Revision as of 08:13, 9 July 2018

Text

River Bend-2014-12 Final Op Test
	ML15007A105
Person / Time
Site:	River Bend
Issue date:	12/12/2014
From:	Vincent Gaddy; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML15007A105 (318)
	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

.

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) Perform Main Turbine BPV Cycle Test (STP-509-0101) S, D 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) Perform UO Actions of AOP

-31 to Operate the Div 1 EDG 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 5 6 6 - / - 2 4 5 0 1 Revision 3

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 post-maintenance run of RCIC is ongoing. Direction will be given to secure RCIC using the SOP. An alarm alerts the applicant of an abnormal condition in the RCIC exhaust drain system. Because of plant conditions, and direction in the Alarm Response Procedure, the applicant will restart the RCIC Gland Seal Compressor

. S3 - This is a replacement JPM for Performing a Pressure Set Adjustment. There were too few steps in the previous JPM

. The plant is operating at power; this JPM is a surveillance to verify the full stroke operation of the Main Turbine Bypass Valves. S4 - This is a replacement JPM for placing the Turbine on the turning gear.

The reactor is shutdown with two loops of shutdown cooling in operation.

This task will have the applicant secure the B loop of SDC. As an alternat e path, a low voltage condition will cause elevated motor amps on the A RHR Pump; the applicant will have to use the ARP to reduce load on the pump by reducing flow

.

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 ha d experienced high containment radiation levels and high volume purge, using Standby Gas Treatment, was placed in service and rad levels reduced. This task will have the applicant secure the containment purge using SOP

-0059. As an alternate Path, a failure of the decay heat removal fan occurs , and the applicant will be required to re-start the standby gas treatment system with a suction from outside air using SOP

-0043. 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 - This task will have the applicant simulate performing a post-maintenance startup of the RPS Motor Generator Set B using SOP-00 79 , Reactor Protection System. An Alternate Path is taken when the MG fails to self

-excite and the applicant must use guidance in the procedure to reset the over excitation trip to allow the motor generator to achieve proper voltage.

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) Perform Main Turbine BPV Cycle Test (STP-509-0101) S, D 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) Perform UO Actions of AOP

-31 to Operate the Div 1 EDG 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 6 5 - / - m) 2 3 4 0 1 Revision 2

NRC

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

. A post-maintenance run of RCIC is ongoing. Direction will be given to secure RCIC using the SOP. An alarm alerts the applicant of an abnormal condition in the RCIC exhaust drain system. Because of plant conditions, and direction in the Alarm Response Procedure, the applicant will restart the RCIC Gland Seal Compressor

. S3 - This is a replacement JPM for Performing a Pressure Set Adjustment. There were too few steps in the previous JPM. The plant is operating at power; this JPM is a surveillance to verify the full stroke operation of the Main Turbine Bypass Valves.

S 4 - This is a replacement JPM for placing the Turbine on the turning gear.

The reactor is shutdown with two loops of shutdown cooling in operation.

This task will have the applicant secure the B loop of SDC. As an alternate path, a low voltage condition will cause elevated motor amps on the A RHR Pump; the applicant will have to use the ARP to reduce load on the pump by reducing flow.

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 ha d experienced high containment radiation levels and high volume purge, using Standby Gas Treatment, was placed in service and rad levels reduced. This task will have the applicant secure the containment purge using SOP-0059. As an alternate Path, a failure of the decay heat removal fan occurs , and the applicant will be required to re-start the standby gas treatment system with a suction from outside air using SOP

-0043. 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 greate 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 - This task will have the applicant simulate performing a post

-maintenance startup of the RPS Motor Generator Set B using SOP-00 79 , Reactor Protection System. An Alternate Path is taken when the MG fails to self

-excite and the applicant must use guidance in the procedure to reset th e

over excitation trip to allow the motor generator to achieve proper voltage

.

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) d. (S4) e. (S5) Stop Cont High Volume Purge

- w/Decay Heat Fan trip S ,A,D, E, EN 9 f. (S6) g. (C1) 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) k. (P3) Perform UO Actions of AOP

-31 to Operate the Div 1 EDG 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 3 3 3 - / - 2 1 2 0 1 Revision 3 RJPM-NRC-D 14-A1 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 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 8 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 INSUFFI CIENT. 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 8 ANSWER KEY SYSTEM HEAT REMOVAL CAPACITY (BTU/HR)

CONDITIONS / ASSUMPTIONS SPC/ADHR 37.67 x 10 6 40.12 x 10 6 70.86 x 10 6 2500 gpm, 83F Service Water &

2250 gpm, 120F Rx Coolant 2250 gpm, 140F Rx Coolant 2250 gpm, 20 0F Rx Coolant

RJPM-NRC-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 4 of 8 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 INSUFF ICIENT.

RJPM-NRC-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 5 of 8 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

. There is a key on page 3 of this JPM.

Results SAT UNSAT RJPM-NRC-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 6 of 8 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 "INSUFFICIENT

". Cue Notes Applicant will use the SPC/ADHR system and temperature to make this determination.

This table (shown on page 3 of this JPM) indicates that a decay heat of just 70.86 x 10 6 BTU/Hr will allow reactor coolant temperature to therefore not allow you to stay in Mode 4.

The current decay heat (determined from Attach 6) is too great for the SPC/ADHR system to remove and not undergo a mode change

. 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 INSUFFICIENT

. This completes this JPM.

STOP TIME:

RJPM-NRC-D 14-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 7 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-A1 Rev. 0 RJPM-NRC-D 14-A1 Rev 0 Page 8 of 8 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) to remain in Mode 4.

RJPM-NRC-D 14-A 2 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 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):

9 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 8 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 8 ANSWER KEY 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 RJPM-NRC-D 14-A 2 Rev 0 Page 4 of 8 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 5 of 8 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 belo w TAF. Cue Notes As seen on the key (page 3 of this JPM), 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 As seen on the key (page 3 of this JPM), the intersection of -185" and 300 psig is 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 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 2 Rev. 0 RJPM-NRC-D 14-A 2 Rev 0 Page 7 of 8 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 8 of 8 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 B fails CLOSED

(Critical Task is for any one of the three listed below)

3. ALARM number 0464 on H13

-P8 63 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 SA T 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 1 River Bend Station Initial License Exam Page 1 of 8 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):

10 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: August 28, 2014 Reviewed: Steve Carter Date: October 1, 2014

(Operations Representative)

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

RJPM-NRC-D 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 2 of 8 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 determin ed 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 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 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 3 of 8 ANSWER KEY ENCLOSURE 23 PAGE 7 OF 7 EOP-0005 REV.-314 PAGE 3 OF 139 RJPM-NRC-D 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 4 of 8 ANSWER KEY ENCLOSURE 23 CONTAINMENT PRESSURE AND WATER LEVEL DETERMINATION TABLE 1 RPV WATER LEVEL TO CONTAINMENT WATER LEVEL CORRELATION RPV WATER LEVEL

- CONTAINMENT WATER LEVEL

-162 in. = 62 ft.

-174 in. = 61 ft.

-186 in. = 60 ft.

-198 in. = 59 ft.

-210 in. = 58 ft.

-222 in. = 57 ft.

-234 in. = 56 ft.

-246 in. = 55 ft.

-258 in. = 54 ft.

-270 in. = 53 ft.

-282 in. = 52 ft.

-294 in. = 51 ft.

-306 in. = 50 ft.

ENCLOSURE 23 PAGE 6 OF 7 EOP-0005 REV.-314 PAGE 4 OF 139 RJPM-NRC-D 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 5 of 8 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 REASON FOR REVISION

Rev 1 - changed validation time from 8 min to 10 min; changed containment pressure from 7.5 to 5 psig and altered the JPM step accordingly added graph key 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 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 6 of 8 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 61 feet. (+/- one foot) Applicant determined water level of containment using the calculation given to be 61.5 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 PCWL = [ (ECCS Suction Press

- CTMT Press) x 2.3 ] + 4

[ (30 - 5) x 2.3 ] + 4 = [ 25 x 2.3 ] +4 = 57.5 + 4 = 61.5 Results SAT UNSAT 2. *Procedure Step:

Determine correlated RPV water level

. Standard Applicant determined the correlated RPV water level using Table 1 to be between -162" to -174". Cue Notes Table 1 and Figure 8 are in the key of this JPM, pages 3 and 4.

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 14-A 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 7 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 4 Rev. 1 RJPM-NRC-D 14-A 4 Rev 1 Page 8 of 8 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 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 1 River Bend Station Initial License Exam Page 1 of 8 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. 1 RJPM-NRC-D 14-A5 Rev 1 Page 2 of 8 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. The wet bulb temperature is 102°F.

4) Solicit and answer any questions the operator may have

.

RJPM-NRC-D 14-A5 Rev. 1 RJPM-NRC-D 14-A5 Rev 1 Page 3 of 8 ANSWER KEY RJPM-NRC-D 14-A5 Rev. 1 RJPM-NRC-D 14-A5 Rev 1 Page 4 of 8 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 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-D 14-A5 Rev. 1 RJPM-NRC-D 14-A5 Rev 1 Page 5 of 8 PERFORMANCE

START TIM E: 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. 1 RJPM-NRC-D 14-A5 Rev 1 Page 6 of 8 4. Procedure Step:

5.3 [2] From Attachment 9.2 by reviewing the table titled Heat Stress Threshold Values 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.

Standa rd Applicant determined that the Heat Stress Threshold is a factor in accordance with Attachment 9.2 by Applicant obtained wet bulb temperature from initial conditions.

Cue 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)

5. *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. 1 RJPM-NRC-D 14-A5 Rev 1 Page 7 of 8 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. 1 RJPM-NRC-D 14-A5 Rev 1 Page 8 of 8 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.

The wet bulb temperature is 102°F.

RJPM-NRC-D 14-A6 Rev 1 River Bend Station Initial License Exam Page 1 of 8 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. 1 RJPM-NRC-D 14-A6 Rev 1 Page 2 of 8 EXAMINER INFO SHEET Task Standard

Applicant determines that the plant startup may not 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-D 14-A6 Rev. 1 RJPM-NRC-D 14-A6 Rev 1 Page 3 of 8 ANSWER KEY Answer Below The Startup may continue YES NO (circle one)

RJPM-NRC-D 14-A6 Rev. 1 RJPM-NRC-D 14-A6 Rev 1 Page 4 of 8 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Determine Actions for Reactor Water Chemist ry 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, Chemistry GOP-0001, Plant Startup, Rev 82 CSP-0100, Chemistry

- Required Surveillances and Actions, Rev 26 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 not continue.

RJPM-NRC-D 14-A6 Rev. 1 RJPM-NRC-D 14-A6 Rev 1 Page 5 of 8 PERFORMANCE

START TIME:

Examiner Note: Give the following procedures to applicant as they are asked for:

GOP-0001, Plant Startup CSP-0100, Chemistry

- Required Surveillances and Actions TR 3.4.13, Chemistry AOP-0058, Abnormal Chemistry

1. *Procedure Step:

1. Determine the limiting chemistry value per TR 3.4.1 3, CSP-0100, and AOP-005 8. Standard Applicant determined the limiting parameter as chlorides in Reactor Water

. Cue Notes Results SAT UNSAT 2. *Procedure Step:

2. Determine the ability to continue plant startup.

Standard Applicant compared values and determined that the plant startup may not continue, based on being in Action Level 2 for Chlorides in AOP

-0058. Cue Notes If applicant uses Attach 1 page 2 (for Startup/Hot Standby) of AOP

-0058, then chlorides are in spec; the conditions of the JPM are for entering Mode 1.

The applicant must recognize that the JPM conditions are for changing Modes and therefore must use the correct graph.

Attachment 1, page 1 (for power > 10%), shows that Reactor Water Chlorides exceed the Action Level 2 criteria. (which may require shutdown)

Results SAT UNSAT Terminating Cue: Applicant determines that the plant startup may not continue. This completes this JPM.

STOP TIME:

RJPM-NRC-D 14-A6 Rev. 1 RJPM-NRC-D 14-A6 Rev 1 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-A6 Rev. 1 RJPM-NRC-D 14-A6 Rev 1 Page 7 of 8 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)

RJPM-NRC-D 14-A6 Rev 1 River Bend Station Initial License Exam Page 8 of 8 Reactor Water Conductivity 0.25 µS/cm p H 7.3 S.U. Chloride 40 ppb Sulfate 1.3 µg/L Feedwater Conductivity 0.061 µS/cm Total Iron 0.92 ppb Total Copper 0.12 ppb Dissolved O 2 27 ppb Condensate Hotwell Conductivity 0.05 µS/cm Control Rod Drive Conductivity 0.10 µS/cm Dissolved O 2 33 ppb RJPM-NRC-D 14-A7 Rev 1 River Bend Station Initial License Exam Page 1 of 7 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):

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: 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. 1 RJPM-NRC-D 14-A7 Rev 1 Page 2 of 7 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

-2.8 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. 1 RJPM-NRC-D 14-A7 Rev 1 Page 3 of 7 ANSWER KEY RJPM-NRC-D 14-A7 Rev. 1 RJPM-NRC-D 14-A7 Rev 1 Page 4 of 7 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 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 ARP-863-72A-A01, Rev 16 SIMULATOR CONDITIONS

&/or SETUP: 1. This is a classroom/Admin JPM

- There is no simulator setup

2. REASON FOR REVISION:

Rev 1 - Changed initial condition to allow for the dat to be plotted on the graph.

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. 1 RJPM-NRC-D 14-A7 Rev 1 Page 5 of 7 PERFORMAN CE: START TIME:

1. Procedure Step:

Determine corrected annulus pressure

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

-3.14 inches WC

. Cue Notes Calculation per STP

-000-0001 step 92.

-2.8 + -0.34 = -3.14 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 See graph key on page 3 of this JPM.

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. 1 RJPM-NRC-D 14-A7 Rev 1 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-A7 Rev. 1 RJPM-NRC-D 14-A7 Rev 1 Page 7 of 7 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

-2.8 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):

10 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 LWS-PNL187-4-C4, Alarm Response

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 LW S-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 release of gaseous radioactivity (AG1).

The plant has experienced a loss of offsite power and a large break LOCA inside containment. 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 ha ve.

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 N o.: 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 Step:

2 Complete the short form using given data.

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

Cue Notes 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 release of gaseous radioactivity (AG1). The plant has experienced a loss of offsite power and a large break LOCA inside containment.

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:

RJPM-NRC-D 14-S1 Rev 1 River Bend Station Initial License Exam Page 1 of 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

1 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 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)

RJPM-NRC-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 2 of 11 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 R M P-18-002, 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.

R M P-18-002 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-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 3 of 11 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING: Pull Control Rods to Achieve Criticality, with a Trip of CRD Pump 201020001001 201006001001 201005 A 3.0 4 201005 A 4.0 1 201001 A2.01 295022 AK2.02 295022 AA1.01 3.3 / 3.3 3.7 / 3.7 3.2 / 3.3 3.1 / 3.1 3.1 /

3.2 REFERENCES

APPLICABLE OBJECTIVES RMP- 18-002 RLP-STM-0 5 0 0, Obj 8, 10, 11, 18 SOP-00 71, 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-18-002 __1__ All other procedures are available in the simulator SIMULATOR CONDITIONS

& SETUP: 1. IC # 2 55 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. Override: DI_C11-C001B, STOP, CRD Pump B Aux Oil Pump Control switch

. 5. Malfunction T3, CRDM4449 ACCUMFLTS (initiate on examiner cue)

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-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 4 of 11 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 R C P-1 8-0 0 2, step 39 by depressing the two rod select numbers simultaneously.

(rod 44-4 9) 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-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 5 of 11 RJPM-NRC-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 6 of 11 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-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 7 of 11 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-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 8 of 11 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 require s Operator Action

s. 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.

If the applicant chooses to use SOP

-0002, CRD, he will call a building operator to perform pre

-start checks.

RJPM-NRC-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 9 of 11 7. Procedure Step:

1. Start the standby CRD Pump as follows:

a. Start Standby CRD Pump Aux Oil Pump C1 1-C001BP Standard Applicant attempts to start the B

- CRD Aux Oil Pump.

Applicant contacts a building operator to investigate the B Aux Oil Pump.

Cue Notes Turning the start switch (spring return) should start the aux oil pump, which would be indicated by a red light on, green light off, but the aux oil pump is faulted to not start, so the green light remains on and the red light remains off. Results SAT UNSAT Evaluator NOTE:

While no CRD pumps are running, control rod accumulator pressure s are lowering. There is an alarm associated with low accumulator pressure: P680 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)

. 8. *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 s on a withdrawn control rod, the applicant placed the mode switch to SHUTDOWN.

Cue Notes Examiner will signal the floor operator to initiate a malfunction which will cause an accumulator fault on a withdrawn control rod. (time compression)

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:

Examiner Note: Inform the applicant of the use of time compression for this JPM.

RJPM-NRC-D 14-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 10 of 11 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-S1 Rev. 1 RJPM-NRC-D 14-S1 Rev 1 Page 11 of 11 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.

R M P-1 8-00 2 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 R M P-18-00 2, beginning at step 39.

RJPM-NRC-D 14-S2 Rev 1 River Bend Station Initial License Exam Page 1 of 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

10 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 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)

RJPM-NRC-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 2 of 11 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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 3 of 11 DATA SHEET TASK Title:

Task Number K&A SYSTEM

K&A RATING

Shutdown RCIC using SOP

- w/ Drain Trap Level High 217018001001 217000 A 4.0 3 2 17 000 A 4.1 0 3.4 / 3.3 3.6 / 3.5 Reason for Revision REFERENCES

APPLICABLE OBJECTIVES S O P-0 0 3 5, Rev 47 RLP-STM-0209, Obj 5,10 ARP-601-2 1-A 0 2 , Rev 3 12 , R CI C Turbine Exhaust D r a in Tra p 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:a

2) 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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 4 of 11 PERFORMANCE

START TIME:

S O P-3 5 , Section 6.1 , RCIC System Shutdown

Examiner Note: The applicant may make a plant announcement about securing RCIC.

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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 5 of 11 5. *Procedure Ste p: 6.1.5 Close E51

-F045, RCIC Steam Supply Turbine Stop Valve and verify the following:

-F025, RCIC STM SPLY DR POT Up Stream ISOL Valve is open.

-F026, RCIC STM SUPLY DR POT Dn Stream ISOL Valve is open.

-F004, RCIC Turb Exh DR POT Up Stream ISOL Valve is open.

-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 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 RJPM-NRC-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 6 of 11 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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 7 of 11 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 E 5 1-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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 8 of 11 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 contact ed 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 STO P. 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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 9 of 11 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-D 14-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 10 of 11 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-S2 Rev. 1 RJPM-NRC-D 14-S2 Rev 1 Page 11 of 11 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-D 14-S 3 Rev 1 River Bend Station Initial License Exam Page 1 of 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE PATH TITLE: Perform BPV Cycle Test (STP

-509-0101) OPERATOR:

DATE: EVALUATOR:

EVALUATOR SIGNATURE:

CRITICAL TIME FRAM E: Required Time (min):

NA Actual Time (min):

NA PERFORMANCE TIME:

Average Time (min):

10 Actual Time (min):

JPM RESULTS*: (Circle one)

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

EVALUATION LOCATION

X Perform Pl ant Simulate X Simulator Control Room Prepared: Dave Bergstrom Date: October 29, 201 4 Reviewed: Steve Carter Date: October 30, 2014 (Operations Representative)

Approved: Joey Clark Date: October 30, 2014 (Facility Reviewer)

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 2 of 11 EXAMINER INFO SHEET Task Standard

Bypass Valve #1 is closed ; STP

-509-0101, Main Turbine Bypass System Valve Cycle Test, Section 7.2, Bypass Valve 1 Test, is complete

.

Synopsis: The reactor is at 70% power during a plant startup. This task will have the applicant perform a surveillance that will demonstrate the #1 BPV is operable by cycling the valve through at least one complete cycle of full travel

.

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 as the Unit Operator to perform STP-509-0101, Main Turbine Bypass System Valve Cycle Test, for Bypass Valve 1 ONLY.

3) Initial Conditions

The reactor is at 70% power during a plant startup

. No Rod withdrawal is scheduled during the performance of this STP. Both Turbine Bypass Valves (BPVs) are closed.

4) Solicit and answer any questions the operator may have

.

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 3 of 11 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Perform BPV Cycle Test (STP-509-0101) 241001002001 241000 K4.1 9 A 4.06 3.6 / 3.7 3.9 /

3.9 REFERENCES

APPLICABLE OBJECTIVES ST P-509-0 1 0 1, Rev 012 RLP-STM-0 110, Obj 2 REQUIRED MATERIALS

SAFETY FUNCTION:

Marked up copy of STP-509-0101, Rev 012

__3__ SIMULATOR CONDITIONS

& SETUP: 1. IC # 2 57 2. Required Power: > 23.8% RTP

3. ERIS operating with computer points available for performing Attachment 9

4. Mark up a copy of STP-509-0101 for the students use in the simulator.

Complete section 6 and NA section 7.3

5. A floor operator will be required to silence and acknowledge the alarm.

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: Bypass Valve #1 is closed ; STP

-509-0101, Main Turbine Bypass System Valve Cycle Test, Section 7.2, Bypass Valve 1 Test, is complete

.

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 4 of 11 PERFORMANCE

START TIME:

ST P-509-0 101, Main Turbine Bypass System Valve Cycle Test 7.1. Pretest Equipment Lineup

1. Procedure Step: 7.1.1 In the BYPASS VALVE TEST STATUS group, depress the TESTING pushbutton momentarily Standard Applicant located/identified and depressed the TESTING pushbutton.

Cue Notes Results SAT UNSAT 2. Procedure Step:

7.1.2 Check the following occurs:

1. The OFF light goes off.

2. The TESTING light comes on.

3. The READY light comes on.

Standard Applicant verified the OFF light is no longer lit.

Applicant verified the TESTING and READY lights are now lit.

Cue Notes Results SAT UNSAT Procedure Note:

The Fast Acting Solenoid can be verified by Bypass Valve (BPV) position indication or Servo current as the BPV opens. There is no sudden change in valve position during the closing stroke.

Valve movement can best be observed at C85AM5, 1 BYPASS VALVE POSITION meter The stroke time of BPV 1 is approximately 4 to 5 seconds, in either direction.

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 5 of 11 7.2 Bypass Valve 1 Test

3. Procedure Step:

7.2.1 Depress and hold the TEST BPV 1 pushbutton.

Standa rd Applicant located and depressed the TEST BPV 1 pushbutton and remains holding the button depressed.

Cue Inform the applicant that the ATC will acknowledge any annunciators.

Notes The sub-steps of 7.2 will be reviewed by the applicant, performed as written, then the paperwork/procedure marking completed.

Results SAT UNSAT 4. Procedure Step:

7.2.2. Check the following occurs:

1. The READY light goes off.

2. The TEST BPV 1 light comes on.

3. Small positive current change on C85AM4, 1 BYPASS VALVE SERVO CURRENT meter.

4. BPV 1 is traveling smoothly in the open direction as indicated on C85AM5, 1 BYPASS VALVE POSITION meter.

5. Annunciator P680

-07A-A07, TURBINE BYPASS VALVE OPEN alarms. Standard Applica nt verified the READY light is no longer lit.

Applicant verified the TEST BPV 1 light is now lit.

Applicant located/identified the C85AM4 meter, and verified a small positive current is present.

Applicant located/identified the C85AM5 meter, and verified that the #1 BPV is travelling in the open direction.

Applicant verified annunciator for the BPV OPEN alarmed.

Cue Notes A floor operator will silence and acknowledge the annunciator.

The stroke time of BPV 1 is approximately 4

- 5 seconds, in either direction. Results SAT UNSAT RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 6 of 11 5. Procedure Step:

7.2.2. Check the following occurs:

6. The Fast Acting Solenoid operates properly as BPV 1 opens.

Standard Applicant verified that BPV 1 traveled smoothly in the open direction.

Cue Notes The Fast Acting Solenoid can be verified by BPV position indication or Servo current as the BPV opens. There is no sudden change in valve position during the closing stroke.

Results SAT UNSAT 6. Procedure Step:

7.2.2. Check the following occurs: 7. Verify BPV 1 is full open by one of the following:

C85AM5, BYPASS VALVE POSITION.

ERIS point C85EA012, BYPASS VALVE 1 POSITION.

Only the FULL OPEN indicator light is on.

Standard Applicant used at least one of the three full open indications to verify that the #1 BPV was full open.

Cue Notes If ERIS point is used, a position of 1.0 indicates full open.

Results SAT UNSAT Procedure Note:

Step 7.2.2.8 may be N/A'd if the FULL OPEN indicator was used to verify valve position in step 7.2.2.7

. 7. Procedure Step:

7.2.2. Check the following occurs:

8. Only the FULL OPEN indicator light is on.

Standard Applicant verified the FULL OPEN indicator is on and the CLOSED indicator is off. Cue Notes The applicant may NA this step if this method was used in step 7.2.2.7 Results SAT UNSAT RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 7 of 11 8. *Procedure Step:

7.2.3 Release the TEST BPV 1 pushbutton

. Standard Applicant released the TEST BPV 1 pushbutton.

Cue Notes Results SAT UNSAT 9. Procedure Step: 7.2.4. Check the following occurs:

1. Small negative current change on C85AM4, 1 BYPASS VALVE SERVO CURRENT meter.

2. BPV 1 is traveling smoothly in the close direction as indicated on C85AM5, 1 BYPASS VALVE POSITION meter

. Standard Applicant located/identified the C85AM4 meter, and verified a small negative current is present.

Applicant located/identified the C85AM5 meter, and verified that the #1 BPV is travelling in the closed direction.

Cue Notes Results SAT UNSAT 10. Procedure Step:

7.2.4. Check the following occurs:

3. Verify BPV 1 is full closed by one of the following:

C85AM5, BYPASS VALVE POSITION.

ERIS point C85EA012, BYPASS VALVE 1 POSITION.

Only the CLOSED indicator light is on.

Standard Applicant used at least one of the three closed indications to verify that the #1 BPV was closed.

Cue Notes If ERIS point is used, a position of 0.0 indicates full closed.

Results SAT UNSAT Procedure Note:

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 8 of 11 Step 7.2.4.4 may be N/A'd if the CLOSED indicator was used to verify valve position in step 7.2.4.3

. 11. Procedure Step:

7.2.4. Check the following occurs:

4. Only the CLOSED indicator light is on

. Standard Applicant verified the CLOSED indicator is on and the OPEN indicator is off.

Cu e Notes The applicant may NA this step if this method was used in step 7.2.4.3 Results SAT UNSAT 12. Procedure Step:

7.2.4. Check the following occurs:

5. Annunciator P680

-07A-A07, TURBINE BYPASS VALVE OPEN clears. 6. The TEST BPV 1 light goes off.

7. The READY light comes on. Standard Applicant verified the alarm cleared as indicated by a slow flashing.

Applicant verified the TEST BPV 1 light is off.

Applicant verified the READY light is on.

Cue Notes Results SAT UNSAT Examiner Note: Section 7.3 for BPV #2 is N/A.

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 9 of 11 7.4 Restoration

13. *Procedure Step:

7.4.1 In the BYPASS VALVE TEST STATUS group, depress the OFF pushbutton.

Standard Applicant depressed the OFF pushbutton.

Cue Notes Results SAT UNSAT Terminating Cue: Bypass Valve #1 is closed ; STP

-509-0101, Main Turbine Bypass System Valve Cycle Test, Section 7.2, Bypass Valve 1 Test, is complete.

This completes this JPM.

STOP TIME:

RJPM-NRC-D 14-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 10 of 11 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-S 3 Rev. 1 RJPM-NRC-D 14-S 3 Rev 1 Page 11 of 11 OPERATOR CUE SHEET INITIAL CONDITIONS:

No Rod withdrawal is scheduled during the performance of this STP.

Both Turbine Bypass Valves (BPVs) are closed.

INITIATING CUE

The CRS has directed you as the Unit Operator to perform STP

-509-0101, Main Turbine Bypass System Valve Cycle Test, for Bypass Valve 1 ONLY.

RJPM-NRC-D 14-S 4 Rev 1 River Bend Station Initial License Exam Page 1 of 9 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

1 5 Actual Time (min):

JPM RESULTS*: (Circle one)

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

EVALUATION LOCATIO N: 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)

RJPM-NRC-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 2 of 9 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-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 3 of 9 DATA SHEET TASK Title:

Task Number K&A SYSTEM

K&A RATING

Reduce SDC to only RHR

-A - w/ overload pre

-trip alarm 205022001001 205000 A 1.0 7 205000 A3.03 205000 A4.09 2.2 / 2.1 3.5 / 3.3 3.1 / 3.1 Reason for Revision REFERENCES

APPLICABLE OBJECTIVES SOP-0031, RHR, Rev 321 RLP-STM-0 204 , 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 97 amps, ramp 18 seconds

6. Event 2: rhfrhr(1) < 6 75 represents RHR Loop Flow of approx.

5 000 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-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 4 of 9 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.

Applicant held the control switch for the HX outlet valve for 5 seconds after the green light comes on to ensure valve closure.

Cue Notes System flow is read on meter E12

-R603B, RHR PMP B LOOP FLOW.

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 observ ed the green light on and the red light off

. Cue Notes Results SAT UNSAT RJPM-NRC-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 5 of 9 3. *Procedure Step:

3. Close the following:

E12-F006 B, 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-F037B, RHR B TO UPPER POOL FPC ASSIST Standard Applicant verified the valve closed by observing the green light on and the red light off.

Cue Notes Results SAT UNSAT 6. 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 positi on and observing the green light on and the red light off.

Cue Notes Results SAT UNSAT RJPM-NRC-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 6 of 9 7. Procedure Step:

3. Close the following:

I F FWS-MO V7B, 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 observ ed 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. If asked, as the CRS, say that RHR

-B is no longer available.

Notes Results SAT UNSAT RJPM-NRC-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 7 of 9 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 throttled either the F003 or the F048 valve closed by intermittently rotating the control switch counterclockwise

, until 601-20A-A04, RHR Pump A Overload Pre

-Trip Warning clears.

Cue Notes Results SAT UN SAT Terminating Cue: RHR-B is secured from SDC and RHR

-A motor amps restored to normal. This completes this JPM.

STOP TIME:

RJPM-NRC-D 14-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 8 of 9 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-S 4 Rev. 1 RJPM-NRC-D 14-S 4 Rev 1 Page 9 of 9 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-S5 Rev. 0 River Bend Station Initial License Exam Page 1 of 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

1 5 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 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)

RJPM-NRC-D14-S5 Rev. 0 RJPM-NRC-D14-S5 Rev 0 Page 2 of 11 EXAMINER INFO SHEET 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

. 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 S O P-005 9, 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

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 RJPM-NRC-D14-S5 Rev 0 Page 3 of 11 DATA SHEET TASK Title:

Task Number K&A SYSTEM

K&A RATING

Secure from Containment High Volume Purge

-w/ trip of Decay Heat Fan 222023001001 295034 E A 1.03 4.0 /

3.9 REFERENCES

APPLICABLE OBJECTIVES

S O P-005 9 , 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 # 2 47 2. Required Power: no requirement

3. High Volume purge in progress

4. T 3 is to trip the decay heat fan with a delay of 5 seconds a) Malf: p863_73a:c_3 fail on Over: DI_GTS-FN2A stop LO_GTS-FN2A-G off LO_GTS-B3-A on Malf: p863_73a:d_6 on

5. Event 3: zdi2(458) = 1 (H VR-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 RJPM-NRC-D14-S5 Rev 0 Page 4 of 11 PERFORMANCE

START TIME:

S O P-005 9 , Section 5.

5, Containment High Volume Purge

. Examiner note: Applicant may make a plant announcement about securing 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 b y 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-AO D 1 A , 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 RJPM-NRC-D14-S5 Rev 0 Page 5 of 11 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 RJPM-NRC-D14-S5 Rev 0 Page 6 of 11 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 close will automatically initiate the malfunction

. Results SAT UNSAT RJPM-NRC-D14-S5 Rev. 0 RJPM-NRC-D14-S5 Rev 0 Page 7 of 11 ALTERNATE PATH:

ANNU NCIATOR, P863

-7 3 A-C03 alarms. Procedure Step:

Respond to ANNU NCIATOR, 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-FN 2A has neither green nor red lights lit

. Applicant dispatches operator to investigate.

Cue As CRS, accept report of fan trip.

As Building Operator, respond to call to investigate decay heat fan trip.

As building operator, after being dispatched, report back that the decay heat fan breaker is closed.

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

RJPM-NRC-D14-S5 Rev. 0 RJPM-NRC-D14-S5 Rev 0 Page 8 of 11 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 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-AO D 1 8A , AUX BLDG to GTS ISOLATION -AOD22A, ANNULUS MIXING OUT DMPR to GTS

2. Outside Air Supply

-AOD263, SGT UPSTREAM SPLY ISOL

-AOD264, SGT DNSTREAM SPLY ISOL Standard Applicant opened the two selected damper s 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 Examiner Note, If the applicant chooses to start Standby Gas on the Aux Building, he may call security to take an aux building door offline.

RJPM-NRC-D14-S5 Rev. 0 RJPM-NRC-D14-S5 Rev 0 Page 9 of 11 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.

Examiner Note: Applicant will make plant announcement about starting Standby Gas Treatment.

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 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 RJPM-NRC-D14-S5 Rev 0 Page 10 of 11 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 RJPM-NRC-D14-S5 Rev 0 Page 11 of 11 OPERATOR CUE SHEET INITIAL CONDITIONS:

Containment radiation levels have been reduced by performing a high volume purge on containment per SOP

-0059, Containment HVAC System.

INITIATING CUE

The CRS has directed you to secure from containment high volume purge using SOP-0059, Containment HVAC System, starting at step 5.5.8.

RJPM-NRC-D 14-S6 Rev. 0 River Bend Station Initial License Exam Page 1 of 10 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

10 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 X Simulator Control Room Prepared: Dave Bergstrom Date: September 2 0, 201 4 Reviewed: Steve Carter Date: October 2, 2014 (Operations Representative)

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

RJPM-NRC-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 2 of 10 EXAMINER INFO SHEET TASK STANDARD: The Suppression Pool Cooling and Cleanup System has been started up using 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

-0 140 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-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 3 of 10 DATA SHEET TASK Title:

Task Number K&A SYSTEM

K&A RATING

Start the Suppression Pool Cooling and Cleanup System 220004001001 209002 A 2.1 4 209001 A2.1 0 3.0 / 3.3 3.1 /

3.4 REFERENCES

APPLICABLE OBJECTIVES

SOP-0140, Rev 28, Section 5.

2 RLP-STM-0 656 Objective 7 , 11 REQUIRED MATERIALS

SAFETY FUNCTION

SOP-0059, Rev 034, Section 5.14

__5__ (Simulator copy)

SIMULATOR CONDITIONS

& SETUP: 1. IC # 257 2. Required Power: Any 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-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 4 of 10 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 UNS AT 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-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 5 of 10 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 switch es in the O P E N position and by checking the RED indicating light s ON and GREEN indicating light s OFF. Cue Notes Results SAT UNSAT RJPM-NRC-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 6 of 10 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:

5.2.1 2 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 check ed the GREEN indicating light OFF and the RED indicating light ON. Cue Notes Applicant may make a plant announcement about starting pump.

Results SAT UNSAT RJPM-NRC-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 7 of 10 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-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 8 of 10 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 TIM E:

RJPM-NRC-D 14-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 9 of 10 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-S6 Rev. 0 RJPM-NRC-D 14-S6 Rev 0 Page 10 of 10 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

-0 140 Section 5.

2.

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 in less than 30 minutes

.

Synopsis: This time critical task will remove DC loads from the station batteries in order to reduce heat load in the control room. Without operator action, during a 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 Cue s: 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 in less than 30 minutes

.

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-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, C OMMUNICATION EQUIPMENT Standard Applicant located and moved the breaker handle to the OFF position

. Cue Notes Results SAT UNSAT RJPM-NRC-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 5 of 12 3. *Procedure Step:

2 Open the following disconnects on panel VBN

-PNL02: Disconnect 2 , C91-P 608 , 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-P 600 , 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

-PNL0 2: 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 6 of 12 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 VB N-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 V BN-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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 7 of 12 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 1 2 , 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 1 3 , 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 8 of 12 15. *Procedure Step:

2 Open the following disconnects on panel VBN

-PNL02: Disconnect 1 4 , 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 1 5 , 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 9 of 12 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-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 10 of 12 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 in less than 30 minutes

. This completes this JPM.

STOP TIME:

(Check time against the Time Critical Limit)

RJPM-NRC-D 14-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 11 of 12 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-C1 Rev. 0 RJPM-NRC-D 14-C1 Rev 0 Page 12 of 12 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-D 14-C2 Rev 0 River Bend Station Initial License Exam Page 1 of 15 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

1 5 Actual Time (min):

JPM RESULTS*: (Circle one)

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

EVALUATION LOCATION

Perfo rm 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)

RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 2 of 15 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-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 3 of 15 ANSWER KEY RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 4 of 15 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Bypass a Control Rod in RACS 214003004001 2 0 1 00 5 K6.0 2 2 0 1 00 5 A 2.0 2 3.2 / 3.3 2.8 /

3.2 REFERENCES

APPLICABLE OBJECTIVES ST P-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 Handout with picture of RACS Cabinet Ident Select Switches 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 1 6-25 has been bypassed in the RACS Cabinets

.

RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 5 of 15 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 Tell the applicant that the key will not be used on this JPM. Notes 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.

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.

RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 6 of 15 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 an inoperable control rod or 3.1.6 Action A.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 Procedure Ste p: 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-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 7 of 15 3. 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.

4. 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 Provide applicant with step 107 of RCP 18

-014 As the concurrent verifier, inform applicant that step 1.7 is verified

. Notes Results SAT UNSAT RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 8 of 15 5. 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-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 9 of 15 6. *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 Applicant simulated placing the switches in the ir proper positions on Panel H13-P651 by drawing arrows on the handout in accordance with the attached key (page 3 of this JPM).

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 Provid e the applicant with one of the handout pictures of the RACS cabinet

. Tell the applicant to draw arrows on the handout to represent positioning the Ident Select Switches.

Collect the handout from the applicant Notes Any row of switches will work.

There are two picture handouts; one will be used to represent P651 and the other will represent P652.

Results SAT UNSAT 7. *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-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 10 of 15 8. 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 9. *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 Applicant simulated placing the switches in the ir proper position s on Panel H13-P 652 by drawing arrows on the handout in accordance with the attached key (page 3 of this JPM)

. 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 Provide the applicant with one of the handout pictures of the RACS cabinet.

Tell the applicant to draw arrows on the handout to represent positioning the Ident Select Switches.

Collect the handout from the applicant Note s Any row of switches will work.

There are two picture handouts; one will be used to represent P651 and the other will represent P652.

Results SAT UNSAT RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 11 of 15 10. 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 11. 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 12. 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:

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

. This completes this JPM.

STOP TIME:

RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 12 of 15 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-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 13 of 15 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-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 14 of 15 RJPM-NRC-D 14-C2 Rev. 0 RJPM-NRC-D 14-C2 Rev 0 Page 15 of 15 RJPM-NRC-D 14-P1 Rev 0 River Bend Station Initial License Exam Page 1 of 7 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE 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):

1 7 Actual Time (min):

JPM RESULTS*: (Circle one)

Refer to Grading Instructions at end of JPM SAT UNSAT 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)

RJPM-NRC-D 14-P1 Rev. 0 RJPM-N RC-D 14-P1 Rev 0 Page 2 of 7 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 Plan t 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-D 14-P1 Rev. 0 RJPM-N RC-D 14-P1 Rev 0 Page 3 of 7 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Vent Scram Air Header per EOP

-5, Enclosure 11 20100100500 1 295037 E A 1.0 5 3.9 /

4.0 REFERENCES

APPLICABLE OBJECTIVES E OP-00 05 , Encl 11, Venting Scram Air Header RLP-HLO-0516, Obj 1 Rev 31 4 REQUIRED MATERIALS

SAFETY FUNCTION:

E OP-00 05, Rev 31 4 , Enclosure 11

__1__ SIMULATOR CONDITIONS

& SETUP: 1. NA - This is a n 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-D 14-P1 Rev. 0 RJPM-N RC-D 14-P1 Rev 0 Page 4 of 7 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 VAL VE (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-D 14-P1 Rev. 0 RJPM-N RC-D 14-P1 Rev 0 Page 5 of 7 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-D 14-P1 Rev. 0 RJPM-N RC-D 14-P1 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-P1 Rev. 0 RJPM-N RC-D 14-P1 Rev 0 Page 7 of 7 OPERATOR CUE SHEET INITIAL CONDITIONS:

An ATWS has occurred. Power is greater than 10%

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

.

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

Refer to Grading Instructions at end of JPM SAT UNSAT 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)

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

Task Number K&A SYSTEM

K&A RATING

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

4.3 REFERENCES

APPLICABLE OBJECTIVES S OP-00 3 7 , Fire Protection Water, Rev 3 5 RLP-STM-0 250, Obj 11 REQUIRED MATERIALS

SAFETY FUNCTION:

SOP-0037, Fire Protection Water, Rev 35

__6__

SIMULATOR CONDITIONS & SETUP: 1. NA - This is a n 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-D 14-P 2 Rev. 0 RJPM-NRC-D 14-P 2 Rev 0 Page 4 of 7 PERFORMANCE

START TIME:

SOP-003 7 , 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-D 14-P 2 Rev. 0 RJPM-NRC-D 14-P 2 Rev 0 Page 5 of 7 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-D 14-P 2 Rev. 0 RJPM-NRC-D 14-P 2 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-P 2 Rev. 0 RJPM-NRC-D 14-P 2 Rev 0 Page 7 of 7 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-D 14-P 3 Rev 2 River Bend Station Initial License Exam Page 1 of 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO A LTERNATE PATH TITLE: Perform UO Actions to Operate the Div 1 EDG, Using AOP

-31 OPERATOR:

DATE: EVALUATOR:

EVALUATOR SIGNATURE:

CRITICAL TIME FRAME:

Required Time (min):

10 Actual Time (min):

PERFORMANCE TIME:

Average Time (min):

1 0 Actual Time (min):

JPM RESULTS*: (Circle one)

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

EVALUATION LOCATION: Perform X Plant X Simulate Simulator Control Room Prepared: Dave Bergstrom Date: November 10, 2014 Reviewed: Steve Carter Date: November 11, 2014

(Operations Representative)

Approved: Joey Clark Date: November 11, 2014 (Facility Reviewer)

RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 2 of 11 EXAMINER INFO SHEET This JPM contains a Time Critical Step.

Task Standard

A reactor Scram confirmatory signal has been initiated within 5 minutes; breakers ENB

-SWG01B ACB 586 and ENB

-SWG01A ACB567 are opened within 10 minutes

and SC V-PNL15A1 Breaker 14 is closed. Synopsis: A fire in the Main Control Room has caused entry into AOP

-0031, Shutdown from Outside the Main Control Room

. The applicant is tasked with performing the Unit Operator Actions of AOP-31 (Attachment 13) starting with initiating a confirmatory scram signal through opening the EPA breakers which is a TIME CRITICAL step (within 5 minutes), then opening two breakers that will close any SRVs that may have opened due to hot shorts

. This is accomplished by performing step 1.2 of attachment 13, which is also a TIME CRITICAL step (within 10 minutes).

Steps 1.3 through 1.5 are performed to transfer control of the Div 1 EDG from the control room to local control.

As an alternate path, the applicant will investigate and correct a loss of transfer relay power per Attachment 4.10 of the same AOP.

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 the UO Actions of A OP-00 31 per Attachment 1

3.

3) Initial Conditions

The Main Control Room has been evacuated due to a fire; the Reactor is in Hot Shutdown and control is being established at the Remote Shutdown Panels.

AOP-0031, Shutdown from Outside the Main Control Room has been entered.

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

RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 3 of 11 DATA SHEET TASK Title

Task Number K&A SYSTEM

K&A RATING

Perform UO Actions to Operate the Div 1 EDG, Using AOP

-31 400076004001 295016 A A1.0 4 AA1.07 3.1 / 3.2 4.2 /

4.3 REFERENCES

APPLICABLE OBJECTIVES A OP-00 3 1 , Shutdown from Outside the Main RLP-OPS-AOP 00 31, Obj 4 , 5 Control Room, Rev 322 REQUIRED MATERIALS

SAFETY FUNCTION:

Attachment 13, UO Actions of AOP-0031, __6__ Shutdown from Outside the Main Control Room, Rev 322 And Attachment 4.10, same procedure SIMULATOR CONDITIONS

& SETUP: 1. NA - This is a n 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: A reactor Scram confirmatory signal has been initiated within 5 minutes, breakers ENB

-SWG01B ACB 586 and ENB

-SWG01A ACB567 are opened within 10 minutes and SCV

-PNL15A1 Breaker 14 is closed

.

RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 4 of 11 PERFORMANCE

START TIME: A OP-00 31 , Shutdown from Outside the Main Control Room , Attachment 13 , UO Actions PROCEDURE NOTE The Unit Operator obtains and completes the steps in this attachment. Upon completion, he remains at the Div 1 RSS Room and conducts operations as directed by the CRS

. 1.1 IF a Control Room fire is in progress, THEN initiate a Reactor Scram confirmatory signal as follows:

PROCEDURE NOTE If a Main Control Room fire is in progress, then Step 1.1.1 shall be completed within 5 minutes of scramming the reactor. 1.1.1 At Control Building 116 ft el Div 1 Electrical Protection Assemblies are a (RPS MG area), perform the following:

1. *Procedure Step:

1.1.1.1 At RPS A MOTOR GENERATOR SET, depress AND hold the RPS MG-SET MOTOR OFF pushbutton until the red MOTOR ON light goes off. Standard Applicant located/identified and simulated depressing the OFF pushbutton. Cue After applicant simulates depressing the pushbutton, inform the applicant that the red MOTOR ON light is no longer lit

. Notes Results SAT UNSAT 2. *Procedure Step:

1.1.1.2 Place the following Div 1 Electrical Protection Assemblies in OFF

C71-S003C C71-S003F C71-S003A C71-S003E Standard Applicant located/identified and simulated turning the four switches counter

-clockwise to the OFF position. Cue Notes Results SAT UNSAT RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 5 of 11 3. *Procedure Step:

1.1.1.3 At RPS B MOTOR GENERATOR SET, depress AND hold the RPS MG-SET MOTOR OFF pushbutton until the red MOTOR ON light goes off. Standard Applicant located/identified and simulated depressing the OFF pushbutton.

Cue After applicant simulates depressing the pushbutton, inform the applicant that the red MOTOR ON light is no longer lit.

Notes Results SAT UNSAT 4. *Procedure Step:

1.1.1.4 Place the following Div 2 Electrical Protection Assemblies in OFF:

C71-S003H C71-S003D C71-S003G C71-S003B Standard Applicant located/identified and simulated turning the four switches counter

-clockwise to the OFF position.

Cue Notes This completes the 5 minute Time Critical action. Results SAT UNSAT Record time to verify Time Critical Step is completed within 5 minutes: __________________

RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 6 of 11 Procedure Step:

1.1.2 Go to CB 98' Div 1 and 2 Swi tchgear Rooms and continue with the next step.

Standard NA Cue Notes This is a placekeeper: the applicant will transition to the 98 ft elev of the Control Building Results SAT UNSAT PROCEDURE NOTE Step 1.2 is required to be completed within 10 minutes of scramming the reactor due to a Main Control Room fire

. The following steps will close any SRVs opened due to hot shorts.

5. *Procedure Step:

1.2 IF a Main Control Room Fire is in progress, THEN open the following breakers: E NB-SWG01A ACB 586, ENB-PNL02A CONTROL ROOM Standard Applicant located/identified and simulated opening ACB 567 by depressing the red TRIP button.

Cue After applicant simulates depressing the TRIP pushbutton, inform the applicant that the window above the trip button now shows green and has the word OPEN.

Notes This breaker is in the Div 1 Switchgear Room on the 98' elevation of the Control Building.

This completes the 10 minute Time Critical action.

Results SAT UNSAT RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 7 of 11 6. *Procedure Step:

1.2 IF a Main Control Room Fire is in progress, THEN open the following breakers: ENB-SWG01A ACB 567, ENB

-PNL02A CONTROL ROOM Standard Applicant located/identified and simulated opening ACB 567 by depressing the red TRIP button.

Cue After applicant simulates depressing the TRIP pushbutton, inform the applicant that the window above the trip button now shows green and has the word OPEN.

Notes This breaker is in the Div 1 Switchgear Room on the 98' elevation of the Control Building.

This completes the 10 minute Time Critical action.

Results SAT UNSAT Record time to verify Time Critical Step is completed within 10 minutes: __________________

PROCEDURE NOTE If a main control room fire is in progress, Steps 1.3 through 1.27 are to be performed, as required based on equipment status, within 45 minutes of scramming the reactor to ensure Div 1 D/G and Div 3 D/G are supplying power to their own divisional buses

. 7. *Procedure Step:

1.3 At EGS

-PNL4A manually transfer control of the Division 1 Emergency Diesel Generator by placing the following switches in EMERGENCY: 43-1EGA N05 Standard Applicant located/identified and rotated the transfer switch clockwise to the EMERGENCY position.

Cue Notes Results SAT UNSAT RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 8 of 11 8. *Procedure Step:

1.3 At EGS

-PNL4A manually transfer control of the Division 1 Emergency Diesel Generator by placing the following switches in EMERGENCY:

43-1EJS A01 Standard Applicant located/identified and rotated the transfer switch clockwise to the EMERGENCY position.

Cue Notes Results SAT UNSAT 9. *Procedure Step: 1.3 At EGS

-PNL4A manually transfer control of the Division 1 Emergency Diesel Generator by placing the following switches in EMERGENCY:

43-1ENS C04 Standard Applicant located/identified and rotated the transfer switch clockwise to the EMERGENCY position. Cue Notes Results SAT UNSAT 10. Procedure Step:

1.4 WHEN Div 1 power is available, THEN on EGS-PNL4A, STBY DIESEL GEN RMT SHUTDN PNL, check CONTROL POWER MONITOR CKT EGA N05 light is on

. Standard Applicant located/identified the EGA N05 light on EGS

-PNL4A. Cue Indicate that this light is NOT lit.

Notes The light is above the transfer switches Results SAT UNSAT RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 9 of 11 ALTERNATE PATH:

11. Procedure Step:

1.5 IF CONTROL POWER MONITOR CKT EGA N05 light is off, THEN inform the CRS and refer to Attachment 4.10

. Standard Applicant reported the failure to the CRS

. {cue} Applicant transitions to Attachment 4.10.

Cue As the CRS, accept the report.

Notes Results SAT UNSAT AOP-0031, Attachment 4.1 0 , Control Power Monitor CKT EGAN05 Out

12. *Procedure Step:

Operator Actions

1. Investigate and correct cause of loss of transfer relay power.

Possible Causes

1. In Div 1 DG Room SCV

-PNL15A1 Bkr 14 is tripped or OFF Standard Applicant located/identified and reset/closed Breaker 14 on SCV Panel 15A1 Cue When applicant locates the correct breaker, indicate the breaker is tripped (not all the way to the left, with a red flag showing

). If asked, as the CRS, give permission for the applicant to reset Bkr 14.

When applicant has simulated resetting and closing the correct breaker, indicate that the breaker is in the closed position.

Notes Typical 120 VAC breaker

- fully open the breaker by moving switch to the right, then close the breaker by moving switch to the left.

Results SAT UNSAT Terminating Cue:

A reactor Scram confirmatory signal has been initiated within 5 minutes, breakers ENB

-SWG01B ACB 586 and ENB

-SWG01A ACB567 are opened within 10 minutes and SCV

-PNL15A1 Breaker 14 is closed

. This completes this JPM. STOP TIME:

RJPM-NRC-D 14-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 10 of 11 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-P 3 Rev. 2 RJPM-NRC-D 14-P 3 Rev 2 Page 11 of 11 OPERATOR CUE SHEET INITIAL CONDITIONS:

The Main Control Room has been evacuated due to a fire; the Reactor is in Hot Shutdown and control is being established at the Remote Shutdown Panels.

AOP-0031, Shutdown from Outside the Main Control Room has been entered.

INITIATING CUE

The CRS has directed you t o perform the UO Actions of A OP-0031 per Attachment 13

.

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.:

NRC-1 (Spare) IC No.: 2 5 1 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 No. Malf. No. Event Type* Event Description 0 MSS007K NA SRV 51C is leaking (Initial Condition) 1 NA R (ATC) Insert Control Rods per RMP step 2 (Reactivity Manipulation) 1a CRDM3633 TS (SRO) Control Rod Accumulator Fault (Tech Spec) 2 NA N (SRO, BOP)

Perform SOP-0031 Section 4.8, Suppression Pool Reject to Radwaste 3 T RHR0 10 A C (SRO, BOP)

RHR 'A' Pump Shaft Shear (Tech Spec) 4 T 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 (Booth call if necessary) 6 T ED003D C (SRO, ATC) Loss of NNS

-SWG2A (AOP

-0005) 7 CRDM2017 CRDM3641 CRDM4425 M (ALL) Reactor scram with turbine trip due to loss of vacuum ATWS - 3 Control Rods 8 MSS005K C (SRO, BOP)

Safety Relief Valve 51C fails open (AOP-0035) 9 RHS-AOV64P C (BOP) RHS-AOV64 Fails to auto isolate. (AOP-0003) * (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-00 06, AOP-000 5, AOP-0035, AOP-0003 Major Transients (1

-2) (1) Reactor scram with turbine trip due to loss of vacuum

/ 3 Control Rod ATWS

December 2014 NRC Exam EOPs entered (1-2) (2) EOP-0001/ EOP-0001A EOP contingencies (0

-2) (1) Enter EOP-000 1A 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 per SOP-0031 section 4.8. 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 (down-scale) for the feedwater level control system. Manual control is established to stabilize and restore RPV water level per Abnormal Operating Procedure AOP

-0006. Event5 - Following failure of the steam flow transmitter Single Element Control is established by the team to allow for automatic RPV level control per SOP-0009 Section 6.3.

Event6 - Next a loss of circulating water switchgear NNS-SWG2A bus occurs, resulting in a loss of most of the condenser cooling pumps requiring entry into abnormal operating procedure AOP-0005 for a loss of condenser vacuum and the plant will have to be shutdown (Scrammed) due to loss of vacuum

. Event 7 - After the mode switch is taken to shutdown, three control rods fail to insert resulting in a low power (0%) ATWS condition. E OP-0001A is entered and action taken to insert the control rods (Critical task to insert all control rods prior exiting EOP-1A, RPV CONTROL, ATWS

) Event 8 - Also following plant shutdown the leaking safety relief valve (SRV 51C) opens fully resulting in an uncontrolled RPV pressure drop, actions are taken per abnormal operating procedure AOP

-0035 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 (RHS-AOV64) to isolate on the low RPV water level 3 received (as expected) during plant shutdown, requiring entry into AOP

-0003.

RIVER BEND STATION SIMULATOR SCENARIO Number: *RSMS-NRC-D14-1 Revision: 00 Page 1 of 29 Approximate Time: 1 Hour(s) 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 201 4 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-201 4 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 KC N Date

Indexing Information

RSMS-N RC-D 14-1 I. DESCRIPTION OF SCENARIO This scenario begins with the plant a t 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) Perform Three element to single element transfer per SOP

-0009, Section 6.3 Loss of NNS

-SWG2A (AOP

-0005)-causes loss of vacuum Rx Scram on Low Vacuu m 3 rods stick out therefore ATWS SRV 51 C fails open following turbine trip RHS-AOV64 fails to auto isolate on level 3 II. TERMINAL OBJECTIVE

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

III. ENABLING OBJECTIVES

1. Reduce reactor power in accordance with EN

-RE-215. 2. Establish Suppression Pool Reject to Radwaste per SOP

-0031 Section 4.8.

3. Respond to RHR pump shaft shear per SOP

-0031 and ARP

- 4. Respond to Steam line flow transmitter A failure low per AOP

-0006. 5. Perform Three element to single element transfer per SOP

-0009, Section 6.3

6. Respond to loss of NNS

-SWG2A and resulting circulating water pump loss per AOP

-0005. 7. Respond to ATWS in accordance with EOP

-0001A. 8. Respond to failed open SRV per AOP

-0035. 9. Respond to failure of RHS

-AOV64 to isolate per AOP

-0003.

RSMS-N RC-D 14-1 IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL CONDITION TRAINING FOCUS EQUIPMENT STATUS REQUIRED DOCUMENTS IC #2 5 1 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-N RC-D 14-1 V. GENERAL INSTRUCTIONS Instructions MFS-OR-REM-SCH Notes Check Boards for Equip Tags Check procedures and hard cards for marks

Check Gauges/Meters for marks.

Make marked-up copies of STPs available.

Check that the Shutdown Plan is appropriate for this scenario.

Check power <3090 MWth Bring up Insight

-

Malfunctions MSS007K, SRV, 1B21*F051C LEAKS CRDM 2017, STUCK, CONTROL ROD 2017 FAILURES CRDM 3641, STUCK, CONTROL ROD 3641 FAILURES CRDM44 25, STUCK, CONTROL ROD 44 25 FAILURES RHS-AOV64P, 100, RH S-AOV64 SPC SUCTION ISOL VALVE POSITION T25 RHS-AOV64P, 100, DELETE 00:00:01, RHS-AOV64 SPC SUCTION ISOL VALVE POSITION T2 CRDM2025, ACCUMFLTS, CONTROL ROD 2025 FAILURES T 3 RHR0 10A, RHR PUMP A SHEARED SHAFT T 4 FWS017A, 0, STEAM FLOW XMITTER, C33

-N003A FAILURE T 6 ED003D, NNS-SWG2A BUS FAULT (4160 VAC)

RSMS-N RC-D 14-1 Instructions MFS-OR-REM-SCH Notes T 7 CRDM 2017, STUCK, DELETE 00:00:01, CONTROL ROD 3641 FAILURES T 7 CRDM 3641, STUCK, DELETE 00:00:01, CONTROL ROD 4041 FAILURES T 7CRDM4 425, STUCK, DELETE 00:00:01, CONTROL ROD 4045 FAILURES T 8 MSS005K, Delay 00:02:00 , SRV 1B21*F051C FAILS OPEN Remote Functions T 29 MSS012 OPERATE SRV 'B' SOLENOID SWITCH ES T 30 MSS009, OUT, MAIN STEAM DIV 1 SRV F051C FUSE T 30 MSS016, OUT, MAIN STEAM DIV 2 SRV F051C FUSE T 1 2 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS)

T 1 2 EOP012B, JUMPRD, EOP-5 ENCL 12 (ARI SIGNALS)

T 1 4 EOP014, JUMPRD, EOP-5 ENCL 14 (RC&IS INTERLOCKS)

RSMS-N RC-D 14-1 Instructions MFS-OR-REM-SCH Notes 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 T27 ECCS003, OUT, LPCS PUMP BREAKER Overrides NONE Events T25 DI_RHS

-AOV64 CLOSE, (ZDI5(632), 601C SPC SUCTION VALVE Even t 0 RUN CREW: Board walk down / Turnover.

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Page 7 of 29 Event # 1 Event

Description:

Insert Control Rods per RMP ; Control Rod Accumulator Fault (Rod 36-33) Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 As console operator following completion of movement of control rod 36

-33 insert T2 CRDM 3633, ACCUMFLTS, CONTROL ROD 36-33 FAILURES ROLE PLAY:

As reactor engineer acknowledge completion of RMP Step 2 a and state that you will be performing monitor cases while they reject suppression pool water.

As reactor building report that accumulator pressure is 1 660 psig and that you will be check for moisture, wait 5 minutes then insert T28 CRDM2025, ACCUMFLTS, Delay 00:05:00, Delete 00:00:01, CONTROL ROD 36-33 FAILURES, and report that 60cc of moisture have been drain and that accumulator pressure is 1 650 psig SRO Annunciator:

ARP-680-07-C03 Accumulator Trouble Direct the ATC to perform RMP Step 2 a to lower reactor power. Acknowledge accumulator trouble on control rod 36-33 and direct performance of ARP

-680-07-C03 actions Enter Technical Specifications TR 3.1.5.1 Control Rod Scram Accumulator Detectors / alarm Instrumentation Condition A

, Verify the affected accumulator pressure >= 1540psig once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Examiner Note: must enter condition A due to alarm above ATC

Accept the direction to perform RMP Step 2 a to lower reactor power

. Perform Shutdown Plan RMP Step 2 a control rod insertion per SOP-0071, ROD CONTROL AND INFORMATION SYSTEM.

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Page 8 of 29 Event # 1 Event

Description:

Insert Control Rods per RMP ; Control Rod Accumulator Fault (Rod 36-33) Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ATC

Utilize the operator control module to select the rod to be moved (20-33) Check that a Rod Insertion Block or Inhibit does not exist Depress and hold C11A

-S314, INSERT Pushbutton When rod is full inserted release the INSERT Pushbutton Rod moves from position 06 to position 00

Utilize the operator control module to select the rod to be moved (25

-33) Check that a Rod Insertion Block or Inhibit does not exist Depress and hold C11A

-S314, INSERT Pushbutton When rod is full inserted release the INSERT Pushbutton Rod moves from position 06 to position 00

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Page 9 of 29 Event # 1 Event

Description:

Insert Control Rods per RMP ; Control Rod Accumulator Fault (Rod 36-33) Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ATC Recognize and report accumulator trouble and perform ARP-680-07-C03 actions as follows:

Determine which rod is alarming by depressing the ACCUM FAULT pushbutton and observing red lights on the Rod Position Display Panel.

Reset annunciator by depressing the ACKN ACCUM FAULT pushbutton.

Verify charging water header pressure is greater than 1 540 psig Dispatch building operator to investigate Scenario # 1_ Revision # _

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Page 10 of 29 Event # 2 Event

Description:

Perform SOP

-0031, Section 4.8, Suppression Pool Reject to Radwaste Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event initiated by crew from turnover sheet.

ROLE PLAY:

As reactor building operator, report pump start checks are satisfactory ROLE PLAY:

As radwaste operator, respond that you are ready to receive suppression pool reject.

As chemistry if contacted report that suppression pool activity is within specifications SRO Direct the UO to perform SOP

-0031 Section 4.8 Suppression Pool Reject to Radwaste.

BOP Accept the direction to perform SOP

-0031 Section 4.8 Suppression Pool Reject to Radwaste. Perform SOP

-0031 Section 4.8.

Throttle E12

-F068A to 5800gpm Plant announcement for start of RHR pump

Start E12-C002A

Annunciator: P601

-19A-F07, Div 1 ADS Logic LPCS/LPCI OPR Permissive

Open E12-F024A, RHR Test Return to Supp Pool

Throttle closed E12

-F048A to obtain desired cooling

Begin Suppression Pool Reject by:

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Page 11 of 29 Event # 2 Event

Description:

Perform SOP

-0031, Section 4.8, Suppression Pool Reject to Radwaste Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Open E12-F049, Up Stream Radwaste Isolation Throttle open E12

-F040, RHR to Radwaste Down Stream Isolation

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Page 12 of 29 Event # 3 Event

Description:

RHR A Pump Shaft Shear Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event initiated at Lead Evaluator discretion while rejecting suppression pool to radwaste.

T3 RHR010A, RHR PUMP A SHEARED SHAFT ROLE PLAY:

As WMC/Maintenance, accept request for help to investigate As reactor building operator, accept direction to investigate RHR 'A' pump (Pump). After

~5 minutes report back that you do not see anything wrong with the pump Time Called Call Back Time

__________

____________

As control building operator, accept direction to investigate RHR 'A' pump (Breaker). After

~ 5 minutes report back that indications on the breaker show that it is closed.

SRO / BOP Annunciators:

P601-20A-C04, RHR Pump A Disch Pressure Hi/Low P601-21A-C07, LPCS Injection Line Pressure Hi/Low

Indications:

RHR A Pump Discharge Pressure lowers to approx. 0 psig RHR Pump Motor Amps lowers drastically SRO Direct the ATC to secure the pump and isolate the radwaste reject and test return flow paths.

Notify WMC/Maintenance of RHR 'A' pump shaft shear.

Complete OSP

-0046 notifications.

Enter Tech Spec 3.5.1 ECCS Operating Condition A One low pressure ECCS injection/spray subsystem inoperable (Note for Examiners: They may also enter Condition C One ECCS and one ECCS spray subsystems inoperable, if LPCS was declared INOP until filled and vented).

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Page 13 of 29 Event # 3 Event

Description:

RHR A Pump Shaft Shear Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Time Called Call Back Time

__________ ____________

ROLE PLAY:

As control building operator if directed to rack out / remove control power fuses for RHR A then insert T26 ECCS004, OUT, RHR A PUMP BREAKER

As control building operator if directed to rack out / remove control power fuses for LPCS then insert T27 ECCS003, OUT, LPCS PUMP BREAKER As back panel if requested, report that RHR system pressure is <28 psig if annunciator P601/20A/C04 is in alarm, OR

> 28 psig if annunciator P601/20A/C04 is clear

As back panel if requested report that LPCS system pressure is stable at 10 psig if annunciator H13

-P601/20A/C04 is in alarm, > 15 psig if annunciator H13

-P601/20A/C04 is clear SRO A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7 days (C.1 Restore one ECCS injection/spray subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , if LPCS declared INOP until filled and vented)

Enter Tech Spec 3.6.2.3 Condition A, One RHR suppression pool cooling subsystem inoperable A.1 Restore RHR suppression pool cooling subsystem to OPERABLE status within 7 days Reference Tech Spec 3.4.9 Condition A, One RHR shutdown cooling subsystem inoperable for applicability.

Applicable in Mode 3 with reactor steam dom e pressure less than the RHR cut in permissive pressure. BOP Recognize/report the shaft shear of RHR pump.

Refer to ARP-601-20A-C04 -F 024A Scenario # 1_ Revision # _

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Page 14 of 29 Event # 3 Event

Description:

RHR A Pump Shaft Shear Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ROLE PLAY:

As building operator if directed to fill and vent systems wait 5 minutes and then report that

systems have been filled and vented.

As building operator if directed to inspect suppression pool for debris then wait 5 minutes and report that there is no debris in the suppression pool.

ROLE PLAY:

As Radwaste operator acknowledge report that suppression pool reject is complete Secure the pump and isolate radwaste reject flow path by closing E12

-F040 and/or E12

-F049 Dispatch building operators to investigate pump issues.

Place RHR A in shutdown lineup per SOP

-0031, RESIDUAL HEAT REMOVAL SYSTEM

Verify closed E12

-F040, RHR A TO RADWASTE DN STREAM ISOL VALVE Verify closed E12

-F049, RHR A TO RADWASTE UP STREAM ISOL VALVE Inform Radwaste personnel suppression pool reject complete Secure suppression pool cooling lineup Verify closed E12

-F024A, RHR PUMP A TEST RTN TO SUP PL Scenario # 1_ Revision # _

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Page 15 of 29 Event # 3 Event

Description:

RHR A Pump Shaft Shear Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Verify E12

-C002A, RHR PUMP A secured Verify open E12

-F003A RHR A HX OUTLET VALVE Verify open E12

-F048A, RHR A HX BYPASS VALVE Verify open E12

-F064A, RHR PUMP A MIN FLOW TO SUP PL Close E12-F068A, RHR HX A SVCE WTR RTN

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Page 16 of 29 Event # 4 Event

Description:

Steam flow transmitter 'A' downscale failure Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 T4 FWS017A, 0, STEAM FLOW XMITTER, C33-N003A FAILURE Event trigger T 4 initiated at Lead Evaluator discretion.

ROLE PLAY:

As WMC/Maintenance, accept request for help to investigate / repair steam flow transmitter issue. As Duty Manager request that feedwater level control be placed in single element while the failure mode analysis team is formed to investigate the steam flow transmitter issue.

SRO Indications:

Feed flow/steam flow mismatch / steam flow downscale Lowering RPV level Possible Annunciator: p680

-3A-B08, RPV High/Low Water Level Accept report from ATC of C33

-N003A failure.

Direct ATC to take manual control of feedwater level Notify WMC/Maintenance of C33

-N003A failure.

Complete OSP

-0046 notifications.

Enter AOP-0006, CONDENSATE/FEEDWATER FAILURES. Reference AOP-0007, LOSS OF FEEDWATER HEATING (Examiner Note: A loss of feedwater heating does not exist)

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Page 17 of 29 Event # 4 Event

Description:

Steam flow transmitter 'A' downscale failure Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ATC Recognize and report C33

-N003A failure Take manual control of feedwater level in accordance with AOP-0006, CONDENSATE/FEEDWATER FAILURES.

Restore RPV level to normal band using the master controller set in manual.

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Page 18 of 29 Event # 5 Event

Description:

Perform SOP

-0009 Section 6.3, Three element to single element control transfer

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event initiated by crew.

SRO Direct the ATC to perform SOP

-00 09 Section 6.3 Three Element to Single Element Control Transfer.

ATC Accept the direction to perform SOP

-00 09 Section 6.3 Three Element to Single Element Control Transfer.

Perform SOP

-00 09 Section 6.3 Three Element to Single Element Control Transfer.

Verify C33R600 in manual 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 Scenario # 1_ Revision # _

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Page 19 of 29 Event # 6 Event

Description:

Loss of NNS

-SWG 2A. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event T6 initiated at Lead Evaluator discretion.

T6 ED003D, NNS-SWG2A BUS FAULT (4160 VAC)

CREW Annunciators

P808-86A-A08, NPS-SWWG1A DIST BRKR AUTO TRIP Several others for various loads that were lost, including:

Service Water Disch Header Pressure Extreme Low STBY Diesel Gen Service Water Low Flow Turbine Bldg Vent Chillers Auto Trip Norm Service Wtr to STBY Service Wtr Low Pressure Control Bldg Chiller 1A or 1C Pre

-Trip SRO Accept report about the Loss of NNS

-SWG2A. Assign AOP-0005, LOSS OF MAIN CONDENSER VACUUM/TRIP OF CIRCULATING WATER PUMP.

Direct the ATC to monitor condenser vacuum.

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Page 20 of 29 Event # 6 Event

Description:

Loss of NNS

-SWG 2A. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ATC Accept assignment of AOP-0005, LOSS OF MAIN CONDENSER 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

-0005 then manually scram the reactor by placing the Mode switch in shutdown.

BOP Recognize and report Loss of NNS

-SWG2A.

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Page 21 of 29 Event # 7 Event

Description:

Reactor Scram with Turbine Trip due to lowering Condenser Vacuum

ATWS due to 3 Control Rods sticking out at position 48.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event 7 initiated as a result of Event 6.

CRDM3641, STUCK, ROD 3641 FAILURES CRDM4041, STUCK, ROD 4041 FAILURES CRDM4045, STUCK, ROD 4045 FAILURES ROLE PLAY Back Panel Operator, accept request to install Enclosures and other back panel operations.

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) SRO Direct/ Acknowledge the ATC to insert a manual reactor scram due to lower condenser vacuum.

Accept the ATWS (Scram)

Report , Acknowledging 3 rod s out ATWS. Enter EOP-1on level 3 and transition to EOP

-1A Direct EOP-1 A actions: ATC - restore and maintain RPV water level from

-20 to 51 inches with Feed & Condensate and stabilize reactor pressure 950

- 1090 psig, and then give band of 800-1090 psig.

UO - Inhibit ADS and Terminate and Prevent HPCS ATC - assigned AOP

-0001, REACTOR SCRAM and AOP-0002, TURBINE AND GENERATOR TRIPS.

U O - assigned AOP

-0003, AUTO ISOLATIONS and installation of EOP

-0005 Enclosure 16 for Air, 12 for RPS, 14 for RC&IS, and 24 for MSIV s Direct reset of scram utilizing AOP

-0001 or EOP-0005 Enclosure 12.

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Page 22 of 29 Event # 7 Event

Description:

Reactor Scram with Turbine Trip due to lowering Condenser Vacuum

ATWS due to 3 Control Rods sticking out at position 48.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 NOTE: When T 7 is activated

, CRDM malfunctions are deleted allowing for control rod insertion, Do Not insert trigger 7 until both the scram and ARI have been reset

. (i.e. SDV vent and drain are open)

. When both the scram and ARI have been reset then insert T8 to allow control rods to be driven in:

T7 CRDM3641, STUCK, DELETE 00:00:01, CONTROL ROD 3641 FAILURES T7 CRDM4041, STUCK, DELETE 00:00:01, CONTROL ROD 4041 FAILURES T7CRDM4045, STUCK, DELETE 00:00:01, CONTROL ROD 4045 FAILURES ATC

When directed, or when condenser vacuum is in the unacceptable region of the graph in AOP

-0005, insert a manual SCRAM by placing the reactor mode switch to shutdown Recognize and report 3 rod out ATWS Provide a ATWS (SCRAM) Report. Restore and maintain RPV water level:

-20 to 51 inches with Feed & Condensate.

Complete actions of AOP

-1, Reactor Scram and AOP-2, Turbine Trip.

Reset scram utilizing AOP

-0001 / EOP

-0005 Enclosure 12.

Place C71A

-S4A, B, C, D to bypass if performing AOP-0001, REACTOR SCRAM, Scram Reset Reset the scram by placing C71A

-S5A, B, C, D to reset Insert Control Rods

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Page 23 of 29 Event # 7 Event

Description:

Reactor Scram with Turbine Trip due to lowering Condenser Vacuum

ATWS due to 3 Control Rods sticking out at position 48.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 ATC CRITICAL TASK

All control rods fully inserted prior to exiting EOP

-1A , RPV CONTROL, ATWS Actions necessary for success include:

EOP-0005, Enclosure 12, DEFEATING RPS AND ARI LOGIC TRIPS EOP-0005, Enclosure 14, DEFEATING RC&IS INTERLOCKS AND EMERGENCY CONTROL ROD INSERTION DATA SHEET Note for Examiners: They must either scram and reset three times to get all the rods in or complete Enclosure 14 and manually drive each one in to be successful).

BOP Perform the following actions per AOP

-0003, AUTOMATIC ISOLATIONS Use Attachment 1, Signal to Actuation/Isolation Relationship to determine which actuations and isolations should have taken place (Step 5.7)

Verify each component from Attachment 2, Isolation Valve Check off Sheet, is in its isolate position, and place an initial in the isolated/initials column of Attachment 2, Isolation Valve Check off Sheet Install EOP

-0005 Enclosures as directed by SRO.

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Page 24 of 29 Event # 8 Event

Description:

SRV 1B21*FO51C fails open

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event T8 initiated at Lead Evaluator discretion.

T8 MSS005K, Delay 00:02:00, SRV 1B21*F051C FAILS OPEN ROLE PLAY As Back Panel Operator, accept request to perform EOP

-0005 enclosures and other back panel operations as follows:

B21-F051C Div 2 switch operation.

T29 MSS012 OPERATE SRV 'B' SOLENOID SWITCHES B21-F051C fuse removal.

T30 MSS009, OUT, MAIN STEAM DIV 1 SRV F051C FUSE T30 MSS016, OUT, MAIN STEAM DIV 2 SRV F051C FUSE

ATC / BOP Annunciator: P601

-19A-A09, Main Steam SRV Open Indications:

Various RPV and Main Steam Line pressure meters indicate a lowering pressure beyond where BPVs should be controlling pressure ( < 900 psig)

SRV 51C control switch red light on/green light off Recognize and report open SRV Recognize and Report an uncontrolled pressure drop in the RPV due to the stuck open SRV.

SRO Accept report of open SRV Re-enter EOP-0002 on suppression pool temperature if

-2 actions:

-B in Suppression Pool Cooling Assign AOP

-0035, SAFETY RELIEF VALVE STUCK OPEN. CRITICAL TASK

SRV closed prior to exceeding the heat capacity temperature limit (HCTL)

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Page 25 of 29 Event # 8 Event

Description:

SRV 1B21*FO51C fails open

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 BOP Perform actions of AOP

-0035, SAFETY RELIEF VALVE STUCK OPEN.

Place the B21

-F051C switch to OPEN.

to OPEN and back to OFF.

Back panel (phone) step 5.5.3 of AOP

-0035 to cycle switch twice.

Monitor Suppression Pool Temperature.

When directed, place RHR B in Supp Pool Cooling

-F068B to establish service water flow

-C002B -F024B, Test Return to Supp Pool Back panel (phone) step 5.7 of AOP

-35 Attach 1 to remove fuses.

Determine that SRV closes by using steam flows, etc.

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Page 26 of 29 Event # 9 Event

Description:

RHS-AOV64 fails to isolate

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-N RC-D 14-1 Event initiated upon receipt of level 3 signal following Mode switch operation.

RHS-AOV64P, 100, RHS-AOV64 SPC SUCTION ISOL VALVE POSITION T25 RHS-AOV64P, 100, DELETE 00:00:01, RHS-AOV64 SPC SUCTION ISOL VALVE POSITION ROLE PLAY As WMC/Maintenance, accept request for help to investigate BOP Indications:

The control switch for RHS

-AOV64 red light is on and the green light is off.

SRO Direct isolation of RHS

-AOV64 BOP Recognize and report failure of RHS

-AOV64 to isolate.

(found during implementation of AOP

-0003) Isolate RHS-AOV64 by taking control switch to CLOSE Report RHS

-AOV64 isolated FREEZE Termination is at the discretion of the Chief Examiner. Critical Task Review

1. SRV closed prior to exceeding the heat capacity temperature limit (HCTL)

2. All control rods fully inserted prior to exiting EOP

-1A, RPV CONTROL, ATWS

RSMS-N RC-D 14-1 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 findicated 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 RHS-AOV64 closed

SRV closed prior to exceeding the heat capacity temperature limit (HCTL).

All control rods fully inserted prior to exiting EOP

-1A, RPV CONTROL, ATWS

RSMS-N RC-D 14-1 VII. REFERENCES A. Plant Procedures

1. ARP-680-07A-C03, ACCUMULATOR TROUBLE

2. SOP-0031, Residual Heat Removal System

3. ARP-601-20A-C04, RHR PUMP A DISCH PRESSURE HI/LOW

4. ARP-680-03A-B08, REACTOR HIGH/LOW WATER LEVEL

5. AOP-0006. Condensate / Feedwater Failure

6. SOP-0009, Reactor Feedwater system

7. AOP-00 05 , Loss of Main Condenser Vacuum, Trip of Circulating Water Pump

8. AOP-0001, Reactor Scram

9. AOP-0002, Turbine Trip

10. AOP-0003, Automatic Isolations

11. AOP-0035, Stuck Open SRV

12. EOP-1, RPV Control

13. EOP-1A, RPV Control ATWS

14. EOP-2, Primary Containment Control

15. EN-OP-115, Attachment 9.8

16. OSP-0053, Emergency and Transient Response Support Procedure

17. Tech Specs

RSMS-N RC-D 14-1 Offgoing OSM: Oncoming OSM: Off-Going Shift

_______________________

_____ ___________________

_____ (Print) KCN (Print) KCN N D 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

a. 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

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.:

NRC-2 IC No.: 2 5 2 Examiners: ________________

Operators:

_____________________________

________________

_____________________________

________________

_____________________________

Initial Conditions: 100% reactor power.

Turnover Shift priorities: 1) STP-309-020 3 in progress

ready to unload and shutdown the HPCS DG per step 7.3 Event No. Malf. No. Event Type*

Event Description 1 NA N (SRO, BOP)

Unload the HPCS DG per STP

-309-0203 Steps 7.3.1 through 7.3.4 2 ED004R zdi5(497)!=0 TS (SRO) E22-ACB03 trips after DG output breaker opens (Tech Spec

) 3 T CCS 00 1B CCS003C C (SRO, BOP) Component Cooling Water pump CCS-P1B trips and pump CCS-P1C fails to auto start (AOP

-0012) 4 T CNM004B C (SRO,ATC)

Condensate pump CNM-P1B trips (RX) (AOP-0006) 5 T N/A TS (SRO) Control Building Fire Door (CB098-10) Failure to close and latch (Tech Spec) 6 T ED010 M (ALL) Loss RSS#1 result in loss of normal feedwater Reactor Scram 7 RCIC002 E51MOVF013P LPCS002 RHR001A ED004Q C (SRO, BOP)

Reduce RPV injection Sources RCIC fails to auto start and must be manually started RCIC Injection Valve limited to approximately 100-200 gpm flow Loss of Low Pressure ECCS automatic injectio n 8 MSS001 M (ALL) Steam Leak in Drywell Must ED on lowering water level prior to -186" RPV level Must restore RPV level with low pressure ECCS to > -186" * (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 , DW Leak , Reduce RPV injection sources Malfunctions after EOP entry (1

-2) (2) Reduce RPV injection sources , DW Leak Abnormal Events (2

-4) (2), AOP-00 12 , AOP-0006 Major Transients (1

-2) (2) Reactor scram due to loss of normal feedwater, DW Leak December 2014 NRC Exam 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 RPV level going below

-186"; Restore RPV water level to -1 86" with in 30 minutes after RPV pressure reaching 200 psig

" 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 (E22-ACB03)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 (CCS-P1B) trips with the standby pump (CCS-P1C) failing to auto start, the operators will manually start the standby pump to restore normal cooling water flow.

Event 4 - Following the temporary reduction in cooling water flow one the three operating condensate pumps (CNM-P1B) trips resulting in AOP-0006 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 barrier (door CB098

-10) Event 6 - A partial loss of offsite power (RSS#1) occurring resulting in a loss of the remaining condensate pumps and a loss of normal feedwater injection requiring the plan t to be shutdown (Scrammed)

Event 7 - The only high pressure injection system available is RCIC and it fails to auto start. When manually started the RCIC injection valve fails to fully open result in reduced injection (around 100

-200gpm). At -143 inches water level in the RPV the Division 2 480 VAC bus loses power (EJS*SWG2B trips open) preventing injection for division 2 low pressure ECCS systems. The RHR A injection valve (E12-MOVF042A) also loses power preventing injection. The LPCS injection valve (E21-MOVF005) fails to automatically open, requiring the BOP operator to open the valve.

Event 8 - Following the scram a steam 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 within 30 minutes of RPV pressure reaching 200 psig)

RIVER BEND STATION SIMULATOR SCENARIO Number: *RSMS-NRC-D 14-2 Revision: 0 1 Page 1 of 28 Approximate Time: 1 Hour(s) 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 201 4 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-201 4 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

RSMS-NRC-D 14-2 Page 2 OF 28 I. DESCRIPTION OF SCENARIO This scenario begins with the plant a t 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 (TS) CCS-P1B trip with failure of CCS

-P1C to auto start CNM-P1B trip / Rx Power reduction with flow CB098-10 Door Broke (TS) Loss of RSS#1 (Loss of normal feed)

Reduce d RPV injection Sources, RCIC flow limited, loss of Div 2 ECCS and RHR A injection valve (Loss Power

) Steam Leak in the drywell II. TERMINAL OBJECTIVE

1. Given a series of events in the simulator, perform actions to mitigate the consequences of the events in accordance with approved station procedures.

III. ENABILING OBJECTIVES

1. Unload the HPCS diesel per STP

-309-0203 2. Respond to Ground Fault on E22

-S002 per ARP

-601- 3. Respond to trip of CCS

-P1B per AOP

-001 2 4. Respond to trip of CNM

-P1B per AOP

-0006 5. Respond to loss of RSS#1 per OSP

-0053 6. Respond to RCIC auto start failure per OSP

-0053 7. Respond to Leak in the Drywell per OSP

-0053 RSMS-NRC-D 14-2 Page 3 OF 28 IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL CONDITION TRAINING FOCUS EQUIPMENT STATUS REQUIRED DOCUMENTS IC #2 5 2 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 to unload and shutdown the HPCS DG STP-309-0203 Problem/Lit annunciators: None RSMS-NRC-D 14-2 Page 4 OF 28 V. GENERAL INSTRUCTIONS Instructions MFS-OR-REM-SCH Notes Simulator Setup Div 3 diesel generator running tied to the grid. Check Boards for Equip Tags Check procedures and hard cards for marks Check Gauges/Meters for marks.

Make marked-up copies of STPs available.

Check that the Shutdown Plan is appropriate for this scenari o. Check power <3090 MWth Bring up Insight Malfunctions T 2 , DED004R , E22*S002 BUS FAULT (480 VAC) T3, CCS001B , TPCCW PUMP B TRIP , CCS003C, CCS-P1C FAILURE TO AUTO START T4, CNM004B

, CONDENSATE PUMP B TRIP T 6, ED010 , RSS TRANSFORMER , XSR1E LOCKOUT RCIC 002 , RCIC FAILS TO AUTO START T7, E51MOVF013P, FV 2, E51-MOV12, POSITION T 8 , MSS001 , FV 1000, Delay 00:01:00

, Ramp 00:10:00, STEAM LEAK IN THE DRYWELL RHR001A, RHR A LOOP INJECTION VALVE, F042A FAILS LPCS002, LPCS INJECTION VALVE, F005 FAILS TO OPEN

RSMS-NRC-D 14-2 Page 5 OF 28 Instructions MFS-OR-REM-SCH Notes T26 LPCS002, DELETE 00:00:01, LPCS INJECTION VALVE, F005 FAILS TO OPEN T25 ED004Q, EJS*SWG2B BUS FAULT (480 VAC) Remote Functions T 27 , ECCS002, OUT , HPCS PUMP BREAKER T 28, RPS005, RPS ALTERNATE EPA BREAKERS DIV 1 T29,BKR069 , SCI-PNL01/02 SELECT SWITCH, 1SCI

-TRS1 T30, EOP032A , EOP-5 ENCL32 (A SDC INJECTION VALVES)

T30, EOP032B , EOP-5 ENCL32 (B SDC INJECTION VALVES)

T19 EOP033, JUMPRD, EOP-5 ENCL 33 (RCIC AREA HIGH TEMPERATURE)

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)

RSMS-NRC-D 14-2 Page 6 OF 28 Instructions MFS-OR-REM-SCH Notes Overrides DI_NNS-ACB24, NEUTRAL, 808-87C 1NNS SWGR 1C/1A BRKR SW Event Triggers T 2, zdi5(497)! =0 , HPCS DG OUTPUT BKR OPEN T 7, zdi 5(534), E51-F013 TO OPEN T 8 , Mode Switch not in run T 25 , Wide Range Level <

-142" T 26 , zdi5(538) E21-MOVF005 to open Event 0 RUN CREW: Board walk down / Turnover.

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Page 7 of 28 Event # 1 Event Description

Perform STP

-309-0203 Steps 7.3.1 through 7.3.4 to unload Div 3 DG Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 7 OF 28 Event initiated by crew from turnover sheet.

ROLE PLAY:

As control building operator, report a full set of PEP

-0026 data has been collected SRO Direct the UO to perform STP-309-0203. BOP Accept the direction to perform STP-309-0203 Perform STP-309-0203 Section 7.3.1 through 7.3.4

Reduce HPCS diesel generator load Reduce loading to 1300 KW in 60

-90 sec Operate at 1300 KW for 60

-90 sec Reduce loading to 200 KW in 60

-90 sec Record time load reduced below 2525KW Open HPCS diesel generator output breaker

Examiner Note: opening the output breaker initiates the next event Scenario # 2_ Revision # _

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Page 8 of 28 Event # 2 Event Description

E22-ACB03 Trips after DG output breaker opens Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 8 OF 28 Event initiated when the generator output breaker is opened.

T2, DED004R, E22*S002 BUS FAULT (480 VAC) ROLE PLAY:

As WMC/Maintenance/Engineering, accept request to investigate / repair E22

-S002 Bus Fault. As building operator if requested to rack out /

pull control power fuses for HPCS pump wait 5 minutes then insert T 27 , ECCS002, OUT , HPCS PUMP BREAKER and report completion.

As Control Building operator if request to adjust HPCS DG speed droop to 0 then report that speed droop has been adjusted to 0 As Chemistry acknowledge that HPCS DG has been secured.

SRO Annunciator: p601

-16A-E03, HPCS System Ground P601-16A-B03, Div III 4KV Bus AUTO TRIP P601-16A-G04, HPCS Inject Line Pressure Low Various others Indications: breaker indication for E22

-ACB03 = tripped HPCS Line Fill Pump = no lights Acknowledge loss of E22

-S002 bus Enter Tech Spec 3.8.9, Distribution Systems

-Operating Condition E, One or more Div 3 AC or DC electrical power distribution subsystems inoperable; Declare HPCS system and SSW Pump 2C inoperable Immediately

Enter Tech Spec 3.5.1, ECCS-Operating Condition B 1 , HPCS System INOP; Verify RCIC system operable with in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Condition B2, Restore HPCS System to OPERABLE status within 14 days

Review Tech Spec 3.7.1, SSW System and Ultimate Heat Sink (UHS)

Condition E, One SSW subsystem with one pump inop; Restore pump to operable status within 30 days

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Page 9 of 28 Event # 2 Event Description

E22-ACB03 Trips after DG output breaker opens Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 9 OF 28 As Control Building operator accept direction to complete performance of STP

-309-0203. Direct HPCS pump breaker to be racked out following receipt of HPCS low pressure alarm

Direct securing HPCS DG per STP

-309-0203 BOP Recognize and report loss of E22

-S002 bus

Respond to ground per ARP

-601-16A-E03 Dispatch operator to investigate (check for evidence of fire)

Direct control building operator to rack out HPCS pump breaker or remove control power fuses per SOP

-0030 precaution and limitation 2.3, upon receipt of HPCS low pressure alarm ARP-601-16 A-G04.

Secure Division 3 EDG per step 7.3.7 of STP-309-0203 Direct building operator to set speed droop to 0

. Adjust HPCS INCOMING voltage to 4.16 KV using the HPCS Diesel Generator Voltage Regulator Control Switch

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Page 10 of 28 Event # 2 Event Description

E22-ACB03 Trips after DG output breaker opens Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 10 OF 28 Adjust HPCS DG frequency to 60 Hz using the HPCS Diesel Generator Governor Control Switch Place Synch Switch E22

-ACB01 to OFF

Stop the Division 3 EDG by momentarily placing the HPCS DSL ENG CONTROL switch to STOP.

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Page 11 of 28 Event # 3 Event Description

Trip of Component Cooling Water Pump CCS-P1B with failure of standby pump CCS-P1C to auto start

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 11 OF 28 Event trigger T3 initiated at Lead Evaluator discretion. T3, CCS001B, TPCCW PUMP B TRIP CCS003C, CCS-P1C FAILURE TO AUTO START ROLE PLAY:

As WMC / FIN / I&C, accept request to investigate / repair trip of CCS

-P1B 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.

Annunciators:

p870-55A-E01, Turb Cmpnt Clg Water Pump Brkr Auto Trip p870-55A-E02, Turb Cmpnt Clg Water Pump Low Disch Press p870-55A-G02, Turb Cmpnt Clg Water Pump 1B Overload Indications:

CCS-P1B yellow trip light on CCS-P1C green light on / red light off CCS Header Pressure < 96 psig (CCS

-PI 116 on p870)

SRO Acknowledge trip of CCS

-P1B Direct start of CCS

-P1C Enter AOP-0012 Scenario # 2_ Revision # _

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Page 12 of 28 Event # 3 Event Description

Trip of Component Cooling Water Pump CCS-P1B with failure of standby pump CCS-P1C to auto start

. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 12 OF 28 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 ove r current. BOP Recognize and report trip of CCS

-P1B Respond to trip of CCS

-P1B per ARP

-870-55A-E01 Start CCS-P1C Implement actions of AOP

-0012 Attempt to start a least on CCS Pump (already performed)

Dispatch an operator to investigate

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Page 13 of 28 Event # 4 Event Description

Trip of Condensate Pump "B" (CNM-P1B) Booth Instructions Time Position Applicant's Actions or Behavi or RSMS-NRC-D 14-2 Page 13 OF 28 Event trigger T4 initiated at Lead Evaluator discretion.

T4, CNM004B, CONDENSATE PUMP B TRIP ROLE PLAY:

As WMC / FIN / maintenance, accept request to investigate / repair condensate pump B issue

As the turbine building operator, accept the direction to investigate the trip of the condensate pump, Call back in 5 minutes to report that there is smell of hot insulation coming from the pump motor.

As the control building operator, accept 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.

Annunciators: P680

-2A-A03, Condensate Pump Auto Trip P680-2A-B03, RX Feed Pumps Low Suction Press P680-2A-C03, Condensate Pump P1B Overload Indications:

Condensate Pump B amps = 0 Condensate Pump B disch pressure lowering

/ feed pump suction pressure alarm RPV Water Level lowering SRO Acknowledge trip of condensate pump B Direct power reduction to 90%

(with Recirc flow) per OSP-0053 Trigger Point Enter AOP-0006 Notify WMC / FIN / Maintenance to investigate / repair condensate pump B issue.

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Page 14 of 28 Event # 4 Event Description

Trip of Condensate Pump "B" (CNM-P1B) Booth Instructions Time Position Applicant's Actions or Behavi or RSMS-NRC-D 14-2 Page 14 OF 28 ATC Recognize and report trip of condensate pump B Implement AOP-0006 Lower reactor power to 90% with recirc flow to mitigate the level transient Possible Reactor High water level annunciator

P680-03A-B08 Respond to CNM

-P1B trip per ARP

-680-02A-A03 Reduce Reactor power as necessary to stay within capability of number of running condensate pumps Dispatch personnel to determine cause of trip and notify OSM/CRS Place condensate pump B in a shutdown status per

SOP-0007 Depress the Close pushbutton for the Pump Disch Valve Inform Aux Control Room of Condensate System status

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Page 15 of 28 Event # 5 Event Description

Fire Door, CB098

-10, Failure to close and Latch Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 15 OF 28 Event trigger T5 initiated at Lead Evaluator discretion.

GAITRONICS CALL As security officer, call the control room on Gaitronics line 3 and report that you have just passed through control bldg door CB

-098-10 located between the two switchgear rooms and that the door would not close and latch behind you.

ROLE PLAY:

As WMC / FIN / maintenance, accept request to investigate / repair CB

-098-10 Door issue

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.

SRO Acknowledge report of CB098

-10 door issue Enter Tech Spec TR 3.7.9.6, Fire Rated Assemblies Condition A.1, One or more of the above required fire

-rated assemblies or sealing devices inoperable; Establish a continuous fire watch on at least one side o f the affected assembly or sealing device within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR Condition A

.2.1, Verify the OPERABILITY of fire detectors on at least one 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 Condition A

.2.1, Establish an hourly fire watch patrol within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Establish fire watch for CB098

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Page 16 of 28 Event # 5 Event Description

Fire Door, CB098

-10, Failure to close and Latch Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 16 OF 28 ROLE PLAY:

As security accept request to establish fire watch for CB098

-10 BO P Take report of CB098

-10 door issue and inform the control room supervisor

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Page 17 of 28 Event # 6 Event Description

Loss of RSS#1 resulting in Loss of Normal Feedwater Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 17 OF 28 Event trigger T 6 is initiated at Lead Evaluator discretion.

T6, ED010, RSS TRANSFORMER , XSR1E LOCKOUT ROLE PLAY As WMC / FIN / I&C, accept request to investigate / repair loss of RSS#1 issue As the control building operator, accept the direction to investigate the loss of RSS #1 As building operator accept request to reset alternate EPA breaker, wait 5 minutes then insert T 28, RPS005, RPS ALTERNATE EPA BREAKERS DIV 1

, and report that EPA breakers are reset.

As building operator accept request to swap SCI source, wait 5 minutes then insert T29,BKR069, SCI-PNL01/02 SELECT SWITCH, 1SCI

-TRS1 and report SCI source has been swapped.

As the outside operator, accept the direction to investigate the loss of RSS #1

SRO Acknowledge loss of RSS#1 Direct actions for Loss of RSS#1 per OSP

-0053 Hard Card Direct Implementation of

AOP-0001, REACTOR SCRAM AOP-0002, MAIN TURBINE AND GENERATOR TRIPS AOP-0003 AUTOMATIC ISOLATIONS Notify WMC / FIN / Maintenance to investigate / repair RSS#1 issue. ATC Recognize and report loss of RSS#1and loss of normal feedwater Implement AOP

-0001, REACTOR SCRAM

Place C71A

-S1, Reactor System Mode Switch, to SHUTDOWN Scenario # 2_ Revision # _

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Page 18 of 28 Event # 6 Event Description

Loss of RSS#1 resulting in Loss of Normal Feedwater Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 18 OF 28 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)

T19 EOP033, JUMPRD, EOP-5 ENCL 33 (RCIC AREA HIGH TEMPERATURE)

Check all control Rods are fully inserted ATC announces "SCRAM REPORT" Select and insert the SRM and IRM detectors Reset the Scram Implement AOP

-0002, MAIN TURBINE AND GENERATOR TRIPS

Verify Main Turbine has tripped Verify Bypass Valves and drains are controlling RPV pressure Verify Main Generator has tripped (Output Breakers Open)

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Page 19 of 28 Event # 6 Event Description

Loss of RSS#1 resulting in Loss of Normal Feedwater Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 19 OF 28 BOP Dispatch building operators to investigate loss of R S S #1. Initiate RCIC to establish injection to the RPV (OK to perform during scram report)

Implement AOP

-0003, AUTOMATIC ISOLATIONS Use Attachment 1, Signal to Actuation/Isolation Relationship to determine which actuations and isolations should have taken place Verify each component from Attachment 2, Isolation Valve Check off Sheet, is in its isolate position, and place an initial in the isolated/initials column of Attachment 2, Isolation Valve Check off Sheet.

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Page 20 of 28 Event # 7 Event Description

Reduce RPV Injection Sources RCIC Fails to Auto start; RCIC Injection Valve Limited to approximately 100

-200 gpm Loss of Low Pressure ECCS automatic injection Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 20 OF 28 Event 7 is initiated concurrently with Event 5.

RCIC002, RCIC FAILS TO AUTO START T7 E51MOVF013P, FV 2, E51-MOV13, POSITION RHR001A, RHR A LOOP INJECTION VALVE, F042A FAILS LPCS002, LPCS INJECTION VALVE, F005 FAILS TO OPEN T25 ED004Q, EJS*SWG2B BUS FAULT (480 VAC) T30, EOP032A , EOP-5 ENCL32 (A SDC INJECTION VALVES)

T30, EOP032B , EOP-5 ENCL32 (B SDC INJECTION VALVES)

ROLE PLAY As reactor building operator acknowledge request to manually open RCIC discharge valve and after 5 minutes report that you are unable to open the valve SRO Acknowledge failure of RCIC to auto start and discharge flow limitations Direct start of RCIC

. Notify WMC / FIN / Maintenance to investigate

/ repair RCIC issue s. Direct installation of EOP

-0005 Enclosure 32, DEFEATING SDC INJECTION VALVES ISOLATION INTERLOCKS BOP Recognize and report failure of RCIC to auto start Manually initiate RCIC Recognize and report RCIC flow limitations (100-200 gpm) following manual initiation

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Page 21 of 28 Event # 7 Event Description

Reduce RPV Injection Sources RCIC Fails to Auto start; RCIC Injection Valve Limited to approximately 100

-200 gpm Loss of Low Pressure ECCS automatic injection Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 21 OF 28 As building operator accept direction to manually open Low Pressure ECCS system injection valves, wait approximately 10 minutes and report that you are unable to open the valves.

As WMC/FIN/Maintenance acknowledge request to investigate / repair RCIC initiation and flow issues.

Direct reactor building operator to manually open RCIC discharge valve per EN-OP-115 Section 5.4 Manual Control Of Automatic Systems

Recognize and report loss of EJS

-SWG2B, DIV 2 480VAC SWITCHGEAR

Recognize and report loss of Power to E12

-MOVF042A, RHR A INJECTION VALVE

Recognize and report failure of E21

-MOVF005, LPCS INJECTION VALVE to automatically open

Manually Open E21

-MOVF005 to inject into the RPV

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Page 22 of 28 Event # 7 Event Description

Reduce RPV Injection Sources RCIC Fails to Auto start; RCIC Injection Valve Limited to approximately 100

-200 gpm Loss of Low Pressure ECCS automatic injection Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 22 OF 28 Critical Task

Emergency Depressurize prior to RPV level going below

-186 inches Restore and maintain RPV water level to >=

-186 within 30 minutes after RPV pressure reaching 200 psig

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Page 23 of 28 Event # 8 Event Description

Steam Leak in the Drywell leading to Emergency Depressurization Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 23 OF 28 Event trigger T8 is initiated when the mode switch is taken out of the RUN position.

T8, MSS001, FV 1000, Delay 00:01:00, Ramp 00:10:00, STEAM LEAK IN THE DRYWELL ENCLOSURES

T20 EOP020, JUMPRD, EOP-5 ENCL 20 (DRYWELL COOLING)

Annunciators:

H13-P680/06A/C05, DRYWELL HIGH/LOW PRESSURE H13-P680/06A/B05, NSSS INIT DRYWELL HIGH PRESSURE Indications:

Rising Drywell pressure as indicated on SPDS displays SRO Recognize leak in the drywell Direct implement OSP

-0053 Leakage Strategies Enter and direct actions of EOP

-0002 ATC Implement OSP

-0053 Leakage Strategies

Lower pressure to minimize effects of the leak Attempt to identify and isolate the leak Trip Reactor Recirc pumps when cooling isolates

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Page 24 of 28 Event # 8 Event Description

Steam Leak in the Drywell leading to Emergency Depressurization Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-2 Page 24 OF 28 BOP Implement OSP

-0053 Leakage Strategies

Verify E CCS initiation and isolations for 1.68 psid in the drywell Attempt to identify and isolate the leak Perform actions as directed to support EOP

-0002: Install Enclosure 20 when directed Place control switches for all tripped Drywell Unit Coolers to OFF Open SWP MOV4A/B and SWP

-MOV5A/B Close breaker EJS

-ACB25 and EJS

-ACB66 Start a minimum of two drywell unit cooler s

RSMS-NRC-D 14-2 Page 25 OF 28 Termination is at the discretion of the Chief Examiner. FREEZE Critical Task Review

1. ED prior to RPV level going below

-186 inches 2. Restore and maintain RPV water level to >

= -186 within 30 minutes after RPV pressure reaching 200 psig

RSMS-NRC-D 14-2 Page 26 OF 28 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 Reactor Power lowered after Condensate Pump trip Tech Specs entered for Div 3 Bus Fault event and for the Control Building Fire Door RCIC initiated

Emergency Depressurized before RPV water level lowers below

-186 inches *Restor e d and maintaining RPV water level to > =

-186 within 30 minutes after RPV pressure reaches 200 psig

RSMS-NRC-D 14-2 Page 27 OF 28 VII. REFERENCES A. Plant Procedures

1. S T P-309-0203 , Division 3 Diesel Generator Operability Test

2. AOP-00 1 2 , Loss of Turbine Plant Component Cooling Water

3. ARP-6 01-16 A-G 0 4 4. ARP-870-5 5 A-E 0 1 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 Scr am 11. AOP-0002, Main Turbine and Generator Trip s 12. AOP-0003, Automatic Isolations

13. EOP-1, RPV Control

14. EOP-2, Primary Containment Control

15. OSP-0053, Emergency and Transient Response Support Procedure

RSMS-NRC-D 14-2 Page 28 OF 28 Offgoing OSM: Oncoming OSM: Off-Going Shift

__________

_____________

_____ ___________________

_____ (Print) KCN (Print) KCN N D Date STP-309-0203 in progress, Ready to unload and secure the Division 3 diesel generator per Step 7.3 STP-00 0-0102 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 the grid for testing

. 8.7 Yellow EQUIPMENT STATUS PROTECTED EQUIPMENT Division 1 and RCIC Night Orders Standing Orders Board Walkdown Temp Alts

__________________________________________

______ (Signature: Oncoming OSM Review Completed)

KCN

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.:

NRC-3 IC No.: 2 5 3 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 No. Malf. No. Event Type* Event 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 T P863_75A:F_6 I (SRO,BOP) SSW SWGR Room Temp Switch, HVY-ESX25B fails high 4 T B21005 TS (SRO) RPV pressure transmitter B21-PTN078A, fails high (TS) 5 T GMC002B GMC001A C (SRO,BOP) Trip of Stator Water Cooling Pump B, Standby pump fails to start 6 T RPS003A C (SRO,BOP)

Loss of RPS

-A (AOP-0010) 7 SWPMOV 4 AP TS (SRO) Failure to isolate (SWP

-MOV 5B) (TS) 8 T GMC00 3A RPS-001B RPS001C M (ALL) Shear of Stator Water Cooling Pump A Shaft

- Requires Scram RPS fails to Automatically and Manually Scram

- Rods inserted by ARI 9 MGEN003 C (ATC,BOP) Main Generator Reverse Power Relay Failure 10 CNM006 HPCS002 C (SRO,BOP)

Condensate Filter High D/P

- Loss of Feed (recoverable)

HPCS injection valve fails to open

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5

-8) (8)HVY-ESX25B fails high GMC-B Trip , Press Transmitter , RPS-A, SWPMOV 5B 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-00 1 0, AOP-000 1, AOP-000 2 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-000 1, 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 - HVY-ESX25B temperature switch fails high bringing in switchgear high temperature annunciator and failing to start HVY-FN25A and HVY25B the operator will start the fans per the alarm response procedure Event 4 - 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 5 - 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 6 - 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 7 - Primary containment isolation SWP

-MOV5B fails to automatically isolate, requiring entry into T.S. 3.6.1.3 Event 8 - 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 RPV level two)

Event 9 - 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 10 - 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 prior to ED required at

-186 inches)

RIVER BEND STATI ON SIMULATOR SCENARIO Number: *RSMS-NRC-D14-3 Revision: 0 1 Page 1 of 28 Approximate Time: 1 Hour(s) Record Type:

Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

RP S Press Transmitter Fail, Trip of Stator Cooling Pump, Loss of RPS, Loss of Stator Cooling, Loss of High Pressure Feed REASON FOR REVISION:

NRC December 201 4 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-201 4 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

RSMS-NRC-D14-3 Page 2 OF 28 I. DESCRIPTION OF SCENARIO This scenario begins with the plant a t 93% power with RCIC tagged out for line fill pump maintenance

. Events for this scenario:

Swap Stator Water Cooling Pumps per SOP Raise Reactor Power with flow Respond to HVY

-ESX25B, Standby Cooling Tower Switchgear Room Temperature switch failure RPV Pressure Transmitter B21

-PTN078A, fails high (Tech Spec)

Trip of Stator Cooling Pump B Loss RPS A Stator Cooling Pump A shaft shear

- Requires Scram Main Generator Reverse Power Relay Failure Condensate Filter High D/P

- Loss of Feed SWP-MOV5 B 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-D14-3 Page 3 OF 28 IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL CONDITION TRAINING FOCUS EQUIPMENT STATUS REQUIRED DOCUMENTS IC #2 5 3 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 (for tagout of GMC

-P1A), Raise Reactor Power IAW RMP (using flow).

RMP Problem/Lit annunciators: None RSMS-NRC-D14-3 Page 4 OF 28 V. GENERAL INSTRUCTIONS Instructions MFS-OR-REM-SCH Notes Simulator Setup Malfunctions Check Boards for Equip Tags Check procedures and hard cards for marks Check Gauges/Meters for marks.

Make marked-up copies of STPs available.

Check that the Shutdown Plan is appropriate for this scenario.

Check power <3090 MWth

Bring up Insight

T3, B2100 5 , RPV PRESS TRANSMITTER B21-PTN078A FAILURE T4, GMC002B, STATOR COOLING WATER PUMP B TRIP GMC001A, GMC-P1A FAILURE TO AUTO START T5, RPS003 A , LOSS OF POWER TO RPS CHANNEL A SWPMOV 5B P, 100, SWP-MOV 4A, POSITION T7, GMC00 3A, STATOR COOLING WATER PUMP A SHEARED SHAFT T 7 RPS00 1B, RPS FAILS TO SCRAM

- AUTO SIGNALS ONLY RPS001 C , RPS FAILS TO SCRAM

- MANUALLY MGEN003, MAIN GENERATOR REVERSE POWER RELAY FAILURE T9, CNM006, FINAL VALUE 1 00 , CONDENSATE FILTER HIGH DIFFERENTIAL PRESS HPCS002, HPCS INJECTION VALVE F004 FAILS TO OPEN T30, CNM006, FINAL VALUE 0, CONDENSATE FILTER HIGH DIFFERENTIAL PRESS

RSMS-NRC-D14-3 Page 5 OF 28 Instructions MFS-OR-REM-SCH Notes Remote Functions T 27 TGS009, RESET, Delete 00:00:02, RESET H2 CLG/STATOR CLG SEAL OIL ALAR M T28, NIS001, NI CABINET 20 VDC POWER SUPPLIES T 29 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, EO P-5 ENCL 12 (RPS SIGNALS) T20 EOP020, JUMPRD, EOP-5 ENCL 20 (DRYWELL COOLING)

T21 p863_75A:F_6, FAIL ON, STBY SERVICE WTR SWGR ROOM B EXTREME HIGH TEMP Overrides NONE Event Triggers T9, Mode switch not in run Event 0 RUN CREW: Board walk down / Turnover Scenario # 3_ Revision # _

0_

Page 6 of 28 Event # 1 Event Description

Shift Stator Cooling Water Pumps per SOP-0020 Section 5.2, Shifting Pumps While Unit Is In Service (from A to B)

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 6 OF 28 Event initiated by crew from turnover sheet.

ROLE PLAY:

As turbine building operator, report GMC B pump start checks are satisfactory As turbine building operator, if requested report post pump start checks are satisfactory As turbine building operator accept direction to reset the Stator Cooling Alarm on panel GMC

-PNL101, After 1 minute insert trigger T 27, TGS009, to reset the Stator Cooling Alarm and report that a pressure control valve lockup occurred during pump swap as expected and has been reset. SRO Direct the UO to perform SOP

-0020 Section 5.2.

BOP Accept the direction to perform SOP

-0020 Section 5.2.

Perform SOP

-0020 Section 5.2:

Depress GMC

-SCPM-B Start Pushbutton Depress GMC

-SCPM-A Stop Pushbutton Verify GMC

-PIEPR-15 reads > 49psig ATC Respond to expected annunciator per ARP

-680-15A-A06 by dispatching an operator to panel GMC

-PNL101 to observe local alarms and reset the alarm.

Scenario # 3_ Revision # _

0_

Page 7 of 28 Event # 2 Event

Description:

Raise Reactor Power with Flow Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 7 OF 28 Event initiated by RE providing EN

-RE-215 RMP flow step.

ROLE PLAY:

As reactor engineer provide next sequential EN-RE-215 RMP flow step to the SRO.

As reactor engineer, if questioned report that monitored and predictor cases for the reactivity manipulation have been run and there are no identified challenges to core thermal limits.

SRO Direct the ATC to perform RMP flow step to raise reactor power ATC

Accept the direction to perform RMP flow step to raise reactor power.

Perform Reactivity Maneuvering Plan flow step:

Utilize the reactor recirculation system flow control valves to raise reactor power in accordance with the RMP, GOP-0005, Power Maneuvering, and SOP

-0003, Reactor Recirculation System

. Verify B33

-K603A(B) M/A station is in MAN Determin e which B33-K603A(B) flow control is to be adjusted by observing loop flows on B33

-R612A(B) Note the current B33

-HYVF060A(B) flow control valve position, generator load, MWt, APRMs and loop flows Raise reactor recirculation flow by toggling momentarily B33-K603A(B) in the open direction (to the right) using slow detent while observing for servo error deviation in the positive direction

.

Scenario # 3_ Revision # _

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Page 8 of 28 Event # 2 Event

Description:

Raise Reactor Power with Flow Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 8 OF 28 ATC Verify the servo error returns to its previous position Observe B33

-HYVF060A(B) flow control valve position, generator load, MWt, APRMs and loop flows for expected changes Repeat until desired reactor power level is achieved

Scenario # 3_ Revision # _

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Page 9 of 28 Event # 3 SSW SWGR Room Temp Switch

, HVY-ESX25B fails high Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 9 OF 28 Event trigger T3 initiated at Lead Evaluator discretion.

T21 , p863_75A:F_6, FAIL ON, STBY SERVICE WTR SWGR ROOM B EXTREME HIGH TEMP ROLE PLAY:

As back panel report HVY

-ESX25B on H13

-P820 show s full upscale 200F As WMC / FIN / I&C, accept request to investigate / repair issue with HVY-ESX25B SRO Annunciator 863

-075A-F6, STBY SERVICE WTR SWGR ROOM B EXTREME HIGH TEMP Direct start of HVY

-FN2B AND HVY

-FN2D STBY SVCE WTR TWR 1 FAN.

Contact work control to investigate / correct instrumentation malfunction for HVY

-ESX25B BOP Recognize/report extreme high temperature alarm Recognize/report failure of HVY

-FN2B and HVY

-FN2D to auto start. Respond to annunciator ARP

-863-75A-F06 Verify Automatic Actions

Start HVY-FN2B, STBY SVCE WTR TWR 1 FAN

Start HVY-FN2D, STBY SVCE WTR TWR 1 FAN

Verify temperature is high on indicator for HVY-ESX25B on H13

-P820 Dispatch operator to investigate

Scenario # 3_ Revision # _

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Page 10 of 28 Event # 4 Event

Description:

RPV PRESS TRANSMITTER B21

-PTN078A FAILURE Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 10 OF 28 Event trigger T 21 initiated at Lead Evaluator discretion.

T3, B210 05, RPV PRESS TRANSMITTER B21-PTN078A FAILS HIGH ROLE PLAY:

As WMC / FIN / I&C, accept request to investigate / repair issue with B21

-PTN078A As Back Panel provide indication that B21

-

N678A trip unit is upscale trip gross fail SRO Direct use of alternate indication to verify reactor pressure.

Enter Tech Spec 3.

3.1.1, REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION Condition A, ONE OR MORE REQUIRED CHANNELS INOPERABLE, Place channel in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or place associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . (System is already in trip due to transmitter failure)

ATC Recognize/report failure Division 1 half scram on RPV pressure high with no single rod scrams

Verify reactor pressure <1075 psig using alternate indications.

Respond to expected annunciators ARP

-680-06A-A05 and ARP-680-05A-A09 Check reactor pressure indications Verify no individual rod scrams

Scenario # 3_ Revision # _

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Page 11 of 28 Event # 5 Event

Description:

Trip of Stator Cooling Water Pump 'B' standby pump fails to auto start Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 11 OF 28 T4, GMC002B, STATOR COOLING WATER PUMP B TRIP GMC001A, GMC-P1A FAILURE TO AUTO START ROLE PLAY:

As WMC / FIN / I&C, accept request to investigate / repair As the turbine building operator, accept the direction to investigate the Stator Water Cooling Pump.

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 T 29, TGS009, to reset the Stator Cooling Alarm SRO Direct verification of start of the standby stator cooling water pump. Notify WMC / FIN / Maintenance to investigate / repair

GM C-SCPM-B pump issue.

BOP Recognize and report trip of stator cooling water pump 'B' Identify failure to auto start of stator cooling water pump 'A' Start stator cooling water pump 'A' Refer to ARP

-870-54A-D01: Verify automatic action occurs (Standby pump starts)

Determine cause of pump trip and initiate corrective action Dispatch turbine building operator to investigate

Scenario # 3_ Revision # _

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Page 12 of 28 Event # 6 Event

Description:

Loss of RPS A Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 12 OF 28 Event trigger T5 is initiated at Lead Evaluator discretion.

T5, RPS003A, LOSS OF POWER TO RPS CHANNEL A ROLE PLAY As WMC / FIN / Maintenance, accept request to investigate / repair issue with RPS A As the control building operator, accept the direction to investigate the loss of RPS 'A',

after 3 minutes report that the MG set is running with its output breaker open

As back panel operator when requested reset nuclear instrumentation by inserting trigger T28, NIS001, NI CABINET 20 VDC POWER SUPPLIES

SRO Annunciator

863-72A-A01, ANNULUS PRESSURE HIGH Indications: H13-P680, all APRM, IRM, and SRM status lights for channels that are not bypassed are lit for the deenergized RPS Bus.

Isolation of many components controlled by RPS

-A Enter and direct implementation of AOP

-0010, LOSS OF RPS BUS for loss of RPS A Notify WMC / FIN / Maintenance to investigate / repair RPS A issue. Enter EOP-0003, Secondary Containment and Radioactivity Release Control for annulus high pressure (No actions to take)

ATC Recognize and report loss of RPS '

A' On H13-P680, all APRM, IRM, and SRM status lights for channels that are not bypassed are lit for the de

-energized RPS Bus

Scenario # 3_ Revision # _

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Page 13 of 28 Event # 6 Event

Description:

Loss of RPS A Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 13 OF 28 BOP Dispatch building operator to investigate loss of RPS '

A'. Perform Actions of AOP

-0010 LOSS OF RPS BUS Place RPS A Power Transfer Switch to the available power source (immediate action of AOP

-10) Depress INBD and OUTBD isolation reset pushbuttons Verify/Restore isolations per AOP

-0010 IAS-MOV106, INST AIR OUTBD ISOL CCP-MOV138, CONTMT SPLY OUTBD ISOL CCP-MOV142, RR PUMP CLG SUPPLY CCP-MOV159, CONTMT TRN OUTBD ISOL

Scenario # 3_ Revision # _

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Page 14 of 28 Event # 6 Event

Description:

Loss of RPS A Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 14 OF 28 Restore Drywell Cooling Place control switches for all tripped Drywell Unit Coolers to OFF Close EJS-ACB25, NHS MCC102A SPLY BRKR Open SWP-MOV4A, DRYWELL UC SUPPLY Verify open SWP

-MOV5B, DRYWELL UC RETURN Start additional Drywell Unit Coolers as needed RCS-MOV61A, FCV A ACTUATOR LEAKOFF RCS-MOV60A, FCV A RETURN ISOL VLV RCS-MOV59A, FCV A CLOSING SPLY VLV RCS-MOV58A, FCV A OPENING SPLY VLV The remaining portions of AOP

-0010 Attachment 1, Subsequent Operator Actions for Loss of RPS Bus A

Scenario # 3_ Revision # _

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Page 15 of 28 Event # 6 Event

Description:

Loss of RPS A Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 15 OF 28 Examiner Note: Please allow applicant time to restore isolations in AOP

-0010, up to Step 13 for Flow Control Valve Hydraulics on H13

-P808 Scenario # 3_ Revision # _

0_

Page 16 of 28 Event # 7 Event

Description:

Failure to isolate (SWP

-MOV5B)) Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 16 OF 28 Event 6 is initiated concurrently with Event 5.

SWPMOV5BP, 100, SWP-MOV5B, POSITION ROLE PLAY As WMC / FIN / Maintenance, accept request to investigate / repair issue with SWP

-MOV5B SRO Acknowledge failure of SWP

-MOV 5B to isolate on loss of RPS 'A'. Enter Tech Spec 3.6.1

.3, PRIMARY CONTAINMENT ISOLATION VALVES (PCIVs)

Condition A

.1 , One or more penetration flow paths with one PCIV INOP except due to leakage not within limit; Isolate the affected penetration flow path by the use of at least one closed and de

-activated automatic valve, closed manual valve, or check valve with flow through the valve secured within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Condition A.2, verify the affected penetration flow path is isolat ed once every 31 days.

Notify WMC / FIN / Maintenance to investigate / repair SWP

-MOV 5B issue.

Scenario # 3_ Revision # _

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Page 17 of 28 Event # 7 Event

Description:

Failure to isolate (SWP

-MOV5B)) Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 17 OF 28 BOP Recognize and report failure of SWP

-MOV 5B to isolat e o n loss of RPS 'A' during performance of AOP

-0010 Attachment 1, Subsequent Operator Actions for Loss of RPS Bus A.

Scenario # 3_ Revision # _

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Page 18 of 28 Event # 8 Event

Description:

Stator Water Cooling Pump 'A' shaft shear resulting in insertion of a Reactor SCRAM.

RPS failure to automatically and manually scram, Rods inserted by ARI Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 18 OF 28 Event trigger T7 is initiated at Lead Evaluator discretion, BOP to complete up to and including Step 14 of AOP

-0010 Attachment 2 prior to trigger.

T7, GMC003A, STATOR COOLING WATER PUMP A SHEARED SHAFT T7 RPS001B, RPS FAILS TO SCRAM

- AUTO SIGNALS ONLY RPS001 C , RPS FAILS TO SCRAM

- MANUALLY 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)

SRO Annunciators

P870/54A/D02, Turb Runback Stator Coolant Trouble P870/54A/C04, Stator Cooling Inlet Water Low Pressure P870/54A/C05, Stator Cooling Inlet Water Low Flow P680/15A/A05, Main Generator Runback in Progress Accept the report of the turbine runback and direct placement of the reactor mode switch to shutdown Notify WMC / FIN / Maintenance to investigate / repair GMC-SCPM-A pump issue.

Enter and take actions per EOP

-0001, RPV Control Direct implementation of AOP

-0001, Reactor Scram and AOP-0003, Automatic Isolations

Scenario # 3_ Revision # _

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Page 19 of 28 Event # 8 Event

Description:

Stator Water Cooling Pump 'A' shaft shear resulting in insertion of a Reactor SCRAM.

RPS failure to automatically and manually scram, Rods inserted by ARI Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 19 OF 28 ATC Recognize and report Turbine Runback Place the reactor mode switch to shutdown Perform actions of AOP

-0001, Reactor Scram to insert control rods

Place the Mode switch to shutdown.

Arm and depress C71A

-S3A, B, C, and D manual scram pushbuttons Arm and depress C11C

-S1A and B ARI manual initiation pushbuttons Verify that all control rods have inserted

Scenario # 3_ Revision # _

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Page 20 of 28 Event # 8 Event

Description:

Stator Water Cooling Pump 'A' shaft shear resulting in insertion of a Reactor SCRAM.

RPS failure to automatically and manually scram, Rods inserted by ARI Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 20 OF 28 Verify the Feedwater system is operating to restore water level Verify Reactor pressure is being maintained by the turbine, bypass valves, or safety relief valves Select and insert the SRM and IRM detectors CRITICAL TASK

Initiate ARI to insert control rods before reaching level two BOP Implement AOP

-0003, AUTOMATIC ISOLATIONS for level 3 Use Attachment 1, Signal to Actuation/Isolation Relationship to determine which actuations and isolations should have taken place Verify each component from Attachment 2, Isolation Valve Check off Sheet, is in its isolate position, and place an initial in the isolated/initials column of Attachment 2, Isolation Valve Check off Sheet.

Scenario # 3_ Revision # _

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Page 21 of 28 Event # 9 Event

Description:

Main Generator Reverse Power Relay Failure.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 21 OF 28 Event 8 is initiated upon the Mode switch being taken to Shutdown.

MGEN003, MAIN GENERATOR REVERSE POWER RELAY FAILURE SRO Accept report of the failure of the main generator to trip Direct implementation of AOP

-0002, Main Turbine and Generator Trips ATC Recognize and report the failure of the main generator to trip

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

Depress VOLTAGE REGULATOR MODE SELCT MAN Pushbutton Using VOLTAGE REGULATOR MANUAL ADJUST Pushbuttons adjust VARs to 0 as indicated on

VAR-1SPGN05 Scenario # 3_ Revision # _

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Page 22 of 28 Event # 9 Event

Description:

Main Generator Reverse Power Relay Failure.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 22 OF 28 Transfer the NPS buses to the Preferred Station Service Transformers Turn 13.8KV SYNC SELECT Switch to PFD for NPS

-SWG1A(B)

Close NPS-ACB11(27) 13.8KV PFD SUPPLY B R KR Trip NPS-ACB09(25) 13.8KV NORM SUPPLY BRKR

Place 13.8KV SYNC SELECT Switch to OFF for N PS-SWG1A Open the main generator output breakers.

Scenario # 3_ Revision # _

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Page 23 of 28 Event # 10 Event

Description:

Condensate Filter High D/P / Spurious RCIC Isolation

- Loss of Feed (Recoverable).

HPCS injection valve fails to open.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 23 OF 28 Event T9 is initiated upon the Mode switch being taken to Shutdown.

T9, CNM006, FINAL VALUE 100, CONDENSATE FILTER HIGH DIFFERENTIAL PRESS HPCS002, HPCS INJECTION VALVE F004 FAILS TO OPEN

ROLE PLAY As ACR operator report that Condensate filter high differential pressures are being experienced and that you are unable to open CNM-FCV200 remotely.

As turbine building operator if dispatched 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

SRO Accept the report for the loss of feed.

Direct dispatching of an operator to open CNM

-FCV200 to bypass the condensate filters and restart a reactor feed pump ATC Recognize and report condensate high differential pressure and loss of normal feed water injection.

After CNM-FCV200 is open, restart a feed pump per OSP-0053 hard card (Attach 16) and restore RPV injectio n: Verify at least one condensate pump running Verify Feed Reg Valves configured to control injection Verify MN and Gear Increaser Lube Oil Pressure Normal lights are lit for Feed Pump to be started.

Reset the Feed Pump High Level Trip Press STOP pushbutton on Feed Pump to be started

Scenario # 3_ Revision # _

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Page 24 of 28 Event # 10 Event

Description:

Condensate Filter High D/P / Spurious RCIC Isolation

- Loss of Feed (Recoverable).

HPCS injection valve fails to open.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D14-3 Page 24 OF 28 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 Start desired feed pump Open Feed Pump Discharge Valve Restore high pressure injection into the RPV and restore RPV water level to directed band.

BOP Recognize and report failure of E22-F004, HPCS INJECT ISOL VA L VE to open Attempt to open E22-F004, HPCS INJECT ISOL VALVE injection valve.

CRITICAL TASK

Restore and maintain RPV water level to >

-186 inches prior to ED required at

-186 inches

RSMS-NRC-D14-3 Page 25 OF 28 Termination is at the discretion of the Chief Examiner. FREEZE Critical Task Review

1. Initiate ARI to insert control rods before reaching RPV level two 2. Restore and maintain RPV water level to >

-186 inches prior to ED required at

-186 inches

RSMS-NRC-D14-3 Page 26 OF 28 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 HVY-FN2B(D) running RPS A power restored Reactor scram inserted due to loss of Stator Water Cooling SWP-MOV 5B 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

RPV water level restore d and maintain ed > -186" RSMS-NRC-D14-3 Page 27 OF 28 VII. REFERENCES A. Plant Procedures

1. SOP-0020, Generator Stator Cooling System

2. AOP-00 10 , Loss of RPS Buss

3. ARP-680-0 6 A-A 0 5 4. ARP-870-54 A-C01, D 0 1 5. ARP-863-75A-F06 6. Tech Specs

7. AOP-0001, Reactor Scram

8. AOP-0002, Main Turbine and Generator Trip s 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-D14-3 Page 28 OF 28 Offgoing OSM: Oncoming OSM: Off-Going Shift

_______________________

_____ ___________________

_____ (Print) KCN (Print) KCN N D Date Swap Stator Water Cooling Pumps (for scheduled tag out of GMC

-SCPM1A for oil change) per SOP-0020 Section 5.2 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

December 2014 NRC Exam Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.:

NRC-4 IC No.: 2 5 4 Examiners: ________________

Operators:

_____________________________

________________

_____________________________

________________

_____________________________

Initial Conditions:

80% reactor power.

Performin g 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 No. Malf. No. Event Type* Event Description 1 NA N (BOP) Start RCIC IAW SOP

-0035, Section 4.2 2 NA N (SRO,ATC) Adjust MVAR on Main Generator 3 NA R (ATC) Raise Power IAW RMP for sequence exchange 4 T DI-HVR-UC1A LO_HVR-UC1A-A P863_71a:f_3 C (SRO,BOP) HVR-UC1A trip (TS) 5 T NMS011F I (SRO,ATC) APRM F fails upscale (TS) 6 T MSS010 I (SRO,BOP) Loss of Steam Seal Header Pressure 7 T RCIC004 RMS215/219 RCIC007/008 M (ALL) Steam Leak in RCIC Room

- Spreads to RHR

-C RCIC Steam Supply Isol Valves (F063 & 64) fail to shut Rx Scram 8 MSS008D,O,G C (SRO,BOP) SRV Failures B21RV41B, D, F 9 RMS110A RMS110B LO-HVR-AOD-164-G LO-HVR-AOD-16 4-R C (SRO,BOP) Auxiliary Building Isolation Damper (HVR

-AOD164) fails to auto shut

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5

-8) (6) HVR-UC1A Trip, APRM upscale, SSE Press , Steam Leak, SRV Failures, HVR-AOD164 fail Malfunctions after EOP entry (1

-2) (2) SRV's, HVR-AOD164 isolation failure Abnormal Events (2

-4) (3) AOP-0001, AOP-0002, ARP for 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) ED within 20 minutes following exceeding max safe Table H in two areas, Isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E

-3 uCi /ml 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 in Table H

- additional SRVs must be opened to ensure RPV is depressurized)

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 Event 9 - Auxiliary building exhaust radiation levels require manual isolation of the auxiliary building. A failure to automatically close on HVR

-AOD164 requires it to be manually closed via the hand switch (Critical Task to isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E-3 uCi/ml)

RIVER BEND STATION SIMULATOR SCENARIO Number: *RSMS-NRC-D 14-4 Revision: 0 1 Page 1 of 25 Approximate Time: 1 Hour(s) Record Type:

Z01.24 TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

Trip of HVR

-UC1A, APRM Upscale , SSE Header Pressure L ow , RCIC Steam Leak, Pressure Control Failure REASON FOR REVISION:

NRC December 201 4 exam PREPARE / REVIEW:

Thomas LaPorte 0160 07-23-201 4 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

RSMS-NRC-D 14-4 Page 2 OF 25 I. DESCRIPTION OF SCENARIO This scenario begins with the plant a t 8 0% power. Events for this scenario:

Start RCIC IAW SOP-003 5 Section 4.

2 Adjust MVAR on Main Generator IAW SOP

-0080, section 5.9 Raise power per RMP control ro d 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 Auxiliary Building Isolation Damper (HVR

-AOD164) fails to auto 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-D 14-4 Page 3 OF 25 IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL CONDITI ON TRAINING FOCUS EQUIPMENT STATUS REQUIRED DOCUMENTS IC #2 5 4 Power: 80% Core: Xenon equilibrium Equipment OOS

APRM B in bypass due to downscale failure 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-D 14-4 Page 4 OF 25 V. GENERAL INSTRUCTIONS Instructions MFS-OR-REM-SCH Notes Simulator Setup Check Boards for Equip Ta gs Check procedures and hard cards for marks

Check Gauges/Meters for marks.

Make marked-up copies of STPs available.

Check that the Shutdown Plan is appropriate for this scenario.

Check power ~ 80%

Bring up Insight

- RCIC cubicle Temperature

Verify APRM B in Bypass Malfunctions T26 E51MOVF022P, FV 25%, DELETE 00:00:03, E51-MOVF022 POSITION T 4 DI_HVR-UC1A, STOP , 863-71C CONTMT UNIT CLR SW T 4 LO_HVR-UC1A-A, ON, 863-71C CONTMT UNIT CLR LTA AMBER T 4 p863_71a:f_3, FAIL ON, CONTAINMENT UNIT COOLERS OUTLET FLOW LOW T5 NMS011F, APRM F FAILS UPSCALE T6 MSS010, GLAND SEAL REG INLET VLV MOVS1 FAILS T25 p863_71a:f_3, FAIL OFF, CONTAINMENT UNIT COOLERS OUTLET FLOW LOW T7 RCIC004, RCIC STEAM LEAK IN RCIC ROOM T7 RMS215, FV 10000, RAMP 00:15:00, RHR EQUIPMENT ROOM MONITOR (RE215)

T7 RMS219 FV 1 0000, RAMP 00:10:00 , RCIC EQUIPMENT ROOM MONITOR (RE21

9) T7 RMS110A FV 0.1, RAMP 00:05:00, AUX BLDG EXHAUST (RE110

-GAS) RAD MONITOR

RSMS-NRC-D 14-4 Page 5 OF 25 Instructions MFS-OR-REM-SCH Notes T7 RMS110B FV 0.00001, RAMP 00:06:00, AUX BLDG EXHAUST (RE110

-PART) MONITOR 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 NMS012B, APRM B FAILS DOWNSCALE Remote Functions T 18 EOP018, JUMPRD, EOP-5 ENCL 18 (FWP LEVEL 8 TRIPS)

T 16 EOP016, JUMPRD, EOP-5 ENCL 16 (CONTAINMENT IAS ISOL)

T 1 2 EOP012A, JUMPRD, EOP-5 ENCL 12 (RPS SIGNALS) Overrides LO_HVR-AOD164-G, OFF, 863-71C UP STREAM ISOL SUPPLY LTG GREEN LO_HVR-AOD164-R, ON, 863-71C UP STREAM ISOL SUPPLY LTR RED

RSMS-NRC-D 14-4 Page 6 OF 25 Instructions MFS-OR-REM-SCH Notes T23 LO_HVR

-AOD164-G, OFF, DELETE 00:00:01 863-71C UP STREAM ISOL SUPPLY LTG GREEN T23 LO_HVR

-AOD164-R, ON, DELETE 00:00:01, 863-71C UP STREAM ISOL SUPPLY LTR RED Event Triggers T 2 3 , zdi2(3 31)==1, DI_HVR-AOD164 T25 , zdi2(326)==1, DI_HVR-UC1C Simulator Setup Event 0 RUN CREW: Board walk down / Turnover.

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Page 7 of 25 Event # 1 Event

Description:

Start RCIC IAW SOP

-0035, Section 4.2 Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 7 OF 25 Event initiated by crew from turnover sheet.

ROLE PLAY: As radiation protection acknowledge RCIC pump operation and report that room conditions are being monitored. As maintenance acknowledge RCIC pump operation and report that mechanics are standing by to perform post maintenance inspections.

As reactor building operation coordinate with unit operator and report that E51

-F022 local valve position indicates 25% open as follows:

On first stroke of E51

-F022 report valve is 15% open On second stroke of E51

-F022 report valve is 25% open and insert trigger 26 to position valve to 25% open.

SRO Direct the UO to perform SOP-003 5 Section 4.

2. UO Annunciator:

P 601-21A-H04, RCIC Dich Line Fill Pump Pressure Low (expected when open E51

-F022 valve)

Accept the direction to perform SOP-003 5 Section 4.

2. Notify Radiation Protection Verify Suppression Pool Cooling and Containment Purge are in-service. Verify STP

-057-0700, being performed by another operator Start Gland Seal Compressor Open E51-F059, Test Return to CST Make Plant announcement Verify P601 B03, Steam Supply Drain Trap Level High is clear. Open E51-F022, Test Bypass to CST to 25% Examiner Note:

this takes coordination with a field operator

Open E51-F045, Steam Supply Stop Valve

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Page 8 of 25 Event # 1 Event

Description:

Start RCIC IAW SOP

-0035, Section 4.2 Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 8 OF 25 Verify closed E51

-F025,F026, F004, F005 (Steam Drains)

Verify E51

-F019, Min Flow to Suppression Pool closed Establish a discharge flow path to the CST (4.2.14, second bullet)

Open E51-F059, Test Return to CST

Throttle E51

-F022, Test Bypass to CST to discharge pressure of approximately 10 00 psig Verify E51

-F019, Min Flow Valve closed Scenario # 4_ Revision # _

0_

Page 9 of 25 Event # 2 Event

Description:

Adjust MVAR on Main Generator to +100 IAW SOP

-0080, Section 5.9 Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 9 OF 25 Event 2 initiated by crew from turnover sheet.

ROLE PLAY: As SOC acknowledge that the RBS main generator MVARS have been raised to +100.

SRO Direct the UO to perform SOP

-00 80 Section 5.9 to raise main generator MVAR to +100

. Report to the SOC that MVARS have been raised to +100.

ATC Accept the direction to perform SO P-0080 Section 5.9 to raise main generator MVAR to +100 Perform SOP

-00 80 Section 5.9: Verify Voltage Regulator Switch in Auto Adjust MVARS to +100 by:

Momentarily depress the RAISE pushbutton Examiner Note: operator may perform this in incremental steps

Verify VAR

-1SPGN05 reads +100

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Page 10 of 25 Event # 3 Event

Description:

Raise power IAW RMP for sequence exchange.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 10 OF 25 Event 3 initiated by RE providing EN

-RE-215 RMP control rod withdraw step.

ROLE PLAY: As reactor engineer provide next sequential EN-RE-215 RMP control rod withdraw step to the SRO SRO Direct the ATC to perform RMP step 12 ATC Accept the direction to perform RMP step 12 Select rod to be moved (20-33) Depress SELECTED GROUP button to check positions of control rods within group are correct prior to movement Check that a Rod Withdrawal Block or Inhibit does not exist Depress C11A

-S334, WITHDRAW Pushbutton

Check that rod notch position displayed is the next highest even number Examiner Note:

first rod motion will be from 00 to 02, the second from 02 to 04 and the third from 04 to 06. After reaching position 04, the following Annunciator comes in:

P680-7A-C01, Control Rod Withdrawal Block The applicant will de

-select the rod and then re

-select the rod to clear the rod block and allow the final withdraw from position 04 to position 06.

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Page 11 of 25 Event # 3 Event

Description:

Raise power IAW RMP for sequence exchange.

Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 11 OF 25 Examiner Not e: the next rod will be moved in the same fashion

36-33 Scenario # 4_ Revision # _

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Page 12 of 25 Event # 4 Event

Description:

Containment Cooler "A" HVR-UC1A trips Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 12 OF 25 Event T4 initiated at Lead Evaluator discretion.

T 4 DI_HVR-UC1A, STOP, 863-71C CONTMT UNIT CLR SW T 4 LO_HVR-UC1A-A, ON, 863-71C CONTMT UNIT CLR LTA AMBER T 4 p863_71a:f_3, FAIL ON, CONTAINMENT UNIT COOLERS OUTLET FLOW LOW T25 p863_71a:f_3, FAIL OFF, Delay 00:00:03 , CONTAINMENT UNIT COOLERS OUTLET FLOW LOW

ROLE PLAY: As WMC/FIN/Maintenance, accept request for maintenance assistance in investigating HVR

-UC1A trip As reactor building operator report as follows:

For breaker investigation report the cause of breaker trip appear s to be over current For unit cooler investigation report that you do not see anything abnormal at

HVR-UC1A SRO Acknowledge trip of HVR

-UC1A Enter Tech Spec 3.6.1.7 , Primary Containment Unit Coolers, Two primary containment unit coolers shall be OPERABLE Condition A, One required primary containment unit cooler inoperable

restore required containment unit cooler to OPERABLE status in 7 days

Direct start of HVR

-UC1C

UO Annunciators:

p863-71A-H03, Containment Unit Cooler Fan Auto Trip p863-71A-F03, Containment Unit Cooler Outlet Flow Low Recognize and report trip of HVR

-UC1A Dispatch operator to investigate Respond to trip of HVR

-UC1A per ARP

-863-71A-H03: Verify that HVR

-UC1A has stopped Start a non

-running unit cooler fan if required

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Page 13 of 25 Event # 4 Event

Description:

Containment Cooler "A" HVR-UC1A trips Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 13 OF 25 ROLE PLAY: For start of HVR

-UC1C report that the unit cooler is operating normally Start HVR-UC1C per SOP-0059, Section 4.2.4 or Section 5.12.2: Depress the START Pushbutton for H VR-UC1C, CONTMT UNIT CLR C Verify HVN

-TV122 opens

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Page 14 of 25 Event # 5 Event

Description:

APRM F fails upscale Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 14 OF 25 Event trigger T 5 initiated at Lead Evaluator discretion.

T5 NMS011F, APRM F FAILS UPSCALE

ROLE PLAY: As back panel report that APRM F indicates full upscale and that all other APRMs indicate

normal. As WMC/FIN/RE/Maintenance, accept request for maintenance assistance in investigating APRM F trip If contacted as I&C, inform the SRO that APRM-B may be taken out of Bypass.

SRO Annunciators:

P680-6A-A03, APRM B or F Upscale Trip or INOP P680-6A-C01, APRM Upscale P680-6A-A02, Neutron Monitoring System P680-5A-A10, RPS Trip Logic B or D Activated P680-7A-C01, Control Rod Withdrawal Block Indications:

C51-R603B, IRM/APRM Level (BLUE) APRM F upscale Accept the report of APRM F upscale failure with Division 2 half scram and no single rod scrams Notify organization of APRM F failure and request assistance.

Enter Tech Spec 3.3.1

.1, Reactor Protection System (RPS) Instrumentation Condition A

.1 , Place channel in trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Condition A.2

, Place associated trip system in trip in

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Scenario # 4_ Revision # _

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Page 15 of 25 Event # 5 Event

Description:

APRM F fails upscale Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 15 OF 25 Contact Work Control about status or availability of restoring APRM B from bypass.

Direct removing APRM B from bypass and placing APRM F in bypass Direct resetting the 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 When directed, remove APRM B from bypass by depressing the top button and moving the toggle switch (C51B S6) from B (left) to center then place APRM F in bypass by depressing the top button and moving the toggle switch from the center to the "F" position (forward)

Reset Division 2 half scram by rotating the spring return switches for Division 2 scram reset.

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Page 16 of 25 Event # 6 Event

Description:

Loss of Steam Seal Header Pressure Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 16 OF 25 Event T 6 initiated at Lead Evaluator discretion.

T6 MSS010, GLAND SEAL REG INLET VLV MOVS1 FAILS ROLE PLAY: As turbine building operator accept request to investigate steam seal evaporator failure and after 5 min report that TME-MOVS1 is closed for some unknown reason.

SRO Annunciator

P 870-54A-E05, Steam Seal Evap Steam Header Low Pressure Acknowledge low steam seal evaporator header pressure Direct operator restoration of steam seal evaporator header pressure per ARP BOP Recognize and report low steam seal evaporator header pressure IAW ARP-870-54 A-E05, verify header pressure on TME

-PIEPR-4, St Seal Header Pressure is approximately 4 psig. IF pressure is low due to failure of the pressure control valve, THEN Take manual control of steam seal header pressure: Open TME-MOVS2 to restore steam seal evaporator header pressure

.

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Page 17 of 25 Event # 7 Event

Description:

Steam Leak in RCIC Room

- Spreads to RHR

-C, RCIC Isolations Fail to Shut Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 17 OF 25 Event T7 initiated at Lead Evaluator discretion.

T7 RCIC004, RCIC STEAM LEAK IN RCIC ROOM T7 RMS215, FV 10000, RAMP 00:15:00, RHR EQUIPMENT ROOM MONITOR (RE215) T7 RMS219 FV 10000, RAMP 00:10:00, RCIC EQUIPMENT ROOM MONITOR (RE219) RCIC007, RCIC OUTBD ISOL VLV, F063, FAILS TO CLOSE RCIC008, RCIC OUTBD ISOL VLV, F064, FAILS TO CLOSE CRITICAL TASK:

ED within 20 minutes after exceeding max

safe Table H in two or more areas

ROLE PLAY:

SRO Annunciators:

P863-71A-A07, Div 1 Main Plant Exhaust PAM Gaseous Rad RMS Display, DRMS Alarms

- Various P601-21A-H02/3, Air Temp Mon RCIC Room Enter EOP-0003, Secondary Containment Control Direct monitoring and reporting of secondary containment parameters Direct Reactor Scram Enter EOP-1 for Level 3 on Scram Direct RPV pressure reduction to combat the RCIC room steam leak.

Direct Emergency Depressurization when any secondary containment parameter exceeds max safe level in any two or more areas.

CRITICAL TASK

Emergency Depressurize RPV within 20 minutes after exceeding max safe Table H in two or more areas (additional SRVs must be opened to ensure RPV is depressurized

-see below for these actions)

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Page 18 of 25 Event # 7 Event

Description:

Steam Leak in RCIC Room

- Spreads to RHR

-C, RCIC Isolations Fail to Shut Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 18 OF 25 As Back panel , provide ECCS cubicle temperatures as follows:

RCIC room temperature

- from insight All other ECCS room temperatures 85F.

As WMC/FIN/Maintenance accept request to assist in isolation of RCIC le ak 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)

ATC Place Mode Switch in Shutdown when directed Provide Scram Report Lower reactor pressure to combat the RCIC room steam leak.

UO Monitor and Report ECCS cubicle temperature and radiation levels. Make Announcement to "Evacuate the Aux Bldg due to steam leak" Open 7 ADS/SRVs when directed to emergency depressurize the RPV.

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Page 19 of 25 Event # 8 Event

Description:

ADS SRVs fail to opera te. Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 19 OF 25 Event initiated upon CRS direction to open 7ADS/SRVs for emergency depressurization.

MSS008D, SRV 1B21*F041B FAIL TO ENERGIZ MSS008O, SRV 1B21*F041D FAIL TO ENERGIZ MSS008G, SRV 1B21*F041F FAIL TO ENERGIZ SRO Direct opening of additional SRVs to ensure RPV is depressurized UO Recognize and report three ADS-SRVs failed to open.

(B21-RVF041B, D, F fail to energize

) Open additional SRVs to ensure RPV is depressurized

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Page 20 of 25 Event # 9 Auxiliary Building Isolation Damper (HVR-AOD164) fail s to shut Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 20 OF 25 Event concurrent with event 7 T7 RMS110A FV 0.1, RAMP 00:05:00, AUX BLDG EXHAUST (RE110

-GAS) RAD MONITOR T7 RMS110B FV 0.00001, RAMP 00:06:00, AUX BLDG EXHAUST (RE110

-PART) MONITOR LO_HVR-AOD164-G, OFF, 863-71C UP STREAM ISOL SUPPLY LTG GREEN LO_HVR-AOD164-R, ON, 863-71C UP STREAM ISOL SUPPLY LTR RED T23 LO_HVR

-AOD164-G, OFF, DELETE 00:00:01 863-71C UP STREAM ISOL SUPPLY LTG GREEN

T23 LO_HVR

-AOD164-R, ON, DELETE 00:00:01, 863-71C UP STREAM ISOL SUPPLY LTR RED CRITICAL TASK:

Isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E

-3 uCi/ml. SRO Annunciators:

RMS-DSPL230/GP110, RMS

-RE110 Gaseous Monitor RMS-DSPL230/2PP110,RMS

-RE110 Particulate Monitor Direct isolation of the auxiliary building per EOP

-0003, SECONDARY CONTAINMENT AND RADIOACTIVITY RELEASE CONTROL and OSP

-0053, EMERGENCY AND TRANSIENT RESPONSE SUPPORT PROCEDURE Direct closure of HVR-AOD164, UP STREAM ISOL SUPPL Y UO CRITICAL TASK: Isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E

-3 uCi/ml Isolate the auxiliary building OSP

-0053, EMERGENCY AND TRANSIENT RESPONSE SUPPORT PROCEDURE Place HVR-AOD22A, ANNULUS MIX SPLY TO SGT in Man Init

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Page 21 of 25 Event # 9 Auxiliary Building Isolation Damper (HVR-AOD164) fail s to shut Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 21 OF 25 Place HVR-AOD22B, ANNULUS MIX SPLY TO SGT in Man Init Depress AUX BLDG TO SGT FLTR A MANUAL INITIATION 'Man Initiate' Pushbutton Depress AUX BLDG TO SGT FLTR B MANUAL INITIATIION 'Man Initiate' Pushbutton Verify the associated dampers are closed Recognize and report failure of HVR

-AOD164 to isolate Close HVR-AOD164, UP STREAM ISOL SUPPLY

Termination is at the discretion of the Chief FREEZE Critical Task Review

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Page 22 of 25 Event # 9 Auxiliary Building Isolation Damper (HVR-AOD164) fail s to shut Booth Instructions Time Position Applicant's Actions or Behavior RSMS-NRC-D 14-4 Page 22 OF 25 Examiner. 1. ED within 20 minutes after exceeding max safe Table H in two or more areas

2. Isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E

-3 uCi/ml.

RSMS-NRC-D 14-4 Page 23 OF 25 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 20 minutes after exceeding max safe Table H in two or more areas

Isolate the auxiliary building within 25 minutes of RMS

-RE110 reaching 6.02E

-3 uCi/ml RSMS-NRC-D 14-4 Page 24 OF 25 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-D 14-4 Page 25 OF 25 Offgoing OSM: Oncoming OSM: Off-Going Shift

_______________________

_____ ___________________

_____ (Print) KCN (Print) KCN N D Date Reactor Power is 80% for sequence exchange RE performing monitor cases for next RMP step RHR-B is in S u ppression Pool Cooling and Containment low volume purge is in service to support RCIC run. STP-057-0700, Suppression Po Ol 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 1000 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 APRM B Bypassed due to downscale failure Div 1 and 3 Night Orders Standing Orders Board Walkdown Temp Alts

__________________________________________

______ (Signature: Oncoming OSM Review Completed)

KCN

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.: A P P L I C A N T E V E N T T Y P E Scenarios 1 IC #251 2 IC #252 3 IC #253 4 IC#254 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX - 0 1 1 0 NOR 2,5 2 1 1 1 I/C 3,4,6 8 4 4 4 2 MAJ 7 1 2 2 1 TS 1 , 3 2 0 2 2 RO ATC SRO-I SRO-U RX 1 1 1 1 0 NOR 5 1 1 1 1 I/C 4,6 2 4 4 2 MAJ 7 1 2 2 1 TS - 0 0 2 2 RO BOP SRO-I SRO-U RX - 0 1 1 0 NOR 2 1 1 1 1 I/C 3 , 8, 9 3 4 4 2 MAJ 7 1 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right

-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.: A P P L I C A N T E V E N T T Y P E Scenarios 1 IC #251 2 IC #252 3 IC #253 4 IC#254 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX - 0 1 1 0 NOR 1 1 1 1 1 I/C 3,4 7 , 8 4 4 4 2 MAJ 6 1 2 2 1 TS 2 , 5 2 0 2 2 RO ATC SRO-I SRO-U RX - 0 1 1 0 NOR - 0 1 1 1 I/C 4, 8 2 4 4 2 MAJ 6 1 2 2 1 TS - 0 0 2 2 RO BOP SRO-I SRO-U RX - 0 1 1 0 NOR 1 1 1 1 1 I/C 3, 7 , 8 3 4 4 2 MAJ 6 1 2 2 1 TS - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.

ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right

-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.: A P P L I C A N T E V E N T T Y P E Scenarios 1 IC #251 2 IC #252 3 IC #253 4 IC#254 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX - 0 1 1 0 NOR 1 1 1 1 1 I/C 3, 5,6 10 5 4 4 2 MAJ 8 1 2 2 1 TS 4,7 2 0 2 2 RO ATC SRO-I SRO-U RX 2 1 1 1 0 NOR - 0 1 1 1 I/C 9 1 4 4 2 MAJ 8 1 2 2 1 TS - 0 0 2 2 RO BOP SRO-I SRO-U RX - 0 1 1 0 NOR 1 1 1 1 1 I/C 3,5,6 9,10 5 4 4 2 MAJ 8 1 2 2 1 TS - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in t he ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right

-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: River Bend Station Date of Exam: 12/08/2014 Operating Test No.: A P P L I C A N T E V E N T T Y P E Scenarios 1 IC #251 2 IC #252 3 IC #253 4 IC#254 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U RX - 0 1 1 0 NOR 2 1 1 1 1 I/C 4,5,68,9 5 4 4 2 MAJ 7 1 2 2 1 TS 4, 5 2 0 2 2 RO ATC SRO-I SRO-U RX 3 1 1 1 0 NOR 2 1 1 1 1 I/C 5 1 4 4 2 MAJ 7 1 2 2 1 TS - 0 0 2 2 RO BOP SRO-I SRO-U RX - 0 1 1 0 NOR 1 1 1 1 1 I/C 4, 6, 8, 9 4 4 4 2 MAJ 7 1 2 2 1 TS - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in t he ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right

-hand columns.

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