Revision as of 00:33, 11 April 2019

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 (see Note) Type Code* Describe activity to be performed Conduct of Operations R, D (A1) Determine the amount of Decay Heat in the Core per OSP-0041 KA 2.1.2 0 (4.6) Ability to interpret and execute procedure steps Conduct of Operations R, D (A 2) Determine corrected Fuel Zone Level Indication KA 2.1.23 (4.3) Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Equipment Control R, N (A3) Use plant drawings to determine effect(s) of fuse removal 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

Emergency Procedures/Plan R, M (A4) Determine Containment Water Level During Containment Flooding 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 (N)ew or (M)odified from

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 rms 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 (see Note) Type Code* Describe activity to be performed Conduct of Operations R, M (A5) Determine stay time for a hot environment 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).

Conduct of Operations R, M (A 6) Determine Actions for Reactor Water Chemistry KA 2.1.34 (3.5) Knowledge of primary and secondary plant chemistry limits.

Equipment Control R, N (A 7) Determine Secondary Containment Operability KA 2.2.1 2 (4.1) Knowledge of surveillance procedures

.

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

Emergency Procedures/Plan R, M (A9) Determine PAR 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 (N)ew or (M)odified from

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-D 14-A1 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

EVALUATION LOCATION: X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: August 28, 201 4 Reviewed: Steve Carter Date: October 1, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 2 of 7 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 u sing Attachments 1 and 6 of OSP

-0041. The applicant will conclu de that SPC/ADHR do es 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 1 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on November 25, 20 14. It is now 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on November 2 6, 20 14. RHR B is operating in SDC and the designated Alternate Decay Heat Removal Method is SPC/ADHR. The following conditions exist:

Reactor coolant Temperature 1 64 Service Water Temperature 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-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 3 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine the amount of Decay Heat in the Core per OSP

-0041 301001005003 G 2.1.20

4.6 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-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 4 of 7 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

__________ 10 6 BTU/HR Standard Applicant determined the core decay heat to be 75 x 10 6 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-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 5 of 7 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 an d the 200temperature 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-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 6 of 7 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-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 7 of 7 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 1 Service Water Temperature 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-D 14-A 2 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

EVALUATION LOCATION

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: August 28, 201 4 Reviewed: Steve Carter Date: October 1, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 2 of 7 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-D 14-A 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 3 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

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

3.9 REFERENCES

APPLICABLE OBJECTIVES SOP-0001, Nuclear Boiler Instrumentation, Rev 1 9 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

Attachment 3 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-D 14-A 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 4 of 7 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-D 14-A 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 5 of 7 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-D 14-A 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 6 of 7 OPERATOR CUE SHEET Initial Conditions

The plant has experienced a LOCA.

Fuel Zone Indication is reading

-1 85 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-D 14-A 2 Rev 0 River Bend Station Initial License Exam Page 7 of 7 RJPM-NRC-D 14-A 3 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

EVALUATION LOCATION

Perform Plant X Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 7, 201 4 Reviewed: Steve Carter Date: October 1, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 2 of 7 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 P 852 to de-energize the damper for work to begin. 4) Solicit and answer any questions the operator may have

.

RJPM-NRC-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 3 of 7 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

-P86 3 Status Light for FB Vent Dampers Loss of Lights for all 4 valves above

RJPM-NRC-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 4 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Use Plant Drawings to Determine Effect of Fuse Removal 300 246003 001 299003001001 G 2.2.1 5

3.9 REFERENCES

APPLICABLE OBJECTIVES E SK-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 P 852 in accordance with the attached key

.

RJPM-NRC-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 5 of 7 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-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 6 of 7 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-D 14-A 3 Rev. 0 RJPM-NRC-D 14-A 3 Rev 0 Page 7 of 7 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 P 852 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-D 14-A 4 Rev 0 River Bend Station Initial License Exam Page 1 of 6 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

Refer to Grading Instructions at end of JPM SAT UNSAT EVALUATION METH OD: 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)

RJPM-NRC-D 1 4-A 4 Rev. 0 RJPM-NRC-D 14-A 4 Rev 0 Page 2 of 6 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) Initi al 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 determine d 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 3:

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-D 1 4-A 4 Rev. 0 RJPM-NRC-D 14-A 4 Rev 0 Page 3 of 6 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Containment Water Level During Containment Flooding 200063005001 G 2.4.2 1

4.0 REFERENCES

APPLICABLE OBJECTIVES EOP-00055, Encl 23 , Containment Water RLP-HLO-0516, Obj 1 Level Determination, Rev 3 1 4 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-D 1 4-A 4 Rev. 0 RJPM-NRC-D 14-A 4 Rev 0 Page 4 of 6 PERFORMANCE

START TIME:

1. *Procedure Step:

3.3 Determine

Containment Water Level

. Standard Applicant determine d 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-D 1 4-A 4 Rev. 0 RJPM-NRC-D 14-A 4 Rev 0 Page 5 of 6 JPM COMMENT SHEET CRITERIA FOR SATISFACTORY EVALUATION

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

d. 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-D 1 4-A 4 Rev. 0 RJPM-NRC-D 14-A 4 Rev 0 Page 6 of 6 OPERATOR CUE SHEET Initi al 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 3:

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-D 14-A5 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

2 0 Actual Time (min):

JPM RESULTS*: (Circle one)

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

EVALUATION LOCATION: X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 7, 201 4 Reviewed: Steve Carter Date: October 2, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 2 of 7 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 9 5°F.

4) Solicit and answer any questions the operator may have

.

RJPM-NRC-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 3 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Stay Time for a Hot Environment 300076003001 G 2.1.2 6

3.6 REFERENCES

APPLICABLE OBJECTIVES EN-IS-108 , Working in Hot Environments, Rev 1 0 REQUIRED MATERIALS

EN-IS-108, Rev 1 0 SIMULATOR CONDITION S &/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-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 4 of 7 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 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 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-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 5 of 7 4. Procedure Step:

5.3 [2] From Attachment 9.2 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 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 102 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 102 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-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 6 of 7 JPM COMMENT SHE ET 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-D 14-A5 Rev. 0 RJPM-NRC-D 14-A5 Rev 0 Page 7 of 7 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-D 14-A6 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

EVALUATION LOCATION: X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 8, 201 4 Reviewed: Steve Carter Date: October 2, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A6 Rev. 0 RJPM-NRC-D 14-A6 Rev 0 Page 2 of 7 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 determin e 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-D 14-A6 Rev. 0 RJPM-NRC-D 14-A6 Rev 0 Page 3 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Actions for Reactor Water Chemistry 400084004001 G 2.1.34

3.5 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-D 14-A6 Rev. 0 RJPM-NRC-D 14-A6 Rev 0 Page 4 of 7 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-D 14-A6 Rev. 0 RJPM-NRC-D 14-A6 Rev 0 Page 5 of 7 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-D 14-A6 Rev. 0 RJPM-NRC-D 14-A6 Rev 0 Page 6 of 7 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-D 14-A6 Rev 0 River Bend Station Initial License Exam Page 7 of 7 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

RJPM-NRC-D 14-A7 Rev 0 River Bend Station Initial License Exam Page 1 of 6 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

Refer to Grading Instructions at end of JPM SAT UNSAT 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)

RJPM-NRC-D 14-A7 Rev. 0 RJPM-NRC-D 14-A7 Rev 0 Page 2 of 6 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 H1 3-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-D 14-A7 Rev. 0 RJPM-NRC-D 14-A7 Rev 0 Page 3 of 6 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Secondary Containment Operability 300 095 003001 G 2.2.1 2

4.1 REFERENCES

APPLICABLE OBJECTI VES 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-D 14-A7 Rev. 0 RJPM-NRC-D 14-A7 Rev 0 Page 4 of 6 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-D 14-A7 Rev. 0 RJPM-NRC-D 14-A7 Rev 0 Page 5 of 6 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-D 14-A7 Rev. 0 RJPM-NRC-D 14-A7 Rev 0 Page 6 of 6 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-D 14-A8 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

X Perform Plant Simulate Simulator Control Room X Classroom Prepared: Dave Bergstrom Date: September 8, 201 4 Reviewed: Steve Carter Date: October 2, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 2 of 7 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-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 3 of 7 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 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-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 4 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Required Actions upon Radioactive Effluent Monitor Failure 300169003002 G 2.3.11

4.3 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-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 5 of 7 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-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 6 of 7 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-D 14-A8 Rev. 0 RJPM-NRC-D 14-A8 Rev 0 Page 7 of 7 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-D 14-A 9 Rev 0 River Bend Station Initial License Exam Page 1 of 8 NUCLEAR PLANT OPERATOR ADMINISTRATIVE JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

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

EVALUATION LOCATION

X Perform Plant Simulate X Simulator Control Room Classroom Prepared: Dave Bergstrom Date: September 8, 201 4 Reviewed: Steve Carter Date: October 2, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 2 of 8 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 TED E 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-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 3 of 8 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 time on Declaration date for 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-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 4 of 8 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine PAR 301 016 00 5 00 3 G 2.4.4 4

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-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 5 of 8 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 St ep: 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-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 6 of 8 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-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 7 of 8 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 6.0 9 E0 5 Miles 9.44E1 10 Miles 1.88 E 0 10 Miles 2.55E1 Meteorological Data

Wind Speed 3.1 mph Wind Direction 350 deg. Delta T -0.7 o F Stability Class D

RJPM-NRC-D 14-A 9 Rev. 0 RJPM-NRC-D 14-A 9 Rev 0 Page 8 of 8 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

time on Declaration date for

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:

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 Thrust Reversal (GOP-0001) S,M 3 d. (S4) Reduce SDC to only RHR

-A - w/ overload pre

-trip alarm S, A,L,N 4 e. (S5) St op Cont High Volume Purg e - 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 Syste ms@ (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 (AOP-14, Sect 5.3 and SOP-49, Sect 5.7) A , E,L,N 6 @ 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 t he control room.

Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 5 5 3 - / - 2 4 7 0 1 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 Thrust Reversal (GOP-0001) S,M 3 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 (AOP-14, Sect 5.3 and SOP

-49, Sect 5.

7) A,E,L,N 6 @ 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 4 4 5 5 - / - 2 3 5 0 1 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 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 120 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 Thrust Reversal (GOP-0001) S,M 3 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 (AOP-14, Sect 5.3 and SOP

-49, Sect 5.

7) A,E,L,N 6 @ 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 2 3 4 - / - 2 2 2 0 1 RJPM-NRC-D 14-C1 Rev 0 River Bend Station Initial License Exam Page 1 of 12 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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)

Refer to Grading Instructions at end of JPM SAT UNSAT 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)

RJPM-NRC-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 2 of 12 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 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 3 of 12 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Shed DC Loads for Station Blackout 400067004001 263000 A 4.0 1 295003 AA1.04 3.3 / 3.5 3.6 /

3.7 REFERENCES

APPLICABLE OBJECTIVES AOP-0050, Station Blackout, Rev 49 RLP-HLO-0 5 41, 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 4 of 12 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-CR 106 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: