the operator control module to select As reactor building report that accumulator and insert control rods.

pressure is 1560 psig and that you will be

Recognize and report accumulator trouble and check for moisture, wait 5 minutes then perform ARP actions as follows:

insert T28 CRDM2025, ACCUMFLTS,

Determine which rod is alarming Delay 00:05:00, Delete 00:00:01,

Reset annunciator CONTROL ROD 2025 FAILURES, and

Verify charging water header pressure is >

report that 60cc of moisture have been 1540 psig drain and that accumulator pressure is 1550

Dispatch building operator to investigate psig RSMS-NRC_DEC14-1 Page 7 OF 20

Event 2 ROLE PLAY: As reactor building SRO

Direct the UO to perform SOP-0031 Section 4.8 operator, report pump start checks are Suppression Pool Reject to Radwaste.

Perform SOP-0031 satisfactory UO

Accept the direction to perform SOP-0031 Section Section 4.8, Reject SP 4.8 Suppression Pool Reject to Radwaste.

to radwaste. ROLE PLAY: As radwaste operator,

Perform SOP-0031 Section 4.8.

Event initiated by respond that you are ready to receive

Align SWP flow, Start RHR Pump A crew from turnover suppression pool reject.

Open Test Return Valve, Close HX bypass sheet.

Open Reject Valves to begin reject RSMS-NRC_DEC14-1 Page 8 OF 20

Event 3 T3 RHR010A, RHR PUMP A SHEARED SRO

Direct the ATC to isolate the radwaste reject and test SHAFT return flow paths.

RHR A pump trip.

Notify WMC/Maintenance of RHR A pump shaft Event initiated at Lead ROLE PLAY: shear.

Evaluator discretion while rejecting As WMC/Maintenance, accept request for

Complete OSP-0046 notifications.

suppression pool to help to investigate

Enter Tech Spec 3.5.1 Condition A (C if LPCS radwaste. declared INOP until filled and vented), One low As reactor building operator, accept pressure ECCS injection/spray subsystem direction to investigate trip of RHR A inoperable.

Time Called pump (Pump). After ~5 minutes report

A.1 Restore low pressure ECCS injection/spray back that you do not see anything wrong subsystem to OPERABLE status within 7 days Call Back Time with the pump (C.1 if LPCS declared INOP until filled and

______________ vented)

As control building operator, accept

Enter Tech Spec 3.6.2.3 Condition A, One RHR Time Called direction to investigate trip of RHR A suppression pool cooling subsystem inoperable

______________ pump (Breaker). After ~ 5 minutes report

A.1 Restore RHR suppression pool cooling Call Back Time back that indications on the breaker show subsystem to OPERABLE status within 7 days

______________ that it is closed.

Reference Tech Spec 3.4.9 Condition A, One RHR shutdown cooling subsystem inoperable for As control building operator if directed to applicability.

rack out / remove control power fuses for

Applicable in Mode 3 with reactor steam dome RHR A then insert T26 ECCS004, OUT, pressure less than the RHR cut in permissive RHR A PUMP BREAKER pressure.

UO

Recognize/report the shaft shear of RHR pump.

As control building operator if directed to

Refer to ARP-601-20A-C04 rack out / remove control power fuses for

Isolate radwaste reject flow path LPCS then insert T27 ECCS003, OUT,

Isolate test return flow path LPCS PUMP BREAKER

Dispatch building operators to investigate pump issues.

As back panel if requested report that RHR system pressure is <28 psig if RSMS-NRC_DEC14-1 Page 9 OF 20

annunciator H13-P601/20A/C04 is in alarm, > 28 psig if annunciator H13-P601/20A/C04 is clear As back panel if requested report that LPCS system pressure is at 10 psig if annunciator H13-P601/20A/C04 is in alarm, > 15 psig if annunciator H13-P601/20A/C04 is clear RSMS-NRC_DEC14-1 Page 10 OF 20

Event 4 ROLE PLAY: SRO

Accept report from ATC of C33-N003A failure.

Steam flow transmitter As WMC/Maintenance, accept request for

Notify WMC/Maintenance of C33-N003A failure.

A failure. help to investigate / repair steam flow transmitter issue.

Complete OSP-0046 notifications.

Event trigger T4

Direct ATC to take manual control of feedwater initiated at Lead level Evaluator discretion. As Duty Manager request that feedwater level control be placed in single element

Enter AOP-0006, CONDENSATE/FEEDWATER per SOP-0009 Section 6.3 while the FAILURES.

failure mode analysis team is formed to ATC

Recognize and report C33-N003A failure investigate the steam flow transmitter issue.

Take manual control of feedwater level in accordance with AOP-0006, CONDENSATE/FEEDWATER FAILURES.

RSMS-NRC_DEC14-1 Page 11 OF 20

Event 5 SRO

Direct the ATC to perform SOP-0009 Section 6.3 Three Element to Single Element Control Transfer.

Perform SOP-0009 Section 6.3, Three ATC

Accept the direction to perform SOP-0009 Section element to single 6.3 Three Element to Single Element Control element control Transfer.

transfer

Perform SOP-0009 Section 6.3 Three Element to Single Element Control Transfer.

Event initiated by

Verify C33R600 in manual crew.

Select 1 ELEM on the SINGLE ELEMENT THREE ELEMENT SELECT

Null out level error with tape setpoint on C33-R6000, FW REG VALVES MASTER FLOW CONTROLLER.

Check for proper operation by adjusting tape set 2 inches above and below while observing deviation signal

Match Tape set to actual level and place in AUTO.

Adjust tape set to maintain the level requested by the CRS.

RSMS-NRC_DEC14-1 Page 12 OF 20

T6 ED003D, NNS-SWG2A BUS FAULT SRO Event 6

Accept report about the Loss of NNS-SWG2A.

(4160 VAC)

Loss of NNS-SWG2A

Assign AOP-0005, LOSS OF MAIN CONENSER VACUUM/TRIP OF CIRCULATING WATER Event T5 initiated at PUMP.

Lead Evaluator discretion.

Direct the ATC to monitor condenser vacuum.

ATC

Accept assignment of AOP-0005, LOSS OF MAIN CONENSER VACUUM/TRIP OF CIRCULATING WATER PUMP.

Monitor condenser vacuum and take action in accordance with AOP-0005.

Reduce power to maintain condenser vacuum in the acceptable region of the graph in AOP-0005.

If condenser vacuum is in the unacceptable region of the graph in AOP-005 the manually scram the reactor by placing the Mode switch in shutdown.

UO

Recognize and report Loss of NNS-SWG2A.

RSMS-NRC_DEC14-1 Page 13 OF 20

CRDM3641, STUCK, CONTROL ROD SRO

Direct/ Acknowledge the ATC to insert a manual Event 7 3641 FAILURES reactor scram due to lower condenser vacuum.

Reactor SCRAM due CRDM4041, STUCK, CONTROL ROD to lowering condenser

Accept the SCRAM Report, Acknowledging 3 rod 4041 FAILURES vacuum. out ATWS.

CRDM4045, STUCK, CONTROL ROD

Enter EOP-1on level 3 and transition to EOP-1A, Event 6 initiated as a 4045 FAILURES consequence of Event direct EOP-1A actions:

5. ROLE PLAY

Verify mode switch in S/D (SCRAM Report)

As Back Panel Operator, accept request to

ATC - restore and maintain RPV water level perform EOP-0005 enclosures and other from -20 to 51 inches with Feed & Condensate back panel operations.

and stabilize reactor pressure 950 - 1090 psig,

T12 EOP012A, JUMPRD, EOP-5 and then give band of 800-1090 psig.

ENCL 12 (RPS SIGNALS)

ATC - assigned AOP-0001, REACTOR SCRAM

T12 EOP012B, JUMPRD, EOP-5 and AOP-0002, MAIN TURBINE AND ENCL 12 (ARI SIGNALS)

GENERATOR TRIPS.

T14 EOP014, JUMPRD, EOP-5 ENCL 14 (RC&IS INTERLOCKS)

UO - assigned AOP-0003, AUTOMATIC

T16 EOP016, JUMPRD, EOP-5 ISOLATIONS and installation of EOP-0005 ENCL 16 (CONTAINMENT IAS Enclosure 16 Air, 12 RPS, 14 RC&IS, and 24 ISOL) MSIV

T18 EOP018, JUMPRD, EOP-5

Refer to EIP-2-001 for possible applicability.

ENCL 18 (FWP LEVEL 8 TRIPS)

Direct reset of scram utilizing AOP-0001 / EOP-

T24 EOP024, JUMPRD, EOP-5 0005 Enclosure 12.

ENCL 24 (MSIV)

RSMS-NRC_DEC14-1 Page 14 OF 20

Event 7 (cont.) CRITICAL TASK: ATC

When directed, insert a manual SCRAM.

All control rods fully inserted prior to

Provide a SCRAM Report.

exceeding the heat capacity NOTE: temperature limit (HCTL)

Recognize and report 3 rod out ATWS When T7 is activated

Restore and maintain RPV water level:

CRDM malfunctions

When both the scram and ARI have -20 to 51 inches with Feed & Condensate.

are deleted allowing been reset then insert T8 to allow for control rod

Complete actions of AOP-1, Reactor Scram and control rods to be driven in:

insertion, Do Not AOP-2, Turbine Trip.

T7 CRDM3641, STUCK, insert trigger 7 until DELETE 00:00:01, CONTROL

Reset scram utilizing AOP-0001 / EOP-0005 both the scram and ROD 3641 FAILURES Enclosure 12.

ARI have been reset (i.e. SDV vent and

T7 CRDM4041, STUCK, DELETE 00:00:01, CONTROL

Insert Control Rods drain are open).

ROD 4041 FAILURES UO

Complete actions of AOP-3, AUTOMATIC

T7CRDM4045, STUCK, ISOLATIONS.

DELETE 00:00:01, CONTROL

Install EOP-0005 Enclosures as directed by SRO.

ROD 4045 FAILURES RSMS-NRC_DEC14-1 Page 15 OF 20

Event 8 T8 MSS005K, Delay 00:02:00, SRV ATC

Recognize and report open SRV 1B21*F051C FAILS OPEN SRV 1B21*FO51C

Recognize and Report an uncontrolled pressure fails open. drop in the RPV due to the stuck open SRV.

CRITICAL TASK:

Event T8 initiated at SRV closed prior to exceeding the SRO

Accept report of open SRV Lead Evaluator heat capacity temperature limit discretion.

Re-enter EOP-0002 on suppression pool (HCTL) temperature if >= 100F; direct EOP-2 actions:

Assign AOP-0035, SAFETY RELIEF VALVE ROLE PLAY STUCK OPEN.

As Back Panel Operator, accept request to

Perform actions of AOP-0035, SAFETY RELIEF UO perform EOP-0005 enclosures and other VALVE STUCK OPEN.

back panel operations as follows:

Place the B21-F051C switch to OPEN.

B21-F051C Div 2 switch operation.

Take control switch for B21F051C to OFF;

T29 MSS012 OPERATE SRV cycle switch to OPEN and back to OFF.

B SOLENOID SWITCHES

Back panel (phone) step 5.5.3 of AOP-0035 to

B21-F051C fuse removal. cycle switch twice.

T30 MSS009, OUT, MAIN

Monitor Suppression Pool Temperature.

STEAM DIV 1 SRV F051C FUSE

When directed, place RHR in Supp Pool Cooling

T30 MSS016, OUT, MAIN

Throttle E12-F068 Service water STEAM DIV 2 SRV F051C

Start RHR Pump - Verify closed the inj.

FUSE Valve

Open E12-F024, Test Return to Supp Pool

Remove fuses IAW step 5.7 of AOP-35 Attach. 1.

Determine that SRV closes by using steam flows, etc.

RSMS-NRC_DEC14-1 Page 16 OF 20

Event 9 RHS-AOV64P, 100, RHS-AOV64 SPC SRO

Direct isolation of RHS-AOV64 SUCTION ISOL VALVE POSITION RHS-AOV64 fails to isolate ROLE PLAY UO

Recognize and report failure of RHS-AOV64 to Event initiated upon As WMC/Maintenance, accept request for isolate.

receipt of level 3 help to investigate

Attempt to isolate RHS-AOV64 signal following Mode switch operation.

Termination is at the FREEZE Critical Task Review:

discretion of the Chief 1. SRV closed prior to exceeding the heat capacity temperature limit Examiner. (HCTL)

2. All control rods fully inserted prior to exceeding the heat capacity temperature limit (HCTL)

RSMS-NRC_DEC14-1 Page 17 OF 20

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated with an *:

RHR A restored to standby lineup with the exception of the pump being tripped.

Feedwater level control operating automatically in single element.

Reactor scram inserted due to lowering vacuum.

Level and pressure control established

Actions taken for stuck open SRV IAW AOP-0035

*SRV closed prior to exceeding the heat capacity temperature limit (HCTL).

All control rods fully inserted prior to exceeding the heat capacity temperature limit (HCTL).

RSMS-NRC_DEC14-1 Page 18 OF 20

VII. REFERENCES A. Plant Procedures

1. AOP-0005, Loss of Main Condenser Vacuum, Trip of Circulating Water Pump

2. ARP-601-20A-E05, RHR PUMP MOTOR A AUTO TRIP

3. ARP-680-03A-B08, REACTOR HIGH/LOW WATER LEVEL

4. Tech Specs

5. AOP-0001, Reactor Scram

6. AOP-0002, Turbine Trip

7. AOP-0003, Automatic Isolations

8. AOP-0035, Stuck Open SRV

9. EOP-1, RPV Control

10. EOP-1A, RPV Control ATWS

11. EOP-2, Primary Containment Control

12. EN-OP-115, Attachment 9.8

13. OSP-0053, Emergency and Transient Response Support Procedure RSMS-NRC_DEC14-1 Page 19 OF 20

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date Reactor Power is 84% Shutting down due to leaking SRV RMP Step 1 has been completed and we a ready to perform Step 2 followed by monitor cases.

B21-F051C, Safety Relief Valve leaking by causing Suppression Pool Level rise.

Place RHR A in Suppression Pool Cooling and Reject Suppression Pool to Radwaste, Chemistry sample is good for reject of suppression pool following performance of RMP step 2.

SIGNIFICANT LCO STATUS EOOS STATUS 10.0 Green EQUIPMENT STATUS PROTECTED EQUIPMENT CWS-P1D is tagged out for motor rewind. Div 2

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-NRC_DEC14-1 Page 20 OF 20

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-2 IC No.: 252 Examiners: ________________ Operators: _____________________________

Initial Conditions: 100% reactor power.

Turnover Shift priorities: 1) STP-309-0203 in progress; ready to unload and shutdown the HPCS DG per step 7.3 Event Malf. Event Type* Event No. No. Description 1 NA N (SRO, BOP) Unload the HPCS DG per STP-309-0203 Steps 7.3.1 through 7.3.4 2 ED004R C (SRO) E22-ACB03 trips after DG output breaker opens (Tech Spec) zdi5(497)!=0 3 CCS001B C (SRO, BOP) CCS-P1B trips CCS-P1C fails to auto start (AOP-0012)

CCS003C 4 CNM004B C (SRO,ATC) CNM-P1B trips (RX) (AOP-0006)

R (ATC) 5 N/A C(SRO) Control Building Fire Door (CB098-10) Failure to close and latch (Tech Spec) 6 ED010 M (ALL) Loss RSS#1 result in loss of normal feedwater 7 RCIC002 C (SRO, BOP) RCIC fails to auto start and must be manually started E51MOVF013P RCIC Injection Valve limited to 2% open 8 MSS001 C (ALL) Steam Leak in Drywell leading to ED on lowering water level and restoration of level with low pressure ECCS

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7) E22-ACB03, CCS-P1B, CNM-P1B,CB098-10, Loss RSS#1, RCIC S/U, DW Leak, Malfunctions after EOP entry (1-2) (2) RCIC S/U, DW Leak, Abnormal Events (2-4) (2), AOP-0012, AOP-0006 Major Transients (1-2) (1) Reactor scram due to loss of normal feedwater EOPs entered (1-2) (2) EOP-0001, EOP-0002.

EOP contingencies (0-2) (1) Alternate level control Critical Tasks (2-3) (2) ED prior to -186; Restore RPV water level to -186

December 2014 NRC Exam General Scenario Outline Event 0 - The team assumes the shift with reactor power at 100% and the division 3 diesel generator month operability surveillance test in progress.

Event 1 - The team unloads and opens the output breaker for the division 3 diesel generator (Normal evolution)

Event 2 - When the output breaker is opened the supply breaker for the division 3 480 volt switchgear trips on overcurrent resulting in Tech Spec 3.8.9 entry and HPCS becoming unavailable Event 3 - Next one of the operating turbine plant component cooling water pumps trips with the standby pump failing to auto start, the operators will manually start the standby pump restore normal cooling water flow.

Event 4 - Following the temporary reduction in cooling water flow one the three operating condensate pumps trips resulting in abnormal operating procedure entry and required power reduction to 90%

Event 5 - A report from a roving security officer results in TRM 3.7.9.6 entry for a failed fire barrio Event 6 - A partial loss of offsite power occurring resulting in a loss of the remain condensate pumps and a loss of normal feedwater injection requiring the plan to be shutdown (Scrammed)

Event 7 - The only high pressure injection system avail is RCIC and it fails to auto start. When started the RCIC injection valve fails to fully open result in reduced injection Event 8 - Following the scram a leak begins in the drywell resulting in loss of coolant accident requiring emergency depressurization due to lowering reactor water level and restoration of RPV water level utilizing low pressure injection systems. (Critical Task to emergency depressurize prior to RPV water level dropping below -186 inches) (Critical Task to restore RPV water level above -186 inches)

Number: *RSMS-NRC_DEC14-2 RIVER Revision: 00 BEND STATION Page 1 of 17 Approximate Time: 1 Hour(s)

SIMULATOR SCENARIO Record Type: *Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

E22-S002 Fault, CCS pump failure, CNM pump failure, Loss RSS #1, RCIC start failure and injection limited, Steam Leak in Drywell REASON FOR REVISION:

NRC December 2014 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-2014 Preparer KCN Date Dave Bergstrom 0257 09-30-2014 Technical Review (SME) KCN Date Steve Carter 0358 10-01-2014 Operations Representative KCN Date Joey Clark 0260 10-18-2014 Facility Reviewer KCN Date

Indexing Information

I. DESCRIPTION OF SCENARIO This scenario begins with the plant at 93% power with HPCS tagged out for line fill pump maintenance.

Events for this scenario:

Unloading of HPCS DG per STP-309-0203

E22-S002 bus fault

CCS-P1B trip with failure of CCS-P1C to auto start

CNM-P1B trip / Rx Power reduction with flow

CB098-10 Door Broke

Loss of RSS#1

RCIC auto start failure with limited injection flow

Steam Leak in the drywell II. TERMINAL OBJECTIVES

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

RSMS-NRC_DEC14-2 Page 2 OF 17

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC #252 Power: 100%

Core: Xenon equilibrium Equipment OOS: None STPs Due: None LCOs: 3.8.1 Condition C Evolutions in progress: STP-309-0203 in progress, ready STP-309-0203 to unload and shutdown the HPCS DG Problem/Lit annunciators: None RSMS-NRC_DEC14-2 Page 3 OF 17

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Actions Simulator Setup Div 3 diesel generator running tied to the grid.

Check Boards for Malfunctions Equip Tags T2, DED004R, E22*S002 BUS FAULT (480 VAC)

Check procedures and T3, CCS001B, TPCCW PUMP BTRIP hard cards for marks CCS003C, CCS-P1C FAILURE TO AUTO START Check Gauges/Meters T4, CNM004B, CONDENSATE PUMP B for marks. TRIP T6, ED010, RSS TRANSFORMER ,

XSR1E LOCKOUT Make marked-up RCIC002, RCIC FAILS TO AUTO copies of STPs START available.

T7, E51MOVF013P, FV 2, E51-MOV12, POSITION Check that the T8, MSS001, FV 1000, Delay 00:01:00, Shutdown Plan is Ramp 00:10:00, STEAM LEAK IN THE appropriate for this DRYWELL scenario.

Remote Functions Check power <3090 T28, RPS005, RPS ALTERNATE EPA MWth BREAKERS DIV 1 T29,BKR069, SCI-PNL01/02 SELECT Bring up Insight SWITCH, 1SCI-TRS1 T30, EOP032A, EOP-5 ENCL32 (A SDC INJECTION VALVES)

RSMS-NRC_DEC14-2 Page 4 OF 17

Event Number MFS-OR-REM-SCH Expected Operator Actions T30, EOP032B, EOP-5 ENCL32 (B SDC INJECTION VALVES)

T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

T20 EOP020, JUMPRD, EOP-5 ENCL 20 (DRYWELL COOLING)

Overrides DI_NNS-ACB24, NEUTRAL, 808-87C 1NNS SWGR 1C/1A BRKR SW Event Triggers T2, ZDI5(497)! =0,HPCS DG OUTPUT BKR OPEN T7, ZDI5(534), E51-F013 TO OPEN T8, Mode Switch not in run Event 0 RUN CREW: Board walk down / Turnover.

RSMS-NRC_DEC14-2 Page 5 OF 17

Event 1 ROLE PLAY: As control building SRO

Direct the UO to perform STP-309-0203.

Perform STP-309- operator, report a full set of PEP-0026 data has been collected UO

Accept the direction to perform STP-309-0203 0203 Steps 7.3.1 through 7.3.4 to

Perform STP-309-0203 Section 7.3.1 through unload Div 3 DG 7.3.4.

Reduce HPCS diesel generator load Event initiated by

Record time load reduced below 2525KW crew from turnover

Open HPCS diesel generator output breaker sheet.

RSMS-NRC_DEC14-2 Page 6 OF 17

Event 2 T2, DED004R, E22*S002 BUS FAULT SRO

Acknowledge loss of E22-S002 bus (480 VAC)

Review Technical Specification 3.8.9 E22-S002 BUS

Condition E, Declare HPCS system and SSW FAULT Pump 2C inoperable Event initiated when ROLE PLAY:

Review Technical Specification 3.5.1 the generator output

Condition B, Verify RCIC system operable with breaker is opened. As WMC/Maintenance/Engineering, accept request to investigate / repair E22- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore HPCS system to S002 Bus Fault. OPERABLE status within 14 days

Review Technical Specification 3.7.1

Condition E, Restore SSW pump to operable status within 30 days

Direct HPCS pump breaker to be racked out following receipt of HPCS low pressure alarm UO

Recognize and report loss of E22-S002 bus

Direct control building operator to rack out HPCS pump breaker upon receipt of HPCS low pressure alarm.

RSMS-NRC_DEC14-2 Page 7 OF 17

Event 3 T3, CCS001B, TPCCW PUMP BTRIP SRO

Acknowledge trip of CCS-P1B CCS003C, CCS-P1C FAILURE TO

Direct start of CCS-P1C Trip of CCS-P1B with AUTO START

Enter AOP-0012 failure of CCS-P1C to auto start. UO

Recognize and report trip of CCS-P1B ROLE PLAY:

Start CCS-P1C Event trigger T3 As WMC / FIN / I&C, accept request to

Implement any required actions of AOP-0012 initiated at Lead investigate / repair trip of CCS-P1B Evaluator discretion.

As the turbine building operator, accept the direction to investigate the trip of CCS-P1B, after approximately 5 minutes report that the outboard motor bearing feels hot.

As the control building operator, accept the direction to investigate the trip of CCS-P1B after approximately 5 minutes report that the breaker appears to have tripped on over current.

RSMS-NRC_DEC14-2 Page 8 OF 17

Event 4 T4, CNM004B, CONDENSATE PUMP B SRO

Acknowledge trip of condensate pump B TRIP Trip of Condensate

Direct power reduction to 90%

pump B. ROLE PLAY:

As WMC / FIN / maintenance, accept

Enter AOP-0006 Event trigger T4 request to investigate / repair condensate

Notify WMC / FIN / Maintenance to investigate /

initiated at Lead pump B issue repair condensate pump B issue.

Evaluator discretion.

As the turbine building operator, accept ATC

Recognize and report trip of condensate pump B the direction to investigate the trip of the

Lower reactor power to 90% with recirc flow condensate pump, Call back in 5 minutes to report that there is smell of hot

Implement AOP-0006 insulation coming from the pump motor.

Place condensate pump B in a shutdown status per As the control building operator, accept SOP-0007 the direction to investigate the trip of the condensate pump, Call back in 5 minutes to report that there is an 86 lockout and over current trips.

RSMS-NRC_DEC14-2 Page 9 OF 17

Event 5 GETRONICS CALL SRO

Acknowledge report of CB098-10 door issue CB098-10 Door open As security officer call the control room

Reference Technical Specification TR 3.7.9.6 and will not close on Getronics line 3 and report that you

Condition A Establish a continuous fire watch have just passed through control building on at least one side or the affected assembly or Event trigger T5 door CB-098-10 located between the two sealing device within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR Verify the initiated at Lead switchgear rooms and that the door would OPERABILITY of fire detectors on at least one Evaluator discretion.

not close and latch behind you. side of the inoperable assembly or sealing device within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Establish an hourly fire ROLE PLAY: watch patrol within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months As WMC / FIN / maintenance, accept request to investigate / repair CB-098-10 UO

Take report of CB098-10 door issue and inform the Door issue control room supervisor As the control building operator, accept the direction to investigate CB098-10 Door issue wait 5 minutes and report that the door will not close there is something wrong with the closing mechanism.

RSMS-NRC_DEC14-2 Page 10 OF 17

Event 6 T6, ED010, RSS TRANSFORMER , SRO

Acknowledge loss of RSS#1 XSR1E LOCKOUT Loss of RSS#1

Direct actions for Loss of RSS#1 per OSP-0053 Hard Card Event trigger T6 is ROLE PLAY initiated at Lead As WMC / FIN / I&C, accept request to

Direct Implementation of AOP-0001, 0002, & 0003 Evaluator discretion. investigate / repair loss of RSS#1 issue

Notify WMC / FIN / Maintenance to investigate /

repair RSS#1 issue.

As the control building operator, accept the direction to investigate the loss of RSS ATC

Recognize and report loss of RSS#1and loss of

1 normal feedwater As building operator accept request to

Place the reactor mode switch in shutdown reset alternate EPA breaker, wait 5 minutes then insert T28, RPS005, RPS

Implement AOP-0001 and AOP-0002 ALTERNATE EPA BREAKERS DIV UO

Dispatch building operators to investigate loss of 1,and report that EPA breakers are reset.

RSS #1.

As building operator accept request to

Perform Actions for loss of RSS#1 per OSP-0053 swap SCI source, wait 5 minutes then Hard Card insert T29,BKR069, SCI-PNL01/02 SELECT SWITCH, 1SCI-TRS1 and report

Implement AOP-0003 SCI source has been swapped.

As the outside operator, accept the direction to investigate the loss of RSS #1 ENCLOSURES:

T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

RSMS-NRC_DEC14-2 Page 11 OF 17

Event 7 RCIC002, RCIC FAILS TO AUTO SRO

Acknowledge failure of RCIC to auto start and START discharge flow limitations RCIC fails to auto start T7 E51MOVF013P, FV 2, E51-MOV13, and injection is POSITION

Direct start of RCIC.

minimal when started.

Notify WMC / FIN / Maintenance to investigate /

Event 7 is initiated repair RCIC issues.

ROLE PLAY concurrently with As reactor building operator acknowledge

Recognize and report failure of RCIC to auto start Event 5. UO request to manually open RCIC discharge and flow limitations following manual initiation valve and after 5 minutes report that you

Direct reactor building operator to manually open are unable to open the valve RCIC discharge valve.

As WMC/FIN/Maintenance acknowledge request to investigate / repair RCIC initiation and flow issues.

RSMS-NRC_DEC14-2 Page 12 OF 17

Event 8 T8, MSS001, FV 1000, Delay 00:01:00, SRO

Recognize leak in the drywell Ramp 00:10:00, STEAM LEAK IN THE Steam leak in the DRYWELL

Direct implement OSP-0053 Leakage Strategies drywell Critical Task Review:

Enter and direct actions of EOP-0002 Event trigger T8 is 1. ED prior to -186 initiated when the

2. Restore and maintain RPV water level ATC

Implement OSP-0053 Leakage Strategies mode switch is taken out of the RUN to >= -186 position. ENCLOSURES:

T20 EOP020, JUMPRD, EOP-5 ENCL UO

Implement OSP-0053 Leakage Strategies 20 (DRYWELL COOLING)

Perform actions as directed to support EOP-0002 T30, EOP032A, EOP-5 ENCL32 (A SDC INJECTION VALVES)

T30, EOP032B, EOP-5 ENCL32 (B SDC INJECTION VALVES)

RSMS-NRC_DEC14-2 Page 13 OF 17

Termination is at the FREEZE Critical Task Review:

discretion of the Chief 1. ED prior to -186 Examiner.

2. Restore and maintain RPV water level to >= -186 RSMS-NRC_DEC14-2 Page 14 OF 17

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated with an *:

Division 3 DG unloaded

CCS-P1C running

RCIC initiated

*Emergency Depressurized prior to -186

*Restored and maintaining RPV water level to > -186 RSMS-NRC_DEC14-2 Page 15 OF 17

VII. REFERENCES A. Plant Procedures

1. STP-309-0203, Division 3 Diesel Generator Operability Test

2. AOP-0012, Loss of Turbine Plant Component Cooling Water

3. ARP-601-16A-G04

4. ARP-870-55A-E01

5. ARP-601-16A-G02

6. AOP-0006, Condensate / Feedwater Failures

7. SOP-0006, Condensate System

8. Tech Specs

9. EN-OP-115, Attachment 9.8

10. AOP-0001, Reactor Scram

11. AOP-0002, Main Turbine and Generator Trips

12. EOP-1, RPV Control

13. EOP-2, Primary Containment Control

14. OSP-0053, Emergency and Transient Response Support Procedure RSMS-NRC_DEC14-2 Page 16 OF 17

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date STP-309-0203 in progress, Ready to unload and secure the Division 3 diesel generator per Step 7.3 STP-000-0102 due in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NPS busses are being supplied from preferred transformers due to questionable oil sample on STX-XSN1A normal station transformer A.

Reactor Power is 100%

SIGNIFICANT LCO STATUS EOOS STATUS T.S. 3.8.1 Condition C, While Division 3 DG is tied to 8.7 Yellow the grid for testing.

EQUIPMENT STATUS PROTECTED EQUIPMENT Division 1 and RCIC

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-NRC_DEC14-2 Page 17 OF 17

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-3 IC No.: 253 Examiners: ________________ Operators: _____________________________

Initial Conditions: 93% reactor power. RCIC tagged out for Line Fill Pump Maintenance.

Turnover Shift priorities: (1) Swap Stator Water Cooling Pumps (for tagout of GMC-P1A);

(2) Raise Reactor Power IAW RMP (using flow)

Event Malf. Event Event No. No. Type* Description 1 NA N (SRO, BOP) Swap Stator Water Cooling Pumps (from A to B) 2 NA R (ATC) Raise Reactor Power with Flow 3 B21005 I (SRO) RPV pressure transmitter B21-PTN078A, fails high (TS) 4 GMC002B C (SRO, BOP) Trip of Stator Water Cooling Pump B, Standby pump fails to start GMC001A 5 RPS003A C (SRO,BOP) Loss of RPS-A 6 SWPMOV4AP C (SRO, BOP) Failure to isolate (SWP-MOV 5B) (TS) 7 GMC003A M (ALL) Shear of Stator Water Cooling Pump A Shaft - Requires Scram RPS-001B RPS fails to Automatically and Manually Scram Rods inserted by ARI RPS001C 8 MGEN003 C (ATC, BOP) Main Generator Reverse Power Relay Failure 9 CNM006 Condensate Filter High D/P - Loss of Feed (recoverable)

C (SRO,BOP)

HPCS002 HPCS injection valve fails to open

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7) GMC-B Trip, Press Xmitter, RPS-A, SWPMOV5B failure to isolate, GMC-A shear, Reverse Power Failure, Loss of Feed Malfunctions after EOP entry (1-2) (2) Reverse Power, HPCS inject failure Abnormal Events (2-4) (3), AOP-0010, AOP-0001, AOP-0002 Major Transients (1-2) (1) Reactor scram with Loss of Stator Water Cooling EOPs entered (1-2) (2) EOP-0001 EOP contingencies (0-2) (1) EOP-0001, Alternate Level Control Critical Tasks (2-3) (2) Initiate ARI; RPV Level Restored

December 2014 NRC Exam General Scenario Outline Event 0 - The team assumes the shift with reactor power 93% following a control rod sequence exchange. RCIC is out of service for line fill pump maintenance.

Event 1 - The team alternates the generator stator cooling water pump in preparation for oil change on the A pump.

Event 2 - Following the stator pump swap the team will raise reactor power with recirculation flow as directed by reactor engineering to 97%

Event 3 - Next the A RPS RPV pressure transmitter fails high causing a 1/2 scram condition resulting in Tech Spec 3.3.1.1 entry Event 4 - The B stator cooling water pump trips next with failure of the A standby pump to auto start. The resulting turbine-generator run back is stopped when the operators manually start the A pump.

Event 5 - Following recovery of stator cooling a loss of RPS A occurs requiring the entry into the abnormal operating procedure and recovery of isolated systems Event 6 - Primary containment isolation SWP-MOV5B fails to automatically isolate, requiring entry into T.S. 3.6.1.3 Event 7 - At this time the shaft of the restarted stator cooling water pump A shears resulting in a turbine generator run back. With no stator cooling water available the team is required to shutdown the reactor (Scram). An RPS failure then requires alternate rod insertion to be initiated to insert all control rods. (Critical Task to imitate ARI prior to level two)

Event 8 - Following reactor shutdown the main generator fails to trip on reverse power. The team will transfer house power prior to opening the main generator output breakers Event 9 - Following reactor shutdown the condensate full flow filters become clogged resulting in a loss of normal feedwater injection. The HPCS injection valve fails to open and the condensate full flow filter bypass valve must be manually opened to recover feed water injection (Critical Task to restore and maintain RPV water level to >-186 inches)

Number: *RSMS-NRC_DEC14-3 RIVER Revision: 00 BEND STATION Page 1 of 18 Approximate Time: 1 Hour(s)

SIMULATOR SCENARIO Record Type: *Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

RPS Press Transmitter Fail, Trip stator cooling, Loss RPS, Loss of Feed REASON FOR REVISION:

NRC December 2014 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-2014 Preparer KCN Date Dave Bergstrom 0257 09-30-2014 Technical Review (SME) KCN Date Steve Carter 0358 10-01-2014 Operations Representative KCN Date Joey Clark 0260 10-18-2014 Facility Reviewer KCN Date

Indexing Information

I. DESCRIPTION OF SCENARIO This scenario begins with the plant at 93% power with HPCS tagged out for line fill pump maintenance.

Events for this scenario:

Swap Stator Water Cooling Pumps per SOP

Raise Reactor Power with flow

RPV Pressure Transmitter B21-PTN078A, fails high (Tech Spec)

Trip of Stator Cooling Pump B

Loss RPS A

Trip of Stator Cooling Pump A - Requires Scram

Main Generator Reverse Power Relay Failure

Condensate Filter High D/P - Loss of Feed

SWP-MOV5B fails to isolate (Tech Spec)

II. TERMINAL OBJECTIVES

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

RSMS-NRC_DEC14-3 Page 2 OF 18

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC #253 Power: 93%

Core: Xenon equilibrium Equipment OOS: RCIC tagged out for line fill pump Maintenance.

STPs Due: None LCOs: None Evolutions in progress: Swap Stator Cooling Water Pumps RMP (for tagout of GMC-P1A), Raise Reactor Power IAW RMP (using flow).

Problem/Lit annunciators: None RSMS-NRC_DEC14-3 Page 3 OF 18

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Actions Simulator Setup Check Boards for Malfunctions Equip Tags T3, B21005, RPV PRESS TRANSMITTER B21-PTN078A Check procedures and FAILURE hard cards for marks T4, GMC002B, STATOR COOLING WATER PUMP B TRIP Check Gauges/Meters GMC001A, GMC-P1A FAILURE TO for marks. AUTO START T5, RPS003A, LOSS OF POWER TO Make marked-up RPS CHANNEL A copies of STPs SWPMOV5BP, 100, SWP-MOV4A, available. POSITION T7, GMC003A, STATOR COOLING Check that the WATER PUMP A SHEARED SHAFT Shutdown Plan is T3 RPS001B, Delay 00:00:05, RPS appropriate for this FAILS TO SCRAM - AUTO SIGNALS scenario. ONLY RPS001C, RPS FAILS TO SCRAM -

MANUALLY Check power <3090 MGEN003, MAIN GENERATOR MWth REVERSE POWER RELAY FAILURE T9, CNM006, FINAL VALUE 100, Bring up Insight - CONDENSATE FILTER HIGH MSTun Temperature DIFFERENTIAL PRESS HPCS002, HPCS INJECTION VALVE APRM B in Bypass F004 FAILS TO OPEN RSMS-NRC_DEC14-3 Page 4 OF 18

Event Number MFS-OR-REM-SCH Expected Operator Actions T30, CNM006, FINAL VALUE 0, CONDENSATE FILTER HIGH DIFFERENTIAL PRESS Remote Functions T27 TGS009, RESET, Delete 00:00:02, RESET H2 CLG/STATOR CLG SEAL OIL ALARM T28, NIS001, NI CABINET 20 VDC POWER SUPPLIES T29 TGS009, RESET Delete 00:00:02, RESET H2 CLG/STATOR CLG SEAL OIL ALARM T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

Overrides NONE Event Triggers T9, Mode switch not in run Event 0 RUN CREW: Board walk down / Turnover.

RSMS-NRC_DEC14-3 Page 5 OF 18

Event 1 ROLE PLAY: As turbine building SRO

Direct the UO to perform SOP-0020 Section 5.2.

Perform SOP-0020 operator, report GMC B pump start checks are satisfactory UO

Accept the direction to perform SOP-0020 Section Section 5.2, Shifting 5.2.

Pumps While Unit Is In Service (from A to

Perform SOP-0020 Section 5.2.

As turbine building operator accept

Depress GMC-SCPM-B Start Pushbutton B) direction to reset the Stator Cooling Alarm

Depress GMC-SCPM-A Stop Pushbutton Event initiated by on panel GMC-PNL101,

Verify GMC-PIEPR-15 reads > 49psig crew from turnover After 1 minute insert trigger T27, TGS009, sheet. to reset the Stator Cooling Alarm and report that a pressure control valve lockup occurred during pump swap as expected and has been reset.

RSMS-NRC_DEC14-3 Page 6 OF 18

Event 2 ROLE PLAY: SRO

Direct the ATC to perform RMP flow step to raise reactor power Raise Reactor Power As reactor engineer provide next with Flow. sequential EN-RE-215 RMP flow step to ATC

Accept the direction to perform RMP flow step to the SRO. raise reactor power.

Event initiated by RE providing EN-RE-215

Perform RMP flow step.

As reactor engineer, if questioned report

Utilize the reactor recirculation system flow control RMP flow step. that monitored and predictor cases for the valves to raise reactor power in accordance with reactivity manipulation have been run and the RMP.

there are no identified challenges to core thermal limits.

RSMS-NRC_DEC14-3 Page 7 OF 18

Event 3 T3, B21005, RPV PRESS SRO

Direct use of alternate indication to verify reactor RPV PRESS TRANSMITTER B21-PTN078A pressure.

TRANSMITTER B21- FAILURE

Reference Technical Specification 3.3.1.1 PTN078A FAILURE

Condition A, Place channel in trip within 12 ROLE PLAY: hours or place associated trip system in trip Event trigger T3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (System is already in trip due initiated at Lead As WMC / FIN / I&C, accept request to to transmitter failure)

Evaluator discretion. investigate / repair issue with B21-PTN078A ATC

Recognize/report failure Division 1 1/2 scram on RPV pressure high with no single rod scrams As Back Panel provide indication that

Verify reactor pressure <1075 psig using alternate B21-N678A trip unit is upscale trip gross indications.

fail RSMS-NRC_DEC14-3 Page 8 OF 18

Event 4 T4, GMC002B, STATOR COOLING SRO

Direct verification of start of the standby stator WATER PUMP B TRIP cooling water pump.

Trip of Stator Cooling GMC001A, GMC-P1A FAILURE TO Water Pump B.

Notify WMC / FIN / Maintenance to investigate /

AUTO START repair GMC-SCPM-B pump issue.

Event trigger T4 initiated at Lead ROLE PLAY: UO

Recognize and report trip of stator cooling water Evaluator discretion. As WMC / FIN / I&C, accept request to pump B.

investigate / repair

Identify failure to automatic start of stator cooling water pump A and start the pump.

As the turbine building operator, accept the direction to investigate the Stator

Refer to ARP-870-54A-D01.

Water Cooling Pump.

Dispatch turbine building operator to investigate.

Call back in 5 minutes to report that the bearing on the pump end of the motor is hot to the touch.

Accept direction to reset the Stator Cooling Alarm on panel GMC-PNL101, After 1 minute insert trigger T29, TGS009, to reset the Stator Cooling Alarm RSMS-NRC_DEC14-3 Page 9 OF 18

Event 5 T5, RPS003A, LOSS OF POWER TO SRO

Direct implementation of AOP-0010, LOSS OF RPS RPS CHANNEL A BUS for loss of RPS A Loss of RPS-A

Notify WMC / FIN / Maintenance to investigate /

Event trigger T5 is repair RPS A issue.

initiated at Lead ROLE PLAY Evaluator discretion. As WMC / FIN / Maintenance, accept ATC

Recognize and report loss of RPS A request to investigate / repair issue with RPS A UO

Dispatch building operator to investigate loss of As the control building operator, accept RPS A.

the direction to investigate the loss of RPS

Perform Actions of AOP-0010 LOSS OF RPS BUS A, after 3 minutes report that the MG set is running with its output breaker open

Place RPS A Power Transfer Switch to the available power source As back panel operator when requested

Depress INBD and OUTBD isolation reset reset nuclear instrumentation by inserting pushbuttons trigger T28, NIS001, NI CABINET 20 VDC POWER SUPPLIES

Verify/Restore isolations per AOP-0010 RSMS-NRC_DEC14-3 Page 10 OF 18

Event 6 SWPMOV5BP, 100, SWP-MOV5B, SRO

Acknowledge failure of SWP-MOV5B to isolate on POSITION loss of RPS A.

Failure to isolate (SWP-MOV5B) ROLE PLAY

Reference Technical Specification 3.6.1.3 As WMC / FIN / Maintenance, accept Event 6 is initiated request to investigate / repair issue with

Condition A, isolate the flow path within 4 concurrently with SWP-MOV5B hours and verify isolation once every 31 Event 5. days.

Notify WMC / FIN / Maintenance to investigate /

repair SWP-MOV5B issue.

UO

Recognize and report failure of SWP-MOV5B to isolation of loss of RPS B RSMS-NRC_DEC14-3 Page 11 OF 18

Event 7 T7, GMC003A, STATOR COOLING SRO

Accept the report of the turbine runback and direct, WATER PUMP A SHEARED SHAFT placement of the reactor mode switch to shutdown Trip of Stator Water T3 RPS001B, Delay 00:00:05, RPS Cooling Pump A FAILS TO SCRAM - AUTO SIGNALS

Notify WMC / FIN / Maintenance to investigate /

resulting in insertion of ONLY repair GMC-SCPM-A pump issue.

a Reactor SCRAM RPS001C, RPS FAILS TO SCRAM -

MANUALLY

Enter and take actions per EOP-0001, RPV Control Event trigger T7 is initiated at Lead CRITICAL TASK:

Direct implementation of AOP-0001, Reactor Scram Evaluator discretion, and AOP-0003, Automatic Isolations

Initiate ARI to insert control rods BOP to complete up to before reaching level two ATC

Recognize and report Turbine Runback and including Step 14 of AOP-0010

When directed place the reactor mode switch to Attachment 2 prior to ENCLOSURES: shutdown trigger. T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

Perform actions of AOP-0001, Reactor Scram to insert control rods T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

Arm and depress C71A-S3A, B, C, and D T12 EOP012A, JUMPRD, EOP-5 ENCL manual scram pushbuttons 12 (RPS SIGNALS)

Arm and depress C11C-S1A and B ARI manual initiation pushbuttons UO

Perform actions of AOP-0003, Automatic Isolations for level 3.

RSMS-NRC_DEC14-3 Page 12 OF 18

Event 8 MGEN003, MAIN GENERATOR SRO

Accept report of the failure of the main generator to Main Generator REVERSE POWER RELAY FAILURE trip Reverse Power Relay

Direct implementation of AOP-0002, Main Turbine Failure. and Generator Trips Event 8 is initiated ATC

Recognize and report the failure of the main upon the Mode switch generator to trip being taken to Shutdown.

Implement AOP-0002, Main Turbine and Generator Trips actions for main generator failure to trip on reverse power

Verify the main turbine has tripped

Attempt to initiate a Generator Reverse Power Trip

Transfer the NPS and NNS buses to the Preferred Station Service Transformers

Open the main generator output breakers.

RSMS-NRC_DEC14-3 Page 13 OF 18

Event 9 T9, CNM006, FINAL VALUE 100, SRO

Direct dispatching of an operator to open CNM-Condensate Filter CONDENSATE FILTER HIGH FCV200 to bypass the condensate filters and restart High D/P / Spurious DIFFERENTIAL PRESS a reactor feed pump RCIC Isolation- Loss HPCS002, HPCS INJECTION VALVE F004 FAILS TO OPEN ATC

Recognize and report condensate high differential of Feed. pressure and loss of normal feed water injection.

CRITICAL TASK:

Event T9 is initiated

Following opening of CNM-FCV200 restart a feed upon the Mode switch

Restore and maintain RPV water pump per OSP-0053 hard card and restore RPV being taken to level to > -186 injection Shutdown.

ROLE PLAY As ACR operator report that Condensate

Restore high pressure injection into the RPV and filter high differential pressures are being restore RPV water level experienced and that you are unable to UO

Recognize and report failure of HPCS injection open CNM-FCV200 remotely.

valve to open As turbine building operator if dispatched

Attempt to open HPCS injection valve.

to open CNM-FCV200, after the team has entered alternate level control wait 2 minutes and insert T30, CNM006, FINAL VALUE 0, CONDENSATE FILTER HIGH DIFFERENTIAL PRESS and then report that you have manually opened CNM-FCV200 As reactor building operator if dispatched report that you are unable to open the HPCS injection valve it appear jammed.

As WMC/FIN/Maintenance accepted request for assistance with HPCS injection valve RSMS-NRC_DEC14-3 Page 14 OF 18

Termination is at the FREEZE Critical Task Review:

discretion of the Chief 1. Initiate ARI to insert control rods before reaching level two Examiner.

2. Restore and maintain RPV water level to > -186 RSMS-NRC_DEC14-3 Page 15 OF 18

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated with an *:

Stator Cooling Water Pump rotation completed

Reactor power raised with recirculation flow

RPS A power restored

Reactor scram inserted due to loss of Stator Water Cooling

SWP-MOV5B failure to isolate identified

AOP-0002 action completed for main generator motoring

CNM-FCV200 opened and a feedwater pump restarted.

*ARI to insert control rods before reaching level two

*RPV water level restored and maintained > -186 RSMS-NRC_DEC14-3 Page 16 OF 18

VII. REFERENCES A. Plant Procedures

1. SOP-0020, Generator Stator Cooling System

2. AOP-0010, Loss of RPS Buss

3. ARP-680-06A-A05

4. ARP-870-54A-C01, D01

5. Tech Specs

6. EN-OP-115, Attachment 9.8

7. AOP-0001, Reactor Scram

8. AOP-0002, Main Turbine and Generator Trips

9. AOP-0003, Automatic Isolations

10. EOP-1, RPV Control

11. EOP-2, Primary Containment Control

12. OSP-0053, Emergency and Transient Response Support Procedure RSMS-NRC_DEC14-3 Page 17 OF 18

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date Swap Stator Water Cooling Pumps (for scheduled tag out of GMC-P1A for oil change)

Reactor power is 93% ramping following sequence exchange, reactor engineering performing monitor case prior to next power increase SIGNIFICANT LCO STATUS EOOS STATUS T.S. 3.5.3 Condition A, 1 day into 14 day LCO 9.1 Green HPCS verified operable.

EQUIPMENT STATUS PROTECTED EQUIPMENT RCIC tagged out for line fill pump maintenance Division 1 and 3

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-NRC_DEC14-3 Page 18 OF 18

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: NRC-4 IC No.: 254 Examiners: ________________ Operators: _____________________________

Initial Conditions: 80% reactor power. Performing Sequence Exchange; RHR-B is in Supp Pool Cooling and Containment Purge is in service for post-maintenance RCIC testing; Turnover Shift priorities: Start RCIC for testing Adjust MVARs Raise Reactor power in accordance with the RMP for sequence exchange; Event Malf. Event Event No. No. Type* Description 1 NA N (BOP) Start RCIC IAW SOP-0035, Section 4.2 2 NA N Adjust MVAR on Main Generator (SRO,ATC) 3 NA R (ATC) Raise Power IAW RMP for sequence exchange 4 DI-HVR-UC1A C (SRO, HVR-UC1A trip (TS)

BOP)

LO_HVR-UC1A-A P863_71a:f_3 5 NMS011F I APRM F fails upscale (TS)

(SRO,ATC) 6 MSS010 I Loss of Steam Seal Header Pressure (SRO,BOP) 7 RCIC004 M (ALL) Steam Leak in RCIC Room - Spreads to RHR-C RMS215 RMS219 8 EHC002B C Main Steam BPVs fail closed MSS008D,O,G (SRO,BOP)

SRV Failures B21RV41B, D, F 9 RCIC007 C RCIC Steam Supply Isol Valves (F063 & 64) fail to shut (SRO,BOP)

RCIC008

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) APRM upscale, SSE Press, HVR-UC1A Trip, Steam Leak, SRV Failures, RCIC Isolation Fail Malfunctions after EOP entry (1-2) (2) SRVs, RCIC Isol Valves Abnormal Events (2-4) (3) AOP-0001, AOP-0002, SSE Press Major Transients (1-2) (1) Steam Leak in RCIC Room - Spreading EOPs entered (1-2) (2) EOP-0001, EOP-0003 EOP contingencies (0-2) (1) EOP-0003 Critical Tasks (2-3) (2) BPVs closed before exceeding cooldown rate, ED before exceeding max safe Table H

December 2014 NRC Exam General Scenario Outline Event 0 - The team assumes the shift with reactor power at 80% for control rod sequence exchange Event 1 - After taking the shift the team will start RCIC CST to CST for post maintenance testing Event 2 - After the start of RCIC, the System Operations Center (SOC) requests that main generator MVAR be raised prior to increasing reactor power Event 3 - The team will raise reactor power with control rods as part of the control rod sequence exchange Event 4 - Following control rod with draw Containment Unit Cooler A trips requiring start of the non-safety related unit cooler C. Entry is made into Tech Spec 3.6.1.7 Event 5 - Next APRM F fails upscale resulting in a 1/2 scram. Entry into Tech Spec 3.3.1.1 will be made and the APRM will be bypassed and the 1/2 scram reset Event 6 - The inlet valve to the turbine steam seal pressure regulator fails next requiring the team to utilize the bypass valve to restore steam seal header pressure prior to a loss of condenser vacuum Event 7 - A steam leak then occurs in the RCIC room. RCIC room temperature and radiation levels begin to rise. The unit is taken offline (Scrammed) when the leak is unable to be isolated. As the steam leak continues radiation levels continue to rise, because the door between the RCIC room and RHR C was left open as the maintenance personnel exited the room, RHR C radiation levels begin to rise. The team will enter EOP-0003 for secondary containment control and track radiation levels. When radiation level reach the MAX SAFE values in both rooms the RPV will be emergency depressurized (Critical Task to emergency depressurize within 20 minutes of exceeding max safe in two or more areas)

Event 8 - During the emergency depressurization three ADS safety relief valves will fail to open requiring the team to open additional safety relief valves to ensure the reactor is depressurized (Critical Task to open additional SRVs to ensure RPV is depressurized)

Event 9 - The RCIC isolation valves fail to isolated allowing steam to continue to enter the RCIC room. The operator should attempt to isolate the valves from the control board.

Number: *RSMS-NRC_DEC14-4 RIVER Revision: 00 BEND STATION Page 1 of 17 Approximate Time: 1 Hour(s)

SIMULATOR SCENARIO Record Type: *Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

APRM UPSCALE, SSE HDR LOW, HVR-UC1A TRIP, RCIC LEAK, SRV FAILURE REASON FOR REVISION:

NRC December 2014 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-2014 Preparer KCN Date Dave Bergstrom 0257 09-30-2014 Technical Review (SME) KCN Date Steve Carter 0358 10-01-2014 Operations Representative KCN Date Joey Clark 0260 10-18-2014 Facility Reviewer KCN Date

Indexing Information

I. DESCRIPTION OF SCENARIO This scenario begins with the plant at 80% power.

Events for this scenario:

Start RCIC IAW SOP-0035 Section 4.2

Adjust MVAR on Main Generator IAW SOP-0080, section 5.9

Raise power per RMP control rod withdrawal

APRM F fails upscale

Loss of Steam Seal Header Pressure

Steam Leak in RCIC Room -Spreads to RHR-C

ADS SRV Failure to Energize (B21-RVF041B, D, F)

RCIC Steam Supply Isol Valves (F063 &64) fail to shut II. TERMINAL OBJECTIVES

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

RSMS-NRC_DEC14-4 Page 2 OF 17

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC #254 Power: 80%

Core: Xenon equilibrium Equipment OOS: None STPs Due: None LCOs: None Evolutions in progress: Performing Sequence Exchange; RHR-B is in Supp Pool Cooling and Containment Purge is in service for post-maintenance RCIC testing.

Problem/Lit annunciators: None RSMS-NRC_DEC14-4 Page 3 OF 17

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Actions Simulator Setup Malfunctions Check Boards for T26 E51MOVF022P, FV 25%,

Equip Tags DELETE 00:00:03, E51-MOVF022 POSITION Check procedures and T4 DI_HVR-UC1A, STOP, 863-71C hard cards for marks CONTMT UNIT CLR SW Check Gauges/Meters T4 LO_HVR-UC1A-A, ON, 863-71C for marks. CONTMT UNIT CLR LTA AMBER T4 p863_71a:f_3, FAIL ON, Make marked-up CONTAINMENT UNIT COOLERS copies of STPs OUTLET FLOW LOW available. T5 NMS011F, APRM F FAILS UPSCALE Check that the T6 MSS010, GLAND SEAL REG INLET Shutdown Plan is VLV MOVS1 FAILS appropriate for this scenario. T25 p863_71a:f_3, FAIL OFF, CONTAINMENT UNIT COOLERS OUTLET FLOW LOW Check power ~ 80%

T7 RCIC004, RCIC STEAM LEAK IN Bring up Insight - RCIC ROOM RCIC cubicle T7 RMS215, FV 10000, RAMP 00:15:00, Temperature RHR EQUIPMENT ROOM MONITOR (RE215)

T7 RMS219 FV 10000, RAMP 00:10:00, RCIC EQUIPMENT ROOM MONITOR (RE219)

RSMS-NRC_DEC14-4 Page 4 OF 17

Event Number MFS-OR-REM-SCH Expected Operator Actions MSS008D, SRV 1B21*F041B FAIL TO ENERGIZ MSS008O, SRV 1B21*F041D FAIL TO ENERGIZ MSS008G, SRV 1B21*F041F FAIL TO ENERGIZ RCIC007, RCIC OUTBD ISOL VLV, F063, FAILS TO CLOSE RCIC008, RCIC OUTBD ISOL VLV, F064, FAILS TO CLOSE Remote Functions T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

Overrides NONE Event Triggers T25 , ZDI2(326)==1, DI_HVR-UC1C Simulator Setup Event 0 RUN CREW: Board walk down / Turnover.

RSMS-NRC_DEC14-4 Page 5 OF 17

Event 1 ROLE PLAY: SRO

Direct the UO to perform SOP-0035 Section 4.2.

Start RCIC IAW SOP- As radiation protection acknowledge UO

Accept the direction to perform SOP-0035 Section 0035, Section 4.2 RCIC pump operation and report that 4.2.

Event initiated by room conditions are being monitored.

Perform SOP-0035 Section 4.2.

crew from turnover As maintenance acknowledge RCIC pump

Notify Radiation Protection sheet. operation and report that mechanics are

Verify SPC and Containment Purge are in-service standing by to perform post maintenance

Verify STP-057-0700, is being performed by inspections. another operator As reactor building operation coordinate

Start Gland Seal Compressor with unit operator and report that E51-

Open E51-F059 F022 local valve position indicates 25%

Make Plant announcement open as follows:

Verify H13-P601-21-B03 is clear

Open E51-F022 to 25%

On first stroke of E51-F022

Open E51-F045 report valve is 15% open

Verify closed E51-F025,F026, F004, F005

On second stroke of E51-F022

Establish a discharge flow path to the CST report valve is 25% open and

Open E51-F059 insert trigger 26 to position valve

Throttle E51-F022 to discharge pressure of to 25% open. approximately 800 psig

Verify E51-F019 closed RSMS-NRC_DEC14-4 Page 6 OF 17

Event 2 ROLE PLAY: SRO

Direct the UO to perform SOP-0080 Section 5.9 to As SOC acknowledge that the RBS main raise main generator MVAR to +100.

Adjust MVAR on generator MVARS have been raised to

Report to the SOC that MVARS have been raised Main Generator to

+100. to +100.

+100 IAW SOP-0080, ATC

Accept the direction to perform SOP-0080 Section Section 5.9 5.9 to raise main generator MVAR to +100

Perform SOP-0080 Section 5.9:

Event initiated by

Verify Voltage Reg Switch in Auto crew from turnover

Adjust MVARS to +100 by:

sheet.

Momentarily depress the RAISE pushbutton

Verify VAR-1SPGN05 reads +100 RSMS-NRC_DEC14-4 Page 7 OF 17

Event 3 ROLE PLAY: SRO

Direct the ATC to perform RMP control rod As reactor engineer provide next withdraw step Raise power IAW sequential EN-RE-215 RMP control rod RMP for sequence ATC withdraw step to the SRO.

Accept the direction to perform RMP control rod exchange.

withdraw step.

Event initiated by RE

Perform RMP control rod withdraw step.

providing EN-RE-215 RMP control rod withdraw step.

RSMS-NRC_DEC14-4 Page 8 OF 17

T4 DI_HVR-UC1A, STOP, 863-71C SRO

Acknowledge trip of HVR-UC1A Event 4 CONTMT UNIT CLR SW HVR-UC1A trips

Reference Technical Specification 3.6.1.7 T4 LO_HVR-UC1A-A, ON, 863-71C Event T4 initiated at CONTMT UNIT CLR LTA AMBER

Condition A, One required primary containment Lead Evaluator T4 p863_71a:f_3, FAIL ON, unit cooler inoperable, restore required discretion. CONTAINMENT UNIT COOLERS containment unit cooler to OPERABLE status in OUTLET FLOW LOW 7 days T25 p863_71a:f_3, FAIL OFF, Delay

Direct start of HVR-UC1C 00:00:03, CONTAINMENT UNIT COOLERS OUTLET FLOW LOW UO

Recognize and report trip of HVR-UC1A ROLE PLAY:

As WMC/FIN/Maintenance, accept request

Start HVR-UC1C IAW ARP-863-71A-H03 and for maintenance assistance in investigating SOP-0059, Section 4.2 or Section 5.12 HVR-UC1A trip As reactor building operator report as follows:

For breaker investigation report the cause of breaker trip appear to be over current

For unit cooler investigation report that you do not see anything abnormal at HVR-UC1A

For start of HVR-UC1C report that the unit cooler is operating normally RSMS-NRC_DEC14-4 Page 9 OF 17

Event 5 T5 NMS011F, APRM F FAILS SRO

Accept the report of APRM F upscale failure with UPSCALE Division 2 half scram and no single rod scrams APRM F fails upscale ROLE PLAY:

Notify organization of APRM F failure and request Event trigger T5 As back panel report that APRM F assistance.

initiated at Lead Evaluator discretion. indicates full upscale and that all other

Reference Technical Specifications 3.3.1.1 APRMs indicate normal.

Potential Tech Spec LCO for tracking Condition As WMC/FIN/RE/Maintenance, accept A entry if another division 2 APRM were to request for maintenance assistance in become inoperable investigating APRM F trip

Direct placing APRM F in bypass and reset of division 2 half scram.

UO

Respond to APRM F failure by investigating and reporting back panel indications ATC

Recognize and report upscale failure of APRM F with a Division 2 half scram and no single rod scrams

Place APRM F in bypass

Reset Division 2 half scram RSMS-NRC_DEC14-4 Page 10 OF 17

Event 6 T6 MSS010, GLAND SEAL REG INLET SRO

Acknowledge low steam seal evaporator header VLV MOVS1 FAILS pressure Loss of Steam Seal Header Pressure ROLE PLAY:

Direct operator restoration of steam seal evaporator As turbine building operator accept request header pressure per ARP Event T6 initiated at to investigate steam seal evaporator failure Lead Evaluator and after 5 min report that TME-MOVS1 is ATC

Recognize and report low steam seal evaporator discretion. closed for some reason header pressure

Take manual control of steam seal header pressure IAW ARP-870-54A-E05

Open TME-MOVS2 to restore steam seal evaporator header pressure RSMS-NRC_DEC14-4 Page 11 OF 17

Event 7 T7 RCIC004, RCIC STEAM LEAK IN SRO

Enter EOP-0003, Secondary Containment Control RCIC ROOM Steam Leak in RCIC T7 RMS215, FV 10000, RAMP 00:15:00,

Direct monitoring and reporting of secondary Room - Spreads to RHR EQUIPMENT ROOM MONITOR containment parameters RHR-C (RE215)

Direct RPV pressure reduction to combat the RCIC Event T7 initiated at T7 RMS219 FV 10000, RAMP 00:10:00, room steam leak.

Lead Evaluator RCIC EQUIPMENT ROOM MONITOR

Direct Emergency Depressurization when any discretion. (RE219) secondary containment parameter exceeds it max CRITICAL TASK: safe level in any two or more areas.

ED within 20 minutes after exceeding max safe Table H in two or more areas ATC

Lower reactor pressure to combat the RCIC room steam leak.

ROLE PLAY:

As Back panel provide ECCS cubicle UO

Monitor and Report ECCS cubicle temperature and temperatures as follows: radiation levels.

RCIC room temperature - from

Open 7 ADS/SRVs when directed to emergency insight depressurize the RPV

All other ECCS room temperatures 85F.

As WMC/FIN/Maintenance accept request to assist in isolation of RCIC leak ENCLOSURES:

T18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T12 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

RSMS-NRC_DEC14-4 Page 12 OF 17

Event 8 MSS008D, SRV 1B21*F041B FAIL TO SRO

Direct opening of additional SRVs to ensure RPV ENERGIZ ADS SRVs fail to is depressurized MSS008O, SRV 1B21*F041D FAIL TO operate. ENERGIZ UO

Recognize and report B21-RVF041B, D, F fail to Event initiated upon MSS008G, SRV 1B21*F041F FAIL TO energize CRS direction to open ENERGIZ

Open additional SRVs to ensure RPV is 7ADS/SRVs for depressurized emergency CRITICAL TASK:

depressurization.

Addition SRVs opened to ensure RPV is depressurized.

RSMS-NRC_DEC14-4 Page 13 OF 17

Event 9 RCIC007, RCIC OUTBD ISOL VLV, SRO

Direct attempted closure of E51-F063 and F064 F063, FAILS TO CLOSE RCIC Steam Supply RCIC008, RCIC OUTBD ISOL VLV,

Contact organization for assistance in closing E51-Isol Valve (F063&64) F064, FAILS TO CLOSE F063 and F064 fail to shut Event concurrent with UO

Attempt closure of E51-F063 and F064 event 7 Termination is at the FREEZE Critical Task Review:

discretion of the Chief 1. ED within 20 minutes after exceeding max safe Table H in two or Examiner. more areas

2. Additional SRV opened to ensure RPV is depressurized.

RSMS-NRC_DEC14-4 Page 14 OF 17

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated with an *:

RCIC started per SOP-0035, Section 4.2

Main Generator MVARS raised to +100

RMP control rod withdraw step completed

APRM F Bypassed; Tech Specs referenced

1/2 Scram reset

Manual control of steam seal header pressure established

HVR-UC1C in-service

*ED within 10 minutes after exceeding max safe Table H in two or more areas

Addition SRVs opened to ensure RPV is depressurized RSMS-NRC_DEC14-4 Page 15 OF 17

VII. REFERENCES A. Plant Procedures

1. SOP-0035, Reactor Core Isolation Cooling System

2. SOP-0080, Turbine Generator Operation

3. ARP-870-54A-E05

4. ARP-863-71A-H03

5. SOP-0059, Containment HVAC System

6. Tech Specs

7. EN-OP-115, Attachment 9.8

8. AOP-0001, Reactor Scram

9. AOP-0002, Turbine Trip

10. AOP-0003, Automatic Isolations

11. EOP-1, RPV Control

12. EOP-2, Primary Containment Control

13. EOP-3, Secondary Containment Control

14. OSP-0053, Emergency and Transient Response Support Procedure RSMS-NRC_DEC14-4 Page 16 OF 17

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date Reactor Power is 80% for sequence exchange RE performing monitor cases for next RMP step RHR-B is in Suppression Pool Cooling and Containment low volume purge is in service to support RCIC run. STP-057-0700, Suppression Poll Average Water Temperature Verification is being performed by another operator.

RCIC post maintenance testing to begin following RCIC start per SOP-0035, Section 4.2, it IS desired to simulate a RCIC injection startup with a discharge pressure of approximately 800 psig establish after startup SOC has requested that main generator MVARS be raise to +100 following RCIC startup to support sys load prior to raising reactor power.

SIGNIFICANT LCO STATUS EOOS STATUS 10.0 Green EQUIPMENT STATUS PROTECTED EQUIPMENT Div 1 and 3

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Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-NRC_DEC14-4 Page 17 OF 17

ML15007A172

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