Text

9-CN-2020-04 Final Operating Test, Cooper Nuclear Station, Administrative Topics Outline
	ML20241A249
Person / Time
Site:	Cooper
Issue date:	08/04/2020
From:	Greg Werner; Operations Branch IV
To:	; Nebraska Public Power District (NPPD)
References
	ES-301-1 CN-2020-4
	Download: ML20241A249 (373)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination: 4/27/2020 Examination Level: RO SRO Operating Test Number: CN-2020-4 Administrative Topic (see Note) Type Describe activity to be performed Code*

A1, modified SKL034-21 Drywell Average Temperature Calculation Conduct of Operations R, M (Normal Method) IAW 5.8.10 K/A G2.1.23 (4.3)

Conduct of Operations N/A A2, Determine mechanical and electrical isolation boundaries for impeller Equipment Control R, N replacement on REC Pump B K/A G2.2.13 (4.1)

From Previous 2 exams randomly selected 3/2017 ILT A4 Radiation Control R, P, D A3. Determine Workers Projected Total Dose (using survey map) 2.3.14 (3.4)

A4, Calculate DW release rate IAW Emergency Plan Implementing Emergency Plan R, D Procedure 5.7.16 K/A G2.4.39 (3.9)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination: 4/27/2020 Examination Level: RO SRO Operating Test Number: CN-2020-4 Administrative Topic (see Note) Type Describe activity to be performed Code*

A5, From Previous 2 exams randomly selected 9/2018 NRC SA5 Conduct of Operations R, P, D Review IST stroke time surveillance for RRMG ventilation dampers (plant OE)

K/A G2.1.20 (4.6)

A6, Determine reportability for Control Room Emergency Filtration System BF-C-1A Emergency Booster Fan non-functional in Conduct of Operations Mode 1. (Group 6 occurs due to R, N inadvertent short (invalid ESF actuation) while I&C working in panel, CREF fan motor fails) (Procedure 2.0.5)

K/A 2.1.18 (3.8), 2.1.20 (4.6)

A7, SKL0345061 (modified to rod 10-11) -

Determine TS Actions for Removal of a Equipment Control R, M Single CRD during Refueling K/A 2.2.40 (4.7)

A8, Determine emergency dose limit, estimated exposure, and whether KI authorization is Radiation Control required for operator to manually close R, N RCIC-MO-15 K/A G2.3.4 (3.7)

A9, SKL034-30-64 (Emergency Classification)

Emergency Plan R, D K/A G2.4.41 (4.6)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

Rev 1

CNS NRC Exam 2020-4 JPM A1 Page 1 of 12 Cooper Nuclear Station Job Performance Measure A-1(RO)

CNS NRC Exam 2020-4 JPM A1 Page 2 of 12 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Calculate Average Drywell Temperature Revision number: 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to calculate average Drywell temperature.

TASK STANDARD: Examinee interpreted the meter and recorder readings from Handout 3 and calculated Average Drywell temperature using Procedure 5.8.10 Attachment 1 IAW the answer key.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A1 Page 3 of 12 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A1 Page 4 of 12 Revision Statements:

Rev 0-New JPM JPM Information:

1. NRC K/A: 295028 EA2.01 (4.0/4.1) 2.1.23 (4.3/4.4)

2. Safety Function: N/A

3. Task No.: 200226A0501 Conduct Average Drywell Calculations for EOPs

4. PSA Applicability: N/A

5. Critical steps stated in procedure step in bold

References:

1. 5.8.10 AVERAGE DRYWELL TEMPERATURE CALCULATION (Rev 8)

Special Conditions, Tools, Equipment:

1. Calculator Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet Handouts:

1. Attachment 2 - Examinee cue sheet

2. 5.8.10 AVERAGE DRYWELL TEMPERATURE CALCULATION

3. Pictures of the following recorders/indicators; PC-TI-508A, PC-TI-505E, PC-TI-510A, PC-TR-502 (CH 1), PC-TR-502 (CH 2)

CNS NRC Exam 2020-4 JPM A1 Page 5 of 12 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1, 2, and 3.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A1 Page 6 of 12 PERFORMANCE:

Start Time: ____________

1. Procedure Step: Procedure 5.8.10, Section 3.

Critical Step NOTE - If any of instruments on Attachment 1 are not available, go to Step 3.2.

Standard Examinee read the note and then referred to pictures provided and determined that step 3.1 is the correct step to perform the calculation.

Cue Notes Results SAT UNSAT

2. Procedure Step: 3.1 Using Attachment 1, Normal Average Drywell Temperature Data Sheet, calculate average drywell temperature as follows:

3.1.1 Record time that data is taken.

Standard Examinee recorded the current time on Attachment 1.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A1 Page 7 of 12

3. Procedure Step: 3.1.2 Record temperatures from following instruments Critical step (VBD-H):

3.1.2.1 PC-TI-508A, RX HEAD FLANGE TEMP (0°).

Standard Examinee recorded 205-210.

Cue Notes Results SAT UNSAT

4. Procedure Step: 3.1.2.2 PC-TI-505E, ZONE 2B TEMP (288°).

Critical step Standard Examinee recorded 190-195.

Cue Notes Results SAT UNSAT

5. Procedure Step: 3.1.2.3 PC-TI-510A, ZONE 2C TEMP (0°).

Critical step Standard Examinee recorded 220-225.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A1 Page 8 of 12

6. Procedure Step: 3.1.2.4 PC-TR-502, RECIRC PUMPS AREA TEMP Critical step (CH 1: PUMP A).

Standard Examinee recorded 180.7.

Cue Notes Results SAT UNSAT

7. Procedure Step: 3.1.2.5 PC-TR-502 RECIRC PUMPS AREA TEMP (CH 2: PUMP B).

Critical step Standard Examinee recorded 179.4.

Cue Notes Results SAT UNSAT

8. Procedure Step: 3.1.3 Multiply readings recorded in Step 3.1.2 by weight factor and record answer to nearest Critical step whole number.

3.1.3.1 PC-TI-508A x 0.1.

Standard Examinee multiplied reading from Step 3.1.2.1 by 0.1 and recorded result on Attachment 1 (Acceptable range 20-21).

Cue Notes Rounding answer to the nearest whole number is not critical.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A1 Page 9 of 12

9. Procedure Step: 3.1.3.2 PC-TI-505E x 0.2.

Critical step Standard Examinee multiplied reading from Step 3.1.2.2 by 0.2 and recorded result on Attachment 1 (Acceptable range 38-39).

Cue Notes Rounding answer to the nearest whole number is not critical.

Results SAT UNSAT

10. Procedure Step: 3.1.3.3 PC-TI-510A x 0.1.

Critical step Standard Examinee multiplied reading from Step 3.1.2.3 by 0.1 and recorded result on Attachment 1 (Acceptable range 22-23).

Cue Notes Rounding answer to the nearest whole number is not critical.

Results SAT UNSAT

11. Procedure Step: 3.1.3.4 PC-TR-502 (CH 1) x 0.3.

Critical step Standard Examinee multiplied reading from Step 3.1.2.4 by 0.3 and recorded result on Attachment 1 (Acceptable range 54-55).

Cue Notes Rounding answer to the nearest whole number is not critical.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A1 Page 10 of 12

12. Procedure Step: 3.1.3.5 PC-TR-502 (CH 2) x 0.3.

Critical step Standard Examinee multiplied reading from Step 3.1.2.5 by 0.3 and recorded result on Attachment 1 (Acceptable range 53-54).

Cue Notes Rounding answer to the nearest whole number is not critical.

Results SAT UNSAT

13. Procedure Step: 3.1.4 Add products of Steps 3.1.3.1 through 3.1.3.5 to determine average drywell temperature.

Critical step Standard Examinee added results from Step 3.1.3.1 through 3.1.3.5 and recorded Average Drywell Temperature on Attachment 1 (Acceptable range 187 to 192).

Cue Notes JPM is complete.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A1 Page 11 of 12 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee INSTRUMENT READING WEIGHT FACTOR SUM TIME PC-TI-508A 205 to 210 x 0.1 = 20 to 21 PC-TI-505E 190 to 195 x 0.2 = 38 to 39 PC-TI-510A 220 to 225 x 0.1 = 22 to 23 PC-TR-502 (CH 1) 180.7 x 0.3 = 54 to 55 PC-TR-502 (CH 2) 179.4 x 0.3 = 53 to 54 AVERAGE DRYWELL TEMPERATURE (SUM) = 187 to 192 Current time Completed By: Date:

CNS NRC Exam JPM A1 Page 12 of 12 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. Reactor is scrammed.

2. Drywell pressure is 4.1 psig and rising slowly.

3. PMIS is unavailable.

INITIATING CUE:

The CRS directs you to determine Average Drywell Temperature using EMERGENCY OPERATING PROCEDURE 5.8.10 AVERAGE DRYWELL TEMPERATURE CALCULATION.

/

Signature Date

CNS NRC Exam 2020-4 JPM A2 Page 1 of 12 Cooper Nuclear Station Job Performance Measure A-2 (RO)

CNS NRC Exam 2020-4 JPM A2 Page 2 of 12 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Determine Mechanical and Electrical Isolation Boundaries Tabletop # 1 Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 30 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to identify the mechanical and electrical isolation boundaries for a clearance order.

TASK STANDARD: Examinee identified the MINIMUM mechanical and electrical boundaries to perform maintenance on REC Pump B per Procedure 0.9, Tagout, IAW the answer key.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A2 Page 3 of 12 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A2 Page 4 of 12 Revision Statements:

Rev 0 - New JPM Rev 1 - Removed The motor space heater breaker and control switches should be identified but are not critical steps from the task standard per CE comments.

Rev 2 - Incorporated NRC prep week comments.

JPM Information:

1. NRC K/A: 2.2.13 (4.1/4.3)

2. Safety Function: N/A

3. Task No.: 299012O0301, Develop Tagouts

4. PSA Applicability: N/A

5. Critical steps stated in procedure step in bold

References:

1. 0.9, Tagout (Rev 101)

2. Burns & Roe Drawing 2031 Sheet 2

3. Burns & Roe Drawing 3006 Sheet 5

4. Burns & Roe Drawing 3029 Sheet 1

5. Burns & Roe Drawing 3031 Sheet 3

6. Burns & Roe Drawing 3037 Sheet 6

7. Burns & Roe Drawing 3035 Sheet 4

8. SOP 2.2.65 REACTOR EQUIPMENT COOLING WATER SYSTEM (Rev 66)

9. SOP 2.2.65.1 REC OPERATIONS (Rev 80)

10. 2.2A.REC.DIV1, REACTOR EQUIPMENT COOLING WATER SYSTEM COMPONENT CHECKLIST (DIV 1) (Rev 1)

Special Conditions, Tools, Equipment:

1. Computer to access prints and procedures Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet Handouts:

1. Attachment 2 - Examinee cue sheet

2. Burns & Roe Drawing 2031 Sheet 2 (full-sized, paper copy)

3. Burns & Roe Drawing 3006 Sheet 5 (full-sized, paper copy)

4. Burns & Roe Drawing 3029 Sheet 1 (full-sized, paper copy)

5. Burns & Roe Drawing 3031 Sheet 3 (full-sized, paper copy)

6. Burns & Roe Drawing 3037 Sheet 6 (full-sized, paper copy)

7. Burns & Roe Drawing 3035 Sheet 4 (full-sized, paper copy)

CNS NRC Exam 2020-4 JPM A2 Page 5 of 12 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A2 Page 6 of 12 PERFORMANCE:

Start Time: ____________

1. Procedure Step: May reference Procedure 0.9.

Standard Examinee referenced Procedure 0.9.

Cue Notes Results SAT UNSAT NOTE to Examiner: Following steps can be completed in any order.

2. Procedure Step: (Procedure 0.9, Tagout)

9. GENERATING A TAGOUT SECTION NOTE 1 - All Tagouts shall be prepared using controlled plant documents (plant drawings, procedures, etc.) except as allowed by Step 3.7.

Standard Examinee references B&R 2031 Sh2, 3006 Sh5, 3029 Sh1, 3031 Sh2, 3037 Sh6, SOP 2.2.65 & 2.2.65.1, 2.2A.REC.DIV1, as necessary, to determine boundaries.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A2 Page 7 of 12

3. Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover planned activity.

Standard Examinee determined REC-SW-SS(RCC-B), REC Pump B Normal/Standby Switch is required to be Caution Tagged in NORMAL.

Cue Notes Results SAT UNSAT

4. Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover planned activity.

Standard Examinee determined REC-SW-RECPB, Control Switch for REC Pump B is required to be Caution Tagged in NORMAL AFTER STOP.

Cue Notes Results SAT UNSAT 5 Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover Critical step planned activity.

Standard Examinee determined breaker EE-MCC-K(4D), REC PUMP B is required to be Danger Tagged in OFF(open) .

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A2 Page 8 of 12 6 Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover planned activity.

Standard Examinee determined breaker EE-PNL-LPR1F(34), REC PUMP B MOTOR HEATER is required to be Danger Tagged in OFF(open).

Cue Notes Results SAT UNSAT 7 Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover Critical step planned activity.

Standard Examinee determined REC-V-13, REC PUMP B DISCHARGE is required to be Danger Tagged closed.

Cue Notes Results SAT UNSAT 8 Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover Critical step planned activity.

Standard Examinee determined REC-V-12, REC PUMP B SUCTION is required to be Danger Tagged closed.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A2 Page 9 of 12 9 Procedure Step: 9.5.2 Determine components to be tagged, required position of each Critical step component, and tagging sequence necessary to cover planned activity.

Standard Examinee determined REC-V-179, REC PUMP B SUCTION DRAIN is required to be Danger Tagged open, Caution Tagged, Step Tagged or No Tagged Open.

Cue Notes Results SAT UNSAT 10 Procedure Step: 9.5.2 Determine components to be tagged, required position of each component, and tagging sequence necessary to cover planned Critical step activity.

Standard Examinee determined REC-V-685, REC PUMP B VENT is required to be Danger Tagged open, Caution Tagged, Step Tagged or No Tagged Open.

Cue Notes JPM Is COMPLETE.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A2 Page 10 of 12 ATTACHMENT 1 ANSWER KEY (Do NOT give to Examinee)

Component Tag Type Tagged Position

REC-SW-SS(RCC-B), REC Pump CAUTION NORMAL B Normal/Standby Switch (Examinee may not tag, not required)

REC-SW-RECPB, Control Switch CAUTION NORMAL AFTER STOP for REC Pump B Breaker EE-MCC-K(4D), REC DANGER OFF PUMP B (Critical Step)

Breaker EE-PNL-LPR1F(34), REC DANGER OFF PUMP B MOTOR HEATER Valve REC-V-13, REC PUMP B CLOSED DANGER DISCHARGE (Critical Step)

Valve REC-V-12, REC PUMP B CLOSED DANGER SUCTION (Critical Step)

DANGER,

Valve REC-V-179, REC PUMP B CAUTION, NO OPEN SUCTION DRAIN TAG OR STEP TAG OPEN

Valve REC-V-685, REC PUMP B DANGER, CAUTION, NO VENT TAG OR STEP TAG

NOT critical

CNS NRC Exam JPM A2 Page 11 of 12 ATTACHMENT 2 (Page 1 of 2)

DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. The Plant is at 100% Power.

2. Work Week preparations are in progress.

INITIATING CUE:

The CRS directs you to determine the minimum boundaries to tagout REC-P-B, Reactor Equipment Cooling Pump B for pump impeller replacement.

Record the required components and corresponding tag type and tagged position on the attached sheet.

CNS NRC Exam JPM A2 Page 12 of 12 ATTACHMENT 2 (Page 2 of 2)

Component Tag Type Tagged Position (Attach additional sheets, if needed)

Performed by: Date:

(Signature)

CNS NRC Exam 2020-4 JPM A3 Page 1 of 13 Cooper Nuclear Station Job Performance Measure A-3 (RO)

CNS NRC Exam 2020-4 JPM A3 Page 2 of 13 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Apply Radiation and Contamination safety procedures Version 1 Revision number: 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to determine a workers estimated dose and whether GMPO authorization is required in accordance with CNS radiation protection procedures.

TASK STANDARD: Examinee determined the projected dose a worker will receive and that CNS Administrative dose limitations that require GMPO authorization will not be exceeded, in accordance with Procedure 9.ALARA.1, Dosimetry Administration, and Answer Key.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A3 Page 3 of 13 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A3 Page 4 of 13 Revision Statements:

Rev 0-New JPM JPM Information:

1. NRC K/A: 2.3.14 (3.4/3.8)

2. Safety Function: N/A

3. Task No.: 299027O0404 Apply Radiation and Contamination safety procedures

4. PSA Applicability: N/A

5. Critical steps stated in procedure step in bold

References:

1. Procedure 9.ALARA.1, Dosimetry Administration (Rev 48)

Special Conditions, Tools, Equipment:

1. Calculator

2. Computer Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet

3. Attachment 3 - Radiological Survey Map for Rx 903 Angle Valve Room Handouts:

1. Attachment 2 - Examinee cue sheet

2. Attachment 3 - Radiological Survey Map for Rx 903 Angle Valve Room

CNS NRC Exam 2020-4 JPM A3 Page 5 of 13 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 2 and 3.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A3 Page 6 of 13 PERFORMANCE:

Start Time: ____________

1. Procedure Step: Determine dose for area directly outside the Rx 903 Angle Critical Step Valve room.

Standard Examinee determined dose for Staging - staging time in access area directly outside the Rx 903 Angle Valve room (45 min) 0.75 Hr X 5 mr/hr = 3.75 mrem (Accept 3.7 to 3.8 mrem).

Cue Notes Results SAT UNSAT

2. Procedure Step: Determine dose for area directly inside the Rx 903 Angle Valve Critical Step room.

Standard Examinee determined dose for Staging - staging time in area directly inside the Rx 903 Angle Valve room step off pad.

(15 min) 0.25 Hr X 16 mr/hr = 4 mrem.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A3 Page 7 of 13

3. Procedure Step: Determine dose for work in RHR-MO-25B area.

Critical Step Standard Examinee determined dose for work - work time at RHR-MO-25B 1.5 Hr X 325 mr/hr = 487.5 mrem (Acceptable range 487 to 488 mrem).

Cue Notes Results SAT UNSAT

4. Procedure Step: Determine transition dose.

Critical Step Standard Examinee determined dose for transition - an additional 5 mrem will be accumulated for transitions per initial conditions.

Cue Notes Results SAT UNSAT

5. Procedure Step: Determine de-staging dose.

Critical Step Standard Examinee determined dose for de-staging - an additional 15 mrem will be accumulated for de-staging activities per initial conditions.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A3 Page 8 of 13

6. Procedure Step: Determine total projected dose for the worker.

Critical Step Standard Examinee determined total dose for job-Total = 3.75 + 4 + 487.5

+ 5 + 15 = 515.25 mrem (Acceptable range 514.7 to 515.8 mrem).

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A3 Page 9 of 13

7. Procedure Step: Determines Worker admin limit authorizations.

Critical Step Standard Examinee determined Worker would NOT require authorization due to already having greater than 2000 mrem and not reaching next admin limit of 3000 mrem since accumulated dose 2415 mrem + estimated dose 515.25 =

2930.25 (Acceptable range 2929.7 to 2930.8 mrem) per Procedure 9.ALARA.1 Step 5.5.

Cue Notes JPM is COMPLETE.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A3 Page 10 of 13 ATTACHMENT 1 ANSWER KEY (Do NOT give to Examinee)

WORKER INITIAL DOSE 2415 mrem PROJECTED DOSE 514.7 to 515.8 mrem PROJECTED TOTAL DOSE 2929.7 to 2930.8 mrem CNS ADMIN DOSE LIMIT REQUIRING YES NO GMPO AUTHORIZATION EXCEEDED?

(Circle Yes or No)

CNS NRC Exam 2020-4 JPM A3 Page 11 of 13 ATTACHMENT 2 (Page 1 of 2)

DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is operating at power

2. RHR-MO-25B has developed a leak

3. One worker is required to perform the leak repair

4. The worker has accumulated 2415 mrem this year (all CNS dose - previously authorized to receive greater than 2000 mrem)

5. The following times for the worker have been estimated for task performance:

Staging time in area directly outside the CA, at the Step-off Pad, of Rx 903 Angle Valve room: 45 min

Staging time in area directly inside CA, just inside the Step-off Pad, of Rx 903 Angle Valve room: 15 min

Work time directly on RHR-MO-25B: 90 min

Transition dose is 5 mrem

Following completion of the job, an additional 15 mrem for the worker will be received during de-staging activities INITIATING CUE:

You are directed to evaluate the leak repair job for possible performance under current plant conditions to include:

1. Determine the total projected dose the worker will receive to pre-stage, perform the leak repair and de-stage.

2. Based upon the projected total accumulated dose for this job, determine if any CNS administrative dose limitations will be exceeded requiring GMPO authorization prior to performing job.

3. Complete the attached form to document your answers.

CNS NRC Exam 2020-4 JPM A3 Page 12 of 13 ATTACHMENT 2 (Page 2 of 2)

WORKER INITIAL DOSE PROJECTED DOSE PROJECTED TOTAL DOSE CNS ADMIN DOSE LIMIT REQUIRING YES NO GMPO AUTHORIZATION EXCEEDED?

(Circle Yes or No)

Performed by: Date:

(Signature)

CNS NRC Exam 2020-4 JPM A3 Page 13 of 13 ATTACHMENT 3

CNS NRC Exam 2020-4 JPM A4 Page 1 of 17 Cooper Nuclear Station Job Performance Measure A-4 (RO)

CNS NRC Exam 2020-4 JPM A4 Page 2 of 17 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Release Rate Determination based on Drywell Curie Content and Vent Flow Rate Revision number: 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to calculate the release rate based on drywell curie content and vent flow rate per Procedure 5.7.16, Release Rate Determination.

TASK STANDARD: Examinee calculated the noble gas release rate as 9.64E4 to 1.05E5 µCi/sec and completed Attachment 7 of Procedure 5.7.16, Release Rate Commented [k1]: added title Determination, IAW the answer key.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A4 Page 3 of 17 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A4 Page 4 of 17 Revision Statements:

Rev 0 - New JPM Rev 1 - Added marked-up Procedure 5.7.16 Att. 8 and 10 as answer keys per CE comments.

JPM Information:

1. NRC K/A: 2.4.39 (3.9/3.8)

2. Safety Function: N/A

3. Task No.: 200150P0501

4. PSA Applicability: N/A

5. Critical steps stated in procedure step bold

References:

1. Procedure 5.7.16, Release Rate Determination (Rev 27)

Special Conditions, Tools, Equipment:

1. Calculator Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet Handouts:

1. Attachment 2 - Examinee cue sheet

CNS NRC Exam 2020-4 JPM A4 Page 5 of 17 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A4 Page 6 of 17 PERFORMANCE:

Start Time: ____________

1. Procedure Step: Procedure 5.7.16, Section 2. Instructions 2.1 SELECT and PERFORM appropriate release rate determination attachment per Table 1.

(Table 1)

All of following met:

ERP KAMAN Noble Gas not ERP or available. Drywell Curie Attachment 6 Ground Level Content and either

PC venting and Noble Gas actual or estimated occurring or Attachment 7 Release Rate Vent Flow Rate anticipated, either controlled or uncontrolled.

Standard Examinee referred to 5.7.16 Attachments 6, 7, 8 and 10.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 7 of 17

2. Procedure Step: Attachment 6, step 1 NOTE - Reactor shutdown is met by any of following conditions:

All rods fully inserted.

Reactor scram and power below 3%.

Cold shutdown boron weight injected per EOPs.

Standard Examinee reviewed note.

Cue Notes Results SAT UNSAT

3. Procedure Step: Attachment 6, step 1 Critical step

1. DETERMINE time since shutdown (EFFECTIVE AGE) in hours.

1.1 OBTAIN or VERIFY time of reactor shutdown from RCM, Operations, and/or Engineering.

1.2 RECORD time in hours in Table 7-1, Column 1, EFFECTIVE AGE.

1.2.1 IF not shutdown, THEN RECORD zero (0).

Standard Examinee determined time since shutdown was 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and recorded in Table 7-1, Column 1.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 8 of 17

4. Procedure Step: 2. OBTAIN highest exposure rate of high range in-containment radiation monitor in rem/hr from one of following:

Critical step

In-containment monitor readouts located in Control Room behind front panel labeled PNL 9-02 DRYWELL RAD MONITOR RMA-RM-40A & RMA-RM-40B.

PMIS Display PMIS05 or SPDS01.

2.1 RECORD ACTUAL CONT. EXPOSURE RATE value in rem/hr in Table 7-1, Column 2.

Standard Examinee determined highest exposure rate from DRYWELL RAD MONITOR RMA-RM-40A and recorded 40 Rem/hr in table 7-1 Column 2.

Cue Notes Results SAT UNSAT

5. Procedure Step: 3. USE EFFECTIVE AGE to determine projected DBA-LOCA dose rate from Attachment 8.

Critical step 3.1 RECORD PROJECTED DBA-LOCA EXPOSURE RATE AT EFFECTIVE AGE value in rem/hr in Table 7-1, Column 3.

Standard Examinee determined PROJECTED DBA-LOCA EXPOSURE RATE for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months effective age was 3.35E6 Rem/hr and recorded in Table 7-1 Column 3.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 9 of 17

6. Procedure Step: CAUTION - Error in release rate determination will occur if either IODINE or TOTAL curves are used on Attachment 10.

Standard Examinee reviewed caution.

Cue Notes Results SAT UNSAT

7. Procedure Step: 4. APPLY EFFECTIVE AGE to NOBLE GAS curve and DETERMINE Critical step projected DBA-LOCA noble gas drywell curie content from Attachment 10.

4.1 RECORD PROJECTED DBA-LOCA NOBLE GAS CURIE CONTENT (Ci) value in Table 7-1, Column 4.

Standard Examinee determined PROJECTED DBA-LOCA NOBLE GAS CURIE CONTENT was 2.2E8 to 2.4E8 Ci from NOBLE GASES curve on Attachment 10 and recorded in Table 7-1 Column4.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 10 of 17

8. Procedure Step: 5. CALCULATE Estimated Drywell Noble Gas Curie Content on Table 7-1.

Critical step 5.1 DIVIDE Column 2 by Column 3 to determine fraction of DBA-LOCA.

5.2 MULTIPLY results by Column 4.

(Column 2) x (Column 4) = (Column 5)

(Column 3) 5.3 RECORD ESTIMATED DRYWELL NOBLE GAS CURIE CONTENT (Ci) value in Table 7-1, Column 5.

Standard Examinee calculated ESTIMATED DRYWELL NOBLE GAS CURIE CONTENT.

(40 Rem/hr) x (2.2E8 to 2.4E8 Ci) = (2626 to 2866 Ci)

(3.35E6 Rem/hr)

Examinee recorded 2626 to 2866 Ci in Table 7-1 Column 5.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 11 of 17

9. Procedure Step: 6. DETERMINE Noble Gas Concentration (Ci/ft ) in drywell on 3

Table 7-1.

Critical step 6.1 DIVIDE Column 5 by Column 6.

(Column 5) ÷ (Column 6) = (Column 7) 6.2 RECORD NOBLE GAS CONCENTRATION (Ci/ft3) value in Table 7-1, Column 7.

Standard Examinee determined Noble Gas Concentration (Ci/ft3) in drywell.

(2626 to 2866 Ci) = (1.81E-2 to 1.98E-2 Ci/ft3)

(1.45E5 ft3)

Examinee recorded 1.81E-2 to 1.98E-2 Ci/ft3 in Table 7-1 Column 7.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 12 of 17

10. Procedure Step: 7. USE Table 6-1 to determine DRYWELL VENTING FLOW RATE.

Critical step NOTE - Exact vent flow rates for containment pressures may not be available, resulting in using calculated maximum vent flow rate in Table 6-1.

7.1 SELECT Maximum Vent Flow rate based on vent flow path and Containment Pressure.

7.2 IF venting from both Drywell and Torus PC lines, THEN USE vent flow rate of 638 cfm based on calculated maximum flow rate per line in Table 6-1.

Table 6-1 ASSUMED CALCULATED CONTAINMENT MAXIMUM VENT VENTING FROM: PRESSURE FLOW RATE Torus via PC-MO-1308 and PC-MO- 65 psid 319 cfm 305 Drywell via PC-MO-1310 and PC-MO- 65 psid 319 cfm 306 15 < P 56 psig 17,850 cfm Torus via HCVS P 15 psig 14,450 cfm 7.3 RECORD DRYWELL VENTING FLOW RATE (cfm) value in Table 7-1, Column 8.

Standard Examinee determined DRYWELL VENTING FLOW RATE was 319 cfm and recorded in Table 7-1 Column 8.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A4 Page 13 of 17

11. Procedure Step: 8. CALCULATE NOBLE GAS RELEASE RATE on Table 7-1.

Critical step 8.1 MULTIPLY Column 7 by Column 8 by Column 9.

(Column 7) x (Column 8) x (Column 9) = (Column 10) 8.2 RECORD NOBLE GAS RELEASE RATE (µCi/sec) value in Table 7-1, Column 10.

Standard Examinee calculated NOBLE GAS RELEASE RATE.

(1.81E-2 to 1.98E-2 Ci/ft3) x (319 cfm) x (1.67E4) =

(9.64E4 to 1.05E5 µCi/sec)

Examinee recorded 9.64E4 to 1.05E5 µCi/sec in Table 7-1 Column 10.

Cue Notes Results SAT UNSAT

12. Procedure Step: N/A Standard Recorded Completed By and Date on Table 7-1.

Cue Notes JPM is COMPLETE.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A4 Page 14 of 17 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee Table 7-1 (5)

(3) ESTIMATED PROJECTED (4) DRYWELL DBA-LOCA PROJECTED NOBLE GAS (2) EXPOSURE DBA-LOCA CURIE (8)

ACTUAL RATE AT NOBLE GAS CONTENT (7) DRYWELL (9) (10)

(1) CONT. EFFECTIVE CURIE (Ci) (6) NOBLE VENTING CONV. NOBLE GAS EFFECTIVE EXPOSURE AGE CONTENT D/W GAS CONC. FLOW FACTOR RELEASE RATE (2) (Ci/min to AGE RATE (rem/hr) (Ci) x (4) VOLUME (Ci/ft3) RATE (µCi/sec)

(hours) (rem/hr) (from Att. 8) (from Att. 10) (3) (ft3) (5) ÷ (6) (cfm) µCi/sec) (7) x (8) x (9) 1.81E-2 to 1 40 3.35E6 2.2E8 to 2.4E8 2626 to 2866 1.45E5 319 1.67E4 9.64E4 to 1.05E5 1.98E-2 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 1.45E5 1.67E4 Completed By: Date:

CNS NRC Exam 2020-4 JPM A4 Page 15 of 17 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee

CNS NRC Exam 2020-4 JPM A4 Page 16 of 17 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee 2.2E8 to 2.4E8

CNS NRC Exam 2020-4 JPM A4 Page 17 of 17 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. A LOCA has occurred.

2. The reactor is shutdown (All Control Rods are in).

3. MSIVs are Closed.

4. The decision has been made to vent the Torus through SBGT using the 1" line via PC-MO-1308 and PC-MO-305 per Procedure 5.8.18.

5. ERP Kaman effluent monitors are out of service.

6. The reactor was scrammed at 1200.

7. Current time is 1300.

8. PMIS system is out of service.

9. RMA-RR-40, high range containment radiation recorder, is out of service.

10. RMA-RR-40A indicates 40 R/hr.

11. RMA-RR-40B indicates 35 R/hr.

INITIATING CUE:

The CRS directs you to perform a release rate determination based on drywell Curie content and vent flow rate using Procedure 5.7.16, Release Rate Determination.

Another operator will perform step 9 of Attachment 6.

Record your results, including signature and date, by completing Procedure 5.7.16, .

CNS NRC Exam 2020-4 JPM A5 Page 1 of 11 Cooper Nuclear Station Job Performance Measure A-5 (SRO)

CNS NRC Exam 2020-4 JPM A5 Page 2 of 11 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Perform CRS Review of Surveillance 6.SC.202 Results Revision Number: 5 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation time (min): 15 Actual Time (min): Commented [FT1]: NRC calls this validation time JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to perform CRS review of a completed surveillance data package.

TASK STANDARD: Examinee determined HV-AO-265 stroke time exceeded the Operability limit, requiring entry into TS 3.6.4.2 REQUIRED ACTIONS A.1 and A.2, and HV-MO-266 stroke time was below the IST minimum and HV-MO-264 stroke time was above the IST maximum, requiring both valves to be immediately retested, IAW Procedure 6.SC.202, Secondary Containment (RRMG H&V) Valve Operability Test (IST).

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant (RCA )

Simulate x Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A5 Page 3 of 11 Comments (Required for Unsat ):

CNS NRC Exam 2020-4 JPM A5 Page 4 of 11 Revision Statements:

Rev 0 - new JPM Rev 1 - Changed JPM designation from A5 to SA5 per CE comments Rev 2 - Per NRC prep week comments, added that examinee may identify retest is required but that is not a critical portion of the JPM at step 4 and on answer key Rev 3 - Updated to new JPM format Rev 4 - Added TS 3.6.4.2 specific required actions A.1 and A.2 to task standard and JPM step 4 standard, added entire procedure 6.SC.202 as an additional handout, removed page from 6.SC.202 section 7 from examinee cue sheet, since entire procedure will be given as a handout.

Rev 5 - Deleted examiner note on key that immediate retest is not critical.

JPM Information:

1. NRC K/A Number and rating: 2.1.20 (4.6)

2. Safety Function: N/A

3. Task Number: 342026W0303 Review Results of Surveillance Test Commented [FT2]: Is this a facility-specific learning

4. PSA Applicability: N/A objective? If not, good to have that referenced.

5. Critical Steps stated in procedure step in bold References (include revision number if applicable):

1. Procedure 6.SC.202, Secondary Containment (RRMG H&V) Valve Operability Test (IST)

(Rev 16)

2. 0.26 SURVEILLANCE PROGRAM (Rev 71)

3. Tech Specification LCO 3.6.4.2 Special Conditions, Tools, Equipment:

1. Computer access Attachments:

1. Answer Key

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet and completed surveillance data sheets

2. Attachment 3 - Procedure 6.SC.202, Secondary Containment (RRMG H&V) Valve Operability Test (IST) (Rev 16)

CNS NRC Exam 2020-4 JPM A5 Page 5 of 11 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A5 Page 6 of 11 PERFORMANCE:

Start Time: ____________

1. Procedure Step: 7.1 Values recorded in shaded blocks on Attachment 1 within OPERABILITY LIMITS. [SR 3.6.4.2.2] IST Critical step Standard Examinee determined HV-AO-265 stroke time > Operability limit and recorded these conclusions on JPM Att. 2.

Cue Notes Results SAT UNSAT

2. Procedure Step: 7.2 CLOSING STROKE TIME recorded in shaded blocks on Critical step Attachment 1 within IST ACCEPTABLE RANGE. IST Standard Examinee determined HV-MO-266 stroke time is < IST minimum, immediate retest valve is required and Examinee determined HV-MO-264 stroke time is > IST maximum, immediate retest valve is required and recorded these conclusions on JPM Att. 2.

Cue Notes Results SAT UNSAT

3. Procedure Step: 7.3 RETEST STROKE TIME recorded in shaded blocks on Attachment 1 within IST ACCEPTABLE RANGE. IST Standard Examinee determined this step will be performed later, after valves are retested, and proceeded to step 7.4.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A5 Page 7 of 11

4. Procedure Step: 7.4 IF Step 7.1 not satisfied, THEN PERFORM following:

Critical step 7.4.1 DECLARE applicable valve inoperable.

7.4.2 ENTER appropriate CONDITIONS and REQUIRED ACTIONS.

Standard Due to HV-AO-265 stroke time > Operability limit in step 7.1, examinee declared valve inoperable and determined immediate entry into TS 3.6.4.2 REQUIRED ACTIONS A.1 and A.2 and recorded these conclusions on JPM Att. 2.

Cue Notes Retest required may be identified but is not a critical portion of this JPM.

JPM is COMPLETE.

Results SAT UNSAT Stop Time: __________ Total Time: ___________

CNS NRC Exam 2020-4 JPM A5 Page 8 of 11 Attachment 1 Answer Key Do NOT give to Examinee IST CLOSING RETEST ACCEPTABLE OPERABILITY VALVE STROKE TIME STROKE TIME RANGE LIMIT NUMBER seconds seconds seconds seconds HV-MO-262 54.8 N/A 49.6 to 67.0 79 N/A HV-MO-266 48.1 48.2 to 65.0 77 N/A HV-MO-264 64.3 47.1 to 63.5 75 N/A HV-MO-268 66.5 49.4 to 66.8 79 N/A HV-AO-263 4.7 2.2 to 6.4 8 N/A HV-AO-267 6.2 2.2 to 6.4 8 N/A HV-AO-265 8.2 2.2 to 6.6 8 N/A HV-AO-269 5.2 2.1 to 6.3 8 On JPM Att. 2 List conclusions of your review below:

1) HV-MO-266 stroke time < IST minimum, immediate retest required ________

2) HV-MO-264 stroke time > IST maximum, immediate retest required __

3) HV-AO-265 stroke time > Operability limit, declare valve inoperable and immediately enter REQUIRED ACTIONS A.1 and A.2 of TS 3.6.4.2 Examinees Signature / Todays Date Signature Date

CNS NRC Exam 2020-4 JPM A5 Page 9 of 11 ATTACHMENT 2 (page 1 of 3)

(Give to Examinee)

DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. The plant is operating at 100% RTP

2. BOP just completed performing 6.SC.202, Secondary Containment (RRMG H&V)

Valve Operability Test (IST)

INITIATING CUE:

You are directed to perform the CRS review of the completed surveillance data sheet, attached.

List conclusions and any actions, including TS Actions, to be taken (if required) based on your review below:

/

Signature Date

CNS NRC Exam 2020-4 JPM A5 Page 10 of 11 Attachment 2 ((page 2 of 3) continued)

(Give to Examinee)

ATTACHMENT 1 SECONDARY CONTAINMENT ISOLATION VALVE DATA SHEET Stopwatch Calibration Due Date: 2/18/2021 Stopwatch Identification Number: IS-11525 IST CLOSING RETEST ACCEPTABLE OPERABILITY VALVE STROKE TIME STROKE TIME RANGE LIMIT NUMBER seconds seconds seconds seconds HV-MO-262 54.8 N/A 49.6 to 67.0 79 N/A HV-MO-266 48.1 48.2 to 65.0 77 N/A HV-MO-264 64.3 47.1 to 63.5 75 N/A HV-MO-268 66.5 49.4 to 66.8 79 N/A HV-AO-263 4.7 2.2 to 6.6 8 N/A HV-AO-267 6.2 2.2 to 6.4 8 N/A HV-AO-265 8.2 2.2 to 6.6 8 N/A HV-AO-269 5.2 2.1 to 6.3 8 Procedure 6.SC.202 Revision 16 Page 12 of 16

CNS NRC Exam 2020-4 JPM A5 Page 11 of 11 Attachment 2 ((page 3 of 3) continued)

(Give to Examinee)

ATTACHMENT 2 SIGN-OFF AND REVIEWSHEET Initials Printed Name Initials Printed Name DB / Dan Brown /

MN / Marty Nott / _

Acceptance Criteria Satisfied: [ ] YES; [ ] NO Initials/Date:

Shift Manager Review: Date:

System Engineer Review (required): Date:

IST Engineer Review (required): Date:

Procedure 6.SC.202 Revision 16 Page 13 of 16

CNS NRC Exam 2020-4 JPM A6 Page 1 of 12 Cooper Nuclear Station Job Performance Measure A-6 (SRO)

CNS NRC Exam 2020-4 JPM A6 Page 2 of 12 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Reportable Occurrences to the NRC (#9)

Revision number: 1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to determine an NRC Reportable Occurrence has occurred and correctly complete NRC Form 361 per Procedure 2.0.5, Reports to NRC Operations Center.

TASK STANDARD: Examinee determined a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report to the NRC was required and NRC Form 361 contained the correct technical information (10 CFR50.72 non-emergency classification; 10CFR 50.72(b)(3)(v)(D)) per Procedure 2.0.5, Reports to NRC Operations Center. (See Answer Key).

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A6 Page 3 of 12 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A6 Page 4 of 12 Revision Statements:

Rev 0-New JPM JPM Information:

1. NRC K/A: 2.1.18 (3.6/3.8) 2.1.20 (4.6)

2. Safety Function: N/A

3. Task No.: 341014O0303

4. PSA Applicability: N/A

5. Critical steps stated in procedure step bold

References:

1. Procedure 2.0.5, Reports to NRC Operations Center (Rev 52)

2. NUREG 1022 (Rev 3)

Special Conditions, Tools, Equipment:

1. Calculator Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet

3. Attachment 3 - NRC Form 361, Reactor Plant Event Notification Worksheet Handouts:

1. Attachment 2 - Examinee cue sheet

2. Attachment 3 - NRC Form 361, Reactor Plant Event Notification Worksheet

CNS NRC Exam 2020-4 JPM A6 Page 5 of 12 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A6 Page 6 of 12 PERFORMANCE:

Start Time: ____________

1. Procedure Step: (Procedure 2.0.5, Reports to NRC Operations Center)

Standard Referred to body of Procedure 2.0.5, Section 4 and Attachments 1, 2 and 8.

Cue Notes Results SAT UNSAT

2. Procedure Step: 4.1 DETERMINATION OF REPORTABILITY FOR 10CFR20, 26, 37, 50.72, 70.52, 72.75, and 73.77 EVENTS 4.1.1 If immediate notification is required due to declaration of an emergency classification, perform the emergency notifications per Procedure 5.7.6.

Standard Examinee determined emergency notification was not required due to no emergency declaration exists.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A6 Page 7 of 12

3. Procedure Step: 4.1.7 The SM shall determine the appropriate reporting category Critical step (i.e., immediate, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

Guidance is provided in Attachments 1 through 4 for determining the category for immediate notifications.

4.1.7.1 NUREG 1022 shall be referenced for all 10CFR50.72 reporting decisions.

Standard Examinee reviewed Attachments 1 and 2 and NUREG 1022 as necessary and determined 8-hour report is required under 10CFR50.72 non-emergency classification; 10 CFR 50.73(b)(3)(v),

Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to:

4) Mitigate the consequences of an accident.

Cue Notes IAW procedure 2.0.5 Att. 1 flowchart, Att. 2 line 8, and NUREG 1022 pages 38 and 40.

Results SAT UNSAT

4. Procedure Step: 4.4 PREPARE NRC FORM 361 (ATTACHMENT 8) AND CONTACT THE NRC OPERATIONS CENTER Critical step 4.4.3 Preparer should ensure the worksheet is accurate and properly filled out.

Standard Examinee completed information on the NRC Form 361 IAW answer key.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A6 Page 8 of 12

5. Procedure Step: Submits NRC Form 361 Critical step Standard Examinee provided NRC Form 361 to the Examiner.

Cue Notes JPM is complete.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A6 Page 9 of 12 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN #

NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-3469*, BACKUPS - [1st] 301-951-0550 or 800-449-3694*

[2nd] 301-415-0550 and [3rd]301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers FACILITY OR ORGANIZATION UNIT NOTIFICATION TIME NAME OF CALLER CALL BACK #

Cooper Nuclear Station 1 Examinees Name 402-825-5253 Event time and zone Event date Power/mode before Power/mode after Current Time Todays Date 100% / Mode 1 90% / Mode 1 Event classification 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU X (v)(D) Accident Mitigation AIND UNSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED X 50.72 NON-EMERGENCY (See Next Column) (iv) (B) RPS Actuation (Scram) ARPS (xiii) Loss Comm/Asmt/Resp ACCM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HRT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)

OTHER UNSPECIFIED REQMT. (See Last Column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (continue on back)

Control Room Emergency Filtration System BF-C-1A, Emergency Booster Fan was discovered to be non-functional during an invalid ESF actuation.

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NOT YES (Explain above) NO NRC RESIDENT X UNDERSTOOD?

STATE(s) X DID ALL SYSTEMS FUNCTION YES AS REQUIRED? NO (Explain above)

LOCAL X OTHER GOV AGENCIES X MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK RESTART DATE: Date + 4 or YES NO MEDIA/PRESS RELEASE X UNTIL CORRECTED: 1 unknown at this time Examiner Note: Only items that are bolded and yellow highlighted are critical. Identification of 60-day report for invalid ESF actuation is allowed but is NOT critical, since that is the responsibility of Licensing.

CNS NRC Exam 2020-4 JPM A6 Page 10 of 12 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. Plant was in Mode 1, 100% power when I&C working in Panel 9-17 cause a momentary short that caused a Group 6 isolation.

2. Reactor power has been lowered to 90%.

3. During verification of the isolation IAW Procedure 2.1.22, it was determined Control Room Emergency Filtration System BF-C-1A, Emergency Booster Fan will NOT start.

4. Group 6 isolation logic has been reset and systems are being returned to normal.

5. Shift Manager's phone number is 402-825-5253.

6. Time of event was today at 13:00.

INITIATING CUE:

You are directed to determine what notification requirements exist and complete the required sections of NRC Form 361. Return the completed form to the evaluator when you have finished.

CNS NRC Exam 2020-4 JPM A6 Page 11 of 12 ATTACHMENT 3 (Page 1 of 2)

NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN #

NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-3469*, BACKUPS - [1st] 301-951-0550 or 800-449-3694*

[2nd] 301-415-0550 and [3rd]301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #

Event time and zone Event date Power/mode before Power/mode after Event classification 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) Accident Mitigation AIND UNSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED 50.72 NON-EMERGENCY (See Next Columns) (iv) (B) RPS Actuation (Scram) ARPS (xiii) Loss Comm/Asmt/Resp ACCM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HRT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)

OTHER UNSPECIFIED REQMT. (See Last Column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (continue on back)

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NOT NRC RESIDENT UNDERSTOOD? YES (Explain above)

NO STATE(s) DID ALL SYSTEMS FUNCTION YES NO (Explain above)

LOCAL AS REQUIRED?

OTHER GOV AGENCIES MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK UNTIL CORRECTED: RESTART DATE: YES NO MEDIA/PRESS RELEASE

CNS NRC Exam 2020-4 JPM A6 Page 12 of 12 ATTACHMENT 3 (Page 2 of 2)

CNS NRC Exam 2020-4 JPM A7 Page 1 of 10 Cooper Nuclear Station Job Performance Measure A-7 (SRO)

CNS NRC Exam 2020-4 JPM A7 Page 2 of 10 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Determine TS Actions for Removal of a Single Control Rod Drive during Refueling Revision number: 8 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS:(Circle one) SAT UNSAT COMMENT SHEET ATTACHED: (circle one) Yes / No (Required for Unsat)

SYNOPSIS: This JPM evaluates the Examinee's ability to determine the control rods associated with a 5X5 array during a single CRD removal during refueling.

TASK STANDARD: Examinee determined that in order to remove CRD 10-11, the following conditions must be satisfied IAW Technical Specification LCO 3.10.5:

All other control rods are fully inserted,

All other control rods in a 5X5 array centered on the withdrawn control rod (10-11) are disarmed (impacted rods as identified on the answer key),

A control rod withdrawal block is inserted and LCO 3.1.1. Shutdown Margin, Mode 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

No other core alterations are in progress.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A7 Page 3 of 10 Comments(Required for Unsat):

CNS NRC Exam 2020-4 JPM A7 Page 4 of 10 Revision Statements:

Rev 6 - Updated JPM to new format Rev 7 - Per CE comments, revised task standard for clarity and specified TS 3.10.5 is the source of the requirement on the answer key.

Rev 8 - Incorporated NRC prep week comments JPM Information:

1. NRC K/A Number and rating: G 2.4.40 (4.7)

2. Safety Function: N/A

3. Task No: 341030W0303 Evaluate Plant Systems performance and Coordinate the appropriate Actions per Tech Specs in the Event a LCO is Entered

4. PSA Applicability/OE: CR-CNS-2009-09138 Unplanned Entry Tech Spec required action 3.10.4 B

5. Critical Steps in the Procedure step in bold References (include revision number if applicable):

1. Technical Specifications

2. Technical Specification Bases Special Conditions, Tools, Equipment:

1. None Attachments:

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

CNS NRC Exam 2020-4 JPM A7 Page 5 of 10 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A7 Page 6 of 10 PERFORMANCE:

START TIME:

1. Procedure Step:

Standard Obtained copy of Technical Specifications and Bases.

Cue Notes Examinee will use computer to access Technical Specifications and Bases, or if computer is unavailable hard copies can be provided.

Results SAT UNSAT

2. Procedure Step: TS LCO 3.10.5 applies.

Critical Step Standard Examinee determined that TS 3.10.5 applies in this case.

Cue Notes Operations Department expectation is both Technical Specifications and Bases are to be referenced when making Technical Specification determinations. This will NOT result in a failure, but needs to be noted if the trainee fails to reference both documents.

Results SAT UNSAT

3. Procedure Step: TS LCO 3.10.5 Standard Examinee read the LCO and determined the requirements of LCO 3.10.5 are listed on page 3.10-13.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A7 Page 7 of 10

4. Procedure Step: TS LCO 3.10.5 Critical Step Standard Examinee filled out Attachment 3 of this JPM with the requirements listed on Attachment 1 Answer Sheet.

Cue Notes Results SAT UNSAT

5. Procedure Step: N/A Critical step Standard Examinee provided the Attachment 3 to the evaluator, and the data on attachment 3 matches the data on Attachment 1 (Answer Key).

Cue Notes The JPM is Complete.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A7 Page 8 of 10

- ANSWER KEY**

NOTE TO EXAMINER: Text in bold is required for successful completion of this JPM.

The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring"; LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.9.2, "Refuel Position One-Rod-Out Interlock"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITYRefueling," may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;

b. All other control rods in a five by five array centered on the withdrawn control rod (10-11) are disarmed;

c. A control rod withdrawal block is inserted, and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

d. No other CORE ALTERATIONS are in progress.

Rods list:

51 02-19 06-19 47 10-19 14-19 43 18-19 39 06-15 10-15 35 14-15 OR 18-15 31 06-11 14-11 27 18-11 10-07 23 14-07 19 X X X X X 18-07 18-03 15 X X X X 11 X X X 07 X X X 03 X 02 06 10 14 18 22 26 30 34 38 42 46 50

- ANSWER KEY**

CNS NRC Exam JPM A7 Page 9 of 10 ATTACHMENT 2 (page 1 of 2)

DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. The Reactor is in MODE 5 (Refuel).

2. The core is fully loaded with fuel.

INITIATING CUE:

You are to determine the requirements for the removal of CRD 10-11 during refueling (with no fuel removed) in accordance with Technical Specifications. List the specific Technical Specification requirement(s) and indicate/mark any of the impacted control rods or list the impacted control rods on Attachment 2 (page 2 of 2). Provide this information to the SM when complete.

CNS NRC Exam JPM A7 Page 10 of 10 Examinee Answer Sheet ATTACHMENT 2 (page 2 of 2) 51 47 Rods list:

43 39 35 31 27 OR 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 Signature _________________

CNS NRC Exam 2020-4 JPM A8 Page 1 of 10 Cooper Nuclear Station Job Performance Measure A-8 (SRO)

CNS NRC Exam 2020-4 JPM A8 Page 2 of 10 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Determine Emergency Exposure Requirements Revision number: 1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to determine estimated dose for a worker, the maximum emergency dose allowed IAW Procedure 5.7.12, and whether KI is required to be authorized IAW Procedure 5.7.14.

TASK STANDARD: Examinee determined up to 10R is allowed for the task IAW Procedure 5.7.12, Emergency Radiation Exposure Control, the estimated dose is 7.76 R, and Potassium Iodide (KI) is NOT required to be authorized IAW Procedure 5.7.14, Stable Iodine Thyroid Blocking (KI).

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A8 Page 3 of 10 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A8 Page 4 of 10 Revision Statements:

Rev 0 - New JPM Rev 1 - Incorporated NRC prep week comments JPM Information:

1. NRC K/A: 2.3.4 (3.7)

2. Safety Function: N/A

3. Task No.: N/A

4. PSA Applicability: N/A

5. Critical steps stated in procedure step bold

References:

1. Procedure 5.7.12, Emergency Radiation Exposure Control (Rev 17)

2. Procedure 5.7.14, Stable Iodine Thyroid Blocking (KI) (Rev 22)

3. Procedure 5.7.1, Emergency Classification, Attachment 4, Emergency Action Level Matrix (EPIPEALHOT) (Rev 18)

Special Conditions, Tools, Equipment:

1. Calculator Attachments

1. Attachment 1 - Answer Key

2. Attachment 2 - Examinee cue sheet and answer sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

CNS NRC Exam 2020-4 JPM A8 Page 5 of 10 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task.

When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A8 Page 6 of 10 PERFORMANCE:

Start Time: ____________

1. Procedure Step (Procedure 5.7.12, Emergency Radiation Exposure Control)

NOTE - Emergency exposures are allowed above 10CFR20 limits in emergency situation as per Emergency Exposure Guidelines (NUREG 0654, NUREG 0737, ICRP Reports, and EPA Guides).

2.3 Emergency Director EVALUATE request for exposures in excess of occupational limits by reviewing:

Scope of work.

Travel path.

Dose estimates.

Alternative measures considered to avoid exposures in excess of occupational limits, refer to Step 2.2.3.

Attachment 1, Table 1, dose limits versus activity being performed.

Standard Examinee reviewed note and steps as related to initial conditions, and referred to Attachment 1.

Cue Notes Results SAT UNSAT

2. Procedure Step (Procedure 5.7.1, Emergency Classification)

ATT. 4 - Emergency Action Level Matrix (EPIPEALHOT)

Table 1 - GUIDE ON DOSE LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES Standard Examinee reviewed items on EPIPEALHOT Category A and determined offsite release rate was at Site Area Emergency Level (below General Emergency level).

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A8 Page 7 of 10

3. Procedure Step (Procedure 5.7.12, Emergency Radiation Exposure Critical Step Control) 2.4 IF ED determines Table 1 criteria met, THEN only ED AUTHORIZE exposure.

ATT. 1 - EMERGENCY EXPOSURE LIMITS Table 1 - GUIDE ON DOSE LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES Standard Examinee reviewed items on Table 1 and determined up to 10 R was the EMERGENCY LIMIT associated with Isolation of radiological release less than G.E. dose as calculated by Procedures 5.7.17 and 5.7.17.1 and recorded 10 R emergency dose limit on Attachment 2.

Cue Notes Results SAT UNSAT

4. Procedure Step Attachment 1, Emergency Exposure Limits Critical Step NOTE 2 - Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from exposure and intake during an emergency situation.

Standard Examinee calculated estimated dose:

6200 mR/hr X 1.25 hr = 7750 mR = 7.75 R 7750 mR + 10 mR (Thyroid CDE) = 7760 mR = 7.76 R and recorded 7.76 R (7760 mR) estimated dose on JPM Att. 2.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A8 Page 8 of 10

5. Procedure Step (Procedure 5.7.14, Stable Iodine Thyroid Blocking (KI))

Critical Step 1. ENTRY CONDITION 1.1 Emergency declared at CNS and one of following conditions present:

Fuel cladding determined lost per EPIP 5.7.1, Attachment 3.

Calculated dose greater than or equal to 5 rem (0.05 Sv) to thyroid (CDE) likely to be received.

Emergency workers being dispatched to areas where high levels of radio-iodine suspected and no current air sample data available.

General Emergency declared and Emergency Director (ED) expects progression of event with likely damage to fuel and radiological release.

Standard Examinee reviewed entry conditions and determined KI authorization was NOT required due to no entry condition was met and recorded KI NOT required to be authorized on Attachment 2.

Cue Notes JPM is complete.

Results SAT UNSAT STOP TIME: Total Time: _____________

CNS NRC Exam 2020-4 JPM A8 Page 9 of 10 ATTACHMENT 1 ANSWER KEY Do NOT give to examinee INITIATING CUE:

Note: DO NOT use Emergency Director Judgment as a basis for your conclusions

1) Determine the MAXIMUM allowed dose for this task.

2) Determine the estimated dose for the task.

3) Determine whether or not Potassium Iodide (KI) is required to be approved for the operator performing this task.

List your responses below:

1) MAXIMUM DOSE FOR TASK 10 R

2) ESTIMATED DOSE 7.76 R (7760 mR)

3) POTASSIUM IODINE (KI) is REQUIRED (Circle Yes or No) YES NO Examinees Signature / Todays Date Signature Date

- ANSWER KEY**

CNS NRC Exam 2020-4 JPM A8 Page 10 of 10 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. RCIC steam line has ruptured in the steam tunnel.

2. RCIC Outboard Steam Supply Isolation MO-15 is open and has lost power.

3. RCIC Inboard Steam Supply Isolation MO-16 is open and has lost power.

4. There are high radiation levels in the steam tunnel. The general area dose rate is 6,200 mR/hr, steady.

5. Fuel cladding has NOT been lost.

6. Off-site protective actions have NOT been completed.

7. A radiation release is occurring with projected dose of 300 mRem TEDE and 6 mRem Thyroid CDE at the site boundary

8. RCIC-MO-16 must be manually closed locally to terminate the release.

9. It will take one operator 75 minutes to manually close RCIC-MO-16.

10. The operator is expected to incur a Thyroid CDE dose of 10 mRem based on air sample data.

11. The operators year-to-date dose history is 200 mRem.

INITIATING CUE:

Note: DO NOT use Emergency Director Judgment as a basis for your conclusions

1) Determine the MAXIMUM allowed dose for this task.

2) Determine the estimated dose for the task.

3) Determine whether or not Potassium Iodide (KI) is required to be authorized for the operator performing this task.

1) MAXIMUM DOSE FOR TASK

2) ESTIMATED DOSE

3) POTASSIUM IODINE (KI) is REQUIRED (Circle Yes or No) YES NO

/

Signature Date

CNS NRC Exam 2020-4 JPM A9 Page 1 of 9 Cooper Nuclear Station Job Performance Measure A-9 (SRO)

CNS NRC Exam 2020-4 JPM A9 Page 2 of 9 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Determine Emergency Classifications EAL table top # 10 Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: (circle one) Yes / No (Required for Unsat)

SYNOPSIS: This JPM evaluates the Examinee's ability to make an EAL classification given a set of plant conditions.

TASK STANDARD: Examinee determined an SITE AREA EMERGENCY classification (SS7.1) was required IAW procedure 5.7.1 within 15 minutes of beginning the task.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM A9 Page 3 of 9 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM A9 Page 4 of 9 Revision Statements:

Rev 1 - Updated JPM to new format Rev 2 - Specified EAL Charts are to be provided as full-size, hard copy handouts JPM Information:

1. NRC K/A Number and rating: G 2.4.41 (4.6)

2. Safety Function: N/A

3. Task No: 344018O0303

4. PSA Applicability: N/A

5. Critical Steps denoted by Standard in bold References (include revision number if applicable):

1. Procedure 5.7.1, Emergency Classification (Rev 64)

2. Procedure 5.7.1 Attachment 4, EPIPEALHOT, EAL Matrix (Rev 18).

3. Procedure 5.7.6, Notification (Rev 76), Attachment 1.

Special Conditions, Tools, Equipment:

1. None Attachments:

1. Attachment 1 - N/A

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Procedure 5.7.1 Attachment 4, EPIPEALHOT, EAL Matrix (full-size, hard copy)

3. Procedure 5.7.1 Attachment 4, EPIPEALCOLD, EAL Matrix (full-size, hard copy)

CNS NRC Exam 2020-4 JPM A9 Page 5 of 9 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM A9 Page 6 of 9 PERFORMANCE:

START TIME:

1. Procedure Step: 2.1 AFTER recognition of off-normal event, THEN SM shall PERFORM following:

2.1.1 COMPARE event to EALs on EAL Classification Matrix.

Standard Examinee referred to EAL Classification Matrix, Attachment 4.

Cue Notes Results SAT UNSAT

2. Procedure Step: 2.1.2 IF more than one EAL of different classification levels is reached (i.e., EAL for ALERT and EAL for SITE AREA EMERGENCY), THEN SELECT EAL for most severe emergency classification.

Standard Examinee determined the most severe emergency classification.

Cue Notes Results SAT UNSAT

3. Procedure Step: 2.1.3 IF event appears to meet an EAL and time permits, THEN REFER to Attachment 2 or 3 for further explanation and guidance.

Standard Examinee referred to Attachment 2 or 3 if time permitted.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM A9 Page 7 of 9

4. Procedure Step: 2.1.4 IF determined EAL is met, THEN PERFORM Critical step following within 15 minutes.

Standard Examinee determined classification within 15 minutes of commencing the JPM.

Cue Notes Results SAT UNSAT

5. Procedure 2.1.4.2 DECLARE emergency.

Step:

Critical step Standard Examinee classified the event as a SITE AREA EMERGENCY based on EPIP 5.7.1, SS7.1.

Cue Notes The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

Results SAT UNSAT

6. Procedure N/A Step:

Standard Examinee returned the completed Attachment 2 to the examiner.

Cue Notes JPM is COMPLETE.

Results SAT UNSAT Stop Time: _____________ Total Time: _____________

CNS NRC Exam JPM A9 Page 8 of 9 ATTACHMENT 2 Page 1 of 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

The plant has experienced the events listed on Attachment 2 page 2.

INITIATING CUE:

This is a time critical JPM.

You have been directed to use the attachment provided to classify the event at the highest EAL attained. Also identify the basis for your classification.

Immediately return Attachment 2 to the examiner when you have completed this task.

The completion time for this JPM will be documented when you hand the JPM back to the evaluator.

CNS NRC Exam JPM A9 Page 9 of 9 ATTACHMENT 2 Page 2 of 2 This is a time critical JPM.

Parameter/System/Component Status The plant was initially operating at 100% power. The following conditions have occurred:

EVENT DESCRIPTION:

Minutes

+00 Seismic activity has occurred such that the Main Turbine has tripped coincident with loss of the Startup Transformer.

Breakers 1FS and 1GS remained OPEN.

Both Emergency Diesel Generators started but failed to energize their respective critical bus.

+05 Emergency Transformer voltage was available and breakers 1FS and 1GS were locally CLOSED, energizing both 4160V Critical Buses.

Drywell pressure is 2.7 psig and rising slowly.

RPV Pressure is cycling between 1040 and 1060 psig.

RPV Level -100" by local Fuel Zone and lowering slowly.

RCIC has been started locally and is injecting to the RPV.

Voltage indication remains downscale for both 125/250 VDC Systems.

Turbine Building Operator reports extensive damage to the Control Building in the vicinity of 125/250 VDC Charger and Battery Rooms.

Compensatory Actions are in place for monitoring plant parameters via PMIS/SPDS.

Highest EAL:

Based on (Category and Description)

Signature of Operator/STE:_____________________________________________

Immediately return Attachment 2 to the examiner when you have completed this task.

The completion time for this JPM will be documented when you hand the JPM back to the evaluator.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination: 4/27/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: CN-2020-4 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function S1. Respond to two rods drifting during 6.CRD.301 (Alt Path - Two S, N, A 1 control rods will begin drifting during control rod exercise testing, requiring entry into AOP 2.4CRD and manual scram)

K/A 201003 A2.03 (3.4/3.7) RO, SRO-I S2. Restart RWCU following Group 3 isolation IAW SOP 2.2.66 sect S, P, D 2 6 (9/2018 ILT NRC JPM S2 randomly selected) 9/2018 NRC K/A 204000 A4.01 (3.1/3.0) RO ILT S2 S3. SKL034-20-29R0, Open MSIVs with RPV pressurized (Alt Path S, D, A, EN, L 3

- Steam leak will occur while warming MSLs, automatic Group 1 isolation fails, requiring manually isolating steam supply IAW procedure 2.0.3, Conduct of Operations)

K/A 239001 A4.01 (4.2/4.0) RO, SRO-I S4. SKL034-20-137, Operate RCIC in pressure control (Alt Path - S, D, A, L 4 When RCIC is manually started, the speed controller fails low, requiring securing RCIC to prevent turbine damage IAW a different section of the SOP)

K/A 217000 A4.01 (3.7/3.7) RO, SRO-I, SRO-U S5. Perform 5.2FUEL Att. 2 (Actions to minimize rad release) S, N, L 5 KA 295036 EK3.04 (3.1/3.4) RO, SRO-I S6. Energize 4160V critical Bus 1G from Emergency Station Service S, D, EN 6 XFMR (ESST) (SKL034-20-43 Rev 0)

K/A 262001 A4.01 (3.4/3.7) RO, SRO-I, SRO-U S7. Defeat RPS Logic Trips During Failure-to-Scram (Restoration - S, D 7 Removal of RPS jumpers) IAW EP 5.8.3 section 5 (SKL034-21-79) 212000 K4.12 (3.9/4.1) RO, SRO-I S8. Start SGT B for HPCI operation for level control post-scram. S, N, A, EN, L 9 2.2.73 Section 8. (Alt Path - High Moisture will alarm for the preferred SGT filter train due to heater failure, requiring shifting SGT trains per the alarm card)

KA 261000 A4.07 (3.1/3.2) RO, SRO-I, SRO-U page 1 of 2 Rev 3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1. SKL034-10-128 Startup the RPS Motor Generator Set D, A 7 (RPS MG A)

KA 212000 A2.01 (3.7/3.9) RO, SRO-I, SRO-U P2. SKL034-10-65R9, Conduct alternate rod insertion by manually D, R, L, E 1 venting scram air header K/A 295037 EA1.05 (3.9/4.0),

K/A 201003 A2.05 (4.1/4.1) RO, SRO-I, SRO-U P3. SKL034-10-34 Place the A Air Dryer in Service D 8 K/A 295019 AA1.02 (3.3/3.1) RO, SRO-I

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

Type Codes Criteria for R /SRO-I/SRO-U (Actual)

(A)lternate path 4-6/4-6 /2-3 (5/5/3)

(C)ontrol room (D)irect from bank 9/ 8/ 4 (8/7/4)

(E)mergency or abnormal in-plant 1/ 1/ 1 (1/1/1)

(EN)gineered safety feature 1/ 1/ 1 (control room system) (3/3/2)

(L)ow-Power/Shutdown 1/ 1/ 1 (5/5/3)

(N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (3/3/1)

(P)revious 2 exams 3/ 3/ 2 (randomly selected) (1/0/0)

(R)CA 1/ 1/ 1 (1/1/1)

(S)imulator page 2 of 2 Rev 3

CNS NRC Exam 2020-4 JPM S1 Page 1 of 16 Cooper Nuclear Station Job Performance Measure S-1 Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 2 of 16 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Respond to a Control Rod Drifting In (Alternate Path)

Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the Examinee's ability to perform control rod exercise testing IAW Procedure 6.CRD.301 and then respond to two control rods drifting in IAW Alarm Card 9-5-1/C-4, Rod Drift or Procedure 2.4CRD, CRD Trouble.

TASK STANDARD: Examinee exercised control rods 22-07 and 26-07 IAW Procedure 6.CRD.301 section 3.7, recognized control rods 22-07 and 26-07 were drifting in, and inserted a manual scram IAW Alarm Card 9-5-1/C-4, Rod Drift or Procedure 2.4CRD, CRD Trouble.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 3 of 16 Comments (Required for Unsat):

Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 4 of 16 Revision Statements:

Rev 0-New JPM Rev 1 - Editorial changes per NRC comments Rev 2 - Incorporated NRC prep week comments JPM Information:

1. NRC K/A: 201003 A2.03 (3.4/3.7)

2. Safety Function: 1, Reactivity Control

3. Task No.: 201020O0401 - Respond to a Control Rod Drifting In

4. PSA Applicability: N/A

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 6.CRD.301, Withdrawn Control Rod Operability IST Test (Rev 32)

2. Procedure 2.4CRD, CRD Trouble (Rev 20)

3. Procedure 2.1.5 Reactor Scram (Rev 77)

4. Procedure 2.3_9-5-1 (Rev 36)

Special Conditions, Tools, Equipment:

1. Simulator Set-Up IAW Attachment 2 Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. 6.CRD.301, Withdrawn Control Rod Operability IST Test, with Attachment 3 and associated steps marked up to the point of testing control rod 22-07 per Step 3.7)

3. 2.4CRD, CRD Trouble Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 5 of 16 DIRECTIONS TO EXAMINER:

Note: This is an ALTERNATE PATH JPM. While performing 6.CRD.301, control rods 22-07 and 26-07 will drift in, requiring the examinee to scram the reactor IAW Procedure 2.4CRD.

Note: DO NOT give Procedure 2.4CRD to examinee until requested.

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed.

You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

(DO NOT give Handout 3 (2.4CRD CRD TROUBLE) to examinee until identified by the examinee at JPM step 22, 23, or 24 if asked for.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 6 of 16 PERFORMANCE:

START TIME:

1. Procedure Step: (Procedure 6.CRD.301, Withdrawn Control Rod Operability Critical Step IST Test) (Control rod 22-07)

3. Withdrawn Control Rod Operability IST Test 3.7 For each control rod at 48, PERFORM following:

3.7.1 Using Concurrent Verification, SELECT desired control rod.

Standard Pressed select switch for rod 22-07 on ROD SELECT MATRIX.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 7 of 16

2. Procedure Step: 3.7.2 ENSURE following:

3.7.2.1 Desired control rod only button backlit on ROD SELECT MATRIX.

3.7.2.2 Desired control rod only control rod backlit on FULL CORE DISPLAY.

3.7.2.3 Desired control rod indicated on FOUR ROD DISPLAY.

3.7.2.4 LPRM signals on 16 LPRM readout windows normal or as expected for power level and rod selected.

Standard Checked only rod 22-07 switch on ROD SELECT MATRIX was backlit, only rod 22-07 on FULL CORE DISPLAY was backlit, rod 22-07 as selected on FOUR ROD DISPLAY, and LPRM meters on panel 9-5 and determined readings were normal for rod 26-07 at 90% power.

Cue Notes Results SAT UNSAT

3. Procedure Step: 3.7.3 RECORD in DESIRED ROD SELECTED block for selected rod.

Standard Inscribed check mark in DESIRED ROD SELECTED column on Attachment 3 for rod 22-07.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 8 of 16

4. Procedure Step: 3.7.4 INSERT selected control rod one notch.

Critical Step Standard Placed ROD MOVEMENT CONTROL SWITCH momentarily to left to IN, then released switch and observed ROD IN light illuminated and extinguished, ROD SETTLE light illuminated and extinguished, and rod position on FOUR ROD DISPLAY changed from 48 to 46 for rod 22-07.

Cue Notes Results SAT UNSAT

5. Procedure Step: 3.7.5 WITHDRAW selected control rod by performing following:

Critical Step 3.7.5.1 APPLY continuous withdraw signal.

Standard Simultaneously placed ROD MOVEMENT CONTROL SWITCH momentarily to right to OUT NOTCH and EMERGENCY NOTCH OVERRIDE to right to OVERRIDE and held both switches.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 9 of 16

6. Procedure Step: 3.7.5.2 CHECK red DRIFT light on full core display for selected rod not on.

3.7.5.3 CHECK Annunciator 9-5-1/B-4, ROD OVERTRAVEL, does not alarm.

3.7.5.4 RECORD WITHDRAW STALL FLOW from CRD-FI-305 for selected control rod.

Standard Checked drift light for rod 22-07 on FULL CORE DISPLAY was not lit, Annunciator 9-5-1/B-4, ROD OVERTRAVEL, did not alarm, and noted flow indicated on CRD-FI-305, DR WTR FLOW.

Cue Examiner reads stall flow.

Notes Examinee cannot record stall flow due to 2-handed operation to hold rod control switches until completed with coupling check.

Results SAT UNSAT

7. Procedure Step: 3.7.5.5 RELEASE continuous withdraw signal.

Critical Step Standard Released ROD MOVEMENT CONTROL SWITCH and EMERGENCY NOTCH OVERRIDE switches.

Cue Notes Results SAT UNSAT

8. Procedure Step: 3.7.6 IF Steps 3.7.5.2 and 3.7.5.3 satisfied, THEN RECORD in COUPLING CHECK block for selected control rod.

Standard Inscribed check mark in COUPLING CHECK column on Attachment 3 for rod 22-07.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 10 of 16

9. Procedure Step: 3.7.7 IF control rod inserted and withdrew one notch, THEN RECORD in CONTROL ROD EXERCISED block for selected control rod.

Standard Inscribed check mark in CONTROL ROD EXERCISED column on Attachment 3 for rod 22-07, and initialed in PERFORMED BY column on Attachment 3 for rod 22-07.

Cue Notes Results SAT UNSAT

10. Procedure Step: (Control rod 26-07)

Critical Step 3.7 For each control rod at 48, PERFORM following:

3.7.1 Using Concurrent Verification, SELECT desired control rod.

Standard Pressed select switch for rod 26-07 on ROD SELECT MATRIX.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 11 of 16

11. Procedure Step: 3.7.2 ENSURE following:

3.7.2.1 Desired control rod only button backlit on ROD SELECT MATRIX.

3.7.2.2 Desired control rod only control rod backlit on FULL CORE DISPLAY.

3.7.2.3 Desired control rod indicated on FOUR ROD DISPLAY.

3.7.2.4 LPRM signals on 16 LPRM readout windows normal or as expected for power level and rod selected.

Standard Checked only rod 26-07 switch on ROD SELECT MATRIX was backlit, only rod 26-07 on FULL CORE DISPLAY was backlit, rod 26-07 was selected on FOUR ROD DISPLAY, and LPRM meters on panel 9-5 and determined readings were normal for rod 26-07 at 90% power.

Cue Notes Results SAT UNSAT

12. Procedure Step: 3.7.3 RECORD in DESIRED ROD SELECTED block for selected rod.

Standard Inscribed check mark in DESIRED ROD SELECTED column on Attachment 3 for rod 26-07.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 12 of 16

13. Procedure Step: 3.7.4 INSERT selected control rod one notch.

Critical Step Standard Placed ROD MOVEMENT CONTROL SWITCH momentarily to left to IN, then released switch and observed ROD IN light illuminate and extinguish, ROD SETTLE light illuminate and extinguish, and rod position on FOUR ROD DISPLAY change from 48 to 46 for rod 26-07.

Cue Notes Results SAT UNSAT

14. Procedure Step: N/A Alternate Path Standard Recognized and responded to Annunciator 9-5-1/C-4, ROD DRIFT.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 13 of 16 Note to Examiner: Examinee may reference Alarm Card 9-5-1/C-4 or may enter Procedure 2.4CRD. If Examinee states they are entering Procedure 2.4CRD and requests a copy, give the examinee Handout 3 (Procedure 2.4CRD).

15. Procedure Step: (Alarm Card 9-5-1/C-4)

Alternate Path 2.1 Check full core display for rod drift light(s) to determine which rod(s) is drifting.

Standard Checked red drift LEDs for control rods 22-07 and 26-07 on FULL CORE DISPLAY were lit, and reported to the CRS that the drift lights for 22-07 and 26-07 were on and scram action is met.

Cue Notes Results SAT UNSAT Note to Examiner: Both Alarm Card 9-5-1/C-4 and Procedure 2.4CRD contain a step to insert a manual scram if more than one control rod is drifting in.

Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 14 of 16

16. Procedure Step: (Alarm Card 9-5-1/C-4)

Alternate Path 2.2. IF more than one rod is drifting, THEN SCRAM and Critical Step concurrently enter Procedure 2.1.5.

and/or (2.4CRD) 4.2 If more than one rod drifting, SCRAM and concurrently enter Procedure 2.1.5.

Standard Inserted SCRAM by depressing RX SCRAM CH A and CH B push buttons OR by placing the Reactor Mode Switch to SHUTDOWN on panel 9-5.

Cue JPM is complete Notes Results SAT UNSAT Stop Time: _____________ Total Time: _____________

Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 15 of 16 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC IC - 320; ~90% power C. Run schedule File 2020-4JPMS1 D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

1. Triggers None Scram Outlet

2. Malfunctions RD03C Valve Leakage 1 N/A 20.5 N/A N/A 22-07 Scram Outlet RD03H Valve Leakage 1 N/A 20.5 N/A N/A 26-07

3. Remotes None

4. Overrides None

5. Panel Setup a. Ensure RX Power is ~90% and both RR Pump Controllers in P.

Time Event Action Description 00:00 Insert malfunction RD03C at Scram Outlet Valve Leakage 22-07 20.5 on event 1 00:00 Insert malfunction RD03H at Scram Outlet Valve Leakage 26-07 20.5 on event 1 00:00 create event 1 rdsdrpos(128) <= Control rod 26-07 inserted to position 736 46 00:00 1 create event 11 zlorpsds1a == 0 Scram logic lights OFF

& zlorpsds1b == 0 11 Delete malfunction RD03C Scram Outlet Valve Leakage 22-07 11 Delete malfunction RD03H Scram Outlet Valve Leakage 26-07 Rev 2

CNS NRC Exam 2020-4 JPM S1 Page 16 of 16 ATTACHMENT 2 Directions to Examinee: Commented [k1]: undelined in JPM P1 Read the following, and inform the examiner when you are ready to begin:

INITIAL CONDITIONS:

1. Reactor is at 90% power.

2. The WCO is available to act as the second checker.

3. Reactor Engineer is present in the control room.

4. All fully withdrawn control rods through rod 18-07 on 6.CRD.601 Attachment 3 have already been tested.

INITIATING CUE:

You are directed to perform operability testing of fully withdrawn control rods IAW Procedure 6.CRD.301, Withdrawn Control Rod Operability IST Test, step 3.7, beginning at control rod 22-07.

Inform the CRS when testing is complete.

CNS NRC Exam 2020-4 JPM S2 Page 1 of 22 Cooper Nuclear Station Job Performance Measure S-2 Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 2 of 22 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Place the Reactor Water Cleanup system in operation with the reactor at rated temperature Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to place the RWCU system in service at rated RPV temperature.

TASK STANDARD: Examinee placed RWCU Pump A in service by closing RWCU-MO-68, opening RWCU-MO-74, opening RWCU-MO-15, opening RWCU-MO-18 without causing a Group 3 isolation on high RWCU system flow, and starting RWCU Pump A while throttling open RWCU-MO-68 and achieving 200 psig on RWCU-PI-131, IAW Procedure 2.2.66 section 6 using the alternate method.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 3 of 22 Comments (Required for Unsat):

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 4 of 22 Revision Statement:

Rev 1-Updated 9/2018 ILT NRC JPM S2 to new format Rev 2 - Editorial changes per NRC comments Rev 3 - Added JPM S2 to header JPM Information:

1. NRC K/A: 204000 A4.01 (3.1/3.0)

2. Safety Function: 2, Reactor Water Inventory Control

3. Task No.: 204012O0101 - Place the reactor water cleanup system in operation with the reactor at rated temperature

4. PSA Applicability: N/A

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 2.2.66 Reactor Water Cleanup (Rev 118)

Special Conditions, Tools, Equipment:

1. Simulator Set-Up IAW Attachment 1 Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Section 6 of Procedure 2.2.66 marked complete through Step 6.6 Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 5 of 22 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 6 of 22 PERFORMANCE:

START TIME:

Examiner Note: Valves that have oval fluted control switches are throttle MOVs in at least one direction. When fully closing or opening these valves in a throttle direction, the control switch is required to be held for ~5 seconds after fully closed/open indication, as applicable, is received.

Holding switch for 5 seconds is not a critical portion of a JPM step.

1. Procedure Step (Procedure 2.2.66, Reactor Water Cleanup)

Critical Step 6. PLACING SYSTEM IN SERVICE 6.7 ENSURE RWCU-MO-68, RETURN LINE TO RX VLV, closed.

Standard Examinee closed RWCU-MO-68 by placing and holding control switch counter-clockwise to CLOSE and observed green light ON, red light OFF and held control switch in CLOSE for ~5 seconds after red light extinguished.

Cue Notes Holding switch to CLOSE for ~5 seconds after green light extinguished is not a critical portion of this step.

Results SAT UNSAT

2. Procedure Step 6.8 ENSURE output of RWCU-RMC-143, BD VLV 55 FLOW CONTROL, adjusted to zero.

Standard Examinee checked output meter on RWCU-RMC-143 indicated zero.

Cue Notes Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 7 of 22 Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 8 of 22

3. Procedure Step 6.9 ENSURE RWCU-MO-56, BLOWDOWN TO MAIN CNDSR VLV, closed.

Standard Examinee checked RWCU-MO-56 was closed, indicated by green light ON, red light OFF.

Cue Notes Results SAT UNSAT

4. Procedure Step 6.10 ENSURE RWCU-MO-57, DRAIN TO RW COLL TK, closed.

Standard Examinee checked RWCU-MO-57 was closed, indicated by green light ON, red light OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 9 of 22

5. Procedure Step 6.11 ENSURE RWCU-MO-74, DEMIN SUCTION Critical Step BYPASS VLV, open.

Standard Examinee opened RWCU-MO-74 by placing control switch clockwise to OPEN and holding until red light ON and the green light OFF, then releasing.

Cue Notes Results SAT UNSAT

6. Procedure Step 6.12 IF RWCU-MO-15 closed, THEN ENSURE RWCU-MO-18, OUTBD ISOL VLV, closed.

Standard Examinee checked RWCU-MO-18 was closed, indicated by green light ON, red light OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 10 of 22

7. Procedure Step 6.13 ENSURE RWCU-MO-15, INBD ISOL VLV, open.

Critical Step Standard Examinee opened RWCU-MO-15 by placing control switch clockwise to open, then releasing and observing red light ON, green light OFF.

Cue Notes Results SAT UNSAT

8. Procedure Step (Caution is prior to step 6.14)

CAUTION - Group 3 High System Flow isolation may result if RWCU-MO-18 throttled open too quickly.

Standard Examinee read caution.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 11 of 22

9. Procedure Step 6.14 IF RWCU-MO-18, OUTBD ISOL VLV, closed, THEN Critical Step slowly THROTTLE valve full open to equalize RWCU System pressure with reactor pressure.

Standard Examinee opened RWCU-MO-18 slowly by momentarily placing control switch to OPEN, then releasing, and repeating as necessary, while observing pressure indicated on REGEN HX IND RWCU-PI-131 until it reads approximately equal to reactor pressure without causing a Group 3 isolation on high RWCU system flow.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 12 of 22

10. Procedure Step NOTE - Once RWCU pump shutdown after operation without mini-purge for any period of time, mini-purge required for RWCU pump restart.6.15 IF any of following:

MODE 1, 2, or 3.

MODE 4 or 5 and CRD available.

RWCU pump being started after operation without mini-purge.

THEN at CRD System Valve Station (R-903-SE),

PERFORM following to align mini-purge to available RWCU pumps:

6.15.1 ENSURE CRD-189 open.

6.15.2 ENSURE CRD-257, RWCU PUMP A MINI-PURGE ROOT, open.

6.15.3 ENSURE CRD-258, RWCU PUMP B MINI-PURGE ROOT, open.

6.15.4 IF CRD-FI-130A, RWCU PUMP A SEAL PURGE FLOW, not 1 to 2 gpm, THEN ADJUST CRD-FREG-1A, RWCU PUMP A MINI-PURGE FLOW REGULATOR, as follows: (Steps 6.15.4.1 thru 6.15.4.3).

6.15.5 IF CRD-FI-130B, RWCU PUMP B SEAL PURGE FLOW, not 1 to 2 gpm, THEN ADJUST CRD-FREG-1B, RWCU PUMP B MINI-PURGE FLOW REGULATOR, as follows: (Steps 6.15.5.1 thru 6.15.5.3).

Standard Examinee read note and called NLO to complete step 6.15.

Cue NLO reports that all steps of 6.15 are complete, RWCU-FI-130A and RWCU-FI-130B are reading 1.8 gpm.

Booth Operator Align mini-purge by inserting the following remote functions Action to OPEN:

(CU01) RWCU A CRD Mini Purge PCV-FREG-1A (CU02) RWCU B CRD Mini Purge PCV-FREG-1B Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 13 of 22

11. Procedure Step NOTE - 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months RWCU pump run time limit without mini-purge not cumulative (i.e., allowable to run RWCU pump up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months without mini-purge, align mini-purge 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , then restart RWCU pump for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months without mini-purge).

6.15.6 IF both of following:

MODE 4 or 5.

CRD not available.

THEN PERFORM following:

Standard Examinee read note and N/Ad step since the plant is currently in Mode 3 as stated in the Initial Conditions.

Cue Notes Results SAT UNSAT

12. Procedure Step 6.16 In RWCU Pump Rooms (R-931-W), CHECK following for available RWCU pumps:

Pumps free of debris.

Oil reservoir levels satisfactory.

Mechanical seals appear to be operational.

Standard Examinee called NLO to complete pre-start checks for RWCU Pump A per step 6.16.

Cue NLO reports that pre-start checks for RWCU Pump A are complete and SAT, step 6.16 is complete.

Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 14 of 22

13. Procedure Step 6.17 IF RWCU pump maintenance affecting pump integrity performed, THEN perform following:

Standard Examinee determined step 6.17 was N/A due to no maintenance being performed in Initial Conditions.

Cue Notes Results SAT UNSAT

14. Procedure Step 6.18 MAINTAIN REC flow to NRHX less than or equal to 400 gpm.

Standard Examinee read step.

Cue Notes Results SAT UNSAT

15. Procedure Step 6.19 IF in MODE 1, 2, or 3, THEN THROTTLE REC-56, NON REGEN HX OUTLET, to obtain less than or equal to 400 gpm on REC-FI-459, REC TO NON-REGEN HEAT EXCHANGER (R-931-SW).

Standard Examinee called NLO to perform step 6.19.

Cue NLO reports step 6.19 is complete and flow on REC-FI-459 is ~390 gpm.

Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 15 of 22

16. Procedure Step NOTE 1 - Events with lower potential effect on RWCU System chemistry:

Routine RWCU System maintenance.

Normal RWCU System and F/D removal from service.

NOTE 2 - Events with lower potential effect on RWCU System chemistry:

Prolonged RWCU System out of service time.

Intrusive RWCU System maintenance (e.g., piping replacement, etc.).

CAUTION - Resin injection may result from placing RWCU in service using ALTERNATE METHOD after events affecting chemistry.

6.20 SM/CRS determine how RWCU will be placed in service as follows:

6.20.1 IF any of following:

Placing system in service after maintenance affecting chemistry.

System requires heatup.

Resin injection likely.

THEN PLACE system in service per normal method (preferred) in Step 6.21.

6.20.2 IF all of following:

System heatup not required.

Maintenance affecting chemistry not performed.

Resin injection not likely.

THEN PLACE system in service per alternate method in Step 6.22.

Standard Examinee read notes and caution and determined steps 6.20.1 was N/A and that 6.20.2 was required, because CRS has instructed ALTERNATE METHOD per step 6.20.2 is to be used based on Initiating Cue and proceeded to step 6.22.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 16 of 22 Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 17 of 22

17. Procedure Step 6.22 IF placing RWCU in service using alternate method, THEN PERFORM following:

NOTE - Operator needed locally to validate pump low flow trip instrument greater than trip setpoint for pump being started prior to releasing switch.

6.22.1 STATION Operator locally to monitor pump low flow trip instrument for pump being started.

Standard Examinee read note and called and briefed NLO of requirement.

Cue Notes Results SAT UNSAT

18. Procedure Step (Cautions are prior to step 6.22.2)

CAUTION 1 - Pump runout could result from allowing pressure on RWCU-PI-131 to drop below 200 psig.

CAUTION 2 - RWCU pump motor damage could result from repeated RWCU pump starts.

Standard Examinee read cautions.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 18 of 22 Examiner Note: Two-handed operation is required in the next JPM step.

19. Procedure Step 6.22.2 IF starting RWCU PUMP A, THEN PERFORM Critical Step following:

6.22.2.1 PERFORM following concurrently:

a. Place and hold RWCU PUMP A switch to START.

b. Slowly THROTTLE OPEN RWCU-MO-68 to maintain pressure on RWCU-PI-131, REGEN HX IND, as follows:

As steady as possible.

Greater than or equal to 200 psig.

Standard Examinee placed and held RWCU-P-A control switch clockwise to START AND throttled open RWCU-MO-68 by placing its control switch clockwise to OPEN until >

200 psig was indicated on RWCU-PI-131, then released switch for RWCU-MO-68.

Cue Notes Results SAT UNSAT

20. Procedure Step 6.22.2.2 ENSURE RWCU-DPIS-125A, RWCU PUMP DISCHARGE FLOW (R-931-NW on LR 25-2-1),

greater than 2" wg.

Standard Examinee called NLO to verify if RWCU-DPIS-125A was >

2 WG.

Cue NLO reports that RWCU-DPIS-125A is > 2 WG.

Notes Booth Operator On INSIGHT ensure point CUF(14) is above 13.9. There is Action no indication in the control room to monitor DPIS. This point is monitored to ensure adequate RWCU flow.

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 19 of 22 Results SAT UNSAT

21. Procedure Step 6.22.2.3 RELEASE RWCU PUMP A switch Critical Step Standard Examinee released RWCU-P-A control switch.

Cue Notes Results SAT UNSAT

22. Procedure Step 6.22.3 IF starting RWCU PUMP B, THEN PERFORM following:

Standard Examinee determined step was N/A because Initiating Cue stated to start RWCU Pump A, not B.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 20 of 22

23. Procedure Step 6.23 PLACE available F/D(s) in service per one of following:

Procedure 2.5RWCU.F/DA.

Procedure 2.5RWCU.F/DB.

Section 10.

Section 11.

Standard Informed CRS RWCU Pump A has been started IAW procedure 2.2.66 section 6 ALTERNATE METHOD to the point of placing F/Ds in service.

Cue Acknowledge report as CRS Notes JPM is COMPLETE Results SAT UNSAT Stop Time: _____________ Total Time: _____________

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 21 of 22 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC IC319 (performed with S5)

C. Load Schedule File None D. Change the simulator conditions Number Title Tgr TD Sev Ramp Initial as follows:

1. Events None

2. Malfunctions N/A

3. Remotes None

4. Overrides None The IC has the following conditions:

a. Rx Scrammed and Plant has stabilized

b. insert mf rp10a to cause Group 3

c. insert mf rp10b to cause Group 3

d. delete mf rp10a to allow Group 3 to be reset

e. delete mf rp10b to allow Group 3 to be reset

f. RWCU-MO-15 closed

g. RWCU-MO-18 closed

5. Panel Setup h. RWCU Pumps tripped

i. Group 3 isolation has been reset

j. Throttle open RWCU-MO-74 just until red light comes on

k. RWCU Mini-purge isolated per SOP 2.2.66 step 6.5 (RFs for CU01 and CU02 are closed)

Open Insight and monitor point CUF(14). This point will need to be above 13.9 to ensure adequate RWCU flow to avoid the low flow trip setpoint while starting RWCU-P-A.

Rev 2

CNS NRC Exam 2020-4 JPM S2 Page 22 of 22 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following, and inform the examiner when you are ready to begin:

INITIAL CONDITIONS:

1. The plant scrammed from 100% power and is in Mode 3.

2. RWCU Pump A tripped due to a spurious Group 3 isolation signal.

3. The cause of the Group 3 isolation signal has been corrected.

4. Group 3 isolation has been verified AND reset per 2.1.22.

5. No maintenance has been performed on the RWCU System.

6. CRD mini purge was in service to RWCU prior to isolation.

7. ALL steps of Procedure 2.2.66 section 6 up to step 6.7 have been completed.

8. An operator with a copy of the procedure is standing by to perform local steps, as necessary.

INITIATING CUE:

The Control Room Supervisor directs you to place RWCU Pump A in service IAW Procedure 2.2.66, section 6, beginning at step 6.7 AND to use the ALTERNATE METHOD per step 6.22.

Inform the CRS when RWCU Pump A has been started and RWCU pressure is stable.

Another operator will place the RWCU F/Ds in service.

CNS NRC Exam 2020-4 JPM S3 Page 1 of 13 Cooper Nuclear Station Job Performance Measure S-3 Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 2 of 13 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Open MSIVs with Reactor Pressurized (Alternate Path)

Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

FRAME:

PERFORMANCE Validation Time (min): 11 Actual Time (min):

TIME:

JPM RESULTS:(Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to place MSLs in service from an isolated condition with the reactor pressurized.

TASK STANDARD: Examinee opened Outboard MSIVs and began warming main steam lines IAW 2.2.56 section 6, recognized a main steam line leak, isolated the main steam lines IAW Procedure 2.0.3, Conduct of Operations, by closing at least one of the following: MS-MO-74, MS-MO-77, or MS-MO-78.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 3 of 13 Comments (Required for Unsat):

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 4 of 13 Revision Statement:

Rev 1-JPM updated to new format Rev 2 - Editorial changes per NRC comments Rev 3 - Added JPM S3 to header and modified Examiner Note to allow manually triggering Event 3 JPM Information:

1. NRC K/A: 239001 A4.01 (4.2/4.0)

2. Safety Function: 3, Reactor Pressure Control

3. Task No.: 239020P0101 Open MSIVs with Reactor Pressurized

4. PSA Applicability: Top 10 Risk Significant System - PCIS

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 2.2.56, Main Steam System (Rev 53)

2. Procedure 2.0.3, Conduct of Operations (Rev 104)

Special Conditions, Tools, Equipment:

1. Simulator Set-up: See Attachment 1.

Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Procedure 2.2.56, Main Steam System section 6, marked up through step 6.10 complete Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 5 of 13 DIRECTIONS TO EXAMINER:

Note: This is an ALTERNATE PATH JPM. MSL B will rupture as MSLs downstream of inboard MSIVs are being pressurized, requiring manual isolation of MSL warmup steam supply valves.

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed.

You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 6 of 13 PERFORMANCE:

START TIME:

Examiner Note: Valves that have fluted oval control switches are throttle MOVs in at least one direction. When fully closing or opening these valves in a throttle direction, the control switch is required to be held for ~5 seconds after fully closed/open indication, as applicable, is received.

Holding switch for 5 seconds is not a critical portion of a JPM step.

Examiner Note: Order is not critical for the next 4 JPM steps.

1. Procedure Step (Procedure 2.2.56, Main Steam System)

Critical Step 6. Opening MSIVs with Reactor Pressurized 6.11 ENSURE following open:

MS-AO-86A.

MS-AO-86B.

MS-AO-86C.

MS-AO-86D.

Standard Examinee opened each of the following Outboard MSIVs by placing its respective control switch clockwise to OPEN on panel 9-3, and checked its respective red light ON and green light OFF at the control switch and on the Isolation Valve Positions mimic on panel 9-3.

MS-AO-86A.

MS-AO-86B.

MS-AO-86C.

MS-AO-86D.

Cue Notes Verifying position on the Isolation Valve Position mimic on Panel 9-3 is not critical.

Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 7 of 13

2. Procedure Step 6.12 ESTABLISH drain path by ensuring following open:

Critical Step

MS-MO-74

MS-MO-77

MS-MO-79, RO BYPASS VLV Standard Examinee opened each of the following MSL Drain valves by placing its control switch clockwise to OPEN on panel 9-4, and checked its respective red light ON and green light OFF at the control switch and on the Isolation Valve Positions mimic on panel 9-3.

MS-MO-74, INBD ISOL VLV

MS-MO-77, OUTBD ISOL VLV

MS-MO-79, RO BYPASS VLV Cue Notes Control switch for MS-MO-79 must be held in OPEN until valve reaches fully open position.

Verifying position on the Isolation Valve Position mimic on Panel 9-3 is not critical.

Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 8 of 13

3. Procedure Step 6.13 AFTER drain path established ~ 1 minute, THEN Critical Step PERFORM following:

6.13.1 CLOSE MS-MO-79.

Standard Using a suitable chronograph (simulator clock, stopwatch, wristwatch, etc.), the examinee verified at least 50 seconds had elapsed after MS-MO-79 reached fully open in previous step, the examinee CLOSED MS-MO-79, (MSL Drain) RO BYPASS VLV, by placing its control switch counter-clockwise to CLOSE on panel 9-4 and holding until green light ON and red light OFF at the control switch and on the Isolation Valve Positions mimic on panel 9-3, then releasing switch.

Cue Notes Closing MS-MO-79 is the only critical portion of this step, verifying elapsed time is NOT critical.

Verifying position on the Isolation Valve Position mimic on Panel 9-3 is not critical.

Results SAT UNSAT Examiner Note: For the next step, Examiner states that a plant announcement Admitting steam to Main Steam Lines was made to preempt examinee using PA system.

Examiner Note: In the next step, when equalizing header pressure reaches 200 psig, steam leak into MSL Tunnel malfunction will go active, OR Event 3 may be manually triggered at the discretion of the Examiner when equalizing header pressure is > 50 psig.

Booth Operator: If directed by Examiner, when MS-MO-78 has been throttled open, trigger Event 3.

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 9 of 13

4. Procedure Step 6.13 AFTER drain path established ~ 1 minute, THEN Critical Step PERFORM following:

6.13.2 THROTTLE OPEN MS-MO-78 to start pressurizing main steam lines while preventing water hammer and limiting pressurization rate to less than or equal to 100 psi/min.

Standard Examinee slowly opened MS-MO-78, (MSL Drain)

OUTBD THROTTLE VLV on Panel 9-4, by jogging control switch clockwise to open and observing equalizing header pressure indicated on MAIN STEAM MS-PR-81D on panel B (and/or PMIS pt. T015 or DEH HMI throttle pressure) slowly rising 100 psig per minute.

Cue Notes The examinee may monitor any one of multiple indications to determine pressurization rate.

Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 10 of 13

5. Procedure Step: N/A Alternate Path Standard After equalizing header pressure rises to >200 psig, Examinee recognized equalizing header pressure lowering on MAIN STEAM MS-PR-81D on panel B (and/or PMIS pt.

T015 or DEH HMI throttle pressure) and 9-3-1/E-10 AREA HIGH TEMP on and 9-5-1/E1 MAIN STEAM LINE AREA HIGH TEMP CHANNEL A and 9-5-1/E2 MAIN STEAM LINE AREA HIGH TEMP CHANNEL B.

Announced EOP-5A entry condition

Checked SPDS and/or panel 9-21 and determines MSL Tunnel temperature rising on MS-TE-126A/B/C/D, STEAM TUNNEL LINE A/B/C/D Cue IF examinee requests guidance, ask what examinee recommends Notes Results SAT UNSAT Examiner Note: For the next step, the examinee may pull the alarm card for 9-5-1/E-1 or E-2 and be directed to insert a full group 1 isolation or may use 2.0.3 Conduct of Operations.

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 11 of 13

6. Procedure Step Procedure 2.0.3, Conduct of Operations Alternate Path 10.3 SAFETY SYSTEM OPERATION Critical Step 10.3.5 Upon recognition of a failure of automatic action, the CRO shall manually perform those actions necessary to fulfill the safety function and report the completion of the manual action to the CRS as soon as possible.

Standard Examinee isolated MSLs by closing MS-MO-74 and/or MS-MO-77 by placing valve control switch to CLOSE and/or closing MS-MO-78 by placing valve control switch to CLOSE and holding until green light ON and red light OFF before SW Quad area or SE Quad area temperature reaches 195°F on SPDS.

Cue State this JPM is complete when MSLs are isolated.

Notes JPM is Complete Results SAT UNSAT STOP TIME: ____________ TOTAL TIME: __________

Rev 3

CNS NRC Exam 2020-4 JPM S3 Page 12 of 13 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC 322 C. Load Schedule File 2020-4JPMS3 D. Change the simulator conditions Number Title Tgr TD Sev Ramp Initial as follows:

create event 3 zaomspr81d > 0.100(downstream

1. Events of MSL @200psi)

MSL B leak

2. Malfunctions ms03b 3 N/A 100 N/A N/A outside Ctmt Group 1 fail to rp04 A N/A N/A N/A N/A auto isolate

3. Remotes None

4. Overrides None

a. Ensure all four Group 1 Condenser Low Vacuum Bypass switches to BYPASS on panels 9-15 and 9-17. (Part of

5. Panel Setup IC)

b. Ensure Group 1 isolation logic is reset. (Part of IC)

Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.

Rev 3

CNS NRC Exam JPM S3 Page 13 of 13 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is in Mode 3 following a turbine trip at 100% power.

2. Reactor pressure is approximately 675 psig.

3. MSIVs closed on low reactor pressure with the Reactor Mode Switch in RUN.

4. Reactor Mode Switch is now in SHUTDOWN.

5. CRS directed reopening MSIVs to establish the condenser as a heat sink.

6. Procedure 2.2.56, Main Steam System, section 6, has been completed through step 6.10.

INITIATING CUE:

The CRS directs you to reopen MSIVs IAW Procedure 2.2.56, Main Steam System, section 6, beginning at step 6.11.

Inform the CRS when you have completed the task.

CNS NRC Exam 2020-4 JPM S4 Page 1 of 19 Cooper Nuclear Station Job Performance Measure S-4 Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 2 of 19 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Operate RCIC in Pressure Control (Hard Card) (Alternate Path #2)

Revision: 3 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS: (Circle one)

SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat )

SYNOPSIS: This JPM evaluates the examinee's ability to operate RCIC in the pressure control mode per the hard card in procedure 2.2.67.1, Reactor Core Isolation Cooling System Operations.

TASK STANDARD Examinee aligned RCIC in a recirculation lineup in accordance with Procedure 2.2.67.1, recognized the flow controller automatic mode failed to raise RCIC turbine speed >2200 rpm, and secured RCIC turbine.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 3 of 19 Comments (Required for Unsat):

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 4 of 19 Revision Statements:

Rev 1-2018 Audit JPM updated to new format Rev 2 - Editorial changes per NRC comments Rev 3 - Incorporated NRC prep week comments JPM Information:

1. NRC K/A: 217000 A4.01 (3.7/3.7)

2. Safety Function: 4, HEAT REMOVAL from the CORE

3. Task No.: 217003O0101, Manually Initiate RCIC System

4. PSA Applicability: N/A

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 2.2.67.1, Reactor Core Isolation Cooling System Operations (Rev 45)

2. Operations Desk Guide (ODG) 2, Skill of the Craft Desk Guide (Rev 6)

Special Conditions, Tools, Equipment:

1. Simulator set up IAW Attachment 1 Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Procedure 2.2.67.1, Attachment 1, RCIC System Operation Hardcard (printed copy for each examinee)

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 5 of 19 DIRECTIONS TO EXAMINER:

Note: This is an ALTERNATE PATH JPM. The examinee will be unable to raise RCIC turbine speed above 2200 rpm, requiring RCIC turbine to be shut down IAW Procedure 2.2.67.1.

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 6 of 19 PERFORMANCE:

START TIME:

1. Procedure Step (Procedure 2.2.67.1 Attachment 1 RCIC System Operation Hardcard)

2. RPV PRESSURE CONTROL WITH RCIC 2.1 ENSURE RCIC auto initiation signal is clear.

Standard Checked RPV water level and verified level above -42 inches, 9-4-1/A-1 RCIC LOGIC ACTUATED alarm clear and INITIATION SIGNAL amber light on apron section OFF.

Cue Notes Results SAT UNSAT

2. Procedure Step 2.2 OPEN RCIC-MO-33.

Critical Step Standard Rotated ECST TEST LINE SHUTOFF VLV MO 33 control switch clockwise to OPEN position and released and checked Red light ON, Green light OFF.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 7 of 19

3. Procedure Step 2.3 START GLAND SEAL VACUUM PUMP.

Critical Step Standard Rotated GLAND SEAL VACUUM PUMP control switch clockwise to START and checked Red light ON, Green light OFF.

Cue Notes Results SAT UNSAT

4. Procedure Step 2.4 OPEN RCIC-MO-132.

Critical Step Standard Rotated TURB OIL COOLING WTR SUPP VLV MO 132 control switch clockwise to OPEN position and released and checked Red light ON, Green light OFF.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 8 of 19

5. Procedure Step 2.5 OPEN RCIC-MO-30.

Critical Step Standard Rotated and held TEST BYP TO ECST VLV MO 30 control switch clockwise to OPEN position until valve indicated open, red light ON green light OFF, then released.

Cue Notes When examinee opens this valve 9-4-1/C-2 RCIC PRESS MAINT SUPPY LOW PRESSURE alarm is expected to come in. Step 2.6 clears this alarm. During validation, some operators stated this and moved to the next step.

Some operators may address this alarm. Addressing 9 1/C-2 RCIC PRESS MAINT SUPPY LOW PRESSURE is not critical to this task.

Results SAT UNSAT

6. Procedure Step 2.6 OPEN RCIC-MO-131.

Critical Step Standard Rotated STM SUPP TO TURB VLV MO 131 control switch clockwise to OPEN position and checked red light ON, green light OFF.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 9 of 19

7. Procedure Step 2.7 ADJUST RCIC-FIC-91, FLOW CONTROLLER, to maintain desired RPV pressure.

Standard Examinee attempted to control RCIC flow with the Controller in AUTO.

Cue Notes Flow remains at ~200 gpm due to malfunction.

Results SAT UNSAT

8. Procedure Step 2.7.1 IF less than 300 gpm and flow oscillations occurring, THEN PLACE RCIC-FIC-91 to MANUAL.

Standard Examinee determined step is N/A due to no flow oscillations occurring.

Cue Notes Flow is 200 and there are no flow oscillations occurring.

Results SAT UNSAT

9. Procedure Step N/A Alternate Path Standard Reported to CRS that RCIC controller has failed in automatic.

Cue If the examinee asks for directions, respond by asking examinee what they recommend.

Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 10 of 19 NOTE to Examiner: It is Operations expectation that the examinee will recognize the failure of RCIC flow controller in auto and will attempt to raise RCIC turbine speed by manual operation of RCIC flow control. Taking manual control of RCIC flow controller is Skill of the Craft (SOC database item ID 74).

Procedure steps are listed as reference, and the Examinee may not refer to the procedure.

10. Procedure Step Procedure 2.2.67.1, Step 5.24.7 Alternate Path 5.24.7 IF transfer to RCIC-FIC-91 MANUAL control desired, THEN PERFORM following:

5.24.7.1 DEPRESS RCIC-FIC-91 A/M button until light next to "M" lit.

Standard Examinee pressed A/M button and observed light next to M lit.

Cue Notes Taking manual control of failed controller is Skill of the Craft.

Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 11 of 19 NOTE to Examiner: Taking RCIC to TURB TEST operating mode is Skill of the Craft (ODG-2, Approved List 1 item 74). Procedure steps are listed as reference and the Examinee may not refer to the procedure. Examinee may or may not perform all steps below due to inability to transfer RCIC-FIC-91 to Manual and may proceed to shutting RCIC down.

11. Procedure Step 5.24.8 IF transfer to RCIC-SIC-100 control desired, Alternate Path THEN PERFORM following:

5.24.8.1 DEPRESS RCIC-FIC-91 A/M button until light by "M" lit.

5.24.8.2 ENSURE FLOW.V displayed.

CAUTION - Turbine speed may change significantly on transfer to TURB TEST if mis-match exists between RCIC-SIC-100 and RCIC-FIC-91.

5.24.8.3 Using RCIC-SIC-100 adjusting knob, ADJUST TEST. V to match FLOW.V on RCIC-FIC-91 as close as possible.

5.24.8.4 PLACE TURB SPEED TEST control switch to TURB TEST.

Standard Examinee recognized that controller RCIC-FIC-91 did not go into manual in previous step by observing light next to M not lit.

Examinee checked ADJUST TEST. V on RCIC-SIC-100 matched FLOW.V on RCIC-FIC-91, and placed TURB SPEED TEST control switch clockwise to TURB TEST.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 12 of 19 NOTE to Examiner: Adjusting RCIC controller is Skill of the Craft (ODG-2, Approved List 1 item 74). Procedure steps are listed as reference and the Examinee may not refer to the procedure. Examinee may or may not perform next step due to inability to transfer RCIC-FIC-91 to Manual and may proceed to shutting RCIC down.

12. Procedure Step 5.26.8 PERFORM following concurrently to control Alternate Path RCIC flow and discharge pressure:

IF not injecting to RPV, THEN THROTTLE RCIC-MO-30, TEST BYPASS TO ECST VLV, to maintain discharge pressure within 100 psig of RPV pressure.

ADJUST RCIC-SIC-100 to desired flow rate by rotating adjusting knob.

Standard Attempted to raise demand on TEST CONTROLLER RCIC-SIC-100 by turning adjusting knob clockwise and recognized RCIC speed did not rise.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 13 of 19

13. Procedure Step Procedure 2.2.67.1, Precaution and Limitation step 2.5 Alternate Path RCIC turbine damage and repetitive exhaust check valve slamming may occur below 2200 rpm.

Standard Examinee identified that RCIC was required to be shut down due to potential damage from operating below 2200 rpm.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 14 of 19

14. Procedure Step (Procedure 2.2.67.1 Attachment 1 RCIC System Alternate Path Operation Hardcard)

Critical Step 3.1 DEPRESS and HOLD TURBINE TRIP pushbutton.

3.1.1 DEPRESS INITIATION SIGNAL RESET pushbutton.

3.1.1.1 IF amber INITIATION SIGNAL indicating light off, THEN CLOSE RCIC-MO-131, STM TO TURB VLV.

a. VERIFY RCIC-MO-14 cycles closed and open to reset TURBINE TRIP & THROTTLE VALVE.

b. VERIFY TURBINE TRIP &

THROTTLE VALVE reset.

3.1.1.2 IF amber INITIATION SIGNAL indicating light remains on, THEN ENSURE RCIC-MO-131 remains open.

3.2 RELEASE TURBINE TRIP button.

Standard Examinee tripped RCIC by pressing and holding TURB TRIP button, closing RCIC-MO-131 by placing STM SUPP TO TURB VLV MO 131 to CLOSE and checking Green light ON and Red light OFF, and verified Turbine trip and throttle valve reset by checking TRIP VALVE OPER POSITION MO 14 cycled closed (Green light ON, Red light OFF) then open (Red light ON, Green light OFF),

and checking TURBINE TRIP & THROTTLE VALVE Red light ON and Green light OFF, and then released the RCIC trip button.

Cue Notes Only securing steam to the RCIC turbine is critical.

Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 15 of 19

15. Procedure Step 3.3 ENSURE RCIC-MO-30 closed.

Alternate Path Standard Examinee checked that RCIC-MO-30 was CLOSED by checking Green light ON, Red light OFF.

Cue Notes Results SAT UNSAT

16. Procedure Step 3.4 IF initiation signal reset, Alternate Path THEN PERFORM following:

3.4.1 ENSURE RCIC-MO-21 closed.

Standard Examinee checked RCIC-MO-21 was CLOSED by checking Green light ON, Red light OFF.

Cue Notes Results SAT UNSAT Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 16 of 19

17. Procedure Step 3.4 IF initiation signal reset, Alternate Path THEN PERFORM following:

3.4.2 CLOSE RCIC-MO-132.

Standard Examinee closed RCIC-MO-132 by placing TURB OIL COOLING WTR SUPP VLV MO 132 to CLOSE and checked Green light ON, Red light OFF.

Cue Notes Results SAT UNSAT

18. Procedure Step 3.4 IF initiation signal reset, Alternate Path THEN PERFORM following:

3.4.3 STOP Gland Seal Vacuum Pump.

Standard Examinee Stopped the gland seal Vacuum pump by placing GLAND SEAL VACUUM PUMP switch to stop and checked Green light ON, Red light OFF.

Cue Notes Inform the examinee that the JPM is complete Results SAT UNSAT STOP TIME: ____________ TOTAL TIME: __________

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 17 of 19 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC 321 (Perform with JPM S-6)

C. Run Schedule File None D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

1. Triggers None Failure to Auto

2. Malfunctions RC01 start.

A N/A N/A N/A N/A Flow controller RC04 A N/A 0 N/A N/A failure

3. Remotes None RCIC Turb

4. Overrides zdircicsws20 Speed Test NORM switch RCIC flow zdircicamsw controller AUTO Auto/Man Ensure the following is built into the IC or perform the following:

a. Place Simulator in RUN.

b. Manually scram the Reactor using 9-5 pushbuttons. Leave the Reactor Mode Switch in RUN until low Reactor pressure Group 1 isolation is received, then place RMS in SHUTDOWN.

c. Trip both RFPs when RPV water level is rising.

d. Place HPCI AOP in PTL.

e. Place MSIV control switches in CLOSE.

5. Panel Setup f. Maintain RPV water level below +30" on the Narrow Range and above

-20" on the Wide Range.

g. Let the simulator run until the first SRV opens.

h. Reset all high level trip signals (if present).

i. Place the Simulator in FREEZE.

j. Insert Malfunctions and Overrides.

Booth Operator note: CRD-V-29 is open to assist with RPV Level control.

Monitor RPV level throughout to maintain +30" on the Narrow Range and above -20" on the Wide Range.

Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 18 of 19 Schedule file Time Event Action Description 00:00:00 create event 4 zlorcicsws3(2) ==1 RCIC-MO-131 red light ON 00:00:00 create event 14 zaorcicsi3067 > 0.166 RCIC speed > 1000 rpm 00:00:00 insert malfunction rc04 to 0 on event 4 RCIC flow controller failure 00:00:00 insert override zaorcic3067 to 1900 in 10 RCIC speed indicator on event 14 00:00:00 create event 24 et_array(4) == 1 & Event 4 true & RCIC-zlorcicsws3(2) == 0 MO-131 red light OFF 00:00:00 insert malfunction rc01 RCIC failure to auto start 00:00:00 insert override zdircicamsw to AUTO RCIC flow controller Auto/Manual 00:00:00 insert override zdircicsws20 to NORM RCIC turbine speed test 00:00:00 create event 25 et_array(24) ==1 l RCIC- MO- 131, 15, or zlorcicsws1(2) ==0 l zlorcicsws2(2) == 0 16 closed or Trip button l zlorcicsws17 == 1 depressed 25 delete override zaorcicsi3067 Rev 3

CNS NRC Exam 2020-4 JPM S4 Page 19 of 19 ATTACHMENT 2 Directions to Examinee:

Read the following, and inform the Examiner when you are ready to begin.

INITIAL CONDITIONS:

1. The Reactor is shutdown following a scram.

2. Reactor water level is being controlled by another licensed operator.

3. Reactor pressure is currently being maintained by Low-Low Set.

4. Suppression Pool Cooling will be placed in service by another licensed operator.

5. Current pressure band is 800 - 1050 psig reactor pressure.

INITIATING CUE:

The Control Room Supervisor directs you to place RCIC in the pressure control mode using Procedure 2.2.67.1 Att. 1, RCIC System Operation hard card.

Inform the CRS when RCIC is operating in the pressure control mode.

CNS NRC Exam 2020-4 JPM S5 Page 1 of 15 Cooper Nuclear Station Job Performance Measure S-5 Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 2 of 15 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Respond to Fuel Element Failure - Align Sump Pumps IAW 5.2FUEL Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS:(Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to align Reactor Building and Control Building sump pumps IAW Procedure 5.2FUEL, Fuel Failure.

TASK STANDARD: Examinee placed all sump pumps for sumps A, B, D, E, and L in OFF, started Sump Pump C-1 and/or C-2, and when Sump C level was less than 9.5 feet, placed Sump Pump C-1 and C-2 in OFF IAW Procedure 5.2FUEL, Fuel Failure, Attachment 2.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 3 of 15 Comments (Required for Unsat):

Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 4 of 15 Revision Statement:

Rev 0-New JPM Rev 1 - Editorial changes per NRC comments Rev 2 - Added panel setup instructions to have copy of EOP-5A available for examinee to access, if desired JPM Information:

1. NRC K/A: 295036 EA1.01 (3.2/3.3), EK3.04 (3.1/3.4); 290001 A4.10 (3.4/3.3),

K4.03 (2.8/2.9)

2. Safety Function: 5, Containment Integrity

3. Task No.: 200041C0401, Respond to Fuel Element Failure

4. PSA Applicability: N/A

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 5.2FUEL, Fuel Failure (Rev 22)

Special Conditions, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Procedure 5.2FUEL, Fuel Failure, Attachment 2, Actions to Minimize Rad Material Release Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 5 of 15 DIRECTIONS TO EXAMINER:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 6 of 15 PERFORMANCE:

START TIME:

1. Procedure Step (Procedure 5.2 Fuel, Fuel Failure)

Critical Step Attachment 2, Actions to Minimize Rad Material Release

1. Place following sump pumps to OFF (VBD-S):

1.1 Both Reactor Building Floor Drain Sump A pumps.

1.1.1 SUMP PUMP A-1.

1.1.2 SUMP PUMP A-2.

Standard Examinee placed control switches for Sump Pumps A-1 and A-2 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 7 of 15

2. Procedure Step 1. Place following sump pumps to OFF (VBD-S):

Critical Step 1.2 Both Reactor Building Floor Drain Sump B pumps.

1.2.1 SUMP PUMP B-1.

1.2.2 SUMP PUMP B-2.

Standard Examinee placed control switches for Sump Pumps B-1 and B-2 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 8 of 15 Examiner Note: Examinee may pull the High-High Level alarm card S-1/A-3 Reactor Building C Sump Hi-Hi Level and place the C-1 and C-2 sump pumps to run to lower the sump level before continuing with this step. This will satisfy step 8 and 9 critical steps.

3. Procedure Step 1. Place following sump pumps to OFF (VBD-S):

Critical Step 1.3 Both Reactor Building Floor Drain Sump C pumps.

1.3.1 SUMP PUMP C-1.

1.3.2 SUMP PUMP C-2.

Standard Examinee placed control switches for Sump Pumps C-1 and C-2 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes This step is only critical if SUMP PUMPs C-1 and C-2 are not started in JPM step 8.

Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 9 of 15

4. Procedure Step 1. Place following sump pumps to OFF (VBD-S):

Critical step 1.4 Both Reactor Building Floor Drain Sump D pumps.

1.4.1 SUMP PUMP D-1.

1.4.2 SUMP PUMP D-2.

Standard Examinee placed control switches for Sump Pump D-1 and D-2 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes Results SAT UNSAT

5. Procedure Step 1. Place following sump pumps to OFF (VBD-S):

Critical Step 1.5 Both Reactor Building Equipment Drain Sump E pumps.

1.5.1 SUMP PUMP E-1.

1.5.2 SUMP PUMP E-2.

Standard Examinee placed control switches for Sump Pumps E-1 and E-2 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 10 of 15

6. Procedure Step 1.6 Operate sump pumps above, only as necessary, to maintain area below Maximum Safe Operating Water Level per Secondary Containment Control EOP.

Standard Examinee checked following sump levels on VBD-S:

RW-LI-828, FLOOR DRAIN AREA NW

RW-LI-829, FLOOR DRAIN AREA NE

RW-LI-830, FLOOR DRAIN AREA SW

RW-LI-831, FLOOR DRAIN AREA SE Cue Notes Results SAT UNSAT

7. Procedure Step 1.6 Operate sump pumps above, only as necessary, to maintain area below Maximum Safe Operating Water Level per Secondary Containment Control EOP.

Standard Examinee determined operation of sump pumps for Sump A, B, D and E not required due to Sump A, B, D and E levels below Maximum Safe Operating limit of 9.5 feet.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 11 of 15

8. Procedure Step 1.6 Operate sump pumps above, only as necessary, Critical Step to maintain area below Maximum Safe Operating Water Level per Secondary Containment Control EOP.

Standard Examinee determined RW-LI-830, FLOOR DRAIN AREA SW was above Maximum Safe Operating limit of 9.5 feet and placed control switch for SUMP PUMP C-1 and/or SUMP PUMP C-2 clockwise to RUN, checked red light On and green light Off for sump pump(s) started, and checked level on RW-LI-830, FLOOR DRAIN AREA SW was lowering.

Cue Notes Results SAT UNSAT

9. Procedure Step 1.6 Operate sump pumps above, only as necessary, Critical Step to maintain area below Maximum Safe Operating Water Level per Secondary Containment Control EOP.

Standard Examinee checked level on RW-LI-830, FLOOR DRAIN AREA SW was lowered below 9.5 feet, then placed control switch for Sump Pump(s) started in JPM step 8 counter-clockwise to OFF and checked respective green lights ON, red lights OFF.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 12 of 15

10. Procedure Step (Procedure 5.2 Fuel, Fuel Failure)

Critical Step Attachment 2, Actions to Minimize Rad Material Release

2. Place both Control Building Sump L pumps to OFF (VBD-S).

2.1 SUMP PUMP L-1.

2.2 SUMP PUMP L-2.

Standard Examinee placed control switch for Sump Pumps L-1 and L-2 counter-clockwise to OFF and checked green light ON, red light OFF.

Cue Notes Results SAT UNSAT

11. Procedure Step (Procedure 5.2 Fuel, Fuel Failure)

Attachment 2, Actions to Minimize Rad Material Release

3. IF Control Building Sump L level must be lowered, THEN perform following:

3.1 Operate Sump L pumps only, as necessary, to lower sump to desired level.

Standard Examinee determined operation of Sump L pumps not required by observing annunciator S-1/E-1, Control Bldg Sump L Hi-Hi Level not On.

Cue Inform the examinee This JPM is complete Examinee should not perform the steps on the front panel.

Notes JPM is Complete Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 13 of 15 STOP TIME: ____________ TOTAL TIME: __________

Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 14 of 15 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC IC319(performed with S2)

C. Load Schedule File 2020-4JPMS5 D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

create event 5 zdirwswc1(2) == 1 l zdirwswc2(2) == 1 NOTE - the value (modifies overrides and PMIS to cause C Sump level to for variable trend downward when either Sump Pump C1 or C2 is LDMSUMPC can be placed to RUN)

1. Events used to add water to create event 15 when et_array(5) ==1 and zdirwswc1(2) ==

Sump C without 1 and zdirwswc2(2) == 1(modifies overrides and PMIS to overriding I/O. cause C Sump level trend to slow when Sump Pump C1 or C2 taken to off) 2.Malfunctions None

3. Remotes None SW Quad/Sump

4. Overrides N397(PMIS) N/A N/A 10 N/A N/A 1C RW-LT-830 Sump C Level zaorwli830 N/A N/A 10 N/A N/A VBD-S Sump C level Hi-p4908 N/A N/A ON N/A N/A Hi annunciator

a. Load schedule file

b. Acknowledge annunciators

5. Panel Setup

c. Ensure a copy of EOP-5A is available near Panel C / VBD-H in case the examinee needs to reference it for MSO water level Note: If this JPM is to be performed more than once, a SNAPSHOT can be taken after the panel setup is complete.

Rev 2

CNS NRC Exam 2020-4 JPM S5 Page 15 of 15 ATTACHMENT 2 Directions to Examinee:

Read the following and inform the evaluator when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is in Mode 3.

2. Chemistry results indicate reactor coolant activity is 4.2 µCi/gm, DOSE EQUIVALENT I-131.

3. Procedure 5.2FUEL, Fuel Failure, has been entered.

4. There is a leak from RHR Pump B suction piping into the RHR B/D pump room.

INITIATING CUE:

The CRS directs you to align all sump pumps IAW Procedure 5.2FUEL, Fuel Failure, , Actions to Minimize Rad Material Release.

Inform the CRS when you have completed the task.

CNS NRC Exam 2020-4 JPM S6 Page 1 of 18 Cooper Nuclear Station Job Performance Measure S-6

CNS NRC Exam 2020-4 JPM S6 Page 2 of 18 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Energize 4160V critical Bus 1G from emergency station service XFMR Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 15 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the Examinee's ability to transfer 4160V Bus 1G from 4160V Bus 1B to the ESST.

TASK STANDARD: Examinee transferred 4160 Bus G, from its normal power supply 4160 Bus B to the ESST by closing 1GS, placing 1FS in PTL, and placing control switch for 1GB to TRIP IAW 2.2.18.1 Section 14.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant (RCA )

Simulate x Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM S6 Page 3 of 18 Comments(Required for Unsat):

CNS NRC Exam 2020-4 JPM S6 Page 4 of 18 Revision Statements:

Rev 0-New JPM Rev 1 - Editorial changes per NRC comments Rev 2 - Modified task standard detailing critical steps JPM Information:

1. NRC K/A Number and rating: 262001 K4.05 (3.4/3.6); K5.01(3.1/3.4) K4.06 (3.6/3.9) A4.01 (3.4/3.7)

2. Safety Function: 6, ELECTRICAL

3. Task No: 262025C0101 Energize 4160V Critical Bus 1F and 1G from emergency station service XFMR

4. PSA Applicability: (EE) Emergency AC Power (including DC Systems)

5. Critical Steps stated in procedure steps in bold References (include revision number if applicable):

1. SOP 2.2.18.1 4160V AUXILIARY POWER DISTRUBUTION SYSTEM (REV 2)

Special Conditions, Tools, Equipment:

1. Simulator Set-Up IAW Attachment 1 Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. SOP 2.2.18.1 Section 14

CNS NRC Exam 2020-4 JPM S6 Page 5 of 18 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM S6 Page 6 of 18 PERFORMANCE:

START TIME:

1. Procedure Step: 14. TRANSFER 4160V BUS 1G FROM BUS 1B TO EMERGENCY TRANSFORMER 14.1 IF in MODE 1, 2, or 3, THEN ENSURE risk has been assessed per Procedure 0.50.5 or 0-CNS-WM-104 for placing Breaker 1FS switch, EMERGENCY XFMR BKR, for Bus 1F in PULL-TO-LOCK.

Standard Examinee determined plant in Mode 3 and risk has been assessed for this task per Procedure 0.50.5 or 0-CNS-WM-104 from initial conditions.

Cue Notes Results SAT UNSAT

2. Procedure Step CAUTION - Panel CDP-1B voltage is limited to less than or equal to 264V Standard Examinee reviewed caution.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 7 of 18

3. Procedure Step: 14.2 IF any of following met,

ESST energized from Transformer T-6.

Breakers are being cycled to demonstrate OPERABILITY and 4160V Bus G will be immediately transferred back to 4160V Bus B.

THEN MARK Step 14.3 N/A.

Standard Examinee determined breakers are being cycled to demonstrate OPERABILITY and 4160V Bus G will be immediately transferred back to 4160V Bus B stated in the Initial Conditions Section and marked step 14.3 N/A.

Cue Notes Results SAT UNSAT

4. Procedure Step: 14.3 CONTACT Engineering to assist evaluation to determine if tap change on CDP1B Supply Transformer required.

Standard Examinee marked step as N/A from previous step.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 8 of 18

5. Procedure Step: 14.4 ENSURE ESST energized.

Standard Examinee verified ESST energized by observing EMERGENCY XFMR VOLTAGE meter ~4400V on Board C.

Cue Notes Results SAT UNSAT

6. Procedure Step: 14.5 IF in MODE 1, 2, or 3, THEN SM/CRS PERFORM following:

14.5.1 DECLARE both off-site circuits inoperable.

14.5.2 ENTER applicable Condition and Required Action of LCO 3.8.1, AC Sources - Operating.

Standard Examinee determined SM had declared both off-site circuits inoperable and entered applicable Condition and Required Action of LCO 3.8.1, AC Sources - Operating, stated in the Initial Conditions Section.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 9 of 18

7. Procedure Step: 14.6 ENSURE SW Pump B running or not selected for Standby.

14.7 ENSURE SW Pump D running or not selected for Standby.

14.8 ENSURE REC Pump C running or not selected for Standby.

14.9 ENSURE REC Pump D running or not selected for Standby.

Standard Examinee verified components running, per board indications and/or initial conditions.

Cue Notes Results SAT UNSAT

8. Procedure Step: 14.10 PLACE SYNCH SWITCH 1GS in 1GS.

Critical step Standard Inserted switch handle and placed SYNCH SWITCH 1GS in 1GS by turning switch clockwise to 1GS.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 10 of 18

9. Procedure Step NOTE 1 - OPPD maintains 69 kV line at 8 MWe available and 10.24 MWe for at least 10 minutes.

NOTE 2 - Breaker 1GB will automatically trip when Breaker 1GS closes.

CAUTION - Maximum load on Emergency Transformer is 10.7 MWe.

Standard Examinee reviewed notes and caution.

Cue Notes Results SAT UNSAT

10. Procedure Step: 14.11 CLOSE Breaker 1GS, EMERGENCY XFMR BKR.

Critical step Standard Closed Breaker 1GS, EMERGENCY XFMR BKR, by placing switch clockwise to close and observing red light ON, green light OFF, then releasing.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 11 of 18

11. Procedure Step: 14.12 VERIFY Breaker 1GS switch spring returns to NORMAL AFTER CLOSE.

Standard Examinee verified Breaker 1GS switch spring returned to NORMAL AFTER CLOSE by observing switch return to center position.

Cue Notes Results SAT UNSAT

12. Procedure Step: 14.13 VERIFY Breaker 1GS switch red flagged.

Standard Examinee verified Breaker 1GS switch red flagged by observing red flag indicated in switch window.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 12 of 18

13. Procedure Step: 14.14 VERIFY Breaker 1GB, BUS 1B TIE BKR, automatically tripped.

Standard Examinee verified Breaker 1GB automatically tripped by observing green light ON and the red light OFF at the control switch.

Cue Notes Results SAT UNSAT

14. Procedure Step: 14.15 VERIFY Breaker 1GB amber tripped light lit.

Standard Examinee verified that 1GB amber light above the control switch is lit.

Cue Notes Results SAT UNSAT

15. Procedure Step: 14.16 VERIFY Annunciator C-4/B-1, 4160V BUS 1G BKR 1GB TRIP, alarms Standard Examinee verified that Annunciator C-4/B-1 alarmed and acknowledged the alarm.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 13 of 18

16. Procedure Step: 14.17 IF any of following met:

4160 Bus 1G voltage less than 3950V.

Panel CDP-1B voltage greater than 264V.

THEN PEFORM any of following until voltage conditions met:

Standard Examinee determined steps 14.17.1 through 14.17.4 were N/A by observing 4160 Bus 1G voltage ~4360V (>3950V) and CDP-1B voltage ~245V (<264V) and marked steps N/A.

Cue Notes None Results SAT UNSAT

17. Procedure Step: 14.18 IF reactor in MODE 1, 2, or 3, THEN PLACE switch for Breaker 1FS in Critical step PULL-TO-LOCK.

Standard Examinee determined reactor was in Mode 3 from Initial Conditions Section, Placed switch for Breaker 1FS in PULL-TO-LOCK by pulling upward and turning switch counter-clockwise, then releasing and ensuring switch handle remained in the same position.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 14 of 18

18. Procedure Step: 14.19 PLACE Breaker 1GB switch in TRIP.

Critical step Standard Examinee placed switch for Breaker 1GB switch in TRIP by turning switch counter-clockwise to TRIP, then releasing.

Cue Notes Results SAT UNSAT

19. Procedure Step: 14.20 VERIFY Breaker 1GB switch spring returns to NORMAL AFTER TRIP.

Standard Examinee verified Breaker 1GB switch spring returned to NORMAL AFTER TRIP by observing switch return to center position when released.

Cue Notes Results SAT UNSAT

20. Procedure Step: 14.21 VERIFY Breaker 1GB switch green flagged.

Standard Examinee verified breaker 1GB switch green flagged by observing green flag indicated in switch window.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 15 of 18

21. Procedure Step: 14.22 VERIFY Breaker 1GB amber tripped light off.

Standard Examinee verified that 1GB amber light above the control switch is OFF.

Cue Notes Results SAT UNSAT

22. Procedure Step: 14.23 VERIFY Annunciator C-4/B-1 clears.

Standard Examinee verified Annunciator C-4/B-1 cleared by observing alarm slow flash and audible reset tone, then reset annunciator.

Cue Notes Results SAT UNSAT

23. Procedure Step: 14.24 PLACE SYNCH SWITCH 1GS in OFF.

Standard Examinee placed SYNCH SWITCH 1GS in OFF by turning switch counter-clockwise to OFF.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S6 Page 16 of 18

24. Procedure Step: Inform the CRS that Bus G 4160 power is supplied by the ESST.

Standard Examinee informed the CRS that the ESST is supplying 4160 Bus G.

Cue Notes JPM is Complete.

Results SAT UNSAT Stop Time: _____________ Total Time: _____________

CNS NRC Exam 2020-4 JPM S6 Page 17 of 18 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC 321(Perform with JPM S-6)

C. Run Schedule File None D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

1. Triggers None

2. Malfunctions

3. Remotes

4. Overrides Ensure the following is built into the IC or perform the following:

a. Ensure SW Pumps A, B, and D running with A and D selected for Standby.

5. Panel Setup b. Ensure REC Pumps A, C, and D running with A and D selected for Standby.

c. Ensure SYNCH SWITCH 1GS is NOT in GS.

d. Ensure switch handle is removed from SYNCH SWITCH 1GS.

CNS NRC Exam 2020-4 JPM S6 Page 18 of 18 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the examiner when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is in Mode 3.

2. 4160V Bus 1G is being powered from 4160V Bus 1B.

3. ESST is energized from 69kV line.

4. 4160V Bus 1G is to be transferred from 4160V Bus 1B to the ESST to demonstrate operability of breakers 1GB and 1GS.

5. 4160V Bus 1G will be immediately transferred back to 4160V Bus B.

6. Risk has been assessed per Procedure 0.50.5 and 0-CNS-WM-104 for placing Breaker 1FS switch, EMERGENCY XFMR BKR, for Bus 1F in PULL-TO-LOCK.

7. SM has declared both offsite circuits inoperable and entered applicable Condition and Required Action of LCO 3.8.1, AC Sources.

8. REC Pumps A, C, and D are running, with pumps A and D in Standby.

9. SW Pumps A, B, and D are running, with pumps A and D in Standby.

INITIATING CUES:

The CRS directs you to transfer 4160KV Bus 1G from 4160KV Bus 1B to the ESST per 2.2.18.1 Section 14.

Inform the CRS when you have completed Section 14 of 2.2.18.1.

CNS NRC Exam 2020-4 JPM S7 Page 1 of 10 Cooper Nuclear Station Job Performance Measure S-7

CNS NRC Exam 2020-4 JPM S7 Page 2 of 10 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Defeat RPS Logic Trips During Failure-to-Scram (5.8.3) (Restoration)

Revision number: 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 5 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the trainee's ability to remove RPS PTMs (jumpers) and reset the reactor scram.

TASK STANDARD: Examinee removed only RPS bypass PTMs and reset the reactor scram in accordance with Procedure 5.8.3,Alternate Rod Insertion Methods, section 5.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Kyle Grillis Date: 3-18-2020 Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM S7 Page 3 of 10 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM S7 Page 4 of 10 Revision Statement:

Rev 0 - Updated JPM SKL034-21-79 (63384) Rev 0 to new format Rev 1 - Added instructions to panel setup to place a marked up ATWS hard card, EP 5.8.3 Attachment 1 on usual cart at Panel 9-5 JPM Information:

1. NRC K/A: 212000 K4.12 (3.9/4.1)

2. Safety Function: 7, Instrumentation

3. Task No.: 212019G0501, Defeat RPS Logic Trips during Failure to Scram (5.8.3)

4. PSA Applicability: Top 10 Risk Significant System - RPS

5. Critical Steps stated in the procedure step in bold

References:

1. Procedure 5.8.3, Alternate Rod Insertion Methods (Rev 17)

Special Conditions, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Applicant Cue Sheet Handouts:

1. Attachment 2 - Applicant Cue Sheet

2. Procedure 5.8.3, Alternate Rod Insertion Methods (Rev 17)

CNS NRC Exam 2020-4 JPM S7 Page 5 of 10 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed.

You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM S7 Page 6 of 10 PERFORMANCE:

START TIME:

1. Procedure Step: 5.6.1 Prior to removing RPS LOGIC TRIP BYPASS jumpers, insert a manual scram.

Standard At 9-5 Panel, depressed RX SCRAM CHAN A and CHAN B buttons.

Cue Notes Results SAT UNSAT

2. Procedure Step: 5.6.2 Remove RPS LOGIC TRIP BYPASS jumper between Terminals DD-41 and DD-42 (BAY-1, PNL 9-15).

Critical Step Standard In Panel 9-15 BAY-1, removed jumper between Terminals DD-41 and DD-42.

Cue Notes Removal of a MSIV LOW WATER LEVEL ISOLATION BYPASS jumper constitutes failure of this critical step.

Results SAT UNSAT

3. Procedure Step: 5.6.3 Remove RPS LOGIC TRIP BYPASS jumper between Terminals BB-41 and BB-42 (BAY-3, PNL 9-15).

Critical Step Standard In Panel 9-15 BAY-3, removed jumper between Terminals BB-41 and BB-42.

Cue Notes Removal of a MSIV LOW WATER LEVEL ISOLATION BYPASS jumper constitutes failure of this critical step.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S7 Page 7 of 10

4. Procedure Step: 5.6.4 Remove RPS LOGIC TRIP BYPASS jumper between Terminals DD-41 and DD-42 (BAY-1, PNL 9-17).

Critical Step Standard In Panel 9-17 BAY-1, removed jumper between Terminals DD-41 and DD-42.

Cue Notes Removal of a MSIV LOW WATER LEVEL ISOLATION BYPASS jumper constitutes failure of this critical step.

Results SAT UNSAT

5. Procedure Step: 5.6.5 Remove RPS LOGIC TRIP BYPASS jumper between Terminals BB-41 and BB-42 (BAY-3, PNL 9-17).

Critical Step Standard In Panel 9-17 BAY-3, removed jumper between Terminals BB-41 and BB-42.

Cue Notes Removal of a MSIV LOW WATER LEVEL ISOLATION BYPASS jumper constitutes failure of this critical step.

Results SAT UNSAT

6. Procedure Step: 5.7 Reset RPS manual scram (PANEL 9-5) by placing REACTOR SCRAM RESET switch to Group 1 and 4, Critical Step Group 2 and 3, then back to NORM.

Standard At Panel 9-5, turned REACTOR SCRAM RESET switch counter-clockwise to Group 1 and 4, clockwise to Group 2 and 3, then counter-clockwise back to NORM.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM S7 Page 8 of 10

7. Procedure Step: 5.8 Inform CRS that RPS logic has been restored.

Standard Informed CRS that RPS logic has been restored.

Cue Notes JPM Complete Results SAT UNSAT STOP TIME: TOTAL TIME:

CNS NRC Exam 2020-4 JPM S7 Page 9 of 10 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC IC 323(Perform with JPM S-8)

C. Load Schedule File D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

1. Events none

2. Malfunctions none

3. Remotes none

4. Overrides none Ensure the following is built into the IC or perform the following:

a. Physically install RPS jumpers in Panels 9-15 bays 1 and 3 AND in and Panel 9-17 bays 1 and 3 IAW 5.8.3 Section 5.

b. Physically install MSIV Low Level jumpers in Panels 9-15 bays 1 and 3 AND in and Panel 9-17 bays 1 and 3 IAW 5.8.20 Attachment 1.

5. Panel Setup c. Ensure RPV level maintained 10 to 40

d. HPCI is in service with flow at 0 gpm. Adjust as necessary to maintain RPV level.

e. Ensure 5.8.3 Attachment 1 hard card is appropriately marked up for Steps ARI-1, 2-16 (RPS jumpers installed) and place on cart in front of Panel 9-5 as usual for ATWS conditions.

Note: If this JPM is to be performed more than once, a SNAPSHOT can be taken after the panel setup is complete.

CNS NRC Exam 2020-4 JPM S7 Page 10 of 10 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the examiner when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is in Mode 3 following a scram from 100% power.

2. RPS PTMs are installed because an ATWS condition was present.

3. All control rods have been inserted using alternate control rod insertion methods.

INITIATING CUE:

The CRS directs you to remove RPS Logic Trip Bypass jumpers and reset the scram logic per procedure 5.8.3, Alternate Rod Insertion Methods, Section 5.

Inform the CRS when you have completed the task.

CNS NRC Exam 2020-4 JPM S8 Page 1 of 16 Cooper Nuclear Station Job Performance Measure S-8 Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 2 of 16 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Place SGT B in Service to Support HPCI Operation (Alternate Path)

Revision number: 2 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to place a SGT subsystem in service and respond to SGT high moisture condition.

TASK STANDARD: Examinee started SGT B exhaust fan IAW Procedure 2.2.73 Section 8, then after SGT B high moisture annunciator (K-2/A-2) was received, started SGT A IAW 2.2.73 Section 8.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant (RCA )

Simulate X Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 3 of 16 Comments (Required for Unsat):

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 4 of 16 Revision Statement:

Rev 0-New JPM Rev 1 - Editorial changes per NRC comments Rev 2 - Designated steps 12 and 13 not critical since controller is already in Manual with V displayed JPM Information:

8. NRC K/A: 261000 A4.07 (3.1/3.2)

9. Safety Function: 9, Radioactivity Release

10. Task No.: 261011P0101, Perform SBGT system support for HPCI operation

11. PSA Applicability: N/A

12. Critical Steps stated in the procedure step in bold

References:

1. Procedure 2.2.73, Standby Gas Treatment System (Rev 60)

2. Alarm Card K-2/A-2, SGT B High Moisture (Rev 8)

Special Conditions, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

Attachments:

1. Attachment 1 - Simulator Set-Up Instructions

2. Attachment 2 - Applicant Cue Sheet Handouts:

1. Attachment 2 - Applicant Cue Sheet

2. Procedure 2.2.73, Standby Gas Treatment System Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 5 of 16 Directions to Examiner:

THIS IS AN ALTERNATE PATH JPM. SGT B High Moisture annunciator will be received after SGT B exhaust fan is started, requiring the examinee place SGT A in service instead.

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. When the examinee has indicated they are ready, place the simulator in run, and tell the examinee to begin.

5. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 6 of 16 PERFORMANCE:

START TIME:

1. Procedure Step (Procedure 2.2.73, Standby Gas Treatment System)

8. Manual Operation to Support HPCI Operation (Notes an Caution before step 8.1)

NOTE 1- Both SGT Subsystems may be placed in service for EOPs.

NOTE 2- Preferred fan does not set a requirement but is meant to help equalize charcoal run time. Either fan may be run at any time based upon circumstance.

CAUTION - Secondary Containment pressure transient and TS LCO 3.6.4.1 entry may occur from starting SGT.

Standard Examinee reviewed notes and caution.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 7 of 16

2. Procedure Step 8.1 PERFORM one of following (VBD-K):

8.1.1 PLACE EF R 1E, SGT A EXHAUST FAN, in service.

8.1.2 PLACE EF R 1F, SGT B EXHAUST FAN, in service.

Standard Examinee determined step 8.1.1 N/A by observing PREFERRED label on SGT B Exhaust Fan, not SGT A Exhaust Fan, and marked steps 8.1.1.1, and 8.1.1.2 N/A.

Examinee proceeded to 8.1.2.

Cue Notes Results SAT UNSAT

3. Procedure Step 8.1.2 PLACE EF-R-1F, SGT B EXHAUST FAN in Critical Step Service:

8.1.2.1 PLACE EF-R-1F in RUN.

Standard Examinee rotated control switch EF-R-1F, SGT B EXHAUST FAN, clockwise to RUN and observed red light On, green light Off.

Cue Notes Results SAT UNSAT Examiner Note: SGT B High Moisture annunciator occurs 30 seconds after SGT B exhaust fan is started. It is expected examinee will perform the next 2 steps before the alarm comes in. If the examinee does not perform the next 2 steps before the alarm is received, they may transition to the alarm card without ever addressing both steps.

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 8 of 16

4. Procedure Step 8.1.2 PLACE EF R 1F, SGT B EXHAUST FAN in Service:

8.1.2.2 VERIFY following:

SGT-AO-250, SGT B INLET, opens.

Standard Examinee checked SGT-AO-250, SGT B INLET, opened by observing red light On, green light Off.

Cue Notes Results SAT UNSAT

5. Procedure Step 8.1.2 PLACE EF R 1F, SGT B EXHAUST FAN in Service:

8.1.2.2 VERIFY following:

SGT-AO-252, SGT B DISCHARGE, opens.

Standard Examinee checked SGT-AO-252, SGT B DISCHARGE, opened by observing red light On, green light Off.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 9 of 16

6. Procedure Step N/A Alternate Path Standard Examinee recognized receipt of annunciator K-2/A-2, SGT B High Moisture and referred to alarm card.

Cue Notes Results SAT UNSAT

7. Procedure Step Alarm Card K-2/A-2 Alternate Path 1. OPERATOR OBSERVATION AND ACTION 1.1 Check heater operation.

Standard Examinee recognized SGT B heater not operating by observing control switch SGT B HEATER CONTROL SGT-HTR-SGHB green lights on and red lights Off for HTR A and HTR B and determined heater control had malfunctioned with switch in HIGH position.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 10 of 16

8. Procedure Step (Alarm Card K-2/A-2)

Alternate Path 1. OPERATOR OBSERVATION AND ACTION 1.2 Start SGT A train and secure SGT B per Procedure 2.2.73.

Standard Examinee notified CRS of SGT B heater malfunction and intent to start SGT A and secure SGT B.

Cue As CRS acknowledge report.

Notes If examinee asks CRS for guidance, respond by asking examinee what they recommend.

Results SAT UNSAT Examiner Note: It is not an objective of this JPM to secure SGT B. IF Examinee proceeds to secure SGT B per Section 10 of 2.2.73 prior to starting SGT A, inform the examinee that another operator will perform that action.

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 11 of 16

9. Procedure Step (Procedure 2.2.73, Standby Gas Treatment System)

Alternate Path 8. Manual Operation to Support HPCI Operation Critical Step 8.1.1 PLACE EF-R-1E, SGT A EXHAUST FAN in Service:

8.1.1.1 PLACE EF-R-1E in RUN.

Standard Examinee rotated control switch EF-R-1E, SGT A EXHAUST FAN, clockwise to RUN and observed red light On, green light Off.

Cue Notes Results SAT UNSAT

10. Procedure Step 8.1.1 PLACE EF-R-1E, SGT A EXHAUST FAN in Service:

Alternate Path 8.1.1.2 VERIFY following:

SGT-AO-249, SGT A INLET, opens.

Standard Examinee checked SGT-AO-249, SGT A INLET, opened by observing red light On, green light Off.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 12 of 16

11. Procedure Step 8.1.1 PLACE EF-R-1E, SGT A EXHAUST FAN in Service:

Alternate Path 8.1.1.2 VERIFY following:

SGT-AO-251, SGT A DISCHARGE, opens.

Standard Examinee checked SGT-AO-251, SGT A DISCHARGE, opened by observing red light On, green light Off.

Cue Notes Results SAT UNSAT

12. Procedure Step 8.2 At VBD-R, ENSURE SGT-DPIC-546, RX BLDG/SGT DP, in MANUAL.

Standard Examinee checked SGT-DPIC-546, RX BLDG/SGT DP, in MANUAL by observing LED lit beside M and LED off beside A.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 13 of 16

13. Procedure Step 8.3 DEPRESS D pushbutton, as necessary, to display Parameter V on SGT-DPIC-546, RX BLDG/SGT DP.

Standard Examinee checked V was displayed near upper right of controller SGT-DPIC-546, RX BLDG/SGT DP.

Cue Notes Results SAT UNSAT

14. Procedure Step 8.4 ADJUST SGT-DPIC-546 to greater than or equal to Critical Step 800 scfm on SGT-FI-545, SGT DISCHARGE HEADER FLOW (VBD-K).

Standard Examinee rotated adjustment knob on SGT-DPIC-546, RX BLDG/SGT DP (VBD-R), as necessary, while observing SGT-FI-545, SGT DISCHARGE HEADER FLOW (VBD-K) until SGT-FI-545 indicated 800 scfm.

Cue Notes Results SAT UNSAT Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 14 of 16

15. Procedure Step 8.5 ENSURE following annunciator(s) clear for SGT train(s) in service:

K-1/A-2, SGT A HIGH MOISTURE.

Standard Examinee checked annunciator K-1/A-2, SGT A HIGH MOISTURE was clear.

Cue Notes Results SAT UNSAT

16. Procedure Step 8.5 ENSURE following annunciator(s) clear for SGT train(s) in service:

K-2/A-2, SGT B HIGH MOISTURE.

Standard Examinee recognized annunciator K-2/A-2 remained lit and determined SGT B was required to be secured per Alarm Card K-2/A-2 IAW Procedure 2.2.73.

Cue Inform the Examinee Another operator will secure SGT B. This JPM is Complete.

Notes JPM is Complete Results SAT UNSAT Stop Time: _____________ Total Time: _____________

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 15 of 16 ATTACHMENT 1 SIMULATOR SET-UP INSTRUCTIONS A. Materials Required None B. Initialize the Simulator in IC IC 323(Perform with JPM S-7)

C. Load Schedule File 2020-4JPMS8 D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

create event 9 zlosgtswefrf(2) == 1

1. Events (SGT B exhaust fan red light on)

PMIS override 30

2. Malfunctions m604 9 high N/A N/A SGT B moisture sec

3. Remotes None SGT B High 30

4. Overrides p4574 Moisture 9 on N/A N/A annunciator sec SGT B filter inlet zaosgtmi533b humidity 9 15 100 60 N/A SGT B HE filter zaosgtmi535b humidity 9 15 100 60 N/A CS for SGT Unit zlosgtswsghb(1)

B HTR A N/A ON N/A N/A CS for SGT Unit zlosgtswsghb(3)

B HTR A N/A ON N/A N/A CS for SGT Unit zlosgtswsghb(2)

B HTR A N/A OFF N/A N/A CS for SGT Unit zlosgtswsghb(4)

B HTR A N/A OFF N/A N/A Ensure the following:

a. Ensure PREFERRED tag is on SGT B.

b. Ensure Parameter P is displayed on SGT-DPIC-546, RX BLDG/SGT DP

5. Panel Setup c. Ensure RPV level maintained 10 to 40 to ensure Group 6 does not occur

d. HPCI is in service with flow at 0 gpm. Adjust as necessary to maintain RPV level.

Note: If this JPM is to be performed more than once, a SNAPSHOT can be taken after the panel setup is complete.

Rev 2

CNS NRC Exam 2020-4 JPM S8 Page 16 of 16 ATTACHMENT 2 Directions to Examinee:

Read the following, and inform the examiner when you are ready to begin.

INITIAL CONDITIONS:

1. Plant is in Mode 3 following loss of RFPs at 25% power.

2. HPCI has been manually started IAW the hard card for level control.

INITIATING CUE:

The CRS directs you to start SGT B to support HPCI operation IAW Procedure 2.2.73, Section 8 Manual Operation to Support HPCI Operation.

Inform the CRS when you have completed the task.

CNS NRC Exam 2020-4 JPM P-1 Page 1 of 14 Cooper Nuclear Station Job Performance Measure P-1 Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 2 of 14 Lesson Number: SKL034-10-128 SAP Course Number: 69502 Lesson

Title:

Startup the RPS Motor Generator Set (RPS MG A)

Revision number: 08 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

FRAME:

PERFORMANCE Validation Time (min): 20 Actual Time (min):

TIME:

JPM RESULTS:(Circle one) SAT UNSAT COMMENT SHEET ATTACHED: (Circle one) Yes / No (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinee's ability to start an RPS MG Set.

TASK STANDARD: The examinee started RPS MG Set A and determined voltage could not be adjusted to within the required range IAW Procedure 2.2.22 Section 5, then secured RPS MG Set A IAW Procedure 2.2.22 Section 11.

EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant (RCA )

X Simulate Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)

(Approval is N/A for NRC ILT Exams)

Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 3 of 14 Comments(Required for Unsat):

Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 4 of 14 Revision Statements:

Rev 0 - Updated to new format Rev 1 - Per CE comments, corrected spelling for voltage in step 9, changed handout from one handout with entire procedure to two separate handouts: one for Section 5 and another for Section 11, and changed examiner instructions to only give procedure Section 5 initially, then give procedure Section 11 when requested at JPM step 11.

JPM Information:

1. NRC K/A Number and rating: 212000 A2.01 (3.7/3.9)

2. Safety Function: 7, Instrumentation

3. Task No: 212003O0104

4. PSA Applicability: Top 10 Risk Significant System - RPS

5. Critical Steps stated in the procedure step in bold References (include revision number if applicable):

1. Procedure 2.2.22, Vital Instrument Power System (Rev 81)

Special Conditions, Tools, Equipment:

1. Each examinee must have key for access to Control Building RPS MG Set Room doors

2. Screwdriver Attachments:

1. Attachment 1 - Examinee Cue Sheet Handouts:

1. JPM Attachment 1 - Examinee Cue Sheet

2. Procedure 2.2.22, Vital Instrument Power System, Section 5

3. Procedure 2.2.22, Vital Instrument Power System, Section 11 Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 5 of 14 Directions to Examiner:

NOTE - DO NOT give the examinee Handout 3 (Procedure 2.2.22, Section 11) until requested at JPM step 11.

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed.

You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handouts 1 and 2. DO NOT give the examinee Handout 3 (Procedure 2.2.22, Section 11) until requested at JPM step 11.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 6 of 14 PERFORMANCE:

START TIME:

1. Procedure Step (Procedure 2.2.22, Vital Instrument Power System)

5. PLACING RPS MG SET IN SERVICE 5.1 Place RPS MG Set A in service by performing following:

5.1.1 At REACTOR PROTECT SYS MOT AND GEN SET

1A CONTROL CUBICLE (RPS MG Set Room A),

perform following:

5.1.1.1 Ensure AC OUTPUT GEN breaker OFF.

Standard Ensured the AC OUTPUT GEN breaker was OFF.

Cue Indicate that breaker handle is pointing towards OFF.

Notes Results SAT UNSAT

2. Procedure Step 5.1.1.2 Ensure AC INPUT MOT breaker OFF.

Standard Ensured the AC INPUT MOT breaker was OFF.

Cue Indicate that breaker handle is pointing towards OFF.

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 7 of 14

3. Procedure Step 5.1.2 At MCC-L (Control Building 882'), ensure Breaker 3D, Critical Step RPS-MG-RPSA, REACTOR PROT SYS A MOTOR GEN SET, closed.

Standard Rotated breaker handle 3D on MCC-L in the upward direction to ON.

Cue (Initially) Indicate breaker handle down and pointing to OFF.

(When operated) Indicate breaker handle up and pointing to ON.

Notes Results SAT UNSAT

4. Procedure Step 5.1.3 At REACTOR PROTECT SYS MOT AND GEN SET #1A CONTROL CUBICLE, perform following:

5.1.3.1 IF VOLTAGE ADJ potentiometer setting was changed while RPS MG Set A was secured, THEN ensure VOLTAGE ADJ potentiometer is at approximately midpoint position.

Standard Determined voltage setting had been changed from initial conditions Cue If asked, indicate that the voltage setting was changed and the potentiometer is at the midpoint position (approximately 5).

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 8 of 14

5. Procedure Step 5.1.3.2 Close AC INPUT MOT breaker.

Critical Step Standard Rotated AC INPUT MOT breaker handle clockwise until handle pointed to ON.

Cue Indicate breaker handle is pointed toward ON.

Notes Results SAT UNSAT

6. Procedure Step 5.1.3.3 Press MOTOR ON button for ~ 15 seconds to allow Critical Step MG Set to come up to speed and release when A-C VOLTS are > 110V.

Standard Depressed MOTOR ON button and released when A-C VOLTS were >110V.

Cue (After ~ 15 seconds) Indicate A-C VOLTS at ~111V.

Notes Results SAT UNSAT

7. Procedure Step 5.1.3.4 Check A-C VOLTS have stabilized between 114V and 126V.

Standard Checked A-C VOLTS have stabilized between 114V and 126V.

Cue Indicate A-C VOLTS are stable at ~111V.

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 9 of 14

8. Procedure Step 5.1.3.5 IF A-C VOLTS not between 114V to 126V, THEN perform following:

a. Loosen VOLTAGE ADJ potentiometer locking screw.

Standard Loosened VOLT ADJ potentiometer locking screw with the screwdriver.

Cue (When stated a screwdriver must be obtained, ask where a screwdriver could be obtained. When the examinee answers, tell the operator the screwdriver has been obtained).

The locking screw is no longer in contact with the dial.

Notes Results SAT UNSAT

9. Procedure Step

b. Make small increment adjustments to VOLTAGE ADJ potentiometer until voltage is in this band.

Standard Rotated potentiometer in the clockwise direction in small incremental adjustments. Determined voltage cannot be adjusted to within 114V to 126V.

Cue Indicate voltage is remaining at ~111V regardless of adjustments.

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 10 of 14

10. Procedure Step c. Tighten VOLTAGE ADJ potentiometer locking screw.

Standard Used screwdriver and turned locking screw clockwise.

Cue The locking screw is tight against the dial.

Notes Results SAT UNSAT

11. Procedure Step d. IF voltage cannot be adjusted to within this band, THEN Alternate Path remove RPS MG Set A from service per Section 0 and inform Electricians.

Standard Transitioned to Section 11 and notified electricians.

Cue When requested, give the examinee Handout 3 (Procedure 2.2.22, Section 11)

As Electrician, acknowledge report.

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 11 of 14

12. Procedure Step 11. REMOVING RPS MG SET FROM SERVICE Alternate Path 11.1 Shut down RPS MG Set A by performing following:

11.1.1 Transfer RPSPP1A to alternate power supply per Section 7 for MODE 1, 2, or 3 and Section 8 for MODE 4 or 5, or remove RPSPP1A from service per Section 10.

Standard Determined step was N/A since RPSPP1A was already on alternate power supply from initial condition Cue Notes Results SAT UNSAT

13. Procedure Step 11.1.2. At ELECTRICAL PROTECTION ASSEMBLY 1A2 (RPS Alternate Path MG Set Room A), place breaker to OFF.

Standard Determined step was N/A by observing ELECTRICAL PROTECTION ASSEMBLY 1A2 breaker already OFF.

Cue Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 12 of 14

14. Procedure Step 11.1.3. At ELECTRICAL PROTECTION ASSEMBLY 1A1 (RPS Alternate Path MG Set Room A), place breaker to OFF.

Standard Determined step was N/A by observing ELECTRICAL PROTECTION ASSEMBLY 1A1 breaker already OFF.

Cue Notes Results SAT UNSAT

15. Procedure Step 11.1.4. At REACTOR PROTECT SYS MOT AND GEN SET Alternate Path #1A CONTROL CUBICLE (RPS MG Set Room A),

perform following:

11.1.4.1 Open AC OUTPUT GEN breaker.

Standard Determined step was N/A due to breaker was already open.

Cue Indicate breaker handle is pointed toward OFF.

Notes Results SAT UNSAT

16. Procedure Step 11.1.4.2 Press and hold MOTOR OFF button; release after Alternate Path off light comes on.

Critical Step Standard Pressed and held MOTOR OFF button; released after off light came on.

Cue After 3 seconds, indicate OFF light came on.

Notes Results SAT UNSAT Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 13 of 14

17. Procedure Step 11.1.4.3 Open AC INPUT MOT breaker.

Alternate Path Critical Step Standard Rotated AC INPUT MOT breaker handle counter-clockwise until handle pointed to OFF.

Cue Indicate breaker handle is pointed toward OFF.

Notes Results SAT UNSAT

5. Procedure Step 11.1.5 IF removed from service for Procedure 6.1RPS.313, Alternate path THEN issue Clearance Order per Procedure 0.9 and tag as follows:

Standard Determined step was N/A and informed CRS that RPSMG set A has been removed from service.

Cue Inform examinee that JPM is complete.

Notes JPM is Complete.

Results SAT UNSAT Stop Time: _____________ Total Time: _____________

Rev 1

CNS NRC Exam 2020-4 JPM P-1 Page 14 of 14 ATTACHMENT 1 DIRECTIONS TO EXAMINEE:

Read the following and inform the examiner when you are ready to begin.

INITIAL CONDITIONS:

1. The plant is operating at 71% power.

2. RPS MG A Set was shut down for maintenance.

3. RPS MG A voltage setting was adjusted during maintenance, and VOLTAGE ADJ potentiometer is at midpoint position.

4. RPS MG Set A maintenance has been completed.

5. RPS Power Panel 1A, RPSPP1A, is supplied by CDP 1B.

INITIATING CUE:

You are directed to place RPS MG Set A in service per Procedure 2.2.22, Vital Instrument Power System Section 5, in preparation for transferring RPSPP1A to RPS MG Set A.

Notify the CRS when RPS MG set A is operating and ready to supply RPSPP1A.

Rev 1

CNS NRC Exam 2020-4 JPM P2 Page 1 of 11 Cooper Nuclear Station Job Performance Measure P-2

CNS NRC Exam 2020-4 JPM P2 Page 2 of 11 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

Conduct Alternate ROD insertion by manually venting the scram air header Revision number: 11 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the Examinee's ability to conduct alternate rod insertion by manually venting the scram air header.

TASK STANDARD: Examinee manually vented the scram header IAW Procedure 5.8.3 Section 8 and repressurized the scram air header.

EVALUATION METHOD: EVALUATION LOCATION:

Perform x Plant (RCA )

x Simulate Simulator or Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM P2 Page 3 of 11 Comments(Required for Unsat):

CNS NRC Exam 2020-4 JPM P2 Page 4 of 11 Revision Statements:

Rev 10-Updated JPM to new format Rev 11 - changed validation time to 10 min, minor formatting changes JPM Information:

1. NRC K/A Number and rating: 295037 EA1.05 (3.9/4.0) 201003 A2.05 (4.1/4.1)

2. Safety Function: 1, Reactivity Control

3. Task No: 200186P0504 CONDUCT ALTERNATE ROD INSERTION BY MANUALLY VENTING SCRAM AIR HEADER

4. PSA Applicability: RPS, Reactor Protection Systems

5. Critical Steps stated in the procedure step in bold References (include revision number if applicable):

1. EOP 5.8.3 ALTERNATE ROD INSERTION METHODS (REV 17)

Special Conditions, Tools, Equipment:

1. None Attachments:

1. Attachment 1 - N/A

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. EOP 5.8.3 Section 8

CNS NRC Exam 2020-4 JPM P2 Page 5 of 11 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions.

Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handout 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM P2 Page 6 of 11 PERFORMANCE:

START TIME:

1. Procedure Step: (EOP 5.8.3 Alternate Rod Insertion Methods) Section 8 CAUTION - This section may require dispatching personnel through or into potentially high radiation areas.

Standard Examinee reviewed the caution.

Cue Notes Results SAT UNSAT

2. Procedure Step: 8.1 Refer to Section 3 when dispatching personnel to perform actions outside Control Room.

Standard Examinee reviewed Section 3.

Cue Notes Results SAT UNSAT

3. Procedure Step: 8.2 Close IA-985, CRD SCRAM DISCHARGE VOLUME

& SCRAM PILOT AIR SUPPLY (R-903-SE; south Critical Step wall; behind rack for CRD-SOV-SO164A, SS0160, S0164B; ~ 3' off floor).

Standard Examinee Closed IA-985.

Cue Resistance is felt while closing the valve and the valve will no longer turn.

Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P2 Page 7 of 11

4. Procedure Step: 8.3 Check open IA-244, PI-229 & PS-230 ROOT (R-903-SE).

Standard Examinee verified IA-V-244 open by attempting to take valve in the clockwise direction and verifying movement and returning valve to original position.

Cue Examinee feels no resistance to turning the valve clockwise, The hand wheel is fully counter-clockwise or returned to original position.

Notes Results SAT UNSAT

5. Procedure Step: 8.4 Remove 3/4" swagelok female connector with 1/4" plug from IA-1601, IA-PI-229 & IA-PS-230 Critical step DRAIN (R-903-SE).

Standard Examinee removed 3/4" swagelok female connector with 1/4" plug from IA-1601, utilizing the wrench attached by lanyard to IA-1601.

Cue 1. The 3/4" swagelok female connector with 1/4" plug is turning.

2. The 3/4" swagelok female connector with 1/4" plug is removed.

Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P2 Page 8 of 11

6. Procedure Step: 8.5 Open IA-1601, IA-PI-229 & IA-PS-230 DRAIN Critical step (R-903-SE).

Standard Examinee opened IA-1601 by turning valve counter-clockwise direction, then positioned valve 1/2 turn clockwise to remove off the back seat.

Cue 1. While the valve hand wheel is turning counter-clockwise, there is the sound of rushing air.

2. Resistance is felt while opening the valve and the valve will no longer turn.

3. Acknowledge removing from backseat Notes Removing from the back seat is not part of the critical step Results SAT UNSAT

7. Procedure Step: 8.6 Inform Control Room that scram air header venting is in progress.

Standard Examinee notified the Control Room the scram air header venting is in progress.

Cue When notified:

1. Acknowledge scram air header venting is in progress and DIRECT operator to stay on the line.

2. After ~1 minute, report that all control rods are inserted and DIRECT restoration of the scram air header.

Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P2 Page 9 of 11

8. Procedure Step: 8.7 WHEN directed to restore scram air header, THEN perform following:

Critical step 8.7.1 Close IA-1601, IA-PI-229 & IA-PS-230 DRAIN (R-903-SE).

Standard Examinee closed IA-1601 by turning the valve in the clockwise direction.

Cue After a few seconds state resistance is felt and can no longer turn.

Notes Results SAT UNSAT

9. Procedure Step: 9.7.2 Install 3/4" swagelok female connector with 1/4" plug on IA-Critical step 1601, IA-PI-229 & IA-PS-230 DRAIN (R-903-SE).

Standard Examinee installed and tighten the 3/4" swagelok female connector with 1/4" plug on IA-1601.

Cue 1. The 3/4" swagelok female connector with 1/4" plug is in place and turning.

2. The 3/4" swagelok female connector with 1/4" plug is tight.

Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P2 Page 10 of 11

10. Procedure Step: 8.7.3 Open IA-985, CRD SCRAM Critical step DISCHARGE VOLUME & SCRAM PILOT AIR SUPPLY (R-903-SE; south wall; behind rack for CRD-SOV-SO164A, SS0160, S0164B; ~

3' off floor).

Standard Examinee slowly opened IA-985 by turning valve counter-clockwise until IA-985 is full open, then positioned valve 1/2 turn clockwise to remove off the back seat.

Cue When the valve is full open, state resistance is felt.

Notes Removing from the back seat is not part of the critical step.

Results SAT UNSAT

11. Procedure Step: 8.8 Inform CRS that scram air header has been restored.

Standard Examinee informed the CRS that the scram air header has been restored.

Cue CRS acknowledges the report.

Notes JPM is Complete.

Results SAT UNSAT Stop Time: _____________ Total Time: _____________

CNS NRC Exam 2020-4 JPM P2 Page 11 of 11 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and tell me when you are ready to begin.

INITIAL CONDITIONS:

1. A failure of RPS and ARI to insert the control rods has occurred.

2. The Control Room Operator has placed all keylock RPS test trip switches to TRIP.

3. The TSC is not yet operational.

4. No ARMs alarms exist.

5. The In-Containment Rad Monitors are reading 100 REM/HR.

INITIATING CUES:

The Control Room Supervisor directs you to manually vent the scram air header per EOP 5.8.3 section 8 and to verify with the Control room that all control rods fully inserted and then to restore the scram air header. Notify the CRS when the task is complete.

CNS NRC Exam 2020-4 JPM P3 Page 1 of 14 Cooper Nuclear Station Job Performance Measure P-3

CNS NRC Exam 2020-4 JPM P3 Page 2 of 14 Lesson Number: ILT SAP Course Number: ILT Lesson

Title:

PLACE THE AIR DRYER IN SERVICE (A DRYER)

Revision number: 0 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE SRO RO NLO ALTERNATE SUCCESS PATH TIME CRITICAL OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

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

PERFORMANCE TIME: Validation Time (min): 10 Actual Time (min):

JPM RESULTS: (Circle one) SAT UNSAT COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat)

SYNOPSIS: This JPM evaluates the examinees ability to place IA Dryer A in service locally.

TASK STANDARD: Examinee placed IA Dryer A in service by closing drain valves IA-58A and IA-166B, opening filter inlet/outlet valves SA-19 and IA-12, closing MCC-L Breaker 2BL, IA-DRY-A, and depressing IA Dryer A START button IAW Procedure 2.2.59 Section 12.1.

EVALUATION METHOD: EVALUATION LOCATION:

Perform X Plant (RCA )

X Simulate Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: N/A Date: N/A Superintendent, Operations Training (or Designee)(Approval is N/A for NRC ILT Exams)

CNS NRC Exam 2020-4 JPM P3 Page 3 of 14 Comments (Required for Unsat):

CNS NRC Exam 2020-4 JPM P3 Page 4 of 14 Revision Statements:

Rev 0- New JPM Rev 1 - Changed validation time to 10 min, added position of valve handles in JPM steps 7 and 8.

JPM Information:

1. NRC K/A number and rating: 295019 AA1.02 (3.3/3.1)

2. Safety Function: 8, PLANT SERVICE SYSTEMS

3. Task No.: 278009P0104 PLACE THE AIR DRYER IN SERVICE

4. PSA Applicability: N/A

5. Critical Steps stated in the procedure steps in bold

References:

1. Procedure 2.2.59, Plant Air System (Rev 76)

2. Alarm Card A-4/F-4, Air Dryer Filter High DP (Rev 44)

Special Conditions, Tools, Equipment:

1. NONE Attachments:

1. NONE

2. Attachment 2 - Examinee Cue Sheet Handouts:

1. Attachment 2 - Examinee Cue Sheet

2. Procedure 2.2.59, Plant Air System, Section 12

CNS NRC Exam 2020-4 JPM P3 Page 5 of 14 Directions to Examiner:

1. IF the following has not been discussed during the pre-job brief for the exam and IF this is the first performance in this setting, THEN brief the examinee as follows:

All actions associated with this job performance measure are to be performed.

You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will give you a sheet with the Initial Conditions and Initiating Cues, then answer any questions related to the task instructions.

2. Give the Examinee Handouts 1 and 2.

3. Answer any questions the examinee may have related to task instructions.

4. Check off either Satisfactory or Unsatisfactory performance. If Unsat, state why in the comments.

CNS NRC Exam 2020-4 JPM P3 Page 6 of 14 PERFORMANCE:

START TIME:

1. Procedure Step (Procedure 2.2.59, Plant Air System)

12. PLACING AIR DRYER IN SERVICE WARNING - There is 115V and 480V power inside control panel.

Standard Examinee reviewed warning.

Cue Tell the examinee NOT to open IA Dryer A control cabinet due to 480V present.

Notes Procedure 2.2.59 provided as handout 2 Results SAT UNSAT

2. Procedure Step 12.1 Place Air Dryer A in service.

Standard Examinee determined that he is to place A Air Dryer in service from the Initiating Cues and continued with step 12.1.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 7 of 14

3. Procedure Step 12.1.1 Ensure a supply of air is available or place dryer in service per placing system in service section of this procedure.

Standard Examinee determined air supply is available from Initial Conditions IA pressure is 103 psig.

Cue Notes Results SAT UNSAT

4. Procedure Step 12.1.2 Inside Air Dryer A Control Panel, ensure following switches are positioned as specified:

12.1.2.1 MODE SELECT switch to HEATED.

Standard Examinee determined MODE SELECT switch is in HEATED from initial conditions.

Cue Notes Results SAT UNSAT

5. Procedure Step 12.1.2.2 POWER SAVER switch to OFF.

Standard Examinee determined POWER SAVER switch is in OFF from initial conditions.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 8 of 14

6. Procedure Step 12.1.2.3 MANUAL SWITCHING switch is down.

Standard Examinee determined MANUAL SWITCHING switch is down from initial conditions.

Cue Notes Results SAT UNSAT

7. Procedure Step 12.1.3 Close IA-166B, DRYER 1A POST FILTER UPPER Critical Step DRAIN.

Standard Examinee closed IA-166B, by turning handle clockwise until resistance was felt.

Cue As-found position of long side of valve handle is in-line with the pipe.

Resistance is felt, handle will not turn further, and handle is perpendicular to the pipe.

Notes When valve is closed handle is perpendicular to the pipe.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 9 of 14

8. Procedure Step 12.1.4 Close SA-58A, DRYER 1A PRE-FILTER LOWER Critical Step MANUAL DRAIN.

Standard Examinee closed SA-58A by turning handle clockwise until resistance was felt.

Cue As-found position of long side of valve handle is in-line with the pipe.

Resistance is felt, handle will not turn further, and handle is perpendicular to the pipe.

Notes When valve is closed handle is perpendicular to the pipe.

Results SAT UNSAT

9. Procedure Step CAUTION - Opening SA-19 rapidly can cause desiccant bed to be disturbed.

Standard Examinee reviewed caution.

Cue Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 10 of 14

10. Procedure Step 12.1.5 Slowly open SA-19, PREFILTER A INLET.

Critical Step Standard Examinee opened SA-19 by slowly turning handle counter-clockwise until resistance was felt, then positioned valve 1/2 turn clockwise to remove off the back seat.

Cue Resistance is felt and handle will not turn further; Acknowledge report if stated took off backseat.

Notes Removing from the back seat is not part of the critical step.

Results SAT UNSAT

11. Procedure Step 12.1.6 Open IA-12, INSTRUMENT AIR POST FILTER A Critical Step OUTLET.

Standard Examinee opened IA-12 by turning handle counter-clockwise until resistance was felt, then positioned valve 1/2 turn clockwise to remove off the back seat.

Cue Resistance is felt and handle will not turn further; Acknowledge report if stated took off backseat.

Notes Removing from the back seat is not part of the critical step.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 11 of 14

12. Procedure Step 12.1.7 Close MCC-T Breaker 2BL, IA-DRY-A, Critical Step INSTRUMENT AIR DRYER A.

Standard Examinee closed MCC-T Breaker 2BL by placing handle upward to ON.

Cue Handle is up, aligned with ON.

Notes Panel indications light up.

Results SAT UNSAT

13. Procedure Step NOTE - Air dryer trouble may alarm.

Standard Examinee reviewed note, and called the Control room to inform of potential alarm.

Cue Acknowledge report if given.

Notes Results SAT UNSAT

14. Procedure Step 12.1.8 Depress START button on front of Air Dryer A Critical Step Control Panel. (north of Dryer A).

Standard Examinee depressed and released START button on front of Air Dryer A Control Panel.

Cue Notes Indications change on the panel for starting up.

Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 12 of 14

15. Procedure Step 12.1.9 Check IA-PI-2336A, IA DRYER A PURGE INDICATOR (back of dryer), indicates ~ 63 psig or adjust using IA-184, IA DRYER A PURGE INLET.

Standard Examinee observed IA-PI-2336A indicates ~ 63 psig or adjusted using IA-184.

Cue IA-PI-2336A indicates 63 psig.

Notes Only one person can fit in area by IA-PI-2336A. When examinee has verified the pressure indicator state the cue to him. You will not be able to point to the indicator.

Results SAT UNSAT

16. Procedure Step 12.1.10 Allow dryer to purge for ~ 30 minutes.

Standard Examinee marked time using suitable time piece for start of 30 minute purge.

Cue 32 minutes have elapsed.

Notes Results SAT UNSAT

17. Procedure Step 12.1.11 Place IA-SW-5A, A LOCKOUT RESET, switch to Critical Step RESET (C-882-N north of Dryer A).

Standard Examinee placed IA-SW-5A switch to RESET.

Cue Switch IA-SW-5A is aligned with RESET.

Notes Results SAT UNSAT

CNS NRC Exam 2020-4 JPM P3 Page 13 of 14

18. Procedure Step NOTE - Air dryer trouble may clear.

Standard Examinee reviewed note, and called the Control room to inform of potential alarm reset.

Cue Acknowledge report if given.

Notes Results SAT UNSAT

19. Procedure Step 12.1.12 Depress START button on front of Air Dryer A Critical Step Control Panel.

Standard Examinee depressed and released START button on front of Air Dryer A Control Panel.

Cue Notes Indications change on the panel for starting up.

Results SAT UNSAT

20. Procedure Step 12.1.13 Check IA-PI-2336A indicates ~ 63 psig or adjust using IA-184.

Standard Examinee observed IA-PI-2336A indicates ~ 63 psig or adjusted using IA-184.

Cue IA-PI-2336A indicates 63 psig. JPM is Complete.

Notes Only one person can fit in area by IA-PI-2336A. When examinee has verified the pressure indicator state the cue to him. You will not be able to point to the indicator.

Results SAT UNSAT STOP TIME: _________________Total Time: _______________

CNS NRC Exam JPM P3 Page 14 of 14 ATTACHMENT 2 DIRECTIONS TO EXAMINEE:

Read the following and inform the Examiner when you are ready to begin.

INITIAL CONDITIONS:

1. The plant is at 100% power.

2. IA Dryer B is in service.

3. Annunciator A-4/F-4, Air Dryer Filter High DP is in alarm.

4. IA header pressure is 103 psig, slowly lowering.

5. IA Dryer A is in standby with the following switch alignment inside Air Dryer A Control Panel:

MODE SELECT switch is in HEATED.

POWER SAVER switch is in OFF.

MANUAL SWITCHING switch is down.

INITIATING CUE:

The CRS directs you to place Instrument Air Dryer A in service IAW Procedure 2.2.59, Section 12.

Notify the CRS when IA Dryer A is in service.

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 1 of 41 Facility: Cooper Nuclear Station Scenario No.: 1 Op-Test No.: CN-2020-04 Examiners: ____________________________ Operators: _____________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Shift CRD Pump B to CRD Pump A in operation

2. Respond to narrow range level transmitter NBI-LT-52C failure

3. Respond to Critical Power Panel CPP-1 loss of power

4. Respond to Condensate Pump B trip, Reactor Recirc Pump A runs back too far, trips

5. Respond to Reactor Recirc Pump B trip with Thermal Hydraulic Instability

6. Respond to a Main Steam Line D leak in the drywell

7. Respond to DW Spray A permissive switch failure

8. Respond to Torus to Drywell Vacuum Breaker failure with failure of RHR Loop B containment sprays Initial Conditions: Plant operating at 100% power near end of cycle.

Inoperable Equipment: Core Spray Pump A is tagged out of service for motor PMs.

Turnover:

Plant operating at operating at 100% power near end of cycle.

Planned activities for this shift are:

Continue steady state power operation.

Continue maintenance on CS Pump A.

Scenario Notes:

This is a new scenario.

Validation Time: 60 minutes Page 1 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 2 of 41 Event Malf. No. Event Type Event No. Description 1 N/A N (ATC,CRS) Shift CRD Pumps (B to A) 2 rr27c TS (CRS) Narrow range level transmitter NBI-LT-52C failure C (BOP,CRS) 3 ed11d Critical power panel CPP-1 loss of power A (CREW)

C (ATC,BOP,CRS) fw14b Condensate Pump B trip, RR Pump A runs back 4 A (CREW) rr17a too far, Reactor Recirc Pump A trip TS (CRS)

Reactor Recirc Pump B shaft binding with Thermal Hydraulic Instability CT#1 rr03b C (ATC, CRS) 5 Manually scram the reactor when both cr04b A (CREW) recirculation pumps trip, prior to exceeding 25% peak to peak neutron flux oscillations.

6 ms02d M (CREW) Main Steam Line D leak in the drywell (Override) 7 C (BOP,CRS) DW Spray A permissive switch failure zdirhrsws17a Torus to Drywell Vacuum Breaker failure, RHR Pumps B and D trip CT#2 When torus pressure cannot be maintained pco2a below the Pressure Suppression Pressure C

8 rh01b (PSP)(approximately 25 psig in this scenario),

(ATC,BOP,CRS) rh08d the crew completes Emergency Depressurization prior to exceeding PCPL-A (62.7 psig). (Anticipating ED and fully opening Bypass valves satisfies this Critical Task)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

Critical Task (As defined in NUREG 1021 Appendix D)

Page 2 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 3 of 41 Quantitative Attributes Table ES-301-4 Actual Attribute Description Target

1. DW Spray A permissive switch failure Malfunctions after 2. Torus to Drywell Vacuum Breaker failure, RHR Pumps B 1-2 2 EOP entry and D trip

1. Critical power panel CPP-1 loss of power

2. Condensate Pump B trip, RR Pump A runs back too far, Abnormal Events 2-4 3 Reactor Recirc Pump A trip

3. Reactor Recirc Pump B shaft binding with Thermal Hydraulic Instability Major Transients 1-2 1 1. Main Steam Line D leak in the drywell EOP entries 1. EOP-1A requiring 1-2 2 2. EOP-3A substantive action EOP contingencies requiring 1 per set 1 1. EOP-2A Contingency #2 - Emergency Depressurization substantive action

1. (CT#1) Manually scram the reactor when both recirculation pumps trip, prior to exceeding 25% peak to peak neutron flux oscillations.

2. (CT#2) When torus pressure cannot be maintained below Pre-identified the Pressure Suppression Pressure (PSP)(approximately 2 2 Critical Tasks 25 psig in this scenario), the crew completes Emergency Depressurization prior to exceeding PCPL-A (62.7 psig).

(Anticipating ED and fully opening Bypass valves satisfies this Critical Task)

Normal Events N/A 1 1. Shift CRD pumps Reactivity 1. none N/A 0 Manipulations

1. Critical power panel CPP-1 loss of power

2. Condensate Pump B trip, RR Pump A runs back too far, Reactor Recirc Pump A trip Instrument/ 3. Reactor Recirc Pump B shaft binding with Thermal Component N/A 5 Hydraulic Instability Failures

4. DW Spray A permissive switch failure

5. Torus to Drywell Vacuum Breaker failure, RHR Pumps B and D trip

1. Critical power panel CPP-1 loss of power

2. Condensate Pump B trip, RR Pump A runs back too far, Reactor Recirc Pump A trip

3. Reactor Recirc Pump B shaft binding with Thermal Total Malfunctions N/A 5 Hydraulic Instability

4. DW Spray A permissive switch failure

5. Torus to Drywell Vacuum Breaker failure, RHR Pumps B and D trip Page 3 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 4 of 41 Top 10 systems and operator actions important to risk that are tested:

Primary Containment, RHR, RHRSW Page 4 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 5 of 41 SCENARIO

SUMMARY

The plant is operating at 100% power near the end of the operating cycle.

After the crew takes the watch, the ATC will shift CRD pumps from CRD Pump B in operation to CRD Pump A in operation IAW Procedure 2.2.8.

After CRD pumps have been shifted, narrow range level transmitter NBI-LT-52C fails high, resulting in a half Main Turbine/RFPT trip. The crew will respond IAW the alarm card and Procedure 4.4.1 to diagnose the failure using the RVLCS HMI. The CRS will enter TS 3.3.2.2 Condition A.

After TS for the failed level transmitter have been addressed, 120V AC power panel CPP-1 will lose power. The crew will respond IAW Procedure 5.3AC120.

The BOP will start a turbine building exhaust fan to restore TB HVAC.

After response to loss of CPP-1 is complete, Main Condensate Pump 1B will trip. The crew will respond to CP B trip and enter 2.4MC-RF to address the tripped MC Pump B. At this power level the Reactor Recirc pumps should run back towards 45% speed and stop running back once Condensate pump discharge header pressure restores, which should occur approximately 50%

Reactor Recirc pump speed. However, Reactor Recirc Pump A will continue to runback for several seconds. If the crew identifies RR Pump A continues to run back, they will lockout the RR A scoop tube. This will require entry into 2.4RR.

After a delay RR Pump A will trip. The CRS will enter TS 3.4.1 Condition A &

B due to single loop operation.

After the TS for RR Pump A failure have been addressed, RR Pump B will trip.

The ATC will respond by inserting a manual scram IAW procedure 2.4RR due to no RR Pumps operating and power above 1%. If a manual scram is delayed, thermal hydraulic instability will occur, also requiring a manual scram per 2.4RR (CT#1).

When the reactor is scrammed, a leak develops on MSL D in the drywell.

Drywell pressure and temperature rise. The crew will enter EOP-1A and EOP-3A due to high drywell pressure. Torus Spray will be required. Only RHR Loop B is available for containment spray due to failure of the spray valve control permissive for RHR Loop A. A Torus to Drywell Vacuum Breaker will fail open, requiring use of Drywell Spray.

Drywell Spray will fail a short time after it has been started due to trip of RHR Pumps B and D. Drywell pressure will rise above the Pressure Suppression Pressure (PSP) limit. Emergency Depressurization will be required (CT#2).

Page 5 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 6 of 41 The exercise ends when the reactor has been depressurized, RPV water level is being controlled +3 to +54 inches.

Page 6 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 7 of 41 CRITICAL TASK BASIS Manually scram the reactor when both recirculation pumps trip, Critical Task #1 prior to exceeding 25% peak to peak neutron flux oscillations.

Analyses of neutronic/thermal-hydraulic instabilities(THI) during failure-to-scram conditions have been performed. Instabilities are manifested by oscillations in reactor power, which, if the reactor cannot be shut down, may increase in magnitude. If the oscillations remain small or moderately sized, they tend to repeat on approximately a two second period. Under certain circumstances, however, the oscillations may continue to grow and become Safety Significance sufficiently large and irregular to cause localized fuel damage.

Analytical results indicate that the fuel clad may experience boiling transition during THI but that it subsequently rewets and is adequately cooled even for oscillations that resemble reactivity excursion events. For an occasional large pulse, however, rewetting of some of the highest-powered locations within the highest-powered fuel bundles may not occur; the clad could then continue to heat up over several oscillation cycles.

Cues SRM period alarms.

Oscillating power indications on neutron monitoring instrument.

Operator depresses both manual scram pushbuttons, or places the Measurable Performance Reactor Mode Switch to SHUTDOWN on panel 9-5.

Indicators On panel 9-5:

RPS status lights de-energized.

Performance Feedback Reactor power level trend.

Control rods inserted.

Applicability Operation in the Stability Exclusion Region with no Recirc pump in operation.

The threshold of 25% peak-to-peak neutron flux oscillations has been chosen to ensure an attempt to shut down the reactor using RPS for the same conditions that require boron injection during failure to scram events. Analysis has shown that APRM peak-to-Justification for the peak amplitudes reach 25% of rated thermal power well before any chosen performance individual LPRM signal reaches an amplitude for which fuel damage limit might be possible. Requiring manual reactor shutdown before 25%

peak-to-peak neutron flux oscillations is reasonable to allow a short time to recognize and diagnose THI, communicate plant conditions, and effect the manual scram.

BWR Owners Group App. B, step RC/Q-6 Appendix Page 7 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 8 of 41 Initial power level following the recirc pump trips, with RPV level in the normal band, should be in the Stability Exclusion Region. THI malfunction CR04A or CR04B must be inserted at a ramped severity that will eventually cause 25% peak-to-peak neutron flux Scenario Guide oscillations, but at long enough delay and/or ramp rate to allow the Requirements crew to recognize and diagnose THI, then communicate and insert a manual scram before 25% peak-to-peak neutron flux oscillations are reached.

Page 8 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 9 of 41 When torus pressure cannot be maintained below the Pressure Suppression Pressure (PSP)(approximately 25 psig in this scenario), the crew completes Emergency Depressurization Critical Task #2 prior to exceeding PCPL-A (62.7 psig). (Anticipating ED and fully opening Bypass valves satisfies this Critical Task)

If suppression pool and/or drywell sprays cannot be initiated or are ineffective in reversing the increasing trend of primary containment pressure, as evidenced by not being able to maintain torus pressure below the Pressure Suppression Pressure, the RPV is depressurized to minimize further release of energy from the RPV to the primary containment. This action serves to terminate or reduce as much as possible any continued primary containment pressure increase.

The Pressure Suppression Pressure (PSP) is the lesser of:

The highest torus pressure which can occur without steam in the torus air space.

The highest torus pressure at which initiation of RPV depressurization will not result in exceeding Primary Containment Pressure Limit before RPV pressure drops to the Minimum RPV Flooding Pressure.

Safety Significance

The highest torus pressure which can be maintained without exceeding the suppression pool boundary design load if SRVs are opened.

The Primary Containment Pressure Limit (PCPL) is the lesser of:

The pressure capability of the primary containment.

The maximum primary containment pressure at which vent valves sized to reject all decay heat from the containment can be opened and closed.

The maximum primary containment pressure at which SRVs can be opened and will remain open.

The PCPL is a function of primary containment water level.

Exceeding the limit may challenge primary containment vent valve operability, SRV operability, or the structural integrity of the primary containment.

Cues Rising torus pressure indicated on SPDS and panel 9-3 recorder PC-LRPR-1A.

Cursor approaching unsafe boundary on PSP graph display on SPDS.

Manipulation of any six SRV controls on panel 9-3:

SRV-71A Measurable Performance SRV-71B Indicators SRV-71E SRV-71G SRV-71H Page 9 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 10 of 41 SRV-71C SRV-71D SRV-71F If ED is anticipated, fully opening Bypass valves on Panel B DEH HMI

Bypass valves selected to MANUAL on HMI

Bypass valves A, B, C indicate ~100% on HMI mimic Crew will observe SRV light indication go from green to red, amber pressure switch lights illuminate, reactor pressure lowering on SPDS and panel 9-3 and 9-5 meters and recorders, and SRV tailpipe temperatures rise on recorder MS-TR-166.

Performance Feedback If ED is anticipated, fully opening Bypass valves on Panel B DEH HMI, crew will observe Bypass valves A, B, C in MANUAL at

~100% position and reactor pressure lowering on SPDS and panel 9-3 and 9-5 meters and recorders.

Applicability EOP-3A conditions with energy being added to primary containment (LOCA) and torus/drywell pressure rising.

When torus pressure cannot be maintained below PSP is the EOP-3A, step PC/P-4 criteria requiring transition to emergency depressurization. Failure to ED early enough to avert exceeding Justification for the PCPL-A could result in failure of the containment barrier.

chosen performance limit Depressuring to the Decay Heat Removal Pressure (50 psig) before PCPL-A is exceeded ensures energy discharged to the primary containment will be within the capacity of the containment vent.

BWR Owners Group App. B, step PC/P-2.

Appendix A leak with failure of torus/drywell sprays and failure of a Torus to Drywell vacuum Breaker is normally required to effect exceeding Scenario Guide PSP. It is important to design the scenario such that the crew has Requirements information early during the LOCA event to determine the rising DW pressure cannot be mitigated and that PSP will be exceeded.

Page 10 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 11 of 41 Related Operating Experience SEN 57 Malfunction of Rosemount pressure and differential pressure transmitters Various failures involving loss of sensing fluid or electronics failure.

INPO ICES 307495 Vital 120V Instrument AC Uninterruptable Power Supply Inverter Output Breaker Trip On 2/23/13 Class 1E 120V Instrument (Inst) AC uninterruptable power supply (UPS) inverter IY23 output breaker 52-23B2 tripped at approximately 04:27 and de-energized all of the Class 1E 120V Inst AC PY23 panel loads. The IY23 output breaker tripping rendered the inverter and its respective instrument AC distribution panel PY23 inoperable. Visual inspection, analysis of plant process computer data did not find evidence of a fault. The output breaker was replaced and the PY23 panel was re-energized. The Apparent Cause Analysis did not find a cause for spurious breaker trip and the presumptive cause was due to aging of the electronic trip unit.

(CNS) CR 2006-09515 ANN -ANN -(C-4/F-6), CRIT INST & CONT PNL CPP LOSS OF VOLT Received Received Annunciator ANN -ANN -(C-4/F-6), CRIT INST & CONT PNL CPP LOSS OF VOLT, in and reset. Checked MCC-TX feeder breaker. All conditions normal. No other indications of loss of panel CPP.

INPO ICES 407759 Condensate Pump Breaker Lockout and Pump Trip On 03/05/2017 steam generator water level deviation annunciators alarmed and the main feedwater reg valves were noted to be opening. Subsequently the condensate pump was discovered to be tripped. This resulted in the unit down powering to 90 percent until repairs to the condensate motor could be made. The condensate motor failed due to an electrical short caused by loose stator bolts in the motor. This event is Consequential because of the unplanned downpower.

SER 23-93 Delayed Manual Scram Following a Core Flow Reduction Event And Entry into a Region of Core Instability (Perry) On July 9, 1993, the reactor was operating at 100 percent power when both reactor recirculation pumps unexpectedly downshifted to low speed, placing the reactor in a region of the operating domain susceptible to core thermal-hydraulic instability. The operators manually scrammed the reactor several minutes after entering this region of the power-to-flow map where an immediate manual scram is procedurally required.

Page 11 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 1 Page 12 of 41 (CNS) CR 2007-03555 Stability Exclusion Region of Power-to-Flow Map entered At 0030 5-19-2007 Abnormal Procedure 2.4RR was entered was entered due to entry into the stability exclusion region. The stability exclusion region was entered when the "A" RRMG was secured for planned maintenance. LCO 3.4.1 Condition A was entered and recirc flow was raised to exit the region as required by 2.4RR and LCO 3.4.1.

Page 12 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 13 of 41 SIMULATOR SET-UP A. Materials Required - none B. Initialize the simulator in IC20 or password protected IC, 100% (EOC)

1. Ensure this schedule file is in the schedule file directory:

Schedule File Name - 2020-4sc1.sch

2. Click on Open in the Schedule window and Open Schedule File 2020-4sc1.sch (in the Schedule Directory)

3. In Schedule window, click on the Stopped red block. The red block will change to a green arrow and indicate the schedule file is active (Running).

4. Take the simulator out of freeze.

5. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section C below. (Note: Any actions in the schedule file without a value in the @Time column will not load into the director until the event trigger goes active.)

Page 13 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 14 of 41 C. File loaded verification:

(Continued on next page.)

Page 14 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 15 of 41 Page 15 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 16 of 41 Page 16 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 17 of 41 D. Panel Setup

1. Ensure PMIS IDTs are blank.

2. Ensure RR Controllers are selected to P.

3. Ensure CRD Drive D/P at 265 psid.

4. Ensure CRD Cooling Water flow at 50 gpm.

5. Ensure RWM is initialized.

6. Place CS Pump A in PTL.

7. Hang a caution tag on CS Pump A control switch.

8. Ensure CS A is OOS on safety system status panel on panel 9-5.

9. Place Protected Equipment placard on Panel 9-3 within Core Spray B area.

10. Ensure SSST Y voltage to RRMGs is set to TAP 2.

11. SSST X Voltage card should read TAP POS 3, MAX 4469 and MIN 4361.

12. Ensure IC20, Rod Sequence Notebook under the RO desk.

Page 17 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 18 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 1 Event

Description:

Shift CRD Pumps from B to A in operation Time Position Applicants Action or Behavior CRS Directs ATC to shift CRD Pumps from B to A per Procedure 2.2.8, Section 15.

Booth Role Play: If asked, as Rx Bldg NLO report 2.2.8 step 15.2 is complete for starting CRD Pump A.

Operator Procedure 2.2.8 [Control Rod Drive Hydraulic System]

15. SHIFTING CRD PUMPS 15.1 ESTABLISH communications between Control Room and CRD pump area.

15.2 IF starting CRD-P-1A, THEN ENSURE following: (step 15.2 has been completed per turnover sheet) 15.3 IF starting CRD-P-1B, THEN ENSURE following: (step is N/A) 15.4 At Panel 9-5, PERFORM following to place CRD-FIC-301, CRD FLOW CONTROL, in MAN:

15.4.1 ADJUST manual output knurled knob until DEVIATION needle centered (aligned with redline on settape).

15.4.2 PLACE selector to MAN.

15.5 START standby CRD pump.

ATC CAUTION - CRDM damage could occur during scram if charging water pressure exceeds 1510 psig.

15.6 (Directs NLO to) Locally CHECK for normal pump operation.

15.7 SHUT DOWN CRD pump being removed from service.

15.8 Slowly ADJUST manual control on CRD-FC-301, CRD FLOW CONTROL, to 50 gpm.

15.9 PERFORM following to balance CRD-FC-301:

15.9.1 ADJUST SETPOINT thumbwheel until DEVIATION needle centered (aligned with redline on settape).

15.9.2 PLACE selector to BAL.

15.10 At Panel 9-5, ENSURE following:

Charging water pressure adjusted to 1425 to 1475 psig.

Drive water P adjusted to 260 to 270 psid.

BOP Provides peer check of ATC actions.

END OF EVENT Page 18 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 19 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 1 Event

Description:

Shift CRD Pumps from B to A in operation Time Position Applicants Action or Behavior Notes Booth Proceed to next event After CRD Pump B has been stopped and at the Operator direction of the Lead Examiner.

Page 19 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 20 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 2 Event

Description:

Level transmitter NBI-LT-52C fails high Time Position Applicants Action or Behavior Booth When directed by Lead Examiner, insert TRIGGER 2, RR27C NBI-LT-52C (NR Level) Failure (LI-94C).

Operator Responds to the following alarm:

9-5-2/G-4, RVLC SYSTEM TROUBLE

A-3/G-4, OWC INJECTION SYSTEM TROUBLE(No Operator action, alarm due to FW flow disturbance)

Recognizes and reports narrow range reactor water level rising on NBI-LI-94C.

Per alarm card 2.3_9-5-2/G-4:

1.1 Stop any power changes in-progress.

ATC 1.2 Verify reactor water level is stable. IF reactor water level is unstable, THEN enter Procedure 2.4RXLVL.

1.3 At a RVLC/RFPT HMI, perform following:

1.3.1 Select RVLC System.

1.3.2 Select ACT. ALARM screen.

1.3.3 Determine cause of alarm.

1.4 Refer to Procedure 4.4.1 [Reactor Vessel Level Control System],

Attachment 2, for resolution of condition(s).

May direct ATC to lower power maintain below thermal power limit, 2419 MWt, CRS IAW Procedure 2.1.10.

May direct ATC to bypass RVLC input from NBI-LT-52C per Procedure 4.4.1.

As directed and if necessary, lowers power using Recirc flow IAW 2.1.10

[Station Power Changes]:

Selects S on RR flow controllers on Panel 9-4 7.41 Lower power by lowering RR pump flow. (by turning speed demand counter-clockwise on one speed controller at a time and allowing ATC conditions to stabilize before adjusting the other controller)

Closely monitors scoop tube position/RR pump flow response on Panel 9-4 and APRM recorders on Panel 9-5.

Repeats as necessary to maintain power <100%.

ATC If directed to bypass NBI-LT-52C in RVLCS, per Procedure 4.4.1 section 8:

Page 20 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 21 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 2 Event

Description:

Level transmitter NBI-LT-52C fails high Time Position Applicants Action or Behavior 8.1 At a RVLC/RFPT HMI, select RVLC System.

8.2 Select MAINT. screen.

8.3 Review disabled parameter points to determine impact of additional bypassing of parameter points (i.e., loss of 3 element selection, loss of AUTO on MASTER LEVEL Controller, loss of LT-59D, etc.). (Determines no other points are bypassed.)

8.4 On MAINT. screen, select desired parameter. (NBI-LT-52C mLT0052C)

ATC Reports that NBI-LT-52C cannot be bypassed because it has a status of invalid.

BOP Provides peer check of ATC actions.

CRS Determines entry into TS 3.3.2.2 Condition A is required.

TS 3.3.2.2 CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.1 Place channel in trip. 7 days turbine high water level trip channel inoperable.

END OF EVENT Notes Booth Proceed to next event when directed by the Lead Examiner.

Operator Page 21 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 22 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 3 Event

Description:

Critical power panel CPP-1 loss of power Time Position Applicants Action or Behavior When directed by the Lead Examiner, insert TRIGGER 3, ED11d Loss of CPP-1 Booth Role Play: If directed as the building operator to investigate CPP-1, wait 2 Operator minutes, then report the CPP-1 supply feeder is closed and you see nothing abnormal.

WCO/BOP Respond to the following alarms:

R-1/A-1, TURBINE BLDG HV-T-1A FAN FAILURE

R-1/A-2, TURBINE BLDG HV-T-1B FAN FAILURE

R-1/A-3, TURBINE BLDG HV-T-1C FAN FAILURE

R-1/B-1, TURBINE BLDG EXH FAN A FAILURE BOP

R-1/B-2, TURBINE BLDG EXH FAN B FAILURE

R-1/C-2, TURBINE BLDG EXH FAN D FAILURE

R-1/B-3, TURBINE BLDG LESS THAN 2 EXH FANS ON

C-3/G-1, MAIN GEN VOLTAGE REG TROUBLE

Multiple Generator H2 Alarms due to loss of CPP-1 Reports loss of CPP-1 power.

Enters Procedure 5.3AC120 [Loss of 120 VAC] with priority on loss of CPP-1, Attachment 8.

CRS May enter 2.4HVAC [Building Ventilation Abnormal] (action only required if TB ventilation cannot be restored).

Role Play: (Note: 5.3AC120 Att 8 step 1.2.4 states Close TEC-201, HYDROGEN COOLER TCV-428 OUTLET (Heater Bay south).

Booth If contacted as TB NLO to close TEC-201, wait 2 minutes, then toggle ON and OFF override A-1 C-2 TG Bldg Corridor to SW Heater Bay Door Open Operator (an:p4228) to simulate going through door during ingress and egress, then insert Remote Function SW53 to to the position directed by the WCO/BOP or to 0% (trigger 13).

Note to Examiners: At Lead Examiners discretion, may proceed to Event 4 after a Turbine Building exhaust fan has been started.

BOP Performs 5.3AC120 Att. 8, as directed:

Page 22 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 23 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 3 Event

Description:

Critical power panel CPP-1 loss of power Time Position Applicants Action or Behavior 1.1 Place one Turbine Building exhaust fan switch to RUN.

1.2 Concurrently perform following to control Main Generator H2 temperatures:

1.2.1 Monitor Average Generator H2 Cold Gas temperature on PMIS Points G023 and/or G024 1.2.2 IF PMIS Points G023 and G024 invalid, THEN monitor individual cooler temperatures: (Step is N/A) 1.2.3 Throttle TEC-MO-149 to maintain Main Generator cold gas temperature at 100°F to 110°F.

1.2.4 Directs NLO to close TEC-201, HYDROGEN COOLER TCV-428 OUTLET.

1.3 Directs NLO to control Main Generator exciter temperatures per 5.3AC120 Att. 8, step 1.3.

Role Play: If contacted as TB NLO to acknowledge alarm (CTLRSW) at the Booth Voltage Regulator Operators Panel, wait 2 minutes, then IRF EG07 Main Operator Generator Alarm Acknowledge or activate TRIGGER 23 to insert override AN:P4047, C-3/G-1 Main Gen Voltage Reg Trouble, to OFF.

Per Alarm card C-3/G-1:

1.1 Send Operator to Voltage Regulator Operator's Panel (T-903-S) to BOP acknowledge and determine which alarms remain active by using Procedure 2.2.14, Operation Of Main Gen Volt Reg Alarm System attachment, as required.

END OF EVENT Notes Booth Proceed to next event when directed by the Lead Examiner.

Operator Page 23 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 24 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 4 Event

Description:

Condensate Pump B trip, RR Pump A runs back too far, Reactor Recirc Pump A trip Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 4, FW14A Condensate Pump A trip.

Auto trigger 14 should go active during the runback when RR Pump A scoop Booth tube lowers to 30%. These triggers cause RR Pump A speed to continue to Operator lower after the runback is complete.

Role Play: If sent to investigate CP A breaker trip, wait 5 minutes and report CP A breaker is tripped on overcurrent. If sent to CP A to investigate, wait 5 minutes and report you see nothing abnormal in the vicinity of CP A.

NOTE to Examiners: RR Pump A speed ramps to 30% in 5 seconds. It is not expected that the operator will have time to lock out the scoop tube in time to mitigate the failure.

RR Pump A trips 3 minutes after the runback.

Recognizes and responds to alarms:

A-3/A-2 Cond Pump B Trip

A-3/B-2 Cond Pump B Ovld/Ground BOP Reports Condensate Pump B trip.

Checks Condensate Booster and RFP suction pressures remain above trip setpoints.

Enters 2.4MC-RF [Condensate and Feedwater Abnormal].

CRS Directs WCO/BOP perform subsequent actions of 2.4MC-RF for trip of a single CP.

Monitors RR runback and RPV water level being maintained.

Updates crew of scram actions from 2.4MC-RF.

ATC Monitors and reports point of operation on Power/Flow Map remains outside or on the edge of the Buffer Zone.

If in the Buffer Region takes action per 2.1.10, Section 12 Recognizes and reports RR runback complete but RR Pump A speed lowered ATC to 30%.

Enters 2.4RR [Reactor Recirculation Abnormal].

CRS May direct locking out RR A scoop tube.

Assigns WCO/BOP 2.4RR Attachment 4 actions.

If directed, locks out RR scoop tube by depressing RR A Scoop Tube Lockout ATC/BOP pushbutton on panel 9-4.

Page 24 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 25 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 4 Event

Description:

Condensate Pump B trip, RR Pump A runs back too far, Reactor Recirc Pump A trip Time Position Applicants Action or Behavior Checks and reports RR loop A and B flows exceed mismatch limit.

Reports operation on edge of Buffered Region of Power/Flow Map.

Responds to alarms:

9-4-3/A-2, RRMG A BKR 1CN TRIP

9-4-3/B-2, RRMG A BKR 1CN LOCKOUT ATC/BOP

9-4-3/C-1, RRMG A LOCKOUT

9-4-3/E-3, RECIRC LOOP A OUT OF SERVICE Reports RR Pump A trip.

Monitors and reports operation still in Buffered Region/Stability Exclusion Region of the Power to Flow Map.

Re-enters procedure 2.4RR for trip of RR Pump A and entry into Stability CRS Exclusion Region of the Power to Flow Map.

Directs 2.4RR Attachment 3 to be performed.

Note to Examiners: Control Rods 26-19, 26-35, 18-27, 34-27, and 10-19 must be inserted to exit the Stability Exclusion Region of the Power-to-Flow Map.

Performs 2.4RR Attachment 3 actions:

1.1 Inform Shift Manager LCO 3.4.1, Condition A, entry required.

1.2 Monitor for abnormal neutron flux oscillations by:

1.2.1 NOISE Program on PMIS computer to monitor peak-to-peak fluctuations of LPRMs and APRMs.

1.2.2 LPRMs using control rod select switch to display LPRM strings which surround following control rods:

ATC 10-43 26-43 42-43 10-27 26-27 42-27 10-11 26-11 42-11 1.2.3 SRM period, APRM, and LPRM indications 1.3 Exit region by performing either or both of following:

1.3.1 Raise speed of operating recirculation pump(s) per Procedure 2.1.10. (crew is NOT expected to exit region by this method)

Page 25 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 26 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 4 Event

Description:

Condensate Pump B trip, RR Pump A runs back too far, Reactor Recirc Pump A trip Time Position Applicants Action or Behavior 1.3.2 Insert Emergency Power Reduction Rods per Procedure 10.13.

1.4 Inform Reactor Engineering if Stability Exclusion Region has been entered.

CRS Determines entry into TS 3.4.1 Condition A & B is required.

TS 3.4.1 CONDITION REQUIRED ACTION COMPLETION TIME Immediately A. One or two recirculation A.1 Initiate action to exit the stability loops in operation with exclusion Region.

core flow as a function of core THERMAL POWER in the Stability Exclusion Region of the power/flow map.

B. Requirements of the B.1 Satisfy the requirements of the LCO. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met for reasons other than Condition A END OF EVENT Notes Booth Proceed to next event when directed by the Lead Examiner.

Operator Page 26 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 27 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 5 Event

Description:

Reactor Recirc Pump B binding, neutron flux oscillations Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 5, RR03B Recirc Pump B Booth shaft binding/trip.

Operator NOTE to Examiners: RR Pump B trips ~ 20 seconds after Trigger 5 is activated. Automatic scram signals are defeated in order to require the ATC to insert a manual scram, even if the APRM high flux scram setpoint is reached due to THI. The next event, MSL D leak in the drywell, begins ramping in 3 minutes after the crew scrams.

Recognizes and reports RR Pump B alarms:

9-4-3/E-4, RECIRC A/B PUMP MOTOR HI/LOW TEMP

9-4-3/C-7, RECIRC B PUMP MOTOR HI VIBRATION

9-4-3/C-5, RRMG B LOCKOUT

9-4-3/A-5, RRMG B BKR 1DS TRIP

9-4-3/E-7, RECIRC LOOP B OUT OF SERVICE ATC Inserts manual scram IAW 2.4RR:

3. Immediate Operator Actions 3.1 IF both RR pumps are tripped and reactor power > 1% rated thermal, THEN perform following:

3.1.1 SCRAM 3.1.2 Enter procedure 2.1.5 Re-enters 2.4RR.

CRS Directs manual scram.

CRITICAL TASK #1: Manually scram the reactor when both recirculation pumps trip, prior to exceeding 25% peak to peak neutron flux oscillations or APRM auto scram setpoint due to neutron flux oscillations.

Perform 2.1.5 [Reactor Scram] Attachment 1 Mitigating Task Scram Actions:

1.1 Press both RX SCRAM buttons.

1.2 Place REACTOR MODE switch to REFUEL.

ATC 1.3 IF reactor power > 3%, THEN perform following:

1.3.1 Place REACTOR MODE switch to SHUTDOWN.

Page 27 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 28 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 5 Event

Description:

Reactor Recirc Pump B binding, neutron flux oscillations Time Position Applicants Action or Behavior 1.3.2 Initiate ARI.

Perform Attachment 2 Reactor Power Control of 2.1.5 as follows:

1 REACTOR POWER CONTROL 1.1 Ensure REACTOR MODE switch is in SHUTDOWN.

1.2 Verify all SDV vent and drain valves are closed.

ATC 1.3 Ensure operating RR pumps have run back to 22% speed (already tripped) 1.4 Verify all control rods are fully inserted.

1.5 Observe nuclear instrumentation and perform following:

1.5.1 Insert SRM detectors.

1.5.2 Insert IRM detectors.

1.5.3 Change APRM recorders to IRMs.

1.5.4 Range IRMs on scale.

1.5.5 Check reactor power is lowering.

Verifies turbine trip IAW 2.2.77 [Main Turbine], Att. 2 hard card:

1.1 Simultaneously DEPRESS TURB TRIP 1 and TURB TRIP 2 buttons, and then check following; N/A if turbine automatically tripped:

1.2 VERIFY following valves closed (Panel B, DEH Main display):

Both stop valves.

BOP

All governor valves.

All reheat stop valves.

All interceptor valves.

1.3 ENSURE following breakers open(Panel C):

1.3.1 345KV BUS, PCB-3310.

1.3.2 345KV BUS, PCB-3312.

1.3.3 GEN EXCITER FIELD BKR.

Page 28 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 29 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 5 Event

Description:

Reactor Recirc Pump B binding, neutron flux oscillations Time Position Applicants Action or Behavior Enters EOP-1A [RPV Control] on low reactor water level due to scram.

Directs BOP to:

Stabilize Rx pressure <1050 psig using Table 1 systems

Assigns Rx pressure band 800 - 1050 psig EOP 1A Pressure CRS Directs ATC to:

Maintain level +3 to + 54 using feedwater CRS ATC Maintains level +3 to + 54 using feedwater, as directed.

END OF EVENT Page 29 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 30 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 5 Event

Description:

Reactor Recirc Pump B binding, neutron flux oscillations Time Position Applicants Action or Behavior Notes The next event, MSL D leak in the drywell, is automatically triggered when a scram Booth is inserted (TRIGGER 6). The steam leak begins ramping in 3 minutes after the Operator crew scrams.

Page 30 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 31 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior Reports drywell pressure/temperature rising.

CREW Announces EOP-1A and EOP-3A entry condition on high DW pressure.

Re-enters EOP-1A.

Directs verifying initiations per EOP-1A step RC/L-1:

CRS Directs performing cooldown per EOP1A Step RC/P-7:

Page 31 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 32 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior Enters EOP-3A [Primary Containment Control].

Directs PC Sprays IAW EOP-3A step PC/P-4 and/or PC/P-5.

Directs Drywell pressure maintained between +2 psig and +10 psig.

CRS Directs BOP to place DW Coolers in override IAW EOP-3A step DW/T-3:

CRS Page 32 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 33 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior (EOP-1A step RC/P-1) Directs WCO/BOP to prevent injection from LPCI and Core Spray.

CRS Performs EOP-1A actions as directed

Verifies ECCS initiations o HPCI Controls HPCI flow rate to maintain level +3 to +54.

ATC/BOP o LPCI o Core Spray

Checks DG1 and DG2 are operating, with Service Water.

Places DW FCU A, B, C, D to OVERRIDE on VBD-H

Verifies group isolations as directed using 2.1.22 hard card NOTE to Examiners: The Containment Spray cooling valve permissive switch will fail for the first RHR loop attempted to be placed in Torus spray, preventing operation of spray valves for that loop. The following steps are written assuming RHR A will be attempted first. If RHR B is started first, failure of its Containment Spray cooling valve permissive switch will require the operator to use RHR A to spray.

Role Play: If asked to install EOP PTM 97-100, wait 7 minutes, then insert Remote Functions RH46 (EOP PTM 97 & 98) at INSTALL, and RH47 (EOP PTM 99 & 100) at INSTALL. If already pre-staged to install EOP PTMs97-100, wait 3 minutes then install the PTMs.

Role Play: (Note: procedure 0.31MOV step 6.4 requires de-energizing an MOV Booth before attempting manual operation)

Operator If requested to manually open RHR-MO31A, wait 2 minutes, then insert remote function rh23a to deenerg.

If requested to manually open RHR-MO26A, wait 2 minutes, then insert remote function rh19a to deenerg.

Then 1 minute later, report MO-31A and MO-26A are bound and can NOT be manually opened.

Page 33 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 34 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior BEFORE torus pressure reaches 10 psig, initiates Torus spray per 2.2.69.3

[RHR Suppression Pool Cooling and Containment Spray] hard card (depends on scenario timing and crew actions):

2.1 If required, with CRS permission, PLACE CONTMT COOLING 2/3 CORE VALVE CONTROL PERMISSIVE switch to MANUAL OVERRD.

2.2 If required, PLACE CONTMT COOLING VLV CONTROL PERMISSIVE switch to MANUAL.

2.3 IF reactor pressure less than or equal to 300 psig and injection not desired, THEN CLOSE RHR MO 27A(B), OUTBD INJECTION VLV.

2.4 ENSURE RHR PUMP(s) running.

2.5 If Torus spray required, THEN PERFORM the following:

2.5.1 ENSURE RHR-MO-39A(B) open.

2.5.2 THROTTLE RHR-MO-38A(B) to maintain desired containment BOP pressure.

For RHR A, recognizes and reports MO-39A will not open, shifts to RHR Loop B, and repeats above steps, then continues at next step.

2.7 If PCIS Group 6 lights lit on Panel 9-5, THEN ENSURE one of following open:

REC-MO-711

REC-MO-714 2.8 PLACE RHR SW System in service:

START SWBP(s).

ADJUST SW-MO-89A(B) to maintain flow between 2500 and 4000 gpm.

2.9 THROTTLE RHR-MO-66A(B) to maintain desired cooling rate.

Page 34 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 35 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior Prevent injection for LPCI and Core Spray IAW EOP 5.8 [Emergency Operating Procedures (EOPs)] Att. 4 HARD CARD:

2.1 Prevents both RHR Subsystems by performing one of following in each loop:

2.1.1 Both RHR Systems secured with pumps in PULL-TO-LOCK. (This step will not be performed for RHR B due to it being used for PC Spray.)

2.1.2 IF RPV pressure is maintained 500 psig, THEN operate RHR aligned to suppression pool cooling and/or containment spray per Procedure 2.2.69.3; and 2.1.2.1 Bypass RHR outboard injection valves automatic open signal BOP per Procedure 5.8.20 (PTMs 97 through 100) with injection valves closed.

2.1.3 RHR outboard injection valves automatic open signal bypassed per Procedure 5.8.20 (PTMs 97 through 100) with injection valves closed.

2.3 Prevents CS by performing following:

2.3.1 Ensure CS-MO-12A is closed. (N/A due to CS A is out of service) 2.3.2 Ensure CS Pump A control switch in PULL-TO-LOCK. (N/A due to CS A is out of service and already in PTL))

2.3.3 Ensure CS-MO-12B is closed.

2.3.4 Ensure CS Pump B control switch in PULL-TO-LOCK.

NOTE to Examiners: Auto Trigger 8 initiates Events 8, and 9 Torus to DW vacuum breaker failure and RHR B (30 second delay), D (120 second delay) pump trips and RHR A Containment Spray logic will fail. Trigger 8 will go active when PC spray has reduced DW pressure to ~8 psig.

Events 8 and 9 are automatically triggered (TRIGGER 8) when DW Spray reduces DW pressure to ~8psig.

Booth Operator Action: If the crew sprays the Drywell based on elevated Drywell temperature before Drywell pressure reaches 10 psig, then manually trigger Event 8 when Drywell pressure lowers below 8 psig.

2.2.69.3, Att 1 (Hard Card)

BOP When Torus pressure exceeds 10 PSIG Spray the Drywell:

Page 35 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 36 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 6, 7 Event

Description:

MSL D leak in the drywell, Containment Spray permissive switch failure Time Position Applicants Action or Behavior 2.6 IF drywell spray required, THEN PERFORM following:

2.6.1 OPEN RHR-MO-31A(B).

If attempted for RHR A, recognizes and reports MO-31A will not open.

2.6.2 THROTTLE RHR-MO-26A(B) to maintain desired containment pressure.

May attempt to open RHR-MO-20, CROSSHEADER VLV PER 2.2.69.3, Section 4, PLACING RHR SUBSYSTEM A SUPPRESSION POOL COOLING TO RHR SUBSYSTEM B IN SERVICE USING RHR-MO-20 END OF EVENT Notes Booth Events 8 and 9 are automatically triggered (TRIGGER 8) when DW Spray reduces Operator DW pressure to ~8psig. Proceed to next event when TRIGGER 8 goes true.

Page 36 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 37 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 8 Event

Description:

Torus to DW vacuum breaker failure, RHR Pump B trip, RHR Pump D trip.

Time Position Applicants Action or Behavior Reports trip of RHR Pump B.

Reports trip of RHR Pump D.

CREW Reports DW pressure rising.

Diagnoses failure of Torus to DW vacuum breaker based on reduction of Torus to DW dp.

IAW EOP-1A step RC/P-1, anticipates emergency depressurization will be required per EOP-3A step PC/P-6 due to DW pressure rising at a rate that will exceed PSP.

(EOP-3A step PC/P-6)

CRS (EOP-1A step RC/P-1)

Provides update that emergency depressurization is anticipated.

Directs WCO/BOP to fully open bypass valves IAW 2.2.77.1 [Digital Electro-Hydraulic (DEH) Control System].

Manually opens Bypass valves IAW 2.2.77.1 Att. 1 hard card:

3.1 On BYPASS VALVE POSITION control, press OPEN to access controls.

3.2 Press MANUAL button and check it backlights yellow.

BOP 3.3 On BYPASS VALVE POSITION control, use UP/DOWN, JOG UP/JOG DOWN and FAST/SLOW controls to adjust BYPASS VALVE POSITION to desired value (fully open).

Page 37 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 38 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 8 Event

Description:

Torus to DW vacuum breaker failure, RHR Pump B trip, RHR Pump D trip.

Time Position Applicants Action or Behavior When Torus pressure cannot be maintained in the safe zone of the PSP graph,

ensures injection source is available

exits EOP-1A pressure leg and enters EOP-2A [Emergency RPV Depressurization]

Requests mark PC water level >6ft for EOP-2A step RC/P-12

Directs WCO/BOP to open 6 SRVs CRS CRITICAL TASK #2: When torus pressure cannot be maintained below the Pressure Suppression Pressure (PSP)(approximately 25 psig in this scenario), the crew completes Emergency Depressurization prior to exceeding PCPL-A (62.7 psig). (Anticipating ED and fully opening Bypass valves satisfies this Critical Task)

Reports PC water level.

Places control switches for 6 SRVs in OPEN.

BOP Monitors reactor pressure and when RPV pressure reaches 50 psig, reports emergency depressurization is complete.

CRS Directs ATC to maintain normal level band +3 to +54 using Condensate System.

Monitors Condensate for injection via startup level control.

ATC When ED is complete, controls Condensate to restore/maintain +3 inches to +54 inches.

Page 38 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 39 of 41 Op-Test No.: CNS 2020-4 Scenario No.: 1 Event No.: 8 Event

Description:

Torus to DW vacuum breaker failure, RHR Pump B trip, RHR Pump D trip.

Time Position Applicants Action or Behavior NOTE to Examiners: Scenario objectives have been met when the crew has commenced lowering reactor pressure, OR at Lead Examiners discretion.

END OF SCENARIO Notes Booth When directed by the Lead Examiner, place the simulator in freeze and tell Operator the crew to stop operating.

Page 39 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 1 Page 40 of 41 IX. INITIAL CONDITIONS A. Plant Status:

1. 100% power, steady state, near End of Cycle.

B. Tech. Spec. Limitations in effect:

1. Day 1 of 7 day LCO per 3.5.1 A.1 for Core Spray A INOPERABLE.

C. Significant problems/abnormalities:

1. Core Spray Pump A tagged out for motor preventive maintenance.

2. CS B is protected.

D. Risk :

1. PRA Risk is Green

2. Aggregate Risk is 0 E. Evolutions/maintenance for the on-coming shift:

1. Per SOP 2.2.8, Section 15, shift CRD Pumps from B to A in operation.

Prestart checks are complete per step 15.2.

2. Continue full power operation.

3. Continue maintenance on Core Spray Pump A motor.

Page 40 of 41 Rev 2

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 4/2020 Scenario 1 Page 41 of 41 Form Password is pepetf Activities Planned or in Progress: Core Spray Pump A motor preventive maintenance window Risk Green Rev: 0 Page 1 of 1 Creation Date: Current SM Review: Shift Manager Window Start: Yesterday Window Close: Tomorrow Sign(s)

Number Installed Removed Protected Sign Placement of Initials/ Initials/

Equipment Location Sign(s)* Date Date Magnetic sign on door:

Core Spray Loop B 1 NLO R105, R-903-SE Quad CS Pump B 4160 Bkr Magnetic Sign On: EE-CB- 1 NLO 4160G(CSP1B)

MCC-Y Barrier erected and Sign 1 NLO Posted: Around MCC-Y CS-Loop B controls panel 9-3 Magnetic sign placed on 1 WCO panel 9-3: within CS B area Page 41 of 41 Rev 2

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 1 of 49 Facility: Cooper Nuclear Station Scenario No.: 3 Op-Test No.: CN-2020-04 Examiners: ____________________________ Operators: _____________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Raise reactor power using Reactor Recirculation flow

2. Respond to a control rod drifting out

3. Respond to Service Water Pump C trip

4. Respond to Circulating Water pump inlet screen clogging and partial loss of CW pumps, resulting in degraded condenser vacuum

5. Respond to complete loss of Circulating Water pumps, loss of condenser vacuum

6. Respond to hydraulic block ATWS

7. Respond to failure of Reactor Recirc Pump B to trip on ATWS/RPT

8. Respond to SLC B relief valve failing open

9. Respond to trip of RHRSWB pump operating for Suppression Pool Cooling Initial Conditions: Plant operating at 97% power following a sequence exchange near middle of cycle.

Inoperable Equipment: Core Spray Pump A is tagged out of service for motor PMs.

Turnover:

Plant operating at 97% power following a sequence exchange near middle of cycle.

Core Spray Pump A is tagged out of service for motor PMs.

Planned activities for this shift are:

Raise power to 100% IAW Procedure 2.1.10. There are NO preconditioning holds.

Continue maintenance on CS Pump A.

Scenario Notes:

This is a new scenario.

Validation Time: 60 minutes Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 2 of 49 Event Malf. No. Event Type Event No. Description Raise reactor power using Reactor Recirculation 1 N/A R (ATC,CRS) flow Control rod 18-19 drifts out CT#1 C When an inadvertent reactivity addition occurs (ATC,BOP,CRS) (in this case, rod drift out) that would cause 2 rd101819 power to rise above 100% rated thermal power, A (CREW) crew lowers power to restore and maintain TS (CRS) power 100% rated thermal power by inserting the control rod and/or lowering Reactor Recirc flow before PMIS point NSSRP641 (30 minute power average) exceeds 2419 MWt.

C (BOP,CRS) 3 sw01c Service Water Pump C trip TS (CRS) mc06a mc05a C (ATC,CRS) Circulating Water pump inlet screen clogging and 4 partial loss of CW pumps, resulting in degraded mc03a,b,c,d A (CREW) condenser vacuum Complete loss of Circulating Water pumps, loss of mc05b,c,d condenser vacuum, hydraulic block ATWS mc01 CT#2 When control rods fail to scram and energy is rd02a discharging to the primary containment (e.g.

5 M (CREW) rd02b SRVs, LOCA), crew initiates SLC injection or inserts all control rods to at least position 02 (override) before exceeding the Boron Injection Initiation Temperature (BIIT) curve.

zdiarsw150mv Failure of Reactor Recirc Pump B to trip on 6 rr24b C (ATC,CRS) ATWS/RPT 7 sl03b C (ATC,CRS) SLC B relief valve fails open 8 sw04a(b, c, or d) C (BOP,CRS) First RHRSWB pump started for Suppression Pool Cooling trips (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

Critical Task (As defined in NUREG 1021 Appendix D)

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 3 of 49 Quantitative Attributes Table ES-301-4 Actual Attribute Description Target

1. Failure of Reactor Recirc Pump B to trip on ATWS/RPT Malfunctions after 2. SLC B relief valve fails open 1-2 3 EOP entry 3. First RHRSWB pump started for Suppression Pool Cooling trips

1. Control rod 18-19 drifts out

2. Circulating Water pump inlet screen clogging and partial Abnormal Events 2-4 2 loss of CW pumps, resulting in degraded condenser vacuum

1. Complete loss of Circulating Water pumps, loss of Major Transients 1-2 1 condenser vacuum, hydraulic block ATWS EOP entries 1. EOP-3A requiring 1-2 2 2. EOP-6A substantive action EOP contingencies requiring 1 per set 1 1. EOP-7A Contingency #5 - Level/Power Control substantive action

1. (CT#1) When an inadvertent reactivity addition occurs (in this case, rod drift out) that would cause power to rise above 100% rated thermal power, crew lowers power to restore and maintain power 100% rated thermal power by inserting the control rod and/or lowering Reactor Recirc flow before PMIS point NSSRP641 (30 minute Pre-identified power average) exceeds 2419 MWt.

2 2 Critical Tasks

2. (CT#2) When control rods fail to scram and energy is discharging to the primary containment (e.g. SRVs, LOCA), crew initiates SLC injection or inserts all control rods to at least position 02 before exceeding the Boron Injection Initiation Temperature (BIIT) curve.

Normal Events N/A 1 1. none Reactivity 1. Raise reactor power using Reactor Recirculation flow N/A 1 Manipulations

1. Control rod 18-19 drifts out

2. Service Water Pump C trip

3. Circulating Water pump inlet screen clogging and partial loss of CW pumps, resulting in degraded Instrument/ condenser vacuum Component N/A 6 4. Failure of Reactor Recirc Pump B to trip on Failures ATWS/RPT

5. SLC B relief valve fails open

6. First RHRSWB pump started for Suppression Pool Cooling trips Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 4 of 49

1. Control rod 18-19 drifts out

2. Service Water Pump C trip

3. Circulating Water pump inlet screen clogging and partial loss of CW pumps, resulting in degraded condenser vacuum Total Malfunctions N/A 6

4. Failure of Reactor Recirc Pump B to trip on ATWS/RPT

5. SLC B relief valve fails open

6. First RHRSWB pump started for Suppression Pool Cooling trips Top 10 systems and operator actions important to risk that are tested:

RPS, RHR, RHRSW Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 5 of 49 SCENARIO

SUMMARY

The plant is operating at 97% power during power ascension.

After the crew takes the watch, the crew raises power to 100% using Reactor Recirculation flow control.

After the crew has raised power, control rod 18-19 drifts out. The crew responds IAW Procedure 2.4CRD and inserts rod 18-19, but the rod does not latch. The crew scrams rod 18-19 IAW Procedure 2.4CRD and it then latches.

The crew must insert rod 18-19 and/or lower Reactor Recirc flow to prevent the 30-minute power average from exceeding the License Condition limit (CT#1).

The CRS enters TS 3.1.3 Condition C for rod 18-19.

After the TS for rod 18-19 has been addressed, Service Water Pump C will trip.

The BOP will start SW Pump B IAW the alarm card. The CRS will enter TS 3.7.2 Condition A for SW Pump C.

After the TS for SW Pump C has been addressed, Circulating Water travelling screens will begin to block due to river debris. After a delay, CW Pump A will trip, followed later by CW Pump B. Condenser vacuum will lower. The crew will respond IAW Procedure 2.4VAC and lower power to stabilize condenser vacuum.

After power has been lowered and vacuum stabilized, CW Pumps C and D will trip due to travelling screen failure. The crew will insert a manual scram IAW Procedure 2.4VAC when vacuum cannot be maintained above 23 Hg.

When the reactor is scrammed, control rods will fail to insert due to blockages in both scram discharge volumes. Reactor power will be approximately 30%.

EOP-6A and 7A are entered via EOP-1A. Reactor Recirc Pump B to trip on ATWS/RPT requiring the operator to manually tip the Recirc Pump. The crew injects SLC and installs the necessary PTMs to bypass interlocks and insert control rods individually via RMCS. MSIVs will close on low condenser vacuum. With MSIVs closed and SRV operating to control reactor pressure, either SLC must be initiated or all controls rods inserted to at least position 02 before Suppression Pool temperature exceeds the Boron Injection Initiation Temperature (BIIT) curve (CT#2). SLC B relief valve will fail open when SLC Pump B is started.

Stop and Prevent is required because reactor power is above 3%. RPV level is intentionally lowered below -60 inches wide range in order to lower core inlet subcooling and lower reactor power. ADS is inhibited when EOP-7A is entered Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 6 of 49 to avert uncontrolled depressurization due to lowering level. HPCI and RCIC are available for RPV level control.

Suppression Pool Cooling will be required due to SRV operation. The RHRSWB pump associated with the first loop of SPC attempted to be placed into service will trip, requiring the operator to start the other SWB pump in that RHR loop or transition to the other RHR loop for SPC.

Once several control rods have been inserted, the ATC begins alternately resetting RPS, driving rods individually while allowing the SDV to drain, and reinserts a manual scram. All control rods will fully insert upon the scram. The CRS will transition from ATWS to non-ATWS flowcharts, SLC pumps are stopped, and RPV level restoration is directed.

The exercise ends when control rods are inserted or Hot Shutdown Boron weight has been injected, and the CRS has reset the level band to +3 to +54.

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 7 of 49 CRITICAL TASK BASIS When an inadvertent reactivity addition occurs (in this case, rod drift out) that would cause power to rise above 100% rated thermal power, crew lowers power to restore and maintain power 100%

Critical Task #1 rated thermal power by inserting the control rod and/or lowering Reactor Recirc flow before PMIS point NSSRP641 (30 minute power average) exceeds 2419 MWt.

License Condition C.1 states 2419 MWt is the Maximum Power Level authorized. The licensed 100% power limit is a basis for assumptions in the plants safety analysis. Sustained operation above 2419 MWt may Safety Significance place unit operation outside of the plant design basis. NUREG 1021 App. D, section D states a CT must be essential to safety, and lists actions to for which operation or correct performance prevents violation of a facility license condition as one example of a CT.

Cues Annunciators 9-5-1/C-4, Rod Drift, Red drift LED lit for rod 18-19 on full core display on panel 9-5, When selected, control rod 18-19 position rising on panel 9-5, Reactor power rising indicated on IRM/APRM recorders NM-NR-46A-D, SPDS, PMIS.

Operator selects rod 18-19 and places Emergency Notch Override switch to EMER ROD IN on panel 9-5, and/or Operator Selects S on Measurable RR flow controllers RRFC-SIC-16A(B) on panel 9-4 and lowers RR Performance pump flow (by turning speed demand counter-clockwise on one speed Indicators controller at a time) until power stabilizes below 100% on IRM/APRM recorders NM-NR-46A-D.

Reactor power stabilizes below 100% on IRM/APRM recorders NM-NR-Performance 46A-D and on PMIS points NSSRP640, NSSRP641, NSSRP642, Feedback NSSRP643, and NSSRP645.

Applicability Any time a rod drift out would cause reactor power to exceed 100% with no operator intervention.

License Condition C.1 lists 2419 MWt as the Maximum Power Level for CNS. Procedure 2.1.10, Station Power Changes, sections 10 and 11 describes the methodology for adherence to this limit. A note at step 11.1 states Minor power fluctuations due to automatic control system response, random processes such as bi-stable flow, and flow meter measurement uncertainties are inherent to BWR operating Justification for the characteristics. Small, short-term fluctuations in power that are not under the direct control of a Licensed Reactor Operator are not chosen performance considered intentional. Step 11.1 states It is prohibited to intentionally limit operate greater than the applicable licensed power limit as determined in Section 10. If core thermal power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average calculation exceeds applicable licensed power limit, action shall be taken to ensure subsequent hourly average remains less than or equal to applicable limit. Step 11.4 directs monitoring and maintaining PMIS Point NSSRP643 (running 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average) and PMIS Point NSSRP645 (running 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months average) below 2419 MWt. The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months point is the legal Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 8 of 49 record for plant power level. PMIS point NSSRP641 (30 minute average) was chosen because it is more limiting and provides timely update to maintain adequate margin to the core thermal power limit.

BWR Owners Group N/A Appendix Scenario Guide Initial power level must be near 100% and the rod drift out must cause Requirements reactor power to rise above 100% with no operator intervention.

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 9 of 49 Category EOPS When control rods fail to scram and energy is discharging to the primary containment (e.g. SRVs, LOCA), crew initiates SLC injection or inserts all control rods to at least position 02 Critical Task #2 before exceeding the Boron Injection Initiation Temperature (BIIT) curve.

Failure to effect shutdown of the reactor when a RPS setting has been exceeded would unnecessarily extend the level of degradation of the safety of the plant. This could further degrade into damage to the principle fission product barriers if left unmitigated. Action to shut down the reactor is required when RPS and control rod drive systems fail.

The Boron Injection Initiation Temperature (BIIT) is the greater of:

The highest suppression pool temperature at which initiation of boron injection will permit injection of the Hot Shutdown Boron Weight of boron before suppression pool temperature exceeds the Heat Capacity Temperature Limit.

The suppression pool temperature at which a reactor scram is required by plant Technical Specifications.

Safety Significance The BIIT is a function of reactor power. If boron injection is initiated before suppression pool temperature reaches the BIIT, emergency RPV depressurization may be precluded at lower reactor power levels. At higher reactor power levels, however, the suppression pool heatup rate may become so high that the Hot Shutdown Boron Weight of boron cannot be injected before suppression pool temperature reaches the Heat Capacity Temperature Limit even if boron injection is initiated early in the event. Since failure-to-scram conditions may present severe plant safety consequences, the requirement to initiate boron injection is independent of any anticipated success of control rod insertion. When attempts to insert control rods satisfactorily achieve reactor shutdown, the requirement for boron injection no longer exists. (Control rod insertion is directed under Step RC/Q-7 concurrently with Step RC/Q-6.)

Cues Manual scram is initiated and numerous control rods indicate beyond position 00 and reactor power not downscale on panel 9-5 indications.

Suppression Pool temperature rising on PMIS and panel indications.

Operator manipulates keylocked switch for SLC A pump to START on panel 9-5. (SLC Pump B relief valve fails open in this scenario.)

Measurable Performance Indicators Operator selects individual control rods by depressing the respective pushbutton on the panel 9-5 matrix and inserts the rod by manipulating the emergency in switch on panel 9-5.

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 10 of 49 SLC A pump red light illuminated, SLC discharge pressure rising, SLC tank level lowering by 26% on panel 9-5 (from ~80% to below

~54% for this scenario).

Performance Feedback Operator selecting and inserting control rods indicated by rod position decreasing to 00 for selected rod on panel 9-5.

Applicability ATWS with power >3% following trip of both recirc pumps per EOP-7A, energy being discharged to Primary Containment causing Torus water temperature to rise.

If boron injection is initiated or all control rods are inserted to position 02 before suppression pool temperature reaches the BIIT, emergency RPV depressurization may be precluded at lower reactor power levels. At higher reactor power levels, however, the suppression pool heatup rate may become so high that the Hot Shutdown Boron Weight of boron cannot be injected before suppression pool temperature reaches the Heat Capacity Justification for the Temperature Limit even if boron injection is initiated early in the chosen performance event. Since failure-to-scram conditions may present severe plant limit safety consequences, the requirement to initiate boron injection is independent of any anticipated success of control rod insertion.

If the failure to scram EOP were to be exited, other procedures would not provide the guidance for control rod insertion necessary to achieve reactor shutdown. Before exiting EOP-6A ensures guidance to effect reactor shutdown is not removed.

BWR Owners Group App. B, step RC/Q-6 Appendix Initial conditions, combined with the ATWS severity, should result in power >3% following trip of both recirc pumps per EOP-7A.

Scenario Guide Suppression Pool temperature must be rising due to unstoppable Requirements condition such as loss of the main condenser or LOCA. The scenario should be validated to exceed BIIT; therefore, ability to achieve control rod insertion may need to be hampered or delayed.

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 11 of 49 Related Operating Experience INPO ICES 150203 Single Control Rod Drift Out During Reactor Startup Single Control Rod Drift Out During Reactor Startup On December 19, 1994, while withdrawing control rods for unit startup, Control Rod 50-35 drifted from position 06 to 48 (full out). This Control Rod was selected and being withdrawn from position 04 to 06 when the event occurred. Operations personnel recognizing the rod drift condition attempted to stop the control rod by applying an insert signal.

INPO ICES 205668 Control Rod Drift Due to Transponder Card Failure (OE16861)

(Nine Mile Point 1) Control Rod Drift Due to Transponder Card Failure During power ascension from Forced Outage, indications were received that a control rod had drifted.

At the time of the annunciation no control rods were being withdrawn. A failed transponder card was determined to be the cause of event. Previous recurring transponder card failures generally caused a lockup of the Reactor Manual Control System. This particular transponder card failure resulted in a control rod drift.

INPO ICES 230540 Service Water Pump Trip (OE26446)

(Indian Point 2) On 1/27/2008, Service Water Pump tripped on long delay overload due to failure of the 'B' phase termination at 21SWP Motor. 21 Service Water Pump was on the essential SW header at the time thus IP2 entered a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO. Service Water Pump (SWP) tripped on long delay overload due to failure of the 'B' phase termination at 21SWP Motor.

INPO ICES 443918 Service Water Pump Trip (Indian Point 2) On 9/3/2018, Service Water Pump (SWP) breaker tripped open while running, which caused Operations personnel to place the pump in trip-pullout. The 22 SWP was declared inoperable, which resulted in a Maintenance Rule Functional Failure as well as a Mitigating System Performance Index (MSPI) failure of the 22 SWP. The cause for this event was a turn to turn short of the motor. Based on the damage to the motor winding, no definitive apparent cause could be found.

(CNS) CR 2012-02665 Traveling screen trips Received D-1/D-2 traveling screen HI and HI-HI D/P alarms. Started CWP B and D. All traveling screens are in HAND and FAST, current screen coverage is 50%-75%

consisting of grass and leaves due to recent heavy rains in the area.

Rev 3

Appendix D Scenario Outline Form ES-D-1 NRC CNS 2020-4 Scenario 3 Page 12 of 49 INPO ICES 306387 Trip of Circulating Water Traveling Screen Causes Power Reduction of <10%

(CNS) On dayshift ~ 1701 received A1 Traveling water screen High differential pressure (DP), ~3 minutes later HI-HI DP and A1 Screen Trip alarms were received.

Reactor power was reduced, and Circulating Water Pump was secured. Consequences, downpower of ~9.5% and Reactivity Management Event Level 4. Cause was due to high debris in the river due to weather conditions and a restricted flowpath to 'A' Circulating Water Pump.

SEN 134 Failure of control rods to fully insert (Wolf Creek) After a manual reactor scram on January 30, 1996, five control rods failed to fully insert. One control rod indicated 18 steps out, two control rods indicated 12 steps out, and two control rods indicated six steps out.

Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 13 of 49 SIMULATOR SET-UP A. Materials Required - none B. Initialize the simulator in IC-19 or password protected IC 318 with it at 97%

power, 100% or 97% (MOC)

1. Ensure these schedule files are in the schedule file directory:

Schedule File Names - 2020-4sc3.sch sc3event2.sch

2. Click on Open in the Schedule window and Open Schedule File 2020-4sc3.sch (in the Schedule Directory)

3. In Schedule window, click on the Stopped red block. The red block will change to a green arrow and indicate the schedule file is active (Running).

4. Take the simulator out of freeze.

5. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section C below. (Note: Any actions in the schedule file without a value in the @Time column will not load into the director until the event trigger goes active.)

Page 13 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 14 of 49 C. File loaded verification:

(Continued on next page.)

Page 14 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 15 of 49 (Continued on next page.)

Page 15 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 16 of 49 Page 16 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 17 of 49 Page 17 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 18 of 49 D. Panel Setup

1. Ensure PMIS IDTs are blank.

2. Ensure reactor power is 97%.

3. Ensure RR Controllers are selected to P.

4. Ensure Service Water Pump C is running.

5. Ensure Service Water Pump C Mode is selected to AUTO.

6. Place CS Pump A in PTL.

7. Hang a caution tag on CS Pump A control switch.

8. Ensure CS A is OOS on safety system status panel on panel 9-5.

9. Place Protected Equipment placard on Panel 9-3 within Core Spray B area.

10. Ensure SSST Y voltage to RRMGs is set to TAP 2.

11. SSST X Voltage card should read TAP POS 3, MAX 4469 and MIN 4361.

12. Ensure MOL Rod Sequence Notebook is under the RO desk.

13. Ensure crew is provided Load Schedule for raising power 97-100% for turnover.

14. If being used for ILT NRC exam, ensure simulator is set to record data file ILT 1801 Scenario 3 on INSIGHT.

Page 18 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 19 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 1 Event

Description:

Raise reactor power to 100% using Reactor Recirculation flow Time Position Applicants Action or Behavior Directs ATC to Raise reactor power using RR flow per Procedure 2.1.10 [Station CRS Power Changes]

Booth Role Play: As Rx Building NLO, when requested to monitor RRMG lube oil temps and maintain 110-130°F, respond you will monitor RRMG lube Operator oil temps and maintain them in band.

NOTE to Examiners: It is important to allow the crew to raise power to at least 99% before proceeding to event 2. This will ensure Event 2 is capable of causing power to exceed the License Condition for Thermal Power Limit, necessary for CT#1.

Raises power using Recirculation flow IAW 2.1.10:

Selects S on RR flow controllers on panel 9-4.

6.4 Raise power by raising RR pump flow as follows:

6.4.1 IF thermal power 2413 (or 2375 if power limited to 2381 MWt),

THEN raise power by raising RR pump flow (by turning speed demand clockwise on one speed controller at a time and allowing conditions to stabilize before adjusting other controller).

6.4.1.1 Maintain rate of power change consistent with system capabilities as determined by Load Dispatcher and TG limits.

6.4.2 IF thermal power > 2413 (or > 2375 if power limited to 2381 MWt),

THEN perform following:

NOTE 1 - A change in scoop tube position indicates if change in RR pump ATC flow will occur. RRMG A scoop tube position can be monitored by PMIS Point N408 and P display on RRFC-SIC-16A, SPEED CONTROL. RRMG B scoop tube position can be monitored by PMIS Point N413 and P display on RRFC-SIC-16B, SPEED CONTROL.

NOTE 2 - Section 11 contains guidance for Operations Near Rated Thermal Power.

6.4.2.1 Raise RR pump flow with a speed demand signal rise of 0.2.

6.4.2.2 Closely monitors scoop tube position/RR pump flow response.

6.4.2.3 IF operating near rated thermal power, THEN verify compliance with both flow and thermal power per Section 11.

6.4.2.4 Repeat 6.4.2.1 through 6.4.2.3 until desired thermal power (target

~100% on PMIS display) achieved.

Page 19 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 20 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 1 Event

Description:

Raise reactor power to 100% using Reactor Recirculation flow Time Position Applicants Action or Behavior Closely monitors reactor power on APRMs and Main Turbine output on DEH HMI.

BOP Provides peer check of ATC actions.

END OF EVENT Notes Booth Proceed to next event after power has been raised to > 99%, or as directed by Operator Lead Examiner.

Page 20 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 21 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 2 Event

Description:

Control rod 18-19 drift out Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 2, to cause Control Rod 18-19 to drift out.

Trigger 2 calls schedule file sc3event2.sch, which inserts malfunction rd10189 Booth and uses multiple overrides to mask selecting and applying a drive signal to Operator 18-19, which is required initiate the rod drift. It also will delete the malfunction when the crew places the scram test switch for 18-19 to TEST.

Role Play: IF sent to CRD HCU 18-19 to investigate, as the building operator wait 5 minutes, then report you do not detect anything unusual at the HCU.

Recognizes and reports alarm:

9-5-1/C-4 Rod Drift Performs alarm card 9-5-1/C-4 actions:

2.1 Check full core display for rod drift light(s) to determine which rod(s) is ATC drifting.

2.2 IF more than one rod is drifting, THEN SCRAM and concurrently enter Procedure 2.1.5.

2.3 Take action per Procedure 2.4CRD as dictated by plant conditions.

Lowers reactor power by performing 2.4CRD [CRD Trouble] actions or per 2.1.10 to restore and maintain 100% rated thermal power Enters 2.4CRD [CRD Trouble].

CRS Directs ATC to perform 2.4CRD Attachment 1 for single rod drifting out.

Critical Task #1: When an inadvertent reactivity addition occurs (in this case, rod drift out) that would cause power to rise above 100% rated thermal power, crew lowers power to restore and maintain power 100% rated thermal power by inserting the control rod and/or lowering Reactor Recirc flow before PMIS point NSSRP641 (30 minute power average) exceeds 2419 MWt.

Page 21 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 22 of 49 Performs 2.4CRD Attachment 1:

Ensures rod 18-19 is selected

Inserts rod using ROD MOVEMENT CONTROL or EMERGENCY IN control switch on panel 9-5

Releases control switch to assess whether the rod will latch

Determines the rod did not latch, applies and maintains continuous insert signal

Establishes communication with BOP at panel 9-16 (scram test panel)

When rod full in, release continuous insert signal

Notify BOP rod did not latch and to scram 18-19

Notifies BOP to return 18-19 scram test switch to normal.

ATC Page 22 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 23 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 2 Event

Description:

Control rod 18-19 drift out Time Position Applicants Action or Behavior BOP Assists ATC perform 2.4CRD Attachment 1:

Places scram test switch for rod 18-19 to TEST when directed.

Returns scram test switch for rod 18-19 to NORM when directed.

Notifies BOP and CRS rod 18-19 latched following scram Performs alarm card 9-5-1/C-4 action:

ATC 2.4 IF cause of rod drift alarm known, THEN place Rod Drift Alarm Test to Reset.

IAW 2.4CRD Attachment 1, notifies Reactor Engineering and System Engineering rod 18-19 drifted out, would not latch, and has been scrammed CRS in.

Determines entry into TS 3.1.3 Condition C is required.

TS 3.1.3 CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control C.1 Fully insert the inoperable control 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months rods inoperable for rod.

reasons other than Condition A or B. AND C.2 Disarm the associated CRD. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months END OF EVENT Notes Booth Proceed to next event when directed by the Lead Examiner.

Operator Page 23 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 24 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 3 Event

Description:

Service Water Pump C trip Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 3, SW01C Service Water Pump C trip.

Booth Role Play: If sent to investigate SW Pump C breaker trip, wait 3 minutes, then as building operator report the 51B overcurrent relay is tripped for SW Operator Pump C.

If sent to SW Pump C itself, wait 4 minutes, then report the motor is hotter to the touch than normal, but you see no abnormality visually.

Recognizes and responds to alarms:

A-4/B-7, Service Water Pump C Trip

A-4/C-7, Service Water Pump C Ovld/Ground Performs alarm card B-3/B-7 actions:

1.2 Maintain SW header pressure > 38 psig on SW-PI-2715A as follows:

1.2.1 Place available non-running SW pump MODE SELECTOR switch(es) in MAN, as necessary.

BOP 1.2.2 Start available SW pump(s), as necessary.

1.3 Ensure MODE SELECTOR switches aligned per Procedure 2.2.71.

1.4 IF cause of trip is unknown, THEN perform following:

1.4.1 (Sends operator to) Record 4160V Switchgear F relay flags 1.4.2 (Sends operator to) Inspect pump for damage.

1.4.3 Place PUMP C SELECTOR switch to MANUAL.

1.5 IF SW-PI-2715A 38 psig, THEN enter Procedure 5.2SW.

Directs starting SW Pump B.

CRS Determines no further action required due to header pressure restored by SW Pump B start.

Enters TS 3.7.2 Condition A due to SW Pump C inoperable.

CRS Determines DG1 remains OPERABLE since SW Pump A is already selected to STDBY.

Page 24 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 25 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 3 Event

Description:

Service Water Pump C trip Time Position Applicants Action or Behavior TS 3.7.2 CONDITION REQUIRED ACTION COMPLETION TIME A. One SW subsystem A.1 NOTES inoperable.

1. Enter applicable Conditions and Required Actions of LCO 3.8.1, AC Sources Operating, for DG made inoperable by SW.

Restore the SW subsystem to OPERABLE status. 30 days END OF EVENT Notes Booth Proceed to next event when directed by the Lead Examiner.

Operator Page 25 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 26 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 4 Event

Description:

Circulating Water pump inlet screen clogging and partial loss of CW pumps, degraded condenser vacuum Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 4,

MC06A - Traveling screen A blockage

MC05A - Circ Water Pump A trip

MC03A,B,C,D - Condenser tube sheet plugging Booth Note: CW Pump A trips 3 minutes after trigger 4 is active. Condenser tube sheets begin to plug 2 minutes after trigger 4 is active. Condenser vacuum Operator degrades to ~23Hg over 10 minutes from activation of trigger 4, if the crew has not lowered power.

Role Play: If sent to investigate, wait 4 minutes, then report there is a large amount of debris on traveling screen A, and the screen appears to have been breached and is still running. The other screens are still running and ~30%

covered.

Responds to annunciator:

Alarm Card A-3/A-6, Traveling Screens High dp BOP Per alarm card A-3/A-6:

2.1 (Sends operator to) Check screen wash pump and traveling screen operation.

Responds to annunciator:

A-4/E-3, Circ Wtr Pmps Disch Tunnel High Pressure BOP Per alarm card A-4/E-3:

2.1 Sends operator to check P indicators for possible fouling of tubes.

Responds to annunciator:

A-4/A-1, Circ Water Pump A Trip

A-4/A-2, Circ Water Pump A OVLD Ground BOP Per alarm card A-4/A-1:

2.1 IF condenser vacuum lowering, THEN concurrently enter Procedure 2.4VAC.

Recognizes and reports condenser vacuum lowering, procedure 2.4VAC entry condition.

NOTE to Examiners: Based on validation, it is expected the CRS will direct a Rapid Power Reduction to 40 Mlbm/hr core flow, which results in power lowering to ~70%.

Page 26 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 27 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 4 Event

Description:

Circulating Water pump inlet screen clogging and partial loss of CW pumps, degraded condenser vacuum Time Position Applicants Action or Behavior Enters 2.4VAC [Loss of Condenser Vacuum]:

CRS 3.1.1 Directs ATCO to reduce power per Procedure 2.1.10 to maintain vacuum 23" Hg.

Lowers power, as necessary, using Recirc flow IAW 2.1.10:

Selects S on RR flow controllers on panel 9-4 7.4.1 Lower power by lowering RR pump flow (by turning speed demand ATC counter-clockwise on one speed controller at a time and allowing conditions to stabilize before adjusting other controller).

Closely monitors scoop tube position/RR pump flow response on panel 9-4 and APRM recorders on panel 9-5.

BOP Reports vacuum stabilized above 23Hg.

END OF EVENT Notes Proceed to next event when directed by the Lead Examiner.

Booth Operator If 2.1.5 is entered by the crew the Lead Examiner may determine to proceed to the next event.

Page 27 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 28 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior When directed by Lead Examiner, insert TRIGGER 5(Unless RX Scram has been inserted)

MC05B - Circ Water Pump B trip

MC05C - Circ Water Pump C trip

MC05D - Circ Water Pump D trip Booth

MC01 - Condenser inleakage Operator Note:. Condenser tube sheets begin plugging and are completely plugged 4 minutes after trigger 5 is active. CW Pump B trips 2 minutes after trigger 5 is active. CW Pumps C & D trip ~4 minutes after trigger 5 is active. MSIVs close

~5 minutes after trigger 5 is active.

Recognizes and reports condenser vacuum lowering.

BOP Reports annunciator:

Alarm Card B-1/B-3, TG Low Vacuum Pre-Trip NOTE to Examiners: At this point in the scenario guide, reactor scram, crew actions are segregated by crew position.

CRS actions begin here.

ATC actions begin on page 34.

BOP actions begin on page 41.

IAW Procedure 2.4VAC:

CRS

Directs ATC to insert scram based on vacuum trend.

Directs BOP to trip the turbine following the reactor scram.

Enter EOP 1A [RPV Control] and transition to EOP 6A [RPV Pressure/Power CRS Control (Failure-to-Scram)] and EOP 7A [RPV Level Control (Failure-to-Scram)]:

Page 28 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 29 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior Directs BOP to:

Verify operation of LLS

Open SRVs until pressure drops to 940 psig

Stabilize pressure <1050 psig using Table 12 systems as necessary EOP 6A Pressure CRS Page 29 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 30 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior Directs ATC to:

Trip RR Pumps IAW EOP-6A step FS/Q-9 (RR Pump B fails to automatically trip on high reactor pressure)

Reset ARI and insert rods IAW EOP-6A step FS/Q-17 CRS CRITICAL TASK #2: When control rods fail to scram and energy is discharging to the primary containment (e.g. SRVs, LOCA), crew initiates SLC injection or inserts all control rods to at least position 02 before exceeding the Boron Injection Initiation Temperature (BIIT) curve.

Page 30 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 31 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior Directs ATC to initiate SLC injection before BIIT curve is exceeded IAW EOP-6A:

CRS Page 31 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 32 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior Directs BOP to inhibit ADS IAW EOP-7A:

EOP 7A RPV Level CRS Directs BOP to stop and prevent injection to lower RPV level below -60 inches.

EOP 7A RPV Level CRS Enter EOP-3A [Primary Containment Control] due to Suppression Pool temperature 95°F.

CRS Direct BOP to place suppression pool cooling into service.

Direct BOP to maintain RPV level between -60 inches and -183 inches using EOP 5.8.13 systems.

Page 32 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 33 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 5,6,7 Event

Description:

Trip of Circulating Water Pumps B, C, and D, loss of condenser vacuum, ATWS, Failure of RR Pump B to trip Time Position Applicants Action or Behavior When HSD boron weight has been injected, directs EOP-7A step FS/L-24 CRS OR When all rods have been inserted to at least position 02, directs ATC to stop SLC pumps, exits EOP-6A and EOP-7A and re-enters EOP-1A, directs EOP-1A step RC/L-3 Directs BOP to slowly raise RPV level to new band of +3 to +54.

Notes NOTE to Examiners: Scenario objectives have been met when HSD boron weight has been injected, or all control rods have been inserted, and level is being raised in a controlled manner to restore it to +3 inches to +54 inches, OR at Lead Examiners discretion.

Page 33 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 34 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior Inserts manual scram:

Performs 2.1.5 [Reactor Scram] Attachment 1 Mitigating Task Scram Actions:

1.1 Press both RX SCRAM buttons.

1.2 Place REACTOR MODE switch to REFUEL.

1.3 IF reactor power > 3%, THEN perform following:

1.3.1 Place REACTOR MODE switch to SHUTDOWN.

1.3.2 Initiate ARI.

ATC Perform Attachment 2 Reactor Power Control of 2.1.5 as follows:

1 REACTOR POWER CONTROL 1.1 Ensure REACTOR MODE switch is in SHUTDOWN.

1.2 Verify all SDV vent and drain valves are closed.

1.3 Ensure operating RR pumps have run back to 22% speed 1.4 Verify all control rods are fully inserted.

Recognize and report ATWS Conditions.

Reports reactor power level to CRS.

ATC When directed by CRS to trip RR Pumps, recognizes RR Pump B failed to trip on high reactor pressure and trips pump by opening breaker 1DS on panel 9-4.

CRITICAL TASK #2: When control rods fail to scram and energy is discharging to the primary containment (e.g. SRVs, LOCA), crew initiates SLC injection or inserts all control rods to at least position 02 before exceeding the Boron Injection Initiation Temperature (BIIT) curve.

Page 34 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 35 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior When directed by the CRS initiates SLC injection

Place both keys in SLC PUMP A and SLC PUMP B keylock switches on Panel 9-5 and place switches to START.

Check both SLC pumps start.

Check white SQUIB VALVE READY DS-3A (1106A) and SQUIB VALVE READY DS-3B (1106B) lights turn off (Panel 9-5).

Check pressure on SLC-PI-65, PUMP PRESSURE (Panel 9-5), is greater than reactor pressure.

Recognizes and reports SLC discharge pressure (~1100 psig) lower than normal for two pumps running (~1300 psig).

ATC

Check Annunciator 9-5-2/G-7, LOSS OF CONT TO SQUIB VLVS, alarms.

Ensure RWCU-MO-15, INBD ISOL VLV (Panel 9-4), is closed.

Ensure RWCU-MO-18, OUTBD ISOL VLV (Panel 9-4), is closed.

Ensure both RWCU pumps are off (Panel 9-4).

Ensure RWCU-MO-74, DEMIN SUCTION BYPASS VLV (Panel 9-4), is throttled open.

Provides CRS initial SLC tank level indicated on SLC-LI-66 TANK LEVEL on panel 9-5 (~80%).

Page 35 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 36 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior Aligns CRD to insert control rods IAW 5.8.3 [Alternate Rod Insertion Methods].

ATC Page 36 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 37 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior Selects the rods starting in the center and works out in a spiral pattern using the 5.8.3 Attachment 2(5.8.3 Board) depicted below.

ATC Booth If requested to install EOP PTMs 61 and 62, wait 3 minutes, then insert Operator RF RD18 and report PTMs 61 and 62 have been installed.

Page 37 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 38 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior Resets scram IAW 5.8.3 Att. 1:

ATC NOTE to Examiners: After the scram has been reset the first time and the Scram Discharge Volume has been allowed to drain, control rods will fully insert when ATC inserts another manual scram.

Page 38 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 39 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior When SDV has drained for > 3 minutes, inserts scram IAW 5.8.3 Att. 1:

ATC ATC Reports all control rods fully inserted.

Page 39 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 40 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6,8 Event

Description:

ATWS, SLC Pump B relief valve fails open Time Position Applicants Action or Behavior Report when >26% (HSD boron weight) has been injected based on SLC ATC tank level lowering below ~54% on SLC-LI-66, TANK LEVEL on panel 9-5, if applicable.

ATC When all control rods are fully inserted, stops SLC pumps, as directed.

Notes NOTE to Examiners: Scenario objectives have been met when HSD boron weight has been injected or all control rods have been inserted, and level is being raised in a controlled manner to restore it to +3 inches to +54 inches, OR at Lead Examiners discretion.

Page 40 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 41 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior As directed by CRS, trips Main Turbine IAW 2.2.77 [Main Turbine], Att. 2 hard card on Panel-B:

1.1 Simultaneously DEPRESS TURB TRIP 1 and TURB TRIP 2 buttons, and then check following:

1.2 VERIFY following valves closed (Panel B, DEH Main display):

Both stop valves.

BOP

All governor valves.

All reheat stop valves.

All interceptor valves.

1.3 ENSURE following breakers open(Panel C):

1.3.1 345KV BUS, PCB-3310.

1.3.2 345KV BUS, PCB-3312.

1.3.3 GEN EXCITER FIELD BKR.

Inhibit ADS when directed by CRS:

BOP At Panel 9-3 place ADS A and ADS B INHIBIT switches to INHIB.

Performs Stop and Prevent IAW EOP 5.8 [Emergency Operating Procedures (EOPs)] Att. 4 HARD CARD:

1. STOP INJECTION 1.1 Stop HPCI by performing one of following:

1.1.1 IF HPCI is not running, THEN place AUXILIARY OIL PUMP switch to PULL-TO-LOCK.

1.1.2 IF HPCI is running, THEN perform one of following:

1.1.2.1 Place HPCI controller to MANUAL and lower on controller to BOP maintain > 100 psig below low-end of RPV pressure band, and

a. Maintain turbine speed > 2050 rpm.

1.1.2.2 Trip HPCI turbine by performing following:

a. Ensure AUXILIARY OIL PUMP control switch in START.

b. Press and hold TURBINE TRIP button.

c. After turbine stops, THEN place AUXILIARY OIL PUMP switch to PULL-TO-LOCK.

d. Release TURBINE TRIP button.

Page 41 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 42 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior 1.2 Stop feedwater by performing following:

1.2.1 IF ENABLE INJECTION button is yellow, THEN on STARTUP VALVE screen, press ENABLE INJECTION button and press "YES" to confirm cancel.

1.2.2 At a RVLC/RFPT HMI, select STARTUP VALVE screen, press STOP AND PREVENT button, and confirm "YES" in pop-up box.

1.2.3 WHEN RF-MO-29 and RF-MO-30 are closed, THEN on STARTUP VALVE screen, press ENABLE INJECTION button and confirm "YES" in pop-up box.1.2.4 1.2.4 IF RF-MO-29 or RF-MO-30 are open and cannot be closed from Control Room, THEN perform following:

1.2.4.1 Trip both RFP's.

1.2.4.2 Trip all operating condensate booster pumps.

CAUTION - If Core Spray and RHR pumps are placed in PULL-TO-LOCK before system flow is reduced to minimum, draining of system may occur.

1.3 Place both core spray pumps in PULL-TO-LOCK.

1.4 Stop RHR by ensuring one of following:

1.4.1 Both RHR Systems secured with pumps in PULL-TO-LOCK.

1.4.2 RHR outboard injection valves automatic open signal bypassed per Procedure 5.8.20 (PTMs 97 through 100) with injection valves closed.

1.4.3 IF RPV pressure is maintained 500 psig, THEN operate RHR aligned to suppression pool cooling and/or containment spray per Procedure 2.2.69.3.

2. PREVENT INJECTION Page 42 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 43 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior 2.1 Prevent both RHR Subsystems by performing one of following in each loop:

BOP 2.1.1Both RHR Systems secured with pumps in PULL-TO-LOCK.

2.1.2 IF RPV pressure is maintained 500 psig, THEN operate RHR aligned to suppression pool cooling and/or containment spray per Procedure 2.2.69.3; and 2.1.2.1 Bypass RHR outboard injection valves automatic open signal per Procedure 5.8.20 (PTMs 97 through 100) with injection valves closed.

2.1.3 RHR outboard injection valves automatic open signal bypassed per Procedure 5.8.20 (PTMs 97 through 100) with injection valves closed.

2.2 Prevent feedwater by performing following:

2.2.1 Ensure RF-MO-29 is closed.

2.2.2 Ensure RF-MO-30 is closed.

2.2.3 Trip condensate and condensate booster pump(s), as required.

2.3 Prevent CS by performing following:

2.3.1 Ensure CS-MO-12A is closed.

BOP 2.3.2 Ensure CS Pump A control switch in PULL-TO-LOCK.

2.3.3 Ensure CS-MO-12B is closed.

2.3.4 Ensure CS Pump B control switch in PULL-TO-LOCK.

2.4 Prevent HPCI by performing following:

2.4.1 IF HPCI is not running, THEN ensure AUXILIARY OIL PUMP switch is in PULL-TO-LOCK.

2.4.2 IF HPCI is running, THEN trip HPCI turbine by performing following:

2.4.2.1 Press and hold TURBINE TRIP button.

2.4.2.2 WHEN turbine is at zero rpm, THEN place AUXILIARY OIL PUMP switch to PULL-TO-LOCK.

Page 43 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 44 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior 2.4.2.3 Release TURBINE TRIP button.

Reports injection systems are stopped and prevented.

Direct NLO to install EOP PTMs 97 through 100 for RHR injection valve BOP control.

Role Play: When directed by BOP to install EOP PTMs97-100, wait 3 Booth minutes then put in the overrides for the PTMs. Report back to BOP Operator when PTMs installed.

When RPV level lowers to less than -60 inches, maintain RPV level between

-60 inches and -183 inches using EOP 5.8.13 systems (HPCI and/or RCIC, CRD and SLC).

BOP Page 44 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 45 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior Monitor and report torus level and temperature as SRVs are utilized for pressure control. Announce EOP 3A entry conditions as necessary.

BOP NOTE to Examiners: The RHRSWB pump associated with the first loop of SPC attempted to be placed into service will trip, requiring the operator to start the other SWB pump in that RHR loop or transition to the other RHR loop for SPC.

Page 45 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 46 of 49 place RHR into suppression pool cooling (after EOP PTMs97-100 are installed) per 2.2.69.3 [RHR Suppression Pool Cooling and Containment Spray] HARD CARD.

1.1 Place RHR SW System in service:

1.1.1 Start SWBP(s) (by placing and holding SWBP switch to start until pump starts, then releasing switch).

1.1.2 Adjust SW-MO-89A(B) to maintain flow between 2500 and 4000 gpm.

Recognizes and reports RHRHSWB trip and proceeds to place other RHRSWBP in the first loop or opposite RHR loop in SPC.

1.1 Place RHR SW System in service:

1.1.1 Start SWBP(s) (by placing and holding SWBP switch to start until pump starts, then releasing switch).

1.1.2 Adjust SW-MO-89A(B) to maintain flow between 2500 and 4000 gpm.

1.2 If required, with CRS permission, place CONTMT COOLING 2/3 CORE VALVE CONTROL PERMISSIVE switch to MANUAL OVERRD.

BOP 1.3 If required, place CONTMT COOLING VLV CONTROL PERMISSIVE switch to MANUAL.

1.4 Open RHR-MO-39A(B).

1.5 If reactor pressure 300 psig and injection not desired, close RHR-MO-27A(B), OUTBD INJECTION VLV.

1.6 Ensure RHR PUMP running.

NOTE - RHR pump operation at minimum flow should be limited to

< 15 minutes or pump damage may result.

1.7 Throttle RHR-MO-34A(B), as required to obtain desired cooling flow.

1.9 Throttle RHR-MO-66A(B), as required to obtain desired cooling rate.

1.10 IF directed by EOP 3A, THEN OBTAIN maximum cooling.

1.11 If PCIS Group 6 lights lit on Panel 9-5, THEN ensure one of following open:

REC-MO-711.

REC-MO-714.

1.12 If additional cooling required, initiate cooling in non-running RHR Loop and start additional pumps.

When directed, raises RPV injection and raise level between +3 inches and BOP

+54 inches.

Page 46 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 47 of 49 Op-Test No.: CNS 2020-4 Scenario No.: 3 Event No.: 6, 9 Event

Description:

ATWS, RHRSW Booster Pump trip Time Position Applicants Action or Behavior NOTE to Examiners: Scenario objectives have been met when HSD boron weight has been injected, or all control rods have been inserted, and level is being raised in a controlled manner to restore it to +3 inches to +54 inches, OR at Lead Examiners discretion.

END OF SCENARIO Notes Booth When directed by the Lead Examiner, place the simulator in freeze and Operator tell the crew to stop operating.

Page 47 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 48 of 49 INITIAL CONDITIONS A. Plant Status:

1. 97% power, steady state, Middle of Cycle following a Control Rod sequence exchange.

B. Tech. Spec. Limitations in effect:

1. Day 1 of 7 day LCO per 3.5.1 A.1 for Core Spray A INOPERABLE.

C. Significant problems/abnormalities:

1. Core Spray Pump A tagged out for motor preventive maintenance.

2. CS B is protected.

D. Risk :

1. PRA Risk is Green

2. Aggregate Risk is Green E. Evolutions/maintenance for the on-coming shift:

1. Continue raising reactor power to 100% per the load schedule.

2. Continue maintenance on Core Spray Pump A motor.

Page 48 of 49 Rev 3

Appendix D Required Operator Actions Form ES-D-2 NRC CNS 2020-4 Scenario 3 Page 49 of 49 Form Password is pepetf Activities Planned or in Progress: Core Spray Pump A motor preventive maintenance window Risk Green Rev: 0 Page 1 of 1 Creation Date: Current SM Review: Shift Manager Window Start: Yesterday Window Close: Tomorrow Sign(s)

Number Installed Removed Protected Sign Placement of Initials/ Initials/

Equipment Location Sign(s)* Date Date Magnetic sign on door:

Core Spray Loop B 1 NLO R105, R-903-SE Quad CS Pump B 4160 Bkr Magnetic Sign On: EE-CB- 1 NLO 4160G(CSP1B)

MCC-Y Barrier erected and Sign 1 NLO Posted: Around MCC-Y CS-Loop B controls panel 9-3 Magnetic sign placed on 1 WCO panel 9-3: within CS B area Page 49 of 49 Rev 3

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Cooper Nuclear Station Date of Exam: 7/27/2020 Operating Test No.: 2020-4 A E Scenarios P V 1 3 4 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U RO RX 0 1 1 1 1 0 NOR 1 0 1 1 1 1 SRO-I I/C 5 6 11 4 4 2 SRO-U MAJ 1 1 2 2 2 1 (U1)

TS 2 2 4 0 2 2 RO RX 0 1 1 1 1 0 (R1)

NOR 0 0 0 1 1 1 SRO-I I/C 4 4 8 4 4 2 MAJ 1 1 2 2 2 1 SRO-U TS N/A N/A 0 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 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 (SRO-I) 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 SRO-I 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 I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Option A

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Cooper Nuclear Station Date of Exam: 7/27/2020 Operating Test No.: 2020-4 A E Scenarios P V 1 3 4 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U RO RX 0 1 1 1 1 0 NOR 1 0 1 1 1 1 SRO-I I/C 5 6 11 4 4 2 SRO-U MAJ 1 1 2 2 2 1 (U2)

TS 2 2 4 0 2 2 RO RX 0 0 0 1 1 0 (R3) NOR 1 0 1 1 1 1 SRO-I I/C 3 3 6 4 4 2 SRO-U MAJ 1 1 2 2 2 1 TS N/A N/A 0 0 2 2 RO RX 0 1 1 1 1 0 (R4)

NOR 0 0 0 1 1 1 SRO-I I/C 4 4 8 4 4 2 SRO-U MAJ 1 1 2 2 2 1 TS N/A N/A 0 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 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 (SRO-I) 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 SRO-I 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 I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Option A

ES-301 Competencies Checklist Form ES-301-6 Facility: CNS Date of Examination: 07/27/2020 Operating Test No.: 2020-4 APPLICANTS R3 R1,R4 U1,U2 RO RO RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO ATC BOP CRS 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,4, 3,4, 3,4, and Conditions 5,6, 5,6, 5,6, 8 7,8 8 Comply with and 1,2, 3,4, 1,2 Use Procedures (1) 4,5, 5,6, 3,4, 6 7,8 5,6, 8

Operate Control 1,4, 3,4, NA Boards (2) 6,8 6,7, 8

Communicate 1,2, 1,3, ALL and Interact 4,5, 4,5, 6,8 6,8 Demonstrate Supervisory NA NA ALL Ability (3)

Comply with and NA NA 2,4 Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

Rev 5

ES-301 Competencies Checklist Form ES-301-6 Facility: CNS Date of Examination: 07/27/2020 Operating Test No.: 2020-4 APPLICANTS R1, R4 R3 U1, U2 RO RO RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO ATC BOP CRS 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,4, 2,3, 2,3, and Conditions 5,6, 4,5, 4,5, 7 8 7,8 Comply with and 1,2, 2,3, 1,2, Use Procedures (1) 4,5, 4,5, 3,4, 6,7 8 5,6 Operate Control 1,2, 2,3, NA Boards (2) 4,5, 5,8 6,7 Communicate 1,2, 1,2, ALL and Interact 4,5, 3,4, 6,7 5,8 Demonstrate Supervisory NA NA ALL Ability (3)

Comply with and NA NA 2,3 Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Rev 5

ES-301 Competencies Checklist Form ES-301-6 Facility: CNS Date of Examination: 07/27/2020 Operating Test No.: 2020-4 APPLICANTS RO RO RO RO SRO-I SRO-I SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO ATC ATC BOP BOP CRS CRS 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 3,4, 4,5, 2,3, 2,3, 3,4, 2,3, and Conditions 5,7, 6,7 4,5, 4,5, 5,6, 4,5, 8 8 6,7 8,9, 6,7 10 Comply with and 1,2, 1,4, 5,6, 2,3, 1,2, ALL Use Procedures (1) 3,4, 6,7 8,9, 4,5, 3,4, 6,7, 10 6,7 5,6, 10 8,9, 10 Operate Control 1,2, 1,4, 5,8, 2,5, NA NA Boards (2) 3,4, 6,7 9,1 6,7 6,7, 0 10 Communicate 1,2, 1,4, 1,2, ALL ALL ALL and Interact 3,4, 5,6, 3,4, 6,8, 7 5,6, 10 9,1 0

Demonstrate Supervisory NA NA NA NA ALL ALL Ability (3)

Comply with and NA NA NA NA 4,5 3,5 Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Rev 5

ML20241A249

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