Text

Final Operating Test (Sections a, B, and C) (Folder 3)
	ML17101A468
Person / Time
Site:	Nine Mile Point
Issue date:	04/10/2017
From:	Isham P; Exelon Generation Co
To:	Brian Fuller; Operations Branch I
Shared Package
ML16210A438	List: ML16225A390; ML17101A467; ML17101A468; ML17109A226; ML17109A227; ML18088A717; ML18088A721; ML18088A723; ML18088A726; ML18088A728; NMP1L3120, Draft - Outlines (Folder 2), (Facility Letter Dtd - 12/6/2016;
References
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	Download: ML17101A468 (273)
	v • d • e

fraining Id: NMP1 2017 NRC RO-SRO Admin C001 Revision: -0.0

Title:

Control Rod Position Verification and Determine Reactivity Severity Approvals:

nature Printed Name Developed By '"<~~ul Isham 4/5/2016 Validated By Kevin Hines 8/23/16 Facility Reviewer Pat O'Brien 121.S/f(;,

Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC JPM RO-SRO COOl Page 1of10 February 2017

_.,,,," Exelon Generation References

1. N 1-0P-42, Process Computer/ SPDS

2. Nl-OP-5, Control Rod Drive System

3. OP-AA-300, Reactivity Management

4. OP-AA-300-1540, Reactivity Management Administration

5. BWROG-TP-09-025, Monitoring of Reactivity Management Issues

6. NUREG 1123 K/A 2.1.37 (4.3/4.6)

7. Unit 1 Technical Specifications NMP1 NRC JPM RO-SRO C001 Page 2 of 10 February 2017

~, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's knowledge of reactivity management processes, and tests the operator's ability to determine whether control rod patterns correctly reflect the desired plant lineup by performing a control rod position verification.

b. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. Nl-SOPl.5-03001-07, Concurrent mitigation of control rod mispositiong

b. NUREG 1123 K/A 2.1.37 (4.3/4.6), Knowledge of procedures, guidelines, or limitations associated with I reactivity management.

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Classroom

5. JPM Setup

a. Provide sufficient copies of OP-AA-300, Reactivity Management

b. Provide sufficient copies of OP-AA-300-1540, Reactivity Management Administration

c. Provide sufficient copies of BWROG-TP-09-025, Monitoring of Reactivity Management Issues

d. Provide sufficient copies of Nl-OP-5 for the SRO candidates

e. Provide A2 startup sequence completed up to final rod position verification

f. Provide printout of rod positions from the PPC NMPl NRC JPM RO-SRO COOl Page 3 of 10 February 2017

_,,,,.. Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC JPM RO-SRO COOl Page 4 of 10 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

A plant startup is in progress.

All RWM Group 9 Rods have been withdrawn.

An independent verification of control rod positions for RWM group 9 must be performed prior to moving ahead with the start up.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING {Operators Name), perform the Independent Verification of final CUE control rod positions for RWM group 9 using the plant process computer rod position data.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue p SAT/ UNSAT Cue: Acknowledge repeat back providing STD: Proper correction if necessary.

communications used

2. Obtain a copy of the reference handouts. p SAT/ UNSAT STD: Obtains copy of A2 startup sequence and PPC rod position printout.

3. Identify rod position discrepancy p *PASS/ FAIL STD: Identifies rod 34-47 is fully inserted and should be at position 12. Rod 30-47 is at position 12 and should be fully inserted.

When the candidate identifies the control rod position discrepancy, provide the RO/SRO worksheet and all applicable references.

NMPl NRC JPM RO-SRO COOl Page 5 of 10 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 4 From RO/SRO Worksheet, makes p *PASS/ FAIL determination of mispositioned control rod in STD: Determines this DOES accordance with OP-AA-300-1540, Reactivity meet the definition of a Management Administration. mispositioned control rod.

Note: OP-AA-300-1540 references BWROG Reactivity Controls Review Committee "Guidelines for Excellence," Section 5.0 "Monitoring of Reactivity Management Issues", where mispositioned control rod is clearly defined in definition 'I'.

5 From RO/SRO Worksheet, determines the p *PASS/ FAIL reactivity event severity level in accordance STD: Determines this is a with OP-AA-300-1540, Reactivity significance level 2 reactivity Management Administration. event.

Note: OP-AA-300-1540 directs the use of BWROG Reactivity Controls Review Committee "Guidelines for Excellence, "Section 5.0 "Monitoring of Reactivity Management Issues", where a mispositioned control rod due to personnel error is example 2-5. (significance level 2).

Evaluator Cue: When the RO candidates have completed the worksheet, inform them their task is complete.

When the SRO candidates have completed the RO/SRO worksheet, provide them with the SRO Only worksheet and Nl-OP-5.

NMPl NRC JPM RO-SRO COOl Page 6 of 10 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 6 SRO Only: Makes determination of who is p *PASS I FAIL required to be notified in accordance with STD: Determines Shift Manager Nl-OP-5. (H.9.1), Reactor Engineering (H.9.3), and General Supervisor Operations Note: Nl-OP-5 step H.9.5.3 directs notifying (H.9.5.3) are required to be the General Supervisor Operations. This title notified.

was changed to Shift Operations Superintendant (SOS). Either answer is Additionally, an IR would be acceptable. generated. The applicant may include this in the required notifications, but it is not required to pass this step.

TASK Control rod position verification is complete. Mispositioned control rod STANDARD identified and severity level classified.

STOP TIME NMP1 NRC JPM RO-SRO C001 Page 7 of 10 February 2017

~* Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

A plant startup is in progress.

All RWM Group 9 Rods have been withdrawn.

An independent verification of control rod positions for RWM group 9 must be performed prior to moving ahead with the start up.

INITIATING (Operators Name), perform the Independent Verification of final CUE control rod positions.

NMPl NRC JPM RO-SRO COO! Page 8 of 10 February 2017

~, Exelon Generation RO/SRO Worksheet Handout

Does this issue meet the definition of a "mispositioned control rod"?

Investigation reveals that this issue was caused by human error, not an equipment malfunction. What is the associated significance level of this issue?

NMPl NRC JPM RO-SRO COOl Page 9 of 10 February 2017

~ Exelon Generation SRO Only Worksheet

Determine the required notifications that must be made for this incident in accordance with Nl-OP-5.

NMPl NRC JPM RO-SRO COOl Page 10 of 10 February 2017

~- Exelon Generation;*

Training Id: NMP1 2017 NRC SRO Ad min JPM C002 Revision: 0.0

Title:

Determine Operator Qualifications Using LMS Approvals:

Signature I Printed Name

~~**

Developed By ~ Paul Isham 3/24/16 Validated By Kevin Hines 8/23/16 Facility Reviewer Pat O'Brien Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC JPM SRO C002 Page 1of8 February 2017

~* Exelon Generation References

1. NUREG 1123, 2.1.8 (4.1)

NMP1 NRC JPM SRO C002 Page 2 of 8 February 2017

-*"" Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the senior operator's ability to evaluate an operator's qualifications to perform specific tasks.

b. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. NS-FLDSUP-001 - Lead Prejob Briefs for Operator Teams

b. K/A 2.1.8 (4.1), Ability to coordinate personnel activities outside the control room.

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOO >1.0 Yes

4. Recommended Start Location

a. Training Classroom

5. JPM Setup (if required)

a. Provide copies of LMS printouts for each applicant

b. Provide copies of OP-CE-109-101 NMPl NRC JPM SRO C002 Page 3 of 8 February 2017

_.,.. Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC JPM SRO C002 Page 4 of 8 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

A maintenance activity is being planned.

Qualifications need to be verified for the following aspects of the maintenance activity:

1. Write the clearance (tagout) for a system (which will include disabling fire suppression systems)

2. Accept and Release the tagout

3. Hang/remove tags and align systems IAW the clearance

4. Perform duties as the fire watch while the clearance is active Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), Given the LMS sheets and the tasks required, CUE determine which Operator is qualified to perform the tasks.

START TIME PERFORMANCE ACT. CODE EVALUATOR PI 5 I NA

1. Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper communications correction if necessary. used.

2. Obtains and Reviews the tasks and the LMS SAT I UNSAT sheets and determines who is qualified to STD: LMS sheets and task perform the tasks as shown on the KEY and information obtained and below: p reviewed.

Note: Applicant can evaluate the operators in any order.

2a. Evaluates R01 PASS/ FAIL p STD: Determines ROl can perform tasks #1, #2, &

3.

NMP1 NRC JPM SRO C002 Page S of 8 February 2017

~* Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 2b. Evaluates R02 PASS/ FAIL p STD: Determines R02 can perform tasks #1, #3, &

4.

2c. Evaluates EOl p PASS/ FAIL STD: Determines EOl can perform tasks #3 and #4 2d. Evaluates E02 p PASS/ FAIL STD: Determines E02 can perform only task #4 TASK Applicant determines which Operators are qualified to perform the tasks STANDARD using LMS.

STOP TIME NMPl NRC JPM SRO C002 Page 6 of 8 February 2017

~ Exelon Generation

- - - - Answer Key*****

Do Not Provide to Applicant Task Number Task Descrigtion 1 Write a clearance (tagout) for a system (which will include disabling fire suppression systems)

Qualification Required: N-NM-SA-CT-WRT 2 Review and approve the clearance Qualification Required: N-CE-SA-CT-HLD 3 Hang/remove the tags and align the systems IAW the clearance Qualification Required: N-NM-SA-CT-AR 4 Perform the duties of a fire watch while the clearance is active Qualification Required: N-AN-SA-FIREWATCH Is the Ogerator Qualified to Perform the Task? CYes I Nol Ogerator Task 1 Task 2 Task 3 RO 1 RO 2 EO 1 EO 2

- - - - Answer Key*****

Do Not Provide to Applicant NMPl NRC JPM SRO C002 Page 7 of 8 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

A maintenance activity is being planned.

Qualifications need to be verified for the following aspects of the maintenance activity:

1. Write the clearance (tagout) for a system (which will include disabling fire suppression systems)

2. Accept and Release the tagout

3. Hang/remove tags and align systems IAW the clearance

4. Perform duties as the fire watch while the clearance is active INITIATING (Operators Name), Given the LMS sheets and the tasks required, CUE determine which Operator is qualified to perform the tasks.

Task Number Task DescriRtion 1 Write a clearance (tagout) for a system (which will include disabling fire suppression systems) 2 Review and approve the clearance 3 Hang/remove the tags and align the systems IAW the clearance 4 Perform the duties of a fire watch while the clearance is active Is the Om;!erator Qualified to Perform the Task? {Yes l No}

Om;!erator Task 1 Task 2 Task 3 Task4 RO 1 RO 2 EO 1 EO 2 NMP1 NRC JPM SRO C002 Page 8 of 8 February 2017

~-~a~r Exelon Generation,,

Training Id: NM Pl 2017 NRC RO-SRO Admin EC Revision: 0.0

Title:

Perform Daily Thermal Limit Surveillance Approvals:

Signature I Printed Name Developed By ~~Paul Isham 4/5/2016 Validated By Kevin Hines 8/23/16 Facility Reviewer Pat O'Brien tzJS/16 Approximate Duration: 20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC JPM RO-SRO EC Page 1of8 February 2017

_,,._ Exelon Generation References

1. Nl-RESP-lA, Daily Thermal Limit Surveillance Short Form

2. 3D Monicore

3. NUREG 1123, 2.2.12 (3.7/4.1)

NMPl NRC JPM RO-SRO EC Page 2 of 8 February 2017

.-.r Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to evaluate plant thermal limits in accordance with surveillance requirements.

b. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. NS-REL-03002, Review Results of Surveillance Tests to Ensure Compliance with Specifications.

b. K/A 2.2.12 (3. 7/4.1), Knowledge of Surveillance Procedures.

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Training Classroom

5. JPM Setup (if required)

a. Provide two 3D Monicore cases ("today's" and "yesterday's"). Yesterday's case should be normal. Today's case should have MFLCPR edited to be above 1.0 with MCPR edited accordingly.

b. Provide enough copies of Nl-RESP-lA completed up to section 8.2.2.

c. Ensure tech specs are available for SROs NMPl NRC JPM RO-SRO EC Page 3 of 8 February 2017

_.._ Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC JPM RO-SRO EC Page 4 of 8 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

The plant is operating at approximately 100% power with 5 Recirculation pumps in service.

No change in power or control rod position has occurred since the current 3D Monicore case was generated.

The following data is provided:

Computer Point A-390 reads 354°F Computer Point A-392 reads 352°F LEFM Flow correction factor process computer point J385 reads 0.9990 LEFM Flow correction factor process computer point J386 reads 0.9907 LEFM Flow correction factor from CRC Book - West = 0.9990 LEFM Flow correction factor from CRC Book - East= 0.9907 Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), perform the Daily Thermal Limit Surveillance in CUE accordance with N1-RESP-1A, section 8.2.

START TIME PERFORMANCE ACT. CODE EVALUATOR PI 5 I NA

1. Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper correction if necessary.

communications used.

2. Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the p procedure. STD: Nl-RESP-lA and 30 Monicore cases obtained Evaluator Provide copies of N1-RESP-1A and 3D monicore case edits (current and previous Note: day). Only provide Nl-OP-16, attachment 4 if requested.

NMP1 NRC JPM RO-SRO EC Page 5 of 8 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Complete N1-RESP-1A section 8.2 PASS/ FAIL Note: Refer to KEY for completed STD: Nl-RESP-lA surveillance. The following steps are the completed per the key critical steps:

8.2.5, 8.2.6, 8.2.7, and 8.2.9 p Role Play: If asked how to proceed at step 8.2.6 with MFLCPR above 1.0, acknowledge condition and direct the Candidate to complete the rest of section 8.2.

4. Identify discrepancy in N1-RESP-1A section PASS/ FAIL 8.2 STD: Identifies that SRO Only Cue: Once the SRO Candidate p MFLCPR/MCPR have has identified MFLCPR/MCPR violation, direct exceeded the limit them to determine the required action for this condition.

5. SRO Only - Determine required action for p PASS/ FAIL MFLCPR/MCPR violation STD: Determines Technical Specification 3.1.7.c is not met.

NMPl NRC JPM RO-SRO EC Page 6 of 8 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA p PASS/ FAIL (JPM Step 5 continued)

STD: Determines action shall be initiated within 15 minutes to restore operation to within the prescribed limit. If all the operating MCPRs are not returned to within the prescribed limit within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10%

per hour until MCPR is within the prescribed limit.

TASK Daily thermal limit surveillance completed in accordance with Nl-RESP-lA STANDARD section 8.2, with all discrepancies identified. For SRO Candidates, required actions identified.

STOP TIME NMPl NRC JPM RO-SRO EC Page 7 of 8 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is operating at approximately 100% power with 5 Recirculation pumps in service.

No change in power or control rod position has occurred since the current 3D Monicore case was generated.

The following data is provided:

Computer Point A-390 reads 354°F Computer Point A-392 reads 352°F LEFM Flow correction factor process computer point J385 reads 0.9990 LEFM Flow correction factor process computer point J386 reads 0.9907 LEFM Flow correction factor from CRC Book - West = 0.9990 LEFM Flow correction factor from CRC Book - East = 0.9907 INITIATING (Operators Name), perform the Daily Thermal Limit Surveillance in CUE accordance with N1-RESP-1A, section 8.2.

NMP1 NRC JPM RO-SRO EC Page 8 of 8 February 2017

r--_-Y;J~ Exelon Generation, Training Id: NM Pl 2017 NRC RO Admin JPM RC Revision: 0.0

Title:

Application of Radiation Exposure Limits IAW RP-AA-203 - SDC Room Approvals:

Signature I Printed Name Developed By ~/~ Paul Isham 3/25/16 Validated By Phil Carroll 8/23/16 Facility Reviewer ~<JP~ Pat O'Brien Approximate Duration: - - - 15 -

minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC JPM RO RC Page 1of7 February 2017

_.,, Exelon Generation References

1. RP-AA-203, Exposure Control and Authorization

2. RP-AA-300, Radiological Survey Program

3. NUREG 1123, 2.3.4 (3.2)

NMPl NRC JPM RO RC Page 2 of 7 February 2017

_,,,,,, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to evaluate radiological survey data against exposure limits in order to determine availability to perform operator tasks.

2. Task Information:

a. GAP-RPP07-00002, Comply with administrative exposure limits.

b. K/A 2.3.4 (3.2), Knowledge of radiation exposure limits under normal or emergency conditions.

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Training Classroom

5. JPM Setup (if required)

a. Provide copy of the SDC room survey map for each operator performing the JPM.

b. Ensure sufficient copies of RP-AA-203 and RP-AA-300 are available.

NMPl NRC JPM RO RC Page 3 of 7 February 2017

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC JPM RO RC Page 4 of 7 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

The plant is at coasting down at the end of the cycle

Preparations are being made to use of the Shutdown Cooling System during the shutdown/cooldown

Each Shutdown Cooling Pump needs to have its oil changed

Assume NO radiation exposure is received in transit to and from the job location.

Evaluator: Ask trainee if he/she has any questions a~er presenting initial conditions INITIATING (Operators Name), given supporting information, determine which jobs CUE you can complete without exceeding your administrative dose limit. The jobs are to be performed in the order stated. Your current dose is 1915 mrem.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper correction if necessary.

communications used.

2. Using the provided survey map and job descriptions, calculate the respective dose for each job as follows:

2a. Dose for Job 1: (1 /2 hour x 50 mrem/hr) = 25 mrem PASS I FAIL p

STD: Determines dose for Job 1 is 25 mrem 2b. Dose for Job 2: (1/2 hour x 60 mrem/hr} = 30 mrem PASS/ FAIL p

STD: Determines dose for Job 2 is 30 mrem NMP1 NRC JPM RO RC Page S of 7 February 2017

Exelon Generation(,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA 2c. Dose for Job 3: (1/2 hour x 80 mrem/hr) = 40 mrem p PASS/ FAIL STD: Determines dose for Job 3 is 40 mrem

3. Determines remaining dose the operator is p SAT/ UNSAT allowed to receive.

2000 mrem - 1915 mrem = 85 mrem STD: Determines the operator can receive 85 mrem prior to exceeding administrative dose limits

4. Determines which jobs can be completed p PASS/ FAIL without exceeding administrative dose limits.

STD: Determine that jobs 1 and 2 can be performed without exceeding the administrative dose limit.

85 mrem remaining is < the 95 mrem required for jobs 1, 2, and 3.

(or 1915 mrem + 95 mrem

= 2010 > 2000 mrem administrative limit)

TASK Calculates the dose for each job and determines that only jobs 1 & 2 can STANDARD be performed without exceeding the administrative dose limit of 2000 mrem/yr.

STOP TIME NMP1 NRC JPM RO RC Page 6 of 7 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is at coasting down at the end of the cycle

Preparations are being made to use of the Shutdown Cooling System during the shutdown/cooldown

Each Shutdown Cooling Pump needs to have its oil changed

Assume NO radiation exposure is received in transit to and from the job location.

INITIATING (Operators Name), given supporting information, determine which jobs you CUE can complete without exceeding your administrative dose limit. The jobs are to be performed in the order stated. Your current dose is 1915 mrem.

JOB DESCRIPTION

1. JOB 1

a. Drain SDC Pump 11 oil

b. Refill SDC Pump 11 with oil

i. Total time (for oil drain and refill): 30 minutes at the pump/motor

2. JOB 2

a. Drain SDC Pump 12 oil

b. Refill SDC Pump 12 with oil

i. Total time (for oil drain and refill): 30 minutes at the pump/motor

3. JOB 3

a. Drain SDC Pump 13 oil

b. Refill SDC Pump 13 with oil

i. Total time (for oil drain and refill): 30 minutes at the pump/motor NMPl NRC JPM RO RC Page 7 of 7 February 2017

h--,,_w' Exelon Generation, Training Id: 2017 NRC SRO Admin JPM RC Revision: -0.0

Title:

Determine Actions for Inoperable Service Water Radiation Monitor Approvals:

Developed By Paul Isham 4/1/16 Validated By Kevin Hines 8/23/16 Facility Reviewer Pat O'Brien i2/.S lk Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Stop Completion Time: Time: Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC JPM SRO RC Page 1of10 February 2017

~** Exelon Generation References

1. NUREG 1123 K/A 2.3.15, (3.1)

2. ARP Hl-4-5

3. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. lB

4. DER NM-2003-5168, ODCM Entry Due to SW RM Low Flow

5. DER NM-2004-976, Unplanned LCO - SW RM Low Flow NMPl NRC JPM SRO RC Page 2 of 10 February 2017

_.,,,. Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the SRO's knowledge of the Service Water Radiation monitor and the SRO's ability to use the ODCM to determine appropriate actions when the radiation monitor is inoperable.

b. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. NS-OM207-03002-02, Perform an administrative review to determine operability of a system, structure, or component.

b. NUREG 1123 K/A 2.3.15 (3.1), Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3. Evaluation /Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task No Alternate Path No LOO >1.0 Yes

4. Recommended Start Location

a. Training Classroom

5. JPM Setup

a. Provide a copy of ARP Hl-4-5 and a copy of the ODCM NMP1 NRC JPM SRO RC Page 3 of 10 February 2017

Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC JPM SRO RC Page 4 of 10 February 2017

Exelon Generation,,

INITIAL Given:

CONDITIONS

The plant is operating at 100% power.

High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.

Hl-4-5, LQ PROCESS RAD MON, has alarmed.

Computer Point Fl 72, SERVICE WATER SKID FAILURE, is in alarm.

Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.

Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).

Sample flow cannot be adjusted.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), determine the appropriate actions and CUE compensatory measures in response to ARP Hl-4-5. Record your findings on the provided attachment.

ISTARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper correction if necessary.

communications used

2. Obtain a copy of the reference procedure and p SAT I UNSAT review/utilize the correct section.

STD: ARP Hl-4-5 obtained.

Operator Actions referenced.

ODCM obtained. DLCO 3.6.14 referenced. Table D 3.6.14-1 referenced.

NMP1 NRC JPM SRO RC Page 5 of 10 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Per ARP Hl-4-5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:

3a Notify SM to evaluate EALs SAT/ UNSAT p

Role Play: As SM, acknowledge report. STD: Notifies SM to evaluate EALs.

3b Notify Radiation Protection Instrument SAT/ UNSAT Support for repair.

p STD: Notifies Radiation Role Play: As RP, acknowledge report. Protection Instrument Support to initiate repairs.

3c Initiate LCO sampling (Chemistry). PASS/ FAIL STD: Directs Chemistry to Role Play: As Chemistry, acknowledge perform DLCO sampling per direction to perform samples.

Table D 3.6.14-1 p

Instrument 1B action (d);

twelve (12) hour grab samples to be collected/analyzed for SW effluent.

4 Reference ODCM and takes appropriate actions.

4a SAT/ UNSAT p STD: Determines SW Radiation Monitor is inoperable.

NMPl NRC JPM SRO RC Page 6 of 10 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA 4b SAT I UNSAT p STD: References ODCM DLCO 3.6.14.a and Table D 3.6.14-1 Instrument lB and note (d) applies.

4c p PASS/ FAIL STD: Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in Table D 3.6.14-1.

4d p PASS I FAIL STD: Determines action (d) applies. Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed SW effluent.

TASK Applicable actions per ARP Hl-4-5 and ODCM in response to service STANDARD water radiation monitor low flow condition have been identified and recorded.

STOP TIME NMPl NRC JPM SRO RC Page 7 of 10 February 2017

~//lllllllJIJ!'"

Exelon Generation Attachment 1

- - - - Answer Key*****

Do Not Provide to Applicant Determine the appropriate actions in response to these conditions.

Action Required By (Document)

Notify Radiation Protection Instrument Support for ARP Hl-4-5 repair.

Direct Chemistry to initiate required LCO sampling Determines SW Radiation Monitor is inoperable. ODCM DLCO 3.6.14 TABLED 3.6.14-1.

Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in Table D 3.6.14-1.

ODCM DLCO 3.6.14 TABLE NOTE Determines action identified in note (d) applies. Effluent (d) releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed.

- - - - Answer Key*****

Do Not Provide to Applicant NMPl NRC JPM SRO RC Page 8 of 10 February 2017

Exelon Generation Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.

Action Required By (Document)

NMP1 NRC JPM SRO RC Page 9 of 10 February 2017

~, Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is operating at 100% power.

High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.

Hl-4-5, LQ PROCESS RAD MON, has alarmed.

Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.

Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.

Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).

Sample flow cannot be adjusted.

INITIATING (Operators Name), determine the appropriate actions and CUE compensatory measures in response to ARP Hl-4-5. Record your findings on the provided attachment.

NMPl NRC JPM SRO RC Page 10 of 10 February 2017

AY

~~-

Exelon Generation.,

Training Id: NMP1 2017 NRC RO Admin JPM EP Revision: 0.0

Title:

Actions for External Security Threats Approvals:

Signature I Printed Name Developed By ?/~ Paul Isham 4/6/2016 Validated By Phil Carroll 8/23/16 Facility Reviewer -p-,'h.*~~,,~""'=------lcc-d=-~'--T--~~*

__ - _ _P_at_o_'_sr_ie_n 1z/s/tt:,

Approximate Duration: - - - 15 -minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

NMPl NRC JPM RO EP Page 1of11 February 2017

Exelon Generation References

1. OP-NM-106-104, Security Contingency Event

2. NUREG 1123, 2.4.28 (3.2)

NMPl NRC JPM RO EP Page 2 of 11 February 2017

~, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to perform control room operator tasks associated with a security event. The operator will complete a Security Event -

Control Room Operator checklist.

2. Task Information:

a. Nl-SOP27.1-00001, Respond to External Security Threats.

b. K/A 2.4.28 (3.2), Knowledge of procedures relating to a security event (non-safeguards information).

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Ul Simulator

5. JPM Setup (if required)

a. Ensure sufficient copies of OP-NM-106-104 Attachment 2 are available.

NMPl NRC JPM RO EP Page 3 of 11 February 2017

_,,,,.,, Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated lPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC JPM RO EP Page 4of11 February 2017

Exelon Generation,,

INITIAL Given:

CONDITIONS

The plant is operating at 100% power.

You are the CRO.

The NRC calls on the ENS line and informs you of the following:

o NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York.

o One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site.

o The event is classified as a credible, probable airborne threat.

o The Shift Manager has declared an Alert based on the threat.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), perform actions in response to this security CUE threat in accordance with OP-NM-106-104 attachment 2.

I STARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper correction if necessary.

communications used.

2. Obtains a copy of the reference procedure SAT I UNSAT and reviews/utilizes the correct section p STD: OP-NM-106-104 attachment 2 obtained.

NMPl NRC JPM RO EP Page 5 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Notifies Shift Manager of security event. SAT I UNSAT I NA Role Play: As Shift Manager, acknowledge STD: Proper communications used report.

p Note: The operator may not notify the SM since the initial conditions indicate the SM has already been notified and has declared an Alert Emergency condition.

4. Checks plant parameters SAT I UNSAT STD: Observes major plant p parameters using control room instrumentation (ex.

Reactor power, pressure and level, Containment conditions)

5. Notifies Security Site Supervisor p PASS/ FAIL Note: Security Site Supervisor may be STD: Proper communications used contacted by Gaitronics page or by calling x5222 or x2591

6. Initiates any Operating, Special Operating or p SAT I UNSAT EOPs required STD: Proper communications used Cue: Inform that other operators are executing the required Operating, Special Operating and Emergency Operating Procedures NMP1 NRC JPM RO EP Page 6 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

7. As directed by Shift Manager, makes announcements.

Cue: As Shift Manager, provide OP-NM-106-104 attachment 6, Aircraft Attack Announcement (JPM Attachment 1)

Note: If candidate begins to broadcast announcement over speakers, examiner should direct the candidate to not broadcast over speakers and direct the announcement to the examiner only.

7a p PASS/ FAIL STD: Places GAitronics in Merge 7b p PASS/ FAIL STD: Sounds Evacuation Alarm for 5 seconds 7c p PASS/ FAIL STD: Depresses pushbutton and announces:

Attention All Plant Personnel, this (is a drill I is an actual emergency)

Aircraft Impact Imminent.

Evacuate the protected area immediately. Report directly to the Learning Center or P-Building. I repeat, this (is a drill I is an actual emergency) 7d p SAT/ UNSAT STD: Repeats Alarm and Announcement NMPl NRC JPM RO EP Page 7 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 7e p SAT/ UNSAT STD: Leaves GAitronics in merge S WHEN Security Event NO longer exists, THEN make a termination announcement PER EP-CE-115, Termination and Recovery Cue: As Shift Manager, report that Security Contingency Event no longer exists and provide EP-CE-115, Emergency Termination Announcement (JPM Attachment 2)

Note: If candidate begins to broadcast announcement over speakers, examiner should direct the candidate to not broadcast over speakers and direct the announcement to the examiner only.

Sa p SAT/ UNSAT STD: Sounds Station Alarm for 10 seconds Sb p SAT/ UNSAT STD: Announces: Attention all personnel, attention all personnel. The Alert has been terminated. I repeat, the Alert has been terminated.

TASK The operator has performed the actions listed in OP-NM-106-104, STANDARD Attachment 2, Security Event, CRO Checklist.

STOP TIME NMPl NRC JPM RO EP Page 8 of 11 February 2017

~* Exelon Generation(,

JPM Handout INITIAL Given:

CONDITIONS

The plant is operating at 100% power.

You are the CRO.

The NRC calls on the ENS line and informs you of the following:

o NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York.

o One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site.

o The event is classified as a credible, probable airborne threat.

o The Shift Manager has declared an Alert based on the threat.

INITIATING (Operators Name), perform actions in response to this security CUE threat in accordance with OP-NM-106-104 attachment 2.

NMPl NRC JPM RO EP Page 9 of 11 February 2017

Exelon Generation,.

JPM Attachment 1 OP-HM* 10b*1CM Revi1&1on ooo I

Page 1e of 20 Page t of 1 Attachment c. Alrcrart Attactt Announcement loday oat.: .....N Time.-* ....o_w AIRCRAFT ATT ACK ANNOUNCEMENT lnatructlone:

1. PLACE Gaitronle& In Merge.

2. IF tne e11en116 a dm. MAKE tne totl<M~ng announcement oetore soundl"lg tne stanon alarm:

"Tnts !6 a <1111. W& Is a Clrl'.!l. *

3. SOUND Station AJarm for ft'I~ (5? &eCO!'lct&

4. ANNOUNCE,

Attenuori. Anen~on al personnel, tN& ts (a dtlll) (an actu.al emergencn An ~reran tmpact win tne &lte Is expe~ to ocaJr wtttiri 30 minutes.

Fire Brigade, snlft Ract1anon Pratecilorl. and snm Chemm$Uf Tecnrvdans report to Securl)' Eat. e.s.o equipment stafng area. AH rem.alMig on"'nm personnel report to your respecti:*..e Control Room. Ai1 remarllng persorine! E'iacuate tne protected area lmmecJ:atety and report to tne P-8ukt1n9.

1repe-at. tnls 15 (a <1111 :1 (an actual emergencn *

5. REPEAT AJal'!'T' AND Annoonoement 6 LEA VE Gart:ronlC$ ri Merge tor tt'le ourauori or tne event

7. UpOn comp&euon, RETURN tnl& attaenm.ent to the EP Dept NMP1 NRC JPM RO EP Page 10 of 11 February 2017

Exelon Generation JPM Attachment . . 2 EP-CE-115 Revision 0 Page6of22 4.4. Event Termination from an Alert or Higher Classmcation NOTE: AU actions in this section of procedure are completed or directed by the Corporate Emergency Director.

The process for transition to Recovery is illustrated in Attachment 2, Illustrated Recovery Process.

As conditions improve and additional personnel and resources become available. certain recovery activities should be initiated prior to termination of the emergency. Refer to section 4.2, At an Alert or Higher Determine need for Recovery for recovery planning actions.

Select emergency response facilities or portions thereof may remain activated for some time after event termination during Recovery (for example, the JIC or Communications portions of the EOF).

1. COMPLETE EP-CE-111-F-O 1. Event Termination Checklist, to determine when termination can be performed.

2. When conditions are met (as outlined on Event Tem1ination Checklist):

A If a Recovery Plan and Organization is required, then TERMINATE the event and ENSURE Recovery Plan Outline and initial Recovery Organization have been established prior to releasing ERO (Refer to Sections 4 .2 and 4 .4 ).

B. If it has been determined that NO Recovery Plan or Organization is needed and all further actions will be performed using the station's normal organizations and processes, then TERMINATE the event

3. PERFORM the following after event termination:

A ANNOUNCE (or direct someone to announce) the following (or similar) message to plant personnel over the public address system:

"Attention all personnel, attention an personnel. The [Alert, Site Area Emergency, General Emergency] has been terminated. I repeat, the (Alert, Site Area Emergency, General Emergency]

has been terminated."

NMPl NRC JPM RO EP Page 11of11 February 2017

d 1

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r--*'.

Exelon Generation Training Id: 2017 NRC SRO Admin JPM EP Revision: -0.0

Title:

Emergency Event Classification and PARs Based on Dose Assessment Approvals:

Signature I Printed Name Developed By ~_,*~au! Isham 4/8/16 Validated By Kevin Hines 8/23/16 Facility Reviewer Pat O'Brien t?(S/(&

Approximate Duration: - - - 15-minutes Documentation of Performance:

Performer:

Evaluator:

Start Stop Completion Time: Time: Time Grade: Pass I Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMP1 NRC JPM SRO EP Page 1of9 February 2017

References

1. NUREG 1123 K/A 2.4.29, (4.4)

2. EP-CE-111, Emergency Classification and Protective Action Recommendations

3. EPIP-EPP-01, Unit 1 EAL Flowchart NMPl NRC JPM SRO EP Page 2 of 9 February 2017

Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the SRO's knowledge of the station's Emergency Preparedness program. The SRO will declare an emergency within 15 minutes of indications being made available that an EAL has been exceeded. PARs will be made after the declaration.

b. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. NS-EPlOl-03013, Make protective action recommendations as necessary to offsite agencies.

b. NUREG 1123 K/A 2.4.29 (4.4), Knowledge of the emergency plan.

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Classroom Time Critical Task Yes Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Training Classroom

5. JPM Setup

a. Provide sufficient copies of EAL flowcharts and the Shift Emergency Director packages.

NMP1 NRC JPM SRO EP Page 3 of 9 February 2017

Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC JPM SRO EP Page 4 of 9 February 2017

Exelon Generation, INITIAL Given:

CONDITIONS

You are the Unit 1 Shift Manager.

Unit 1 was operating at 100% power.

Unit 2 is operating at 100% power.

The following conditions have occurred:

o A loss of coolant accident at Unit 1 has resulted in a Site Area Emergency being declared.

o An Exclusion Area Evacuation has been directed and is in progress.

a The time of shutdown is 20 minutes ago.

a The Dose Assessment team reports 1.1 Rem TEDE at the site boundary.

o Meteorological data is as follows:

30 ft 200 ft Wind Speed 8 mph 8 mph Wind Direction 150° 150° Stability Class E Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), take the required actions as the Shift Manager I CUE Shift Emergency Director. This is a time critical task.

I STARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper correction if necessary.

communications used NMPl NRC JPM SRO EP Page 5 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PI 5 I NA

2. Obtain a copy of the reference procedure and p SAT I UNSAT review/utilize the correct section.

STD: Obtains EAL Flowchart and Shift Emergency Director binder.

3. Using given release data and the EAL PASS/ FAIL Flowchart, determine that a General STD: Determines General Emergency exists based on dose at the Site p Emergency, RGl.2, due to Boundary.

dose at the site boundary

>1000mrem TEDE.

Note: This determination may not be made until JPM step 5.

4 Completes Shift Emergency Director SAT I UNSAT Checklist section 1.1, Entry Into the STD: Name and date Emergency Plan.

entered in step 1.1.1 Role Play: If requested as Shift p SAT I UNSAT Communicator and/or Shift Dose Assessor to report to the control room, acknowledge STD: Communicator and/or request. Shift Dose Assessor requested to report to the control room.

NMPl NRC JPM SRO EP Page 6 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 5 Completes Shift Emergency Director PASS/ FAIL Checklist section 1.2, Emergency STD: Declares the event by Classification and PAR. announcing the following, "I am declaring a General Role Play: If requested as STA to perform Emergency at (time) due to peer check, concur with the applicant dose at the site boundary exceeding 1 Rem and regardless of accuracy of EAL determination.

assuming the role as Shift Emergency Director. (Or similar announcement)

The time difference below must be 15 minutes or less:

JPM Start time:

Declaration time:

PASS/ FAIL p

STD: Determines an OCA evacuation should be implemented. (EP-AA-112-F-57)

Role Play: If the applicant attempts to make the PA announcement or directs the SAT I UNSAT Emergency PA announcement be made, inform them another operator will perform STD: Completes the announcement they determine Emergency PA Announcement form. (Verify appropriate.

General Emergency is selected in Block 4 and OCA Evacuation is selected in Block 9.)

Cue: If the applicant attempts to complete PASS/ FAIL notification paperwork for PARs, direct them to just determine PARs and inform the STD: Determines PARs to examiner. evacuate ERPAs 1, 2, 3, 26, 27, 28, 29.

NMPl NRC JPM SRO EP Page 7 of 9 February 2017

_,.,, Exelon Generation Termination Cue When PARs have been determined, inform the applicant their task is complete.

TASK Applicant has determined a General Emergency exists and the STANDARD appropriate PARs I STOPTIME NMPl NRC JPM SRO EP Page 8 of 9 February 2017

~ Exelon Generation.,

JPM Handout INITIAL Given:

CONDITIONS

You are the Unit 1 Shift Manager.

Unit 1 was operating at 100% power.

Unit 2 is operating at 100% power.

The following conditions have occurred:

o A loss of coolant accident at Unit 1 has resulted in a Site Area Emergency being declared.

o An Exclusion Area Evacuation has been directed and is in progress.

o The time of shutdown is 20 minutes ago.

o The Dose Assessment team reports 1.1 Rem TEDE at the site boundary.

o Meteorological data is as follows:

30 ft 200 ft Wind Speed 8 mph 8 mph Wind Direction 150° 150° Stability Class E INITIATING (Operators Name), take the required actions as the Shift Manager I CUE Shift Emergency Director. This is a time critical task.

NMPl NRC JPM SRO EP Page 9 of 9 February 2017

~* Exelon Generation'"

Training Id: 2017 NRC NMPl Simulator JPM S-1 Revision: 0.0 Synchronize Main Generator to Grid, Main Generator Locks Out

Title:

(Alternate Path)

Approvals:

e Printed Name Developed By Paul Isham 2/18/16 Validated By Phil Carroll 8/23/16

,,~***/'~~

Facility Reviewer _

7

__,,<+*V'~'<_t'C/_*_L/'_,_

. *-~r-

': _,,L-/'_,,....,-_*_ _ _Pa_t_O_'B_r_ie_n ;z/s/lc:,,

Approximate Duration: - - - 20 - minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

NMPl NRC 2017 JPM S-1 Page 1 of 11 February 2017

_,.,_ Exelon Generation References

1. Nl-OP-32, Generator

2. Nl-SOP-31.1, Turbine Trip

3. NUREG 1123 K/A 245000 A4.02, (3.1/2.9)

NMPl NRC 2017 JPM S-1 Page 2 of 12 February 2017

_..,, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate controls associated with the Main Generator, including synchronization and loading.

b. This JPM is considered alternate path because once the Main Generator is given some load, the Main Turbine will trip. The operator will be required to enter and execute the Turbine Trip SOP.

c. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. Nl-245001-01004

b. K/A 245000 A4.02, (3.1/2.9)

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOO >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM 5-1 Page 3 of 12 February 2017

~* Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in a power operating condition (15-20%)

b. Initialize simulator to IC 161

c. The Main Generator is ready to be synchronized

d. Verify the following malfunction:

TCOl, Main Turbine Trip TRG1

e. Verify event trigger, TRG1 is set to activate on "hzleglOc= = l&zdeg lOSO= =O".

f. Verify the following remote functions:

EGll, STATOR COOLING WATER PUMP 11 CONTROL FV=greenf_auto, TRG2

EG12, STATOR COOLING WATER PUMP 12 CONTROL FV=redf, DT=2, TRG2

6. JPM Setup (if required)

a. Nl-OP-32 marked up through step E.3.1. Applicants will start on step E.3.2.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM 5-1 Page 4 of 12 February 2017

Exelon Generation".

INITIAL Given:

CONDITIONS

A plant startup is in progress.

The reactor is operating approximately 18% power.

N1-0P-43A, step E.5.9 is in progress to synchronize and load the turbine and generator.

Nl-OP-32 is completed through step E.3.1.

Nine Mile Point Unit 2 Lines 5 and 6 are in-service.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), complete synchronizing the Main Generator to the CUE grid by starting at step E.3.2 of Nl-OP-32. Load the Generator until all turbine bypass valves are closed. Then, complete the remainder of section E.3.0.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT I UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the p procedure STD: Nl-OP-32 obtained.

Procedure ,; "Per N 1-0P-25, Startup of Steam Jet Air Ejectors, condenser vacuum should be

Note: j stabilized at approximately 26 inHg to 26.5 inHg to minimize turbine vibrations leading to a potential turbine trip." If the applicant questions condenser vacuum due to this note, inform the applicant another operator will manage condenser vacuum.

. 1 NMP1 NRC 2017 JPM S-1 Page 5 of 12 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Verify open R915 and R925 SAT I UNSAT Note: There is a short time delay before p STD: Verifies R915 and movement of MOD-18 results in indicating (3.2) R925 indicate open by light change and clearing of annunciator A7- verifying red lights off, green lights on 1-5 "Generator Switch 18 Open".

4. Close switch SW-18 GENERATOR 1 *PASS/ FAIL p STD: Places SW 18 (3.3) Generator 1 switch to close and verifies green light goes out and red light is on

5. Using Attachment 7, binoculars, AND SAT/ UNSAT spot light if lighting insufficient, locally STD: Verifies all three verify SW 18 is fully closed on ALL three p phases closed by checking phases with the operator in the (3.4) field.

Cue: As operator in the field, confirm all three phases are fully closed on SW 18.

6. IF any phases is NOT fully closed, THEN SAT/ UNSAT p

notify SM AND EMD (3.5) STD: Determines NA based on field report.

7. Insert Sync Key into R915 (R925) *PASS/ FAIL SYNCHRONIZING Switch, AND place R915 (R925) SYNCHRONIZING Switch to ON STD: Inserts Sync Key into p R915 (R925)

Note: If the applicant opts to close R925 (3.6) SYNCHRONIZING Switch, AND places R915 (R925) before R915, the alternate path will need to SYNCHRONIZING Switch to be manually initiated by inserting TRG1 ON

8. Verifies INCOMING and RUNNING voltages SAT I UNSAT are matched p STD: Adjusts voltage as (3.7) needed using the Exciter Rheostat NMPl NRC 2017 JPM S-1 Page 6 of 12 February 2017

Exelon Generation" PERFORMANCE ACT. CODE EVALUATOR PIS I NA

9. Adjust GOVERNOR Switch UNTIL SAT I UNSAT synchroscope is rotating slowly in the FAST direction p STD: Adjusts generator (3.8) frequency using by adjusting the GOVERNOR Switch

10. When INCOMING and RUNNING voltages are *PASS I FAIL matched, AND synchroscope is indicating 3 to 5 degrees lead time, close R915 (R925) p STD: When synchroscope indicates 3 to 5 degrees (3.9) lead time, places control switch for R915 (R925) in the CLOSE position

11. Immediately load the generator to 15-60 SAT/ UNSAT MWe OR UNTIL all Turbine Bypass Valves Close STD: Places governor p control switch in the RAISE position until all turbine (3.10) bypass valves are closed (as observed on panel Al, all Turbine BV indicating lights "green")

12. Place R915 (R925) SYNCHRONIZING Switch SAT/ UNSAT to OFF and remove key p STD: Place R915 (R925)

(3.11)

SYNCHRONIZING Switch to OFF and remove key Alterl1~te .;

When the SYNCHRONIZING Switch is placed in OFF, a trigger with a 10

- - 'i>ath~";:

. *l ;.~.

second time delay will cause a Turbine trip. This initiates the alternate path.

13. Executes alarm response procedures or Nl- SAT/ UNSAT SOP-31.1 STD: Observes P annunciators, determines the Turbine and Generator have tripped and enters Nl-SOP-31.1

14. Verify the following:

NMP1 NRC 2017 JPM S-1 Page 7 of 12 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 14a Turbine Stop valves closed SAT/ UNSAT p STD: Visually observes Turbine Stop Valves closed (green lights on) 14b Turbine Control valves closed SAT/ UNSAT p STD: Visually observes Turbine Control Valves closed (green lights on) 14c Turbine Reheat Stop Valves closed SAT I UNSAT Turbine Intercept Valves closed p STD: Visually observes Combined Reheat Valves closed (green lights on) 14d Bypass valves maintaining Reactor pressure SAT/ UNSAT as necessary STD: Visually observes p Turbine Bypass Valves open to control reactor pressure (red lights on for several valves)

15. Verify the following Electrical Distribution system conditions:

15a 345 Kv Breakers R915, R925 TRIPPED SAT/ UNSAT p STD: Visually observes 345Kv Breakers R915, R925 TRIPPED (Green light on) 15b MOD 18 OPEN SAT/ UNSAT p STD: Visually observes MOD 18 OPEN (Green light on)

NMP1 NRC 2017 JPM S-1 Page 8 of 12 February 2017

Exelon Generation,,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA lSc PB 11, PB12 supplied from Reserve Power SAT I UNSAT Cue: Another Operator will control RPV STD: Visually observes PB water level and pressure. Continue with the p 11, PB12 supplied from actions of SOP-31.1. Reserve Power (R123 and R112 CLOSED, Red lights on)

16. Perform the following:

16a Verify ON, Aux. Oil pumps SAT/ UNSAT STD: Rotates Aux. Oil Pump p switches (2) clockwise, observes red lights illuminate, green lights extinguish 16b Verify A7-3-3 Alarm clears SAT/ UNSAT p

STD: Observes alarm clear on A7 panel 16c Reset Generator 86 relays *PASS/ FAIL p STD: Resets 86 relays by rotating control switches clockwise 16d Restart Stator Water Cooling *PASS/ FAIL Note: When dispatched to restart Stator STD: Dispatches operator p

Water Cooling, insert trigger 2, then report to restart Stator Water the task has been completed with time Cooling compression.

NMPl NRC 2017 JPM S-1 Page 9 of 12 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA 16e Start bearing lift pumps *PASS/ FAIL STD: Rotates Bearing lift p pump switches (5) clockwise, observes red lights illuminate, green lights extinguish 16f Adjust TURBINE OIL TEMP CONTROL setpoint SAT/ UNSAT to 90°F for turning gear operation p STD: Rotates the turbine oil temperature controller knob on A1 panel CCW to adjust setpoint to 90.

17. Shutdown turbine per Nl-OP-31 SAT/ UNSAT p

Cue: Inform candidate that another operator STD: Proper will be tasked with Turbine shutdown. communications used

18. Verify ATS Gross Failure Lights are OFF SAT/ UNSAT p

STD: Observes ATS Gross Failure Lights are OFF

19. Contact Structural Engineering to SAT/ UNSAT perform walkdown of System 03 piping STD: Proper and support for damage communications used p

Role Play: If contacted as Structural Engineer, acknowledge request to perform system walkdowns.

Evaluator Note: Cue: Your task is complete.

NMPl NRC 2017 JPM S-1 Page 10 of 12 February 2017

Exelon Generation TASK The Main Generator was synched to the grid in accordance with Nl-STANDARD OP-32. Then per Nl-SOP-31.1, the Main Turbine is tripped, TCVs, TSVs and Combined Reheat Valves are closed, Generator 86 relays are reset, Stator Water Cooling is restored, Auxiliary Oil pumps are running, and Bearing Lift pumps are on.

ISTOPTIME NMPl NRC 2017 JPM 5-1 Page 11 of 12 February 2017

Exelon Generation,,

JPM Handout INITIAL Given:

CONDITIONS

A plant startup is in progress.

The reactor is operating approximately 18% power.

Nl-0P-43A, step E.5.9 is in progress to synchronize and load the turbine and generator.

Nl-OP-32 is completed through step E.3.1.

Nine Mile Point Unit 2 Lines 5 and 6 are in-service.

INITIATING (Operators Name), complete synchronizing the Main Generator to the CUE grid by starting at step E.3.2 of Nl-OP-32. Load the Generator until all turbine bypass valves are closed. Then, complete the remainder of section E.3.0.

NMPl NRC 2017 JPM 5-1 Page 12 of 12 February 2017

~~.~ Exelon Generation, Training Id: 2017 NRC NMPl Simulator JPM S-2 Revision: -0.0----

Title:

Startup Control Room Ventilation System Approvals:

Developed By 2/17/16 Validated By Kevin Hines 8/23/16 Facility Reviewer - ___ 4~*~*-7~~*

71t# ~

~?'-~-*~*

_..,....__*_ _ _P_a_t_O_'B_r_ie_n _IZ(...5/16 Approximate Duration: - - - 15 -

minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

2017 NMPl NRC JPM 5-2 Page 1of9 February 2017

~ Exelon Generation,,

References

1. Nl-OP-49, Control Room Ventilation System

2. NUREG 1123 K/A 290003 A4.01, (3.2/3.2) 2017 NMP1 NRC JPM S-2 Page 2 of 9 February 2017

Exelon Generation Instructor Information A. lPM Information

1. Description

a. This JPM tests the operator's ability to startup the control room ventilation system.

b. This JPM is NOT considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. Nl-288003-01001, Startup the Control Room Ventilation System

b. K/A 290003 A4.01, (3.2/3.2)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOO >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator 2017 NMPl NRC JPM 5-2 Page 3 of 9 February 2017

Exelon Generation.,

5. Simulator Setup (if required)

a. Initialize simulator to IC-161

b. Verify Control Room Ventilation is secured !AW Nl-OP-49, Section G.

c. Verify Cooling Coil Block Valve selected to 12

d. Verify EVS Fan 11 in Auto

6. JPM Setup (if required)

a. Ensure sufficient copies of Nl-OP-49 P&L's and Section E are available.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

2017 NMPl NRC JPM 5-2 Page 4 of 9 February 2017

jll!IJIJIJ!f/J<rr Exelon Generation,,

INITIAL Given:

CONDITIONS

The control room ventilation system is being restarted following maintenance.

Nl-OP-49, Attachment 1 valve lineup is complete.

Nl-OP-49, Attachment 2 electrical lineup is complete.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), startup the control room ventilation system in CUE accordance with Nl-OP-49, Section E, with the following lineup:

Emergency Fan 12 in Auto

Chiller 11 in service

Cooling Coil 11 in service

Chilled Water Circulating Pump 11 in service

Control Room Circulating Fan 11 in service START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT STD: Proper p

Cue: Acknowledge repeat back providing communications used correction if necessary

2. Obtain a copy of the reference procedure and SAT I UNSAT review / utilize the correct section of the procedure p STD: Nl-OP-49 obtained.

Precautions and limitations reviewed. Section E referenced.

3. Perform the following at the direction of the SAT I UNSAT I NA SM:

Valve Lineup completed per STD: Determines this step p

Attachment 1. is NA per initial conditions

Electrical Lineup performed per Attachment 2.

2017 NMP1 NRC JPM S-2 Page 5 of 9 February 2017

Exelon Generation" PERFORMANCE ACT. CODE EVALUATOR PIS I NA

4. Verify the following open: SAT I UNSAT

210-08, INLET BV 12 STD: Observes 210-08 red light on, green light off p

(E.3.0)

SAT I UNSAT STD: Observes 210-39 red

210-39, INLET BV 11 light on, green light off

5. Verify the following closed: SAT I UNSAT

210-40, 11 CR Emergency Fan Inlet STD: Observes 210-40 BV (DAMPER) green light on, red light off p

(E.4.0)

SAT/ UNSAT STD: Observes 210-41

210-41, 12 CR Emergency Fan Inlet BV (DAMPER) green light on, red light off

6. Place EMER FAN 12 control switch in AUTO. *PASS I FAIL p

STD: Places control room (E.5.0) emergency fan 12 control switch in Auto

7. Place EMER FAN 11 control switch in OFF. *PASS/ FAIL p

STD: Places control room (E.6.0) emergency fan 11 control switch in Off 2017 NMPl NRC JPM S-2 Page 6 of 9 February 2017

Exelon Generation, PERFORMANCE ACT. CODE EVALUATOR PIS I NA

8. Place COOLING COIL 11 BLOCK VALVE SAT/ UNSAT selector switch in position 11.

STD: Places Cooling coil 11 Note: The cooling coil block valve indications in service by rotating will swap when the switch is rotated to p selector switch CCW position 11. Cooling coil block valve 12 red (E.7.0) light will extinguish and the green light will illuminate. Cooling coil block valve 11 green light will extinguish and the red light will illuminate.

9. Depress START pushbutton for CHILLED *PASS/ FAIL WATER CIRCULATING PUMP 11 AND confirm p STD: Depresses start red indicator light lit.

(E.8.0) button for chilled water circulating pump 11 and observes red light lit.

10. Starting CHILLER 11 as follows:

lOa Verify VLV-210.1-142 is open SAT/ UNSAT p

Cue: As operator in the field, report VLV- (E.9.1.1) STD: Confirm valve is open 210.1-142 is open by field operator report.

lOb Depress Chiller 12 START pushbutton at the *PASS I FAIL N Panel in the Control Room OR locally at p Chiller 12. STD: Depresses CHILLER (E.9.1.2) 11 pushbutton, then observes red light lit lOc Confirm at least one lead chiller compressor SAT I UNSAT red indicator light lit.

p STD: Observes red lights lit for "111 CHILLER (E.9.1.3)

COMPRESSOR 112" and/or "121 CHILLER COMPRESSOR 122" 2017 NMPl NRC JPM S-2 Page 7 of 9 February 2017

~* Exelon Generation.,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

11. Starting CR Circulating Fan by performing *PASS/ FAIL the following:

p STD: Circulating Fan 11 IF Control Room EMER FAN 12 was placed in (E.10.2) control switch rotated CW to AUTO, THEN place CONTROL ROOM RUN CIRCULATING FAN 11 in RUN.

12. Inform US that the control room ventilation SAT I UNSAT I NA system is operating. p STD: Proper communications used Evaluator Note: Cue: Your task is complete.

TASK The control room ventilation system is operating with the following lineup:

STANDARD

Emergency Fan 12 in Auto

Cooling Coil 11 in service

Chilled Water Circulating Pump 11 in service

Control Room Circulating Fan 11 in service STOP TIME 2017 NMPl NRC JPM S-2 Page 8 of 9 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The control room ventilation system is being restarted following maintenance.

Nl-OP-49, Attachment 1 valve lineup is complete.

Nl-OP-49, Attachment 2 electrical lineup is complete.

INITIATING (Operators Name), startup the control room ventilation system in CUE accordance with Nl-OP-49, Section E, with the following lineup:

Emergency Fan 12 in Auto

Chiller 11 in service

Cooling Coil 11 in service

Chilled Water Circulating Pump 11 in service

Control Room Circulating Fan 11 in service 2017 NMPl NRC JPM 5-2 Page 9 of 9 February 2017

~~* ,,¥' Exelon Generation(>

Training Id: 2017 NRC NMP1 Simulator JPM S-3 Revision: -0.0

Title:

Channel 11 Non-Coincident Scram Test Approvals:

Si Date Developed By Paul Isham 2/23/16 Validated By Phil Carroll 8/23/16 Facility Reviewer f~~

7>

Pat O'Brien 12{..rllG Approximate Duration: - - minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: ----

Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC 2017 JPM S-3 Page 1of10 February 2017

~, Exelon Generation References

1. Nl-ST-R4, Reactor Mode Switch in Refuel, Shutdown and Scram Dump Volume Level Scram Bypass Instrument Channel Test

2. NUREG 1123 K/A 215004 A4.05, (3.1/3.2)

NMPl NRC 2017 JPM 5-3 Page 2 of 10 February 2017

~* Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate back panel equipment associated with neutron monitoring. The operator will generate a scram signal using SRMs.

b. This JPM is considered NOT alternate path.

c. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. NS-OPS-01007

b. K/A 215004 A4.05, (3.1/3.2)

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM 5-3 Page 3 of 10 February 2017

Jlllllll!f'ffi Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in cold shutdown condition with the Mode Switch in Refuel

b. Initialize simulator to IC 162

6. JPM Setup (if required)

a. Provide sufficient copies of N1-ST-R4, section 8.5. Also include P&Ls and Prerequisites.

B. Read Before Every lPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated lPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM 5-3 Page 4 of 10 February 2017

Exelon Generation,,

INITIAL Given:

CONDITIONS

The reactor is in a shutdown condition with the mode switch in REFUEL.

Non-Coincident Scram testing is to be performed on SRM 11 for Post-Maintenance Testing.

No personnel are working in the CRD Accumulator area.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), perform Nl-ST-R4 Section 8.5, Channel 11 and CUE 12 Non-Coincident Scram Test, for SRM 11 only, steps 8.5.1 through 8.5.13.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT I UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review I utilize the correct section of the p procedure STD: Nl-ST-R4 obtained.

3. Verify RPS clear of half scrams. SAT I UNSAT p

STD: Observes channel 11 (8.5.1) and 12 white scram lights lit on F Panel.

4. IF personnel are working in CRD Accumulator SAT/ UNSAT area, THEN notify personnel a full scram is to p be initiated. (8.5.2) STD: Determines step NA per initial conditions.

NMPl NRC 2017 JPM S-3 Page 5 of 10 February 2017

Exelon Generation,<

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

5. Place REFUEL INST. TRIP BYPASS 11 switch *PASS/ FAIL on M Panel to NON-COINCIDENT position.

p STD: At M Panel, rotate (8.5.3) keylock switch for Refuel Inst Trip Bypass 11 CW to Non-Coincident

6. Place REFUEL INST. TRIP BYPASS 12 switch *PASS I FAIL on M Panel to NON-COINCIDENT position.

p STD: At M Panel, rotate (8.5.4) keylock switch for Refuel Inst Trip Bypass 12 CW to Non-Coincident

7. Place SRM 11 Mode Selector switch to *PASS/ FAIL PERIOD.

p STD: At G Panel, rotates (8.5.5) SRM 11 Mode Selector Switch CCW to Period.

8. Place RESET switch to RAMP AND release *PASS I FAIL STD: At G Panel, rotates p the RESET switch CCW to RAMP, then releases.

(8.5.6)

9. Place AND hold RAMP switch to FIXED. *PASS/ FAIL p STD: At G Panel, holds (8.5.7) RAMP switch CW to FIXED while observing LOG RATE meter indication rising.

NMPl NRC 2017 JPM S-3 Page 6 of 10 February 2017

Exelon Generationc PERFORMANCE ACT. CODE EVALUATOR PIS I NA

10. WHEN LOG RATE meter indicates greater SAT/ UNSAT than 5 x 105 CPS, THEN confirm the following: STD: Verfifies appropriate scram signal indications per step 8.5.8.

Annunciator Fl-3-1, RPS CH 11 MAN REACTOR TRIP - alarmed [T /S]

Annunciator Fl-4-1, RPS CH 11 REFUEL INST TRIP - alarmed

Annunciator F4-3-8, RPS CH 12 MAN REACTORTRIP - alarmed [T /S]

Channel 11 White SCRAM SOLENOID GROUPS lights at M Panel - off

Channel 11 SCRAM SOLENOID GROUPS white lights at F Panel - off

Channel 11 Red B.U. SCRAM S.D.V .

VENT & DRAIN VALVE light at F Panel

- off

Computer Point W022, ***RPS CHll p MAN RX TRIP - YES (8.5.8)

Channel 12 White SCRAM SOLENOID GROUPS lights at M Panel - off

Channel 12 SCRAM SOLENOID GROUPS white lights at F Panel - off

Channel 12 Red B.U. SCRAM S.D.V .

VENT & DRAIN VALVE light at F Panel

- off

Computer Point W068, ***RPS CH12 MAN RX TRIP - YES Note: The RAMP switch will need to be released in order to verify the proper plant response on F and E panels. The applicant may request direction. If so, direct the applicant to release the RAMP switch to verify appropriate plant response. The alarms will continue flashing until acknowledged.

11. Release RAMP switch SAT I UNSAT p

STD: Releases RAMP switch (8.5.9 and allows switch to return to its normal position.

NMPl NRC 2017 JPM S-3 Page 7 of 10 February 2017

Exelon Generation~,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

12. Place SRM 11 Mode Switch to OPERATE *PASS I FAIL p

STD: At G panel, rotates (8.5.10)

SRM 11 Mode Selector Switch CW to OPERATE

13. Reset any SRM 11 (SRM 12) alarms. SAT I UNSAT p

STD: At G Panel, rotates (8.5.11)

RESET switch CW to TRIP and releases

14. IF Scram Dump Volume High Level Automatic Scram is indicated (ANN Fl-1-8 AND/OR F4-1-1), THEN perform the following:

Note: This condition is not expected. These steps are expected to be NA

a. Place SCRAM DISCHARGE VOL HIGH LEVEL SAT/ UNSAT /NA BYPASS CH 11-1/12-1 switch to BYPASS.

p STD: On F Panel, rotates SCRAM DISCHARGE VOL (8.5.12)

HIGH LEVEL BYPASS CH 11-1/12-1 switch CW to BYPASS

b. Place SCRAM DISCHARGE VOL HIGH LEVEL SAT I UNSAT I NA BYPASS CH 11-2/12-2 switch to BYPASS.

p STD: On F Panel, rotates SCRAM DISCHARGE VOL (8.5.12)

HIGH LEVEL BYPASS CH 11-2/12-2 switch CW to BYPASS

c. Reset Reactor Scram SAT I UNSAT I NA p

STD: On F Panel, depresses (8.5.12)

REACTOR TRIP RESET pushbutton and releases.

NMPl NRC 2017 JPM S-3 Page 8 of 10 February 2017

~ Exelon Generation.,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

15. Depress REACTOR TRIP RESET pushbutton at SAT I UNSAT E panel AND confirm the following:

STD: Verfifies appropriate scram signal indications

Annunciator Fl-3-1, RPS CH 11 MAN have cleared per step REACTOR TRIP - clear 8.5.13.

Annunciator Fl-4-1, RPS CH 11 REFUEL INST TRIP - clear

Annunciator F4-3-8, RPS CH 12 MAN REACTOR TRIP - clear

Channel 11 White SCRAM SOLENOID GROUPS lights at M Panel - lit

Channel 11 SCRAM SOLENOID GROUPS white lights at F Panel - lit p

Channel 11 Red B.U. SCRAM S.D.V . (8.5.13)

VENT & DRAIN VALVE light at F Panel - lit

Computer Point W022, ***RPS CHll MAN RX TRIP - NO

Channel 12 White SCRAM SOLENOID GROUPS lights at M Panel - lit

Channel 12 SCRAM SOLENOID GROUPS white lights at F Panel - lit

Channel 12 Red B.U. SCRAM S.D.V .

VENT & DRAIN VALVE light at F Panel

- lit

Computer Point W068, ***RPS CH12 MAN RX TRIP - NO Evaluator Note: Cue: Your task is complete.

TASK Nl-ST-R4 Section 8.5, Channel 11 and 12 Non-Coincident Scram STANDARD Test has been completed for SRM 11.

ISTOPTIME NMPl NRC 2017 JPM S-3 Page 9 of 10 February 2017

~ Exelon Generation" JPM Handout INITIAL Given:

CONDITIONS

The reactor is in a shutdown condition with the mode switch in REFUEL.

Non-Coincident Scram testing is to be performed on SRM 11 for Post-Maintenance Testing.

No personnel are working in the CRD Accumulator area.

INITIATING (Operators Name), perform Nl-ST-R4 Section 8.5, Channel 11 and CUE 12 Non-Coincident Scram Test, for SRM 11 only, steps 8.5.1 through 8.5.13.

NMP1 NRC 2017 JPM 5-3 Page 10 of 10 February 2017

~- J Exelon Generation, Training Id: 2017 NRC NMP1 Simulator JPM S-4 Revision: -0.0

Title:

Vent the Drywell Prior to Personnel Entry <212F Per N1-0P-9 Approvals:

Signature I Printed Name Developed By &~I Isham 02/17/16 Validated By Kevin Hines 8/23/16

__~.$o<-,r'***-b'

~-*-~~-~-/~/'i'___P_at_O_'_B_rie_n Facility Reviewer 7

Approximate Duration: - - - 15 -

minutes (2/.J/f6 Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: Date:

NMPl NRC 2017 JPM S-4 Page 1of9 February 2017

_,,,,_. Exelon Generation.,

References

1. Nl-OP-9, N2 Inerting and H2-02 Monitoring Systems

2. NUREG 1123 K/A 223001, A4.03, (3.4/3.4)

NMP1 NRC 2017 JPM 5-4 Page 2 of 9 February 2017

~** Exelon Generation.,

Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locate and operate containment air dilution valves for inerting and de-inerting the containment. The operator will vent the drywell with the reactor <212F.

b. This JPM is NOT considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. Nl-223003-01004

b. K/A 223001, A4.03, (3.4/3.4)

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM 5-4 Page 3 of 9 February 2017

Exelon Generation,,

5. Simulator Setup (if required)

a. The reactor is in a shutdown condition.

b. Initialize simulator to IC-162.

c. Verify remote PCOS is inserted with valves open.

d. Verify some positive pressure in the drywell.

6. JPM Setup (if required)

a. Nl-OP-9 marked up through G.2.7.b.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM 5-4 Page 4 of 9 February 2017

Exelon Generation,,

INITIAL Given:

CONDITIONS

The plant is shutdown, <212°F.

The Operations Manager has determined a complete de-inert to 19.5% Oxygen is necessary.

Nl-OP-9 is completed through Step G.2.7.b.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), vent the Drywell in accordance with Nl-OP-9, CUE starting at step G.2. 7 .c.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT p

STD: Proper Cue: Acknowledge repeat back providing communications used correction if necessary

2. Obtain a copy of the reference procedure and SAT I UNSAT review I utilize the correct section of the procedure p STD: Nl-OP-9 obtained, precautions and limitation reviewed, section G.2.0 referenced

3. Open the following valves:

3a. 201-10, DW AIR VENT & PURGE ISOLATION *PASS/ FAIL VALVE 11 p (Step 2.7) STD: Rotates 201-10 control switch CW 3b. 201-08, TOR AIR VENT & PURGE ISOLATION *PASS/ FAIL VALVE 11 p (Step 2.7) STD: Rotates 201-08 control switch CW NMPl NRC 2017 JPM S-4 Page 5 of 9 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA 3c. 201-32, DW N2 VENT & PURGE ISOLATION *PASS/ FAIL VALVE 11 p

STD: Rotates 201-32 (Step 2. 7) control switch CW 3d. 201-16, TORUS N2 VENT & PURGE *PASS/ FAIL ISOLATION VALVE 11 p

STD: Rotates 201-16 (Step 2.7) control switch CW

4. Applicant should determine from initial SAT I UNSAT conditions, a full de-inert is required for p

personnel entry to the Drywell and should STD: Determines 19.5%

(Step 2.8) select "Approximately 19.5%". oxygen per the initial conditions.

Note: Step 2.9 is N/A

5. Notify Chemistry that a Drywell purge is SAT/ UNSAT about to commence.

p STD: Proper communications used

6. Start 201-35, DRYWELL & TORUS VENT & *PASS/ FAIL PURGE p

STD: Rotates 201-35 (Step 2.11) control switch CW

7. Verify open the following valves: SAT/ UNSAT

201-21, DW & TOR VENT & PURGE FAN p STD: Observes red light INLET BV (Step 2.12) on, green light off for

201-22, DW & TOR VENT & PURGE FAN both OUTLET BV NMPl NRC 2017 JPM S-4 Page 6 of 9 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA

8. Throttle open 201-31, DW N2 VENT & PURGE *PASS/ FAIL ISOLATION VALVE 12 p STD: Rotates 201-31 (Step 2.13) control switch CW 8a. SAT I UNSAT STD: Throttles 201-31 by using pull-to-stop feature of control switch

9. Throttle open 201-17, TORUS N2 VENT & *PASS I FAIL PURGE ISOLATION VALVE 12 p STD: Rotates 201-17 Cue: After 201-17 is opened, report drywell (Step 2.14) control switch CW and torus pressure is below O psig for purposes of this JPM (time compression used).

9a. SAT/ UNSAT STD: Throttles 201-17 by using pull-to-stop feature of control switch

10. When drywell and Torus pressures drops SAT/ UNSAT BELOW 0 psig, open the following valves:

p STD: Continues the JPM based on examiner cue in JPM step 9.

10a 201-09, DW AIR VENT & PURGE ISOLATION *PASS/ FAIL VALVE 12 p STD: Rotates 201-09 control switch CW NMP1 NRC 2017 JPM S-4 Page 7 of 9 February 2017

Exelon Generation,.

PERFORMANCE ACT. CODE EVALUATOR PIS I NA lOb 201-07, TOR AIR VENT & PURGE ISOLATION *PASS/ FAIL VALVE 12 p STD: Rotates 201-07 control switch CW Cue: Another operator will complete this procedure.

Evaluator Note: Cue: Your task is complete.

TASK Drywell vented to atmospheric pressure in accordance with Nl-OP-9.

STANDARD I STOP TIME NMPl NRC 2017 JPM 5-4 Page 8 of 9 February 2017

Exelon Generation" JPM Handout INITIAL Given:

CONDITIONS

The plant is shutdown, <212°F.

The Operations Manager has determined a complete de-inert to 19.5% Oxygen is necessary.

Nl-OP-9 is completed through Step G.2.7.b.

INITIATING (Operators Name), vent the Drywell in accordance with Nl-OP-9, CUE starting at step G.2.7.c.

NMPl NRC 2017 JPM 5-4 Page 9 of 9 February 2017

~-~-*/;./' Exelon Generation.

Training Id: 2017 NRC NMP1 Simulator JPM S-5 Revision: 0.0

Title:

Respond to a Loss of Service Water (PRA) (Alternate Path)

Approvals:

Si nature rinted Name Developed By ~~Isham 2/23/16 Validated By Phil Carroll 8/23/16 Facility Reviewer ----H!f/,__;;ffb""°-:~"""",'.4-*

p

_ ,_ (: ~, " '- =~- '- ~"- "- -

._ _--_.-*_ _ Pa_t_O_'_Br_ie_n / 7/s/16 Approximate Duration: - - - 10 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: Date:

NMPl NRC 2017 JPM 5-5 Page 1of9 February 2017

~, Exelon Generation References

1. Nl-SOP-18.1, Loss of Service Water

2. NUREG 1123 K/A 295018, AAl.01, (3.3/3.4)

NMPl NRC 2017 JPM 5-5 Page 2 of 9 February 2017

~* Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to safely operate control room systems during a loss of Service Water.

b. This JPM is considered alternate path because after the standby service water pump is started, it trips, requiring override steps in the SOP to be executed.

c. Critical steps are annotated in the Evaluator standard column with a balded PASS/FAIL.

2. Task Information:

a. Nl-SOP-18.1-01000, Respond to Service Water Failure (PRA)

b. K/A 295018, AAl.01, (3.3/3.4)

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM S-5 Page 3 of 9 February 2017

5. Simulator Setup (if required)

a. Initialize Simulator to IC-163

b. Verify Service Water pump 11 is red flagged and Service Water pump 12 is green flagged

c. Verify malfunction CW02B is on trigger 1 with a 10 second time delay

d. Verify trigger 1 command is set to zdcwpstr(4)==1 (Service Water pump 12 control switch in start)

e. Verify malfunction CW02A is active

6. JPM Setup (if required)

a. No steps need to be marked up.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM 5-5 Page 4 of 9 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

The plant is operating at approximately 100% power.

Service Water pump 11 has tripped on overcurrent.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), enter and execute Nl-SOP-18.1 for Service CUE Water Failure.

START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the p procedure STD: Nl-SOP-18.1 obtained.

3. Start standby Service Water pump by placing *PASS I FAIL control switch on Panel H to START STD: Rotates Service Water pump 12 control switch CW Note: Service Water pump 12 will trip after to start, observes red light a 10 second time delay, requiring an p on, green light off, proper alternate path to execute the override for pump amps loss of both Service Water pumps NMPl NRC 2017 JPM S-5 Page 5 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

4. Identifies trip of Service Water pump 12 SAT/ UNSAT STD: Observes Service p Water pump 12 green light on, red light off, pump amps drop to zero, annunciator Hl-2-2 alarms

5. If neither Service Water pump can be started SAT/ UNSAT OR Service Water Header pressure can NOT p

be restored to greater than 60 psig, then STD: Enters override of Nl-performs the following steps: SOP-18.1

6. Start Emergency Service Water pumps *PASS/ FAIL STD: Rotates ESW pump 11 control switch CW to start, observes red light on, green light off, proper pump amps p

PASS/ FAIL STD: Rotates ESW pump 12 control switch CW to start, observes red light on, green light off, proper pump amps

7. SCRAM the Reactor AND concurrently *PASS I FAIL execute Nl-SOP-1 p STD: Rotates the Reactor Mode Switch CW to Cue: Another operator will perform SOP-1 Shutdown actions. Continue in SOP-18.1.

8. Initiate Emergency Condensers *PASS I FAIL p STD: Rotates 39-05 control Cue: Another operator will maintain Reactor switch CW to open and/or pressure per EOP-2. rotates 39-06 control switch CW to open NMPl NRC 2017 JPM S-5 Page 6 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

9. Close MSIVs STD: Rotates 01-01 control switch CCW to close 9b *PASS/ FAIL p

STD: Rotates 01-02 control switch CCW to close 9c *PASS/ FAIL p

STD: Rotates o1-03 control switch CCW to close 9d *PASS/ FAIL p

STD: Rotates 01-04 control switch CCW to close

10. Trip all Rx Recirculation Pumps Cue: Another operator will monitor RBCLC and TBCLC temperatures.

10a *PASS/ FAIL p

STD: Rotates RRP 11 control switch CCW to stop 10b *PASS/ FAIL p

STD: Rotates RRP 12 control switch CCW to stop 10c *PASS/ FAIL p

STD: Rotates RRP 13 control switch CCW to stop NMPl NRC 2017 JPM 5-5 Page 7 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA lOd *PASS/ FAIL p

STD: Rotates RRP 14 control switch CCW to stop lOe *PASS/ FAIL p

STD: Rotates RRP 15 control switch CCW to stop Evaluator Note: Cue: Your task is complete.

TASK Nl-SOP-18.1 actions are completed through the override step for a STANDARD sequential loss of Service Water pumps.

I STOP TIME NMPl NRC 2017 JPM 5-5 Page 8 of 9 February 2017

~, Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is operating at approximately 100% power.

Service Water pump 11 has tripped on overcurrent.

INITIATING (Operators Name), enter and execute Nl-SOP-18.1 for Service CUE Water Failure.

NMPl NRC 2017 JPM 5-5 Page 9 of 9 February 2017

~"~"?- Exelon Generation Training Id: 2017 NRC NMPl Simulator JPM S-6 Revision: -0.0

Title:

Secure a Reactor Recirculation Pump, Pump Trips (Alternate Path)

Approvals:

Signature I Printed Name Developed By

~~------

~/' ~ Paul Isham 2/17/16 Validated By Kevin Hines 8/23/16 Facility Reviewer 7 ,

Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

NMPl NRC 2017 JPM S-6 Page 1of9 February 2017

,.,,._ Exelon Generation References

1. Nl-OP-1, Nuclear Steam Supply System

2. NUREG 1123 K/A 202001 A4.01, (3.7/3.7)

NMPl NRC 2017 JPM 5-6 Page 2 of 9 February 2017

~, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate controls associated with the Reactor Recirculation System.

b. This JPM is considered alternate path because when the operator reduces flow on the pump to be secured, the pump will trip, requiring the operator to respond in accordance with the SOP.

c. Critical steps are annotated in the Evaluator standard column with a balded Pass/Fail.

2. Task Information:

a. Nl-202001-01002

b. K/A 202001 A4.01, (3.7/3.7)

3. Evaluation I Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM 5-6 Page 3 of 9 February 2017

~* Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in a power operating condition

b. Initialize simulator to IC 164

c. Verify the following malfunctions are preset:

RROlA, RR Pump 11 Drive Breaker Trip, TRG 1

TRG 1 event trigger action set to "HZARRFI(l)<0.44" (Causes drive breaker to trip when individual loop flow reaches 8x10 6 lbm/hr)

6. JPM Setup (if required)

a. Verify sufficient copies are available of Nl-OP-1 P&L's and section H.1 B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM S-6 Page 4 of 9 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

The reactor is operating at 90% power

Reactor Recirculation Pump 11 is being removed for maintenance

Reactor power will be allowed to lower for the evolution

Recirculation pump 11 will remain idle and unisolated

Another operator is monitoring computer points during this evolution Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), Remove Recirc Pump 11 from service in accordance CUE with Nl-OP-1, section H.1.0 START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT p STD: Proper Cue: Acknowledge repeat back providing communications used correction if necessary

2. Obtain a copy of the reference procedure and SAT I UNSAT review/ utilize the correct section of the p procedure STD: Nl-OP-1 obtained.

3. IF Recirc Pump 11 is in Local Lock, THEN SAT I UNSAT continue at Step 1.4 p STD: Determines Recirc (H.1.1)

Pump 11 is not in Local Lock.

4. Place RRECIRC PUMP 11 SPEED CONTROL in SAT I UNSAT BAL and null out Deviation Meter (top meter) p STD: Verifies RRECIRC (H.1.2) PUMP 11 SPEED CONTROL in BAL and nulls out Deviation Meter (top meter)

NMPl NRC 2017 JPM S-6 Page 5 of 9 February 2017

~,..,,,;r Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

5. Place RRECIRC PUMP 11 SPEED CONTROL *PASS/ FAIL AUTO/BAL/MAN switch to MAN p STD: Rotates RRECIRC (H.1.3) PUMP 11 SPEED CONTROL AUTO/BAL/MAN switch CW to MAN

6. Verify open REACTOR R PUMP 11 BYPASS SAT/ UNSAT VALVE p STD: Verifies open (H.1.4) REACTOR R PUMP 11 BYPASS VALVE by observing red light on, green light off Note: Step H.1.5 is N/A per initial conditions

7. IF present power level is NOT to be *PASS/ FAIL maintained, THEN reduce flow on Reactor Recirc Pump 11 to 6 to 8 x 106 lbm/hr p STD: Slowly reduces (H.1.6) Recirculation pump 11 flow to 6 to 8xl0 6 lbm/hr by rotating knob CCW

'1 0

i°,'~':'}'.:r~-- '.::~ :::,:~

Altetnate'~~:!' The alternate path starts when the operator is lowering pump flow. The recirc P~!l3f~,;3; pump will trip requiring entry into Nl-SOP-1.3, Recirc Pump Trip at Power.

8. Recognize Recirc Pump 11 trip and required SAT I UNSAT entry in to Nl-SOP-1.3, Recirc Pump Trip at p Power. STD: Enters Nl-SOP-1.3

9. Verify proximity to restricted zone using P/F SAT I UNSAT map for remaining loop operation p STD: Using the four loop power to flow map, confirms the restricted zone has not been entered.

10. Verify ALL operating Recirculation Pumps are SAT/ UNSAT within the following limits:

STD: Verifies recirc pumps Generator MW: 0.790 MW p 12-15 are operating within Generator Amps: 240 A required limits.

RRP Flow: 16.8 x 106 lbm/hr continuous Generator Frequency: 11.5 Hz to 56 Hz NMP1 NRC 2017 JPM S-6 Page 6 of 9 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PI SI NA

11. Notify SM that: SAT/ UNSAT APRMs are inoperable.

8 hr ENS report is required p STD: Makes required notifications to SM.

12. Close RECIRC PUMP 11 DISCHARGE VALVE *PASS/ FAIL Note: Power is expected to rise "' 3% STD: Closes REACTOR R PUMP 11 DISCHARGE p VALVE by rotating control switch CCW and holding until green light is on, red light is off, observes lowering loop flow.

13. Override Statement: *PASS/ FAIL IF RECIRC PUMP 11 DISCHARGE VALVE is STD: Rotates CW and holds closed, THEN Hold open for 2-3 seconds in OPEN position for 2 to 3 p seconds, REACTOR R PUMP RECIRC PUMP 11 DISCHARGE VALVE.

11 DISCHARGE VALVE, observes red light on, green light on.

14. Notify SM that APRMs are operable SAT/ UNSAT p STD: Notifies SM that APRMs are operable.

15. Green Flag RECIRC PUMP 11 SB switch SAT/ UNSAT STD: Green Flags RECIRC PUMP 11 SB switch by rotating CCW NMP1 NRC 2017 JPM S-6 Page 7 of 9 February 2017

~***w Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

16. Place RECIRC PUMP 11 SPEED CONTROL SAT I UNSAT AUTO/BAL/MAN switch to MAN STD: Verifies RECIRC PUMP 11 SPEED CONTROL AUTO/BAL/MAN switch in Note: This step was performed earlier in MAN the JPM Evaluator Note: Cue: Your task is complete.

TASK Recirc Pump 11 is secured with its associated discharge valve closed.

STANDARD I STOP TIME NMPl NRC 2017 JPM S-6 Page 8 of 9 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The reactor is operating at 90% power

Reactor Recirculation Pump 11 is being removed for maintenance

Reactor power will be allowed to lower for the evolution

Recirculation pump 11 will remain idle and unisolated

Another operator is monitoring computer points during this evolution INITIATING (Operators Name), Remove Recirc Pump 11 from service in accordance CUE with Nl-OP-1, section H.1.0 NMP1 NRC 2017 JPM S-6 Page 9 of 9 February 2017

~JjL-~* Exelon Generation Training Id: 2017 NRC NMP1 Simulator JPM S-7 Revision: -0.0 Core Spray Quarterly Surveillance, Suction Strainer Clogging

Title:

(Alternate Path)

Approvals:

Si n ture Printed Name Developed By ~,/~~aul Isham 2/17/16 Validated By Phil Carroll 8/23/16 Facility Reviewer ~- Pat O'Brien Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: ---------- Date:

NMP1 NRC 2017 JPM 5-7 Page 1 of 11 February 2017

~ Exelon Generation References

1. Nl-ST-QlC, CS 112 Pump and Valve Operability Test

2. NUREG 1123 K/A 209001 A4.01, (3.8/3.6)

NMPl NRC 2017 JPM S-7 Page 2 of 11 February 2017

_,.,. Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locate and manipulate control room controls for a Core Spray Surveillance.

b. This JPM is considered alternate path because once the CSTP 112 is started, suction strainer clogging occurs. The operator will need to secure the pump per ARP direction.

c. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. Nl-209001-01004-01, Align Core Spray System Valves

b. K/A 209001 A4.01, (3.8/3.6)

3. Evaluation/ Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path Yes LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMPl NRC 2017 JPM 5-7 Page 3 of 11 February 2017

_,,.,,, Exelon Generation"

5. Simulator Setup (if required)

a. Initialize Simulator to IC-165.

b. Verify Reactor coolant temperature is >212°F.

c. Verify the following remotes are inserted to power Core Spray valves 40-12 and 40-06:

CSO 1A ( 40-06) - close

CS02A (40-12) - close

d. Verify a copy of N1-ST-Q1C is marked up through step 6.4.4, with 6.4.4 N/A.

e. Verify 40-12 is open and 40-06 is closed.

f. Verify malfunction CS05B is on trigger 1 with a 3 minute ramp from 10% to 98%.

g. Verify trigger 1 event action is "zdcspstr(5)==1" (core spray topping pump C/S to start).

6. JPM Setup (if required)

a. Verify adequate copies of N1-ST-Q1C marked up through step 6.4.4.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM 5-7 Page 4 of 11 February 2017

~***R// Exelon Generation INITIAL Given:

CONDITIONS

The plant is in a power operating condition.

N1-ST-Q1C, Core Spray 112 Pump and Valve Operability Test, is in progress for post-maintenance testing.

The procedure is complete up to step 6.4.5.

Operators are on-station in the field for test support.

Exercising of 81-28 in step 6.4.16 is not required.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), perform Core Spray pump 112 testing per N1-CUE ST-Q1C starting at step 6.4.5.

I STARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT I UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review/utilize the correct section of the procedure p STD: N1-ST-Q1C obtained, section 6.4 referenced

3. Verify closed 40-12, CORE SPRAY *PASS I FAIL DISCHARGE IV 11 (OUTSIDE) p STD: Closes 40-12 by (Step 6.4.5) rotating control switch CCW to CLOSE

4. IF this test is being performed with Reactor SAT/ UNSAT coolant temp less than 212°F, THEN unlock AND close the following valves: p STD: Determines Reactor coolant temperature is

>212°F NMP1 NRC 2017 JPM S-7 Page 5 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

5. Verify closed the following valves: SAT/ UNSAT STD: Directs field

50-132, BV - CS LOOP 11 KEEP FILL operator to close valves COND SUPPLY p 50-132 and 40-18

40-18, BV - COND TO CS LOOP 11 (Step 6.4. 7)

KEEP FILL SYSTEM Role Play: Acknowledge direction. Report 50-132 and 40-18 are closed.

6. Unlock AND verify closed 38-178, BV-SDC SAT/ UNSAT WTR SEAL FROM CS LOOP 11 (SDC Rm) p STD: Directs field (Step 6.4.9) operator to unlock and Role Play: Acknowledge direction. Report close valve 38-178 38-178 is unlocked and closed.

7. Verify open 40-06, CORE SPRAY LOOP 11 *PASS I FAIL TEST VALVE TO TORUS p STD: Opens 40-06 by (6.4.10) rotating control switch CW to OPEN

8. Verify unlocked 81-86, MANUAL PCV - CS SAT/ UNSAT LOOP 11 TEST TO TORUS p STD: Directs field (6.4.11) operator to unlock 81-86 Role Play: Acknowledge direction. Report 81-86 is unlocked.

9. Establish communications between 81-86 SAT/ UNSAT AND Control Room p STD: Directs field operator at 81-86 to Role Play: Acknowledge direction. Report (6.4.12) establish communications established.

communications with Control Room

10. Verify full open 81-86 SAT I UNSAT p

STD: Directs field Role Play: Acknowledge direction. Report (6.4.13) operator to verify 81-86 81-86 is full open.

full open NMPl NRC 2017 JPM S-7 Page 6 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

11. Notify SM to log entry into appropriate LCO SAT I UNSAT for plant conditions p STD: Notifies SM to log (6.4.14) entry into appropriate Role Play: Acknowledge direction. Report LCO the appropriate LCO has been entered.

12. Start Core Spray Pump 112 *PASS/ FAIL STD: Starts Core Spray p

Role Play: When asked, inform candidate Pump 112 by rotating that you will perform the concurrent (6.4.15.1) control switch CW to verification. When required, agree with the START candidate's action.

13. Start Core Spray Topping Pump 112 *PASS/ FAIL p STD: Starts Core Spray Role Play: When asked, inform candidate Topping Pump 112 by that you will perform the concurrent (6.4.15.2) rotating control switch verification. When required, agree with the CW to START candidate's action.

Alternate*

1>ath:* . .

When Core Spray Topping Pump 112 control switch is taken to START, trigger 1 inserts the suction strainer clogging malfunction that leads to the alternate path. The next few steps may be N/A depending on how quickly the Candidate observes the malfunction. The malfunction gets worse over time. Eventually Core Spray flow will drop to 0. K2-2-6, CORE SPRAY PUMP 111-112 SUCT P.

.~.~~* LOW, may alarm. The ARP includes a step, "IF cavitation exists AND pump is in test mode, THEN secure pump". K2-4-6 will also direct securing the pump.

14. IF required to support completion of step SAT/ UNSAT /NA 6.4.15, THEN STOP AND RESTART Core p Spray Loop 11 pumps, OTHERWISE MARK STD: Determines step is (6.4.15.3) this step N/A. N/A based on initial conditions NMP1 NRC 2017 JPM S-7 Page 7 of 11 February 2017

~" Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

15. WITHIN approximately 3 minutes of pump SAT I UNSAT I NA start, THROTTLE 81-86, to achieve Core Spray flow of 140 to 145 X 10 4 lbm/hr FI STD: Directs operator to 81.1-20 (Control Room). p throttle 81-86 as (6.4.15.4) necessary Role Play: Acknowledge direction. Report 81-86 has been throttled (if necessary).

16. Verify the following: SAT/ UNSAT / NA STD: Determines step is

Check valve 81-28 is exercised to full p N/A based on initial open position as determined by Non-(6.4.16) conditions Intrusive Test equipment.

Check valve 81-28 is exercised to the closed position as determined by Non-intrusive test equipment.

17. Valve in the temporary f1P Cell SAT I UNSAT I NA p

STD: Directs IMD to Role Play: Acknowledge direction. Report (6.4.17.1) valve in temporary f1P temporary f1P Cell is valved in. Cell

18. VENT CSP 112 temporary pressure gauge to SAT I UNSAT I NA floor drain, allowing any discolored water to clear STD: Directs field p operator to vent CSP 112 (6.4.17.2) temporary pressure Role Play: Acknowledge direction. Report gauge Core Spray pump 112 temporary pressure gauge has been vented.

19. VENT CSTP 112 discharge pressure gauge at SAT/ UNSAT I NA PI-81.1-04R to floor drain, allowing any discolored water to clear STD: Directs field p operator to vent CSTP (6.4.17.3) 112 discharge pressure Role Play: Acknowledge direction. Report gauge Core Spray Topping pump 112 discharge pressure gauge has been vented.

NMPl NRC 2017 JPM S-7 Page 8 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

20. Throttle 81-86 as necessary to establish 135 SAT/ UNSAT / NA (132 to 137) inches of water as indicated on temporary 8P Cell STD: Directs field p operator to throttle 81-(6.4.18) 86 Role Play: Acknowledge direction. 81-86 has been throttled and the temporary 8P Cell indicates 135 inches of water.

21. WHEN pump combination has been run in a SAT/ UNSAT / NA stable condition for at least 2 minutes as indicated on the calibrated stopwatch, THEN STD: Begins recording record the following: various system parameters Cue: Two minutes have elapsed. p (6.4.19)

Role Play: If asks for direction on how to *PASS I FAIL respond to malfunction, direct Candidate to make a recommendation and then carry out STD: Recognizes that recommendation. abnormal system parameters

22. Secures Core Spray Pump 112 and Core SAT I UNSAT Spray Topping Pump 112 STD: Stops Core Spray Topping Pump 112 by Note: Procedural direction to secure Core rotating control switch Spray Pump 112 is found in ARP K2-4-6.

CCW to STOP Core Spray Topping Pump 112 should be secured first. However, when Core Spray p Pump 112 is secured, Core Spray Topping Pump 112 will automatically trip.

PASS I FAIL Candidate may trip pump first then follow up with the ARP. STD: Stops Core Spray Pump 112 by rotating control switch CCW to STOP Evaluator Note: Cue: Your task is complete.

NMPl NRC 2017 JPM S-7 Page 9 of 11 February 2017

~ Exelon Generation TASK Core Spray pump 112 secured from surveillance testing due to STANDARD indications of suction strainer clogging.

I STOP TIME NMPl NRC 2017 JPM 5-7 Page 10 of 11 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is in a power operating condition.

Nl-ST-QlC, Core Spray 112 Pump and Valve Operability Test, is in progress for post-maintenance testing.

The procedure is complete up to step 6.4.5.

Operators are on-station in the field for test support.

Exercising of 81-28 in step 6.4.16 is not required.

INITIATING (Operators Name), perform Core Spray pump 112 testing per Nl-CUE ST-QlC starting at step 6.4.5.

NM Pl NRC 2017 JPM 5- 7 Page 11 of 11 February 2017

~- Exelon Generation" Training Id: 2017 NRC NMPl Simulator JPM S-8 Revision: 0.0

Title:

EDG 103 Control Room Start Following Station Blackout Approvals:

Signature I Printed Name Developed By &~~am 2/17/16 Validated By Terry Bockman 10/7/16 Facility Reviewer Pat O'Brien Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC 2017 JPM 5-8 Page 1of10 February 2017

~" Exelon Generation References

1. Nl-OP-45, Emergency Diesel Generators

2. NUREG 1123 K/A 295003 AAl.02, (4.2/4.3)

NMPl NRC 2017 JPM 5-8 Page 2of10 February 2017

Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate the Emergency Diesel Generator and associated electric plant controls from the control room.

b. This JPM is not considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a bolded Pass/Fail.

2. Task Information:

a. Nl-264000-01004

b. K/A 295003 AAl.02, (4.2/4.3)

3. Evaluation /Task Criteria Evaluation Method Perform Evaluation Location Simulator Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Simulator NMP1 NRC 2017 JPM 5-8 Page 3 of 10 February 2017

~~ Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in a SBO condition

b. Initialize simulator to IC 140

Mode switch in Shutdown

Malfunctions EDOlA, ED02A, EGOl, DGOlA, DGOlB all inserted

AFTER at least 3:00 minutes, delete malfunction DGOlB, DG 103 Fail To Start (Man and Auto), to allow a restart from the control room.

Ensure only one EC is in service.

6. JPM Setup (if required)

a. Provide sufficient copies of Nl-OP-45, section H.19.

B. Read Before Every lPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated lPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC 2017 JPM 5-8 Page 4 of 10 February 2017

Exelon Generation INITIAL

A Station Blackout has occurred CONDITIONS

N1-SOP-33A.2 Station Blackout is being implemented

EDG 102 troubleshooting is in progress

EDG 103 trouble shooting is complete and repairs have been made

EDG 103 is now available and ready to return to service Instructor / Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), Perform a control room start of EDG 103 and CUE energize PB 103 from the EDG 103, per Nl-OP-45 section H.19.0.

START TIME PERFORMANCE ACT. CODE EVALUATOR PI 5 I NA

1. Provide repeat back of initiating cue p SAT I UNSAT STD: 3 way communications are conducted

2. Obtain a copy of the reference procedure and p SAT/ UNSAT review/ utilize the correct section of the STD: Current version of procedure procedure obtained.

Precautions & limitations are reviewed.

3. Verify the following for EDG 103:

3.1 Power Board 103 is de-energized. p SAT I UNSAT (H.19.1.1) STD: Observe PB 103 AC VOLTS indicate 0 on A Panel.

NMPl NRC 2017 JPM S-8 Page 5 of 10 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA 3.2 Normal Supply BKR R1013, PB 103 in PULL TO LOCK.

Alarm AS-1-2, Trans 1015 Aux Fdr 1013 R1013 Trip clears 3.3 Supply BKR R1053, PB 17 (B Section) p SAT/UNSAT CLOSED. (H.19.1.3)

STD: Observe Breaker R1053 red light on and green light off.

3.4 BREAKER R1052, PB 17 Bus Tie (A to B p SAT/UNSAT Section) OPEN. (H.19.1.4)

STD: Observe Breaker R1052 green light on and red light off.

3.5 BV-96-103 EDG103, Starting Air Block Valve p SAT/UNSAT OPEN. (H.19.1.5) STD: Acknowledge report using proper 3 way communications.

Cue: Report air block valve is open.

3.6 R1032, Diesel Generator 103 Output p SAT/UNSAT Breaker, OPEN AND Green Flagged. (H.19.1.6) STD: Observe control switch in green flag position and green light on and red light off.

3. 7 Exceptions to Standby Lineup have been p SAT/UNSAT evaluated by SM for impact on DG operation. (H.19.1.7) STD: 3 way communications are conducted Cue: Report no exceptions to lineup that impact DG operation.

3.8 Lubricating AND coolant levels normal. p SAT/UNSAT (H.19.1.8) STD: 3 way communications are conducted Cue: Report both levels are normal.

NMP1 NRC 2017 JPM S-8 Page 6 of 10 February 2017

~* Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

4. Verify Over-Speed Trip RESET (handle p SAT/UNSAT horizontal). (H.19.2) STD:3 way communications are conducted Cue: Report over-speed trip is reset.

5. Depress 48X RESET button inside Control p SAT/UNSAT Cabinet. (H.19.3) STD:3 way communications are conducted Cue: Report 48X reset button has been depressed.

6. Verify Speed Droop Set to O (Zero). p SAT/UNSAT (H.19.4) STD:3 way communications are conducted Cue: Report speed droop is set to 0.

7. Verify CLOSED DG103 CONT POWER BKR p SAT/UNSAT (DG 103 Control Cabinet). (H.19.5) STD:3 way communications are conducted Cue: Report control power breaker is closed.

8. Verify LOCKOUT 86DG3 Relay Reset (A5- p SAT/UNSAT Panel). (H.19.6) STD: Observe 86DG3 is reset on A Panel.

9. Verify relays reset by taking DIESEL GEN 103 *p Control Switch to EM STOP. . (H.19.7)>.

Alarm AS-3-5 DSL GEN 103 START-RUN OFF NORMAL clears NOTE: DG 103 will be started with an Auto Start Signal to assure the Governor Circuit has DC power from the Battery.

NMP1 NRC 2017 JPM S-8 Page 7 of 10 February 2017

Exelon Generation" PERFORMANCE ACT. CODE EVALUATOR PIS I NA

10. Place in NEUTRAL (green flagged) R1013, PB fr~f~~~~7,;f,A~L

,' /J;>c~'i> '

103 Normal Supply Breaker (DG103 will Auto > "' '. ' .,

Start). ~Mtr61~s~i~c~

L ~r~en.:)ight

~.

lsott> * *

~l~u.;x:~,M~d:~~~

GEN 103 Voltmeter and frequency rise as engine starts 1

}~

el1~ine

'; . ~\'

wilr hot start.

11. Confirm DG output at approximately 60 p SAT/UNSAT Hz/4160V. (H.19.9) STD: Observe GEN 103 Voltmeter reads about 4150 volts and frequency is about 60 Hz.

12. Place Sync Key in R1032 SYN AND place to p ON. (H.19.10) sfl>: ~~~~ k~~ inserted f~r Rih32 and positi~necl to ON.

c:>t>s~r!J~*1i.JcOMrnG AC vc:>C+s r!~:'. 1 .. :. < ~1* ..*........*....

critleal step'Justlficatioo:**1f this.step' l~ not p~rr()rmeci, R1D32 ~Ii'inotdose, preventing bus fr~~*~9;,~~~l~i.ng: , ' *

13. Close R1032 Diesel Generator 103 Output Breaker. !.,;,;J*;* : *<* '",'

STD: Rl~~i caotrolswitch p6Mtio~ t6 tlge ~~ea~er: *Reel ughto~ '8l1cl 9r'ee~ u9'1t of(.

crii:1alfsii~ 3'J$tifi~t1c>~:1f 1 f6is *~1:~~ ts .llot i>giforTXed>

R.fo32'~m c::>:: *..... ,..,* prevent1n

,y.,.rt'tCi6se' 71

'f** ,,. *** . *:* ....9 bus f~m, ~nergiz1Jl9:>: *

'I ' ,~ '. ' ,,,/' ' I "i" ,,;, ,, ;/ '

14. Confirm normal voltage on PB 103. p SAT/UNSAT (H.19.12) STD: Observe PB 103 AC VOLTS indicate about 4160 AC VOLTS.

NMP1 NRC 2017 JPM S-8 Page 8 of 10 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

15. Enter N 1-SOP-33A.1. p SAT/UNSAT (H.19.13) STD: Acknowledge report using proper 3 way communications.

Cue: As US, inform operator that another operator will implement N1-SOP-33A.1 actions.

Evaluator Note: Cue: Your task is complete.

TASK EOG 103 started and PB 103 energized STANDARD I STOP TIME NMP1 NRC 2017 JPM 5-8 Page 9 of 10 February 2017

Exelon Generation JPM Handout INITIAL

A Station Blackout has occurred CONDITIONS

N1-SOP-33A.2 Station Blackout is being implemented

EDG 102 troubleshooting is in progress

EDG 103 trouble shooting is complete and repairs have been made

EDG 103 is now available and ready to return to service INITIATING (Operators Name), Perform a control room start of EDG 103 and CUE energize PB 103 from the EDG 103, per Nl-OP-45 section H.19.0.

NMP1 NRC 2017 JPM S-8 Page 10 of 10 February 2017

iz:P'!"

~-- Exelon Generation,,

Training Id: 2017 NRC NMP1 Plant JPM P-1 Revision: 0.0

Title:

Remove ERV Fuses in the Plant Approvals:

Si rinted Name Developed By Paul Isham 2/22/16 Validated By Phil Carroll 8/25/16 Facility Reviewer Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC 2017 JPM P-1 Page 1of7 February 2017

_,.... Exelon Generation References

1. Nl-SOP-1.4, Stuck Open ERV

2. NUREG 1123 K/A 239002 A2.03 4.1/4.2 NMPl NRC 2017 JPM P-1 Page 2 of 7 February 2017

_.,,, Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locate and operate equipment associated with the Electromagnetic Relief Valves. The applicants will simulate pulling fuses in the Reactor Building for ERV 111.

b. This JPM is NOT considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a balded

Pass/Fail.

2. Task Information:

a. Nl-218000-01012

b. K/A 239002, A2.03 4.1/4.2

3. Evaluation/ Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Reactor Building

5. JPM Setup (if required)

a. Ensure adequate copies of Nl-SOP-1.4 are available.

NMP1 NRC 2017 JPM P-1 Page 3 of 7 February 2017

~* Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMPl NRC 2017 JPM P-1 Page 4 of 7 February 2017

Exelon Generation,,

INITIAL Given:

CONDITIONS

The plant is at 100% power.

Annunciator H3-4-5, "Press Safety/Relief Valves Flow" is in alarm.

ERV 111 has been verified open via the Acoustic Monitor Panel.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), pull the In-Plant Control Power Fuses for ERV-CUE 111 in accordance with Nl-SOP-1.4, Stuck Open ERV.

Note: The Electrical Safety PPE requirements for this task have been assessed and are as follows:

Leather gloves

100% cotton long sleeve shirt and pants OR 100% cotton short sleeve shirt and pants under fire retardant lab coat

Safety glasses or goggles ISTARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper correction if necessary. communications used

2. Obtain a copy of the reference procedure and p SAT I UNSAT review / utilize the correct section of the procedure. STD: Nl-SOP-1.4 obtained Cue: Safety equipment is not required to be obtained.

NMP1 NRC 2017 JPM P-1 Page 5 of 7 February 2017

~ Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Locate Junction Box 11 in the Reactor p SAT/ UNSAT Building STD: Locate JB 11 on RB Note: Safety equipment is not required to be 237' West Side obtained. However the required equipment should be discussed during the performance of the JPM.

4. Pull the positive side fuse for ERV 111, Fl s *PASS/ FAIL POS STD: Fuse Fl is pulled using fuse pullers, located 237 West side cabinet ERV.

5. Pull the negative side fuse for ERV 111, F2 s *PASS/ FAIL NEG STD: Fuse F2 is pulled using fuse pullers, located 237 West side cabinet ERV.

6. Notify Control Room that ERV 111 fuses have p SAT I UNSAT been pulled from cabinet JB 11 on RB 237' STD: Proper Role play: As CRO, acknowledge fuses communications used pulled. Notify Operator "ERV 111 indicates closed.

Evaluator Note: Cue: Your task is complete.

TASK 125 VDC Fuses pulled for ERV 111 and ERV 111 is closed.

STANDARD ISTOPTIME NMPl NRC 2017 JPM P-1 Page 6 of 7 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is at 100% power.

Annunciator H3-4-5, "Press Safety/Relief Valves Flow" is in alarm.

ERV 111 has been verified open via the Acoustic Monitor Panel.

INITIATING (Operators Name), pull the In-Plant Control Power Fuses for ERV-CUE 111 in accordance with Nl-SOP-1.4, Stuck Open ERV.

Note: The Electrical Safety PPE requirements for this task have been assessed and are as follows:

Leather gloves

100% cotton long sleeve shirt and pants OR 100% cotton short sleeve shirt and pants under fire retardant lab coat

Safety glasses or goggles NMPl NRC 2017 JPM P-1 Page 7 of 7 February 2017

Training Id: 2017 NRC NMP1 Plant JPM P-2 Revision: -0.0

Title:

Inject Boron Into the Reactor Using the Hydro Pump (PRA)

Approvals:

Developed By 2/22/16 Validated By Phil Carroll 8/25/16 Facility Reviewer _ _,_.'F-,/~>-~~"---~----/--=-,..~~~=----

/ } _ _,_. _ _ _P_a_t_O_'B_r_ie_n / tlr /!6

~

Approximate Duration: - - - 15 -

minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass / Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC 2017 JPM P-2 Page 1of11 February 2017

~,, Exelon Generation References

1. Nl-EOP-3, Failure to Scram

2. NUREG 1123 K/A 295037, EAl.10, (3.7 / 3.9)

3. Nl-EOP-3.2, Attachment 1 NMPl NRC 2017 JPM P-2 Page 2 of 11 February 2017

~ Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locally inject Boron via alternate methods during an emergency.

b. This JPM is NOT considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a balded

Pass/Fail.

2. Task Information:

a. Nl-EOP-3.2-01001, Implement Alternate Boron Injection

b. K/A 295037, EAl.10, (3. 7 I 3.9)

3. Evaluation /Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path No LOO >1.0 Yes

4. Recommended Start Location

a. Unit 1 Reactor Building Elev. 281

5. JPM Setup (if required)

a. Prepare a copy of Nl-EOP-3.2, up through Attachment 1 to enable P&Ls to be reviewed.

NMPl NRC 2017 JPM P-2 Page 3 of 11 February 2017

Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC 2017 JPM P-2 Page 4 of 11 February 2017

_,,,,_. Exelon Generation" INITIAL Given:

CONDITIONS

Nl-EOP-3 has been entered due to a failure to scram.

An RO has tried to initiate Liquid Poison from the Control Room but the pumps will not start.

RWCU has isolated.

Radiation Protection is providing continuous monitoring of your activities.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name}, lineup and inject boron using the Hydro Pump CUE per Nl-EOP-3.2, Alternate Boron Injection, Attachment 1.

I STARTTIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary. communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review/ utilize the correct section of the p procedure STD: Nl-EOP-3.2 obtained, Attachment 1 referenced

3. Verify RWCU system is isolated SAT/ UNSAT p

STD: Determines RWCU (3.1) system is isolated per initial conditions NMPl NRC 2017 JPM P-2 Page 5 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

4. Notify Rad Protection to provide continuous SAT I UNSAT monitoring p STD: Determines Rad (3.2) Protection is providing continuous monitoring per initial conditions Cue: Once EOP Box 2 is located, prompt candidate to simulate opening the box and describe the equipment to be used.

5. Connect air supply hose from 95-157, BV- *PASS/ FAIL HSA to Alternate Boron Injection System (in overhead above Hydro Pump area), to the STD: Indicates location of Hydro pump 95-157 Note: 95-157 is in the overhead above a small platform. It is not desired for the candidate to access the valve, since this s *PASS/ FAIL would require RP coverage for work above 6 (3.3.1) feet. Successful completion of this JPM step STD: Attaches one end of will be for the candidate to indicate the air supply hose to Hydro general location of the valve.

pump air inlet line Cue: Once candidate indicates location of 95-157, report that the air supply hose is connected to 95-157

6. Connect high-pressure hose to discharge of *PASS I FAIL Hydro pump s STD: Connects one end of (3.3.2) hose to discharge of Hydro pump NMPl NRC 2017 JPM P-2 Page 6 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

7. Connect 2" hose from hose connection *PASS/ FAIL downstream of 89-20, Drain - Liquid Poison Tank, to suction of Hydro pump STD: Connects one end of hose to hose connection downstream of 89-20 s

(3.3.3)

PASS/ FAIL STD: Connects other end of hose to suction of Hydro pump

8. Unlock and verify closed 89-21, Drain - LP *PASS/ FAIL Tank to 55 Gal Drum STD: 89-21 is unlocked Note: 89-21 is normally locked open s

(3.4.1)

PASS/ FAIL STD: 89-21 is closed by rotating handwheel fully clockwise

9. Unlock and close 42-13, BV-LP Squibb Viv 11 SAT/ UNSAT Outlet s STD: 42-13 (LP-11) is (3.4.2) closed by unlocking and turning handwheel fully clockwise (RB Elev. 298')

10. Unlock and close 42-14, BV-LP Squibb Viv 12 SAT I UNSAT Outlet s STD: 42-14 (LP-10) is (3.4.3) closed by unlocking and turning handwheel fully clockwise (RB Elev. 298')

NMP1 NRC 2017 JPM P-2 Page 7 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

11. Unlock and open 41-04, Drain - Liquid *PASS I FAIL Poison Tank s STD: 41-04 (LP-701) is (3.5.1) opened by unlocking and turning handwheel fully counter-clockwise

12. Unlock and open 89-20, Drain - Liquid *PASS/ FAIL Poison Tank s STD: 89-20 is opened by (3.5.2) unlocking and turning handwheel fully counter-clockwise

13. Verify Hydro Pump Air inlet Valve closed SAT/ UNSAT s STD: Hydro pump air inlet (3.6.1) valve is closed by verifying handwheel is rotated fully clockwise (at Hydro pump)

14. Adjust regulator fully clockwise *PASS I FAIL s

(3.6.2) STD: Rotates regulator fully clockwise

15. Depress outer collar of adjusting knob SAT I UNSAT downward to lock pressure setting s (3.6.3) STD: Depresses outer collar of adjusting knob downward

16. Connect high pressure hose (from Hydro *PASS I FAIL pump discharge) to hose connection upstream of 42-10, Drain - LP Sys Hdr STD: Connects other end of s

Before Ck Vlvs - 2nd hose previously attached to (3.7)

(Step 3.7) Hydro pump discharge to hose connection upstream of 42-10 NMPl NRC 2017 JPM P-2 Page 8 of 11 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

17. Unlock and open valve 42-10, Drain - LP SYS *PASS I FAIL HDR BEFORE CK VLVS - 2ND.

STD: 42-10 (LP-708) is s

opened by unlocking and (3.8.1) turning handwheel fully counter-clockwise (RB Elev.

281)

18. Unlock and open valve 42-09, Drain - LP SYS *PASS/ FAIL HDR BEFORE CK VLVS - lST.

STD: 42-09 (LP- 707) is s opened by unlocking and Note: Common locking mechanism with 42- (3.8.2)

10. turning handwheel fully counter-clockwise (RB Elev.

281)

19. Open 95-157, BV-HSA to Alt Boron Injection SAT/ UNSAT System STD: 95-157 is opened Note: 95-157 is in the overhead above a small platform. It is not desired for the candidate to access the valve, since this s

(3.9) would require RP coverage for work above 6 feet.

Cue: Report that 95-157 has been opened by another operator

20. Start pump by opening Air Inlet BV *PASS/ FAIL s STD: Air inlet valve is (3.10) opened by turning handwheel counter-clockwise

21. Notifies Control Room liquid poison being SAT I UNSAT injected with the Hydro Pump.

s Evaluators Cue: Your task is complete.

Note:

NMPl NRC 2017 JPM P-2 Page 9 of 11 February 2017

~, Exelon Generation TASK Alternate Boron injection with the hydro pump has been established STANDARD in accordance with Nl-EOP-3.2.

I STOPTIME NMPl NRC 2017 JPM P-2 Page 10 of 11 February 2017

Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

Nl-EOP-3 has been entered due to a failure to scram.

An RO has tried to initiate Liquid Poison from the Control Room but the pumps will not start.

RWCU has isolated.

Radiation Protection is providing continuous monitoring of your activities.

INITIATING (Operators Name), lineup and inject boron using the Hydro Pump CUE per Nl-EOP-3.2, Alternate Boron Injection, Attachment 1.

NMPl NRC 2017 JPM P-2 Page 11 of 11 February 2017

z1' 1

~

~-

ExelonGeneration; Training Id: 2017 NRC NMP1 Plant JPM P-3 Revision: 0.0

Title:

Transfer Reactor Trip Bus 141 to I&C Bus 130A Approvals:

re Printed Name

/~-------

Developed By /.4-Y~~ Paul Isham 2/22/16 Validated By Phil Carroll 8/25/16 Facility Reviewer /~-~% Pat O'Brien Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: - - - - - - - - - - Date:

NMPl NRC 2017 JPM P-3 Page 1of8 February 2017

-**** Exelon Generation References

1. Nl-SOP-30.2, Loss of Powerboard 12 Attachment 3

2. NUREG 1123 K/A 295003, AAl.01, (3.7 / 3.8)

NMPl NRC 2017 JPM P-3 Page 2 of 8 February 2017

~* Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locally operate AC Distribution components during loss of power situations.

b. This JPM is NOT considered alternate path.

c. Critical steps are annotated in the Evaluator standard column with a bolded

PASS/FAIL.

2. Task Information:

a. Nl-SOP-30.2-04001, Perform the In-Plant Actions for a Loss of Power Board 12

b. K/A 295003, AAl.01, (3. 7 I 3.8)

3. Evaluation I Task Criteria Evaluation Method Simulate Evaluation Location Plant Time Critical Task No Alternate Path No LOD >1.0 Yes

4. Recommended Start Location

a. Unit 1 Turbine Building

5. JPM Setup (if required)

a. Prepare a copy of Nl-SOP-30.2, Attachment'3

b. Fire retardant lab coat may be required if candidate is wearing short sleeves.

NMPl NRC 2017 JPM P-3 Page 3 of 8 February 2017

Exelon Generation B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently.

The CRS has determined that a verifier is not available and that additional verification will not be provided.

NMP1 NRC 2017 JPM P-3 Page 4 of 8 February 2017

Exelon Generation INITIAL Given:

CONDITIONS

The plant is operating at approximately 50% power

A loss of Powerboard 12 has led to the loss of Reactor Trip Bus 141 Evaluator: Ask trainee if he/she has any questions after presenting initial conditions INITIATING (Operators Name), restore power to Reactor Trip Bus 141 from I&C CUE Bus 130A, in accordance with Nl-SOP-30.2, Attachment 3.

Note: The Electrical Safety PPE requirements for this task have been assessed and are as follows:

Leather gloves

100% cotton long sleeve shirt and pants OR 100% cotton short sleeve shirt and pants under fire retardant lab coat

Safety glasses or goggles START TIME PERFORMANCE ACT. CODE EVALUATOR PIS I NA

1. Provide repeat back of initiating cue SAT/ UNSAT p

Cue: Acknowledge repeat back providing STD: Proper correction if necessary. communications used

2. Obtain a copy of the reference procedure and SAT/ UNSAT review/ utilize the correct section of the p procedure STD: Nl-SOP-30.2, Attachment 3 obtained NMP1 NRC 2017 JPM P-3 Page 5 of 8 February 2017

Exelon Generation PERFORMANCE ACT. CODE EVALUATOR PIS I NA

3. Confirm I&C Bus 130A power supply is SAT/ UNSAT available (PB 13B energized)

STD: Determines Powerboard 13B is energized by observing voltage present and/or Cue: If candidate looks at any Powerboard POWERBOARD 13 A TO B 13 voltage indication, report that voltage is SECTION TIE BREAKER 600V p closed (TB 277' South)

(1.1)

Cue: If candidate looks at Powerboard 13 breakers, report breaker position as follows:

PB 13A Feeder - Closed

PB 13 A-B Tie - Closed

PB 13 B-C Tie - Closed

PB 13C Feeder - Open

4. Open REACTOR TRIP BUS #141 NORMAL *PASS/ FAIL SUPPLY FROM M.G. SET #141 (TB 277' East) p STD: Opens breaker REACTOR TRIP BUS #141 (1.2)

NORMAL SUPPLY FROM M.G. SET #141by positioning lever down

5. Close REACTOR TRIP BUS #141 *PASS/ FAIL MAINTENANCE SUPPLY from I&C Bus 130A (TB 277'East) p STD: Closes breaker (1.3) REACTOR TRIP BUS #141 MAINTENANCE SUPPLY by positioning lever up

6. Notify CRO that Rx Trip Bus #141 transfer is SAT/ UNSAT completed AND 1h scram and Feedwater Heaters may be reset STD: Proper p

communications used Role Play: Acknowledge report. Inform (1.4) candidate that the 112 scram has been reset.

Direct candidate to reset Feedwater Heaters 121-125.

7. Reset Feedwater Heater String 12 NMPl NRC 2017 JPM P-3 Page 6 of 8 February 2017

Exelon Generation,,

PERFORMANCE ACT. CODE EVALUATOR PIS I NA 7a SAT/ UNSAT p

STD: Presses Feedwater (3.0) Heater 121 HIGH LEVEL TRIP RESET pushbutton (TB 291' North) 7b SAT I UNSAT p

STD: Presses Feedwater (3.0) Heater 122 HIGH LEVEL TRIP RESET pushbutton (TB 291' North) 7c SAT I UNSAT p

STD: Presses Feedwater (3.0) Heater 123 HIGH LEVEL TRIP RESET pushbutton (TB 291' North) 7d SAT I UNSAT p

STD: Presses Feedwater (3.0) Heater 124 HIGH LEVEL TRIP RESET pushbutton (TB 305' North) 7e SAT/ UNSAT p

STD: Presses Feedwater (3.0) Heater 125 HIGH LEVEL TRIP RESET pushbutton (TB 305' North)

Evaluators Cue: Your task is complete.

Note:

TASK Reactor Trip Bus 141 is energized from I&C Bus 130A and STANDARD Feedwater Heaters are reset in accordance with Nl-SOP-30.2.

STOP TIME NMPl NRC 2017 JPM P-3 Page 7 of 8 February 2017

~** Exelon Generation JPM Handout INITIAL Given:

CONDITIONS

The plant is operating at approximately 50% power

A loss of Powerboard 12 has led to the loss of Reactor Trip Bus 141 INITIATING (Operators Name), restore power to Reactor Trip Bus 141 from I&C CUE Bus 130A, in accordance with Nl-SOP-30.2, Attachment 3.

Note: The Electrical Safety PPE requirements for this task have been assessed and are as follows:

Leather gloves

100% cotton long sleeve shirt and pants OR 100% cotton short sleeve shirt and pants under fire retardant lab coat

Safety glasses or goggles NMPl NRC 2017 JPM P-3 Page 8 of 8 February 2017

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-1 Op-Test No.: LC1 15-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 1% in 5 loop operation during a startup.

ESW Pump 12 is out of service for maintenance.

Turnover: The reactor is critical at approximately 1% power. Perform N1-ST-W15, Manual and Automatic Scram Instrument Channel Test. Continue the startup IAW N1-0P-43A, starting with control rod withdrawals.

Event Malf. Event Event No. No. Type* Description Perform N1-ST-W15, Sections 6.2 and 6.3 (partial), Channel 11 N-BOP, Auto and Manual Scram Tests 1 N/A SRO N1-ST-W15 R-ATC, Withdraw control rods 2 N/A SRO N1-0P-43A, N1-0P-5 C-ATC, Stuck control rod 3 RD04 SRO N1-0P-5, Technical Specifications SRO-TS I-ATC, SRM Fails Upscale 4 NM01C SRO N1-0P-38A CW05A Loss of all TBCLC requires scram and MSIV isolation 5 C-All CW05B N1-SOP-24.1, N1-SOP-1 RP05A I-BOP, RPS fails to scram the reactor, ARI is successful 6

RP05B SRO N1-EOP-2, N1-SOP-1 EC 11 Steam Leak in the Reactor Building 7 EC02 M-All ARP K1-1-1, K1-3-4, N1-SOP-1, N1-EOP-2, N1-EOP-5 EC07A EC 11 will not isolate, requiring a RPV Slowdown 8 EC08A C-All N1-EOP-8 EC08B

(N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior Facility: Nine Mile Point Unit 1 Scenario No.: NRC-1 Op-Test No.: LC115-1

~- Exelon Generation" Copy of __

Training Id: NMP1 NRC 2017 Scenario 1 Revision: -0.0 Low Power, Stuck Rod, SRM Fails Upscale, Loss of TBCLC, Un-

Title:

isolable Steam Leak into Secondary Containment me Date Developed By Paul Isham 3/17/16 Validated By Kevin Hines 8/24/16 Josh House Phil Carroll Facility Reviewer Pat O'Brien /z(J/16 Page 1 of 22 NMP1 NRC Scenario 1 February 2017

Exelon Generation References

1. N1-ST-W15, Manual and Automatic Scram Instrument Channel Test

2. N1-0P-43A, Plant Startup

3. N1-0P-5, Control Rod Drive System

4. N1-0P-38A, Source Range Monitor

5. N1-SOP-24.1, TBCLC Failure

6. N1-SOP-1, Reactor Scram

7. N1-EOP-2, RPV Control

8. N1-EOP-5, Secondary Containment Control

9. N1-EOP-1, NMP1 EOP Support Procedure

10. N1-EOP-8, RPV Slowdown

11. Unit 1 Technical Specifications Page 2 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation@

Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 1% power with a startup in progress. Containment Spray Pump 112 is out of service tor maintenance. Steam Packing Exhauster 12 is out of service due to high vibrations. Control rod withdrawal has been halted tor the turnover and to permit the crew to perform N1-ST-W15, Manual Scram Instrument Channel Test, sections 6.1 to 6.3 tor Channel 11 only. The surveillance test results will be satisfactory.

After completion of the surveillance test the crew will resume withdrawing control rods in approach to criticality.

The second control rod to be moved will be stuck. The crew will enter N1-0P-5, Section H.13 and raise drive water pressure to move the control rod. The control rod will withdraw with increased drive water pressure.

Next, an SRM upscale trip will occur. The crew will respond per ARP F3-4-1 and N1-0P-38A to bypass the SRM.

Then, a complete loss of TBCLC occurs requiring a manual reactor Scram (Critical Task). The Mode Switch will tail to scram the Reactor, however manual ARI actuation will result in successful control rod insertion (Critical Task).

Next, a steam leak will develop from Emergency Condenser 11. The crew will attempt to isolate the leak, however the Emergency Condenser will tail to isolate both automatically and manually. Two General Areas of the Reactor Building will exceed the maximum sate temperatures. The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).

1. Termination Criteria

a. RPV water level controlled in assigned band, RPV Slowdown in progress Page 3 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation"~

2. Critical Tasks CT-1, Given a complete loss of TBCLC, the crew will insert a manual reactor scram in accordance with N1-SOP-24.1.

Justification:

Safety Significance: TBCLC provides cooling to major heat loads in the plant, including Recirc Pump MG sets and Instrument Air Compressors. Either of which, when lost, greatly reduces the level of safety of the reactor.

Cueing: Annunciators and TBCLC indications are available in the control room that will indicate a loss of TBCLC. Nt-SOP-24. 1 gives direction to Scram the reactor under these conditions.

Measurable Performance Indicators: The crew will manually scram the reactor Performance Feedback: Operation of the Mode Switch, RPS pushbuttons, and/or ARI will provide sufficient performance feedback to the evaluators.

CT-2, Given conditions requiring a scram and failure of an RPS channel to trip, the crew will manually initiate Alternate Rod Insertion (ARI) to shutdown the reactor, in accordance with N1-SOP-1 and/or N1-EOP-3.

Justification:

Safety Significance: Inserting control rods during a transient lowers reactor power, which reduces challenges to the plant during the transient. With RPS failing to trip, the crew must rely on backup shutdown methods to ensure control rods are inserted to provide long term, stable, core shutdown.

Cueing: Control rod position, Reactor power indications, and RPS lights will indicate an electric failure to scram. N1-SOP-1 provides direction to initiate ARI.

Measurable Performance Indicators: Manipulation of the Mode Switch and manual ARI will provide observable action for the evaluation team.

Performance Feedback: Control rod position and Reactor power will provide performance feedback regarding success of crew actions to insert control rods.

Page 4 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation" CT-3, Given an un-isolable Emergency Condenser leak outside Primary Containment and two general area temperatures above the maximum safe limit, execute N1-EOP-8, RPV Slowdown, in accordance with N1-EOP-5.

Justification:

Safety Significance: An un-isolable primary system discharging outside of Primary Containment resulting in two general area temperatures above the maximum safe limit indicates a wide-spread problem posing a direct and immediate threat to Secondary Containment. A blowdown minimizes flow through the break, rejects heat to the suppression pool in preference to outside the containment, and places the primary system in the lowest possible energy state.

Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment.

Emergency Condenser valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that two general areas is above the maximum safe temperature limit. Nt-EOP-5 provides direction to blowdown the Reactor.

Measurable Performance Indicators: The crew will manually open ERVs.

Performance Feedback: ERV instrumentation will provide indication that these valves are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

3. Length

a. -60 minutes

4. Mitigation Strategy Code

a. SC1, Primary System Leak in Secondary Containment, Slowdown Required

5. Technical Specifications

a. TS 3.1.6 - CRD

b. TS 3.5.1 - SRM

6. EAL Classification

a. Site Area Emergency per EAL FS1 .1 (Loss or potential loss of ANY two fission product barriers)

7. Special Orders

a. None Page 5 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation("

B. Initial Conditions

1. IC Number

a. IC-171

2. Presets I With Triggers

a. Malfunctions

1) CT01 B, CT Pump 112 Trip Inserted

2) RD04R3447, 34-47 Control Rod Failure - Stuck Inserted

3) RPOSB, Reactor Protection System Failure to Scram Ch 12 Inserted

4) EC07A, Emergency Condenser 11 Fails to Isolate Inserted

5) ECOBA, EC Loop 11 Stm IV Fail to Close 111, FV=50 Inserted

6) ECOBB, EC Loop 11 Stm IV Fail to Close 112, FV=50 Inserted

7) CWOSB, Turbine Building Closed Loop Cooling Pump Trip 12 Inserted

8) NM01C, SRM CHANNEL 13 FAILURE - UPSCALE TRG3

9) CWOSA, Turbine Building Closed Loop Cooling Pump Trip 11 TRGS

10) EC02, Steam Supply Line Break in RB, FV=20% TRG7

b. Remotes

1) None

c. Overrides

1) None

d. Annunciators

1) None Page 6 of 22 NMP1 NRC Scenario 1 February 2017

_.,/Pl'" Exelon Generation

e. Event Triggers Event# Event Action Command TRG 1, Activates when CRD drive water pressure is rdpnep01 >290 dmf rd04r3447 raised above 300 psig to delete stuck rod TRG 7, Initiates EC Steam leak when mode switch is zdrpstdn==1 Blank placed in shutdown

f. Equipment Out of Service

1) Containment Spray Pump 112 in PTL with info tag

2) Containment Spray suction isolation valve 112 closed with info tag

3) Steam Packing Exhauster 12 secured with info tag

g. Support Documentation

1) Control Rod Withdrawal Sequence marked up to current rod (18-47, pg. 16 of A2 Startup)

2) ReMA for plant startup

3) N 1-0P-43A marked up to appropriate step for place in startup (E.3.12)

4) N1-ST-W15 marked complete through 6.2.1

h. Miscellaneous 1)

Page 7 of 22 NMPl NRC Scenario 1 February 2017

~, Exelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: nN ID DATE: _T_o_da~v~--

PARTI: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor startup and heatup is in progress, with the Reactor at approximately 275 psig

Containment Spray Pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is out of service due to high vibrations.

Rod withdrawal has been suspended for completion of N1-ST-W15, Manual and Automatic Scram Instrument Channel Test, for PMT of maintenance

APRM Gains have been adjusted for the startup IAW N1 -REP-12 PART Ill: Remarks/Planned Evolutions:

Perform N1-ST-W15, Manual and Automatic Scram Instrument Channel Test, Sections 6.2 and 6.3 for Channel 11. Perform steps 6.2 and 6.3.1 - 6.3.7, only (APRMs 11 and 13 are to be tested)

Continue withdrawing control rods per the ReMA, starting at rod 18-47 from position 12 to 48.

Page 8 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation".

Shift Turnover Instructor Actions I Plant Response Operator Actions Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the Crew panels.

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 9 of 22 NMP1 NRC Scenario 1 February 2017

Exelon Generation,,

Event #1: Perform Manual and Automatic Scram Instrument Channel Test Event

A Plant startup is in progress Information

Crew will perform partial scram instrument channel test.

Test will be Sat SRO Note: N1-ST-W15 is marked up for PMT, with all

Directs execution of N 1-ST-W 15 steps in section 6.2 required, and steps 6.3.1 through

Provides oversight for evolution 6.3.7 required.

RO

Monitors plant parameters

Provides concurrent verification when required BOP

Acknowledges direction from the SRO

Verifies no half-scrams are present

Notifies RO that the following step will initiate a half scram

Depresses REACTOR TRIP 11 pushbutton at E Panel AND verifies the following:

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at M panel - off

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at F panel - off

Channel 11 Red BU SCRAM/SDV Vent and Drain Valve light at F panel - off

Annunciator F1-3-1, RPS Ch. 11 MAN RX TRIP - alarming

Computer printout W022, ***RPS Ch. 11 MAN RX TRIP YES Page 10 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation" Event 1 continued BOP continued

Depresses REACTOR TRIP RESET pushbutton at E Panel AND verifies the following:

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at M panel - on

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at F panel - on

Channel 11 Red BU SCRAM/SDV Vent and Drain Valve light at F panel - on

Annunciator F1-3-1, RPS Ch. 11 MAN RX TRIP - clear

Computer printout W022, ***RPS Ch. 11 MAN RX TRIP NO

Logs momentary drop in CRD air pressure

Verifies no half-scrams are present

Notifies RO that the following step will initiate a half scram

Places RPS Channel 11 /1 APRM 11 S-10 switch in STANDBY position Note: Annunciator F1 1 will also alarm. The mode

Verifies the following:

switch in startup makes this an expected alarm. The

Annunciator F1 1, RPS CH 11 AUTO crew may not recognize this initially.

REACTOR TRIP - alarm

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at M panel - off

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at F panel - off

Channel 11 Red BU SCRAM/SDV Vent and Drain Valve light at F panel - off

Computer printout W023 ***RPS CH 11 /1 RX NMON 11 - TRIP Page 11 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation" BOP continued Event 1 continued

Places Channel 11 RPS APRM 11 S-1 O switch to OPERATE position Evaluator Cue: If requested, perform Concurrent

Obtains concurrent verification Verification

Depresses REACTOR TRIP RESET pushbutton at E Panel AND verifies the following:

Annunciator F1 1 , RPS CH 11 AUTO REACTOR TRIP - clear

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at M panel - on

Channel 11 White SCRAM SOLENOIDS GROUPS LIGHTS (4) at F panel - on

Channel 11 Red BU SCRAM/SDV Vent and Drain Valve light at F panel - on

Computer printout W023 ***RPS CH 11/1 RX NMON11-NORM Evaluator Cue: If crew attempts to complete acceptance criteria, inform them that another

Logs momentary drop in CRD air pressure operator will perform that action. Direct the crew to

Notify the SRO/Crew that N 1-ST-W15 has been continue on with the startup. successfully completed Page 12 of 22 NMP1 NRC Scenario 1 February 2017

Exelon Generation Events #2 & #3: Withdraw Control Rods, Stuck Control Rod Event

Crew will withdraw rods per the rod movement sheet and RMI Information

Second rod to move will be stuck.

Raising drive water pressure will free the rod.

SRO Note: Verify TAG 1 activates to automatically

Directs RO to withdraw rods per Startup Rod delete malfunction RD04R3447 when CAD drive Sequence and N1-0P-5 section F.1.0 water pressure is raised, to allow the stuck rod to

Provides oversight for reactivity manipulation move.

Acknowledges control rod 34-47 is stuck

Directs RO to perform N1-0P-5 section H.13.0 for the stuck control rod

Acknowledges control rod 34-47 moves with higher drive water pressure RO

Withdraws control rod 18-47 per the rod sequence sheet

Verifies Control Rod Power is On

Depresses Rod Select pushbutton for control rod 18-47 Note: Operator will withdraw one control rod prior to

Places 4S1 Control Rod Movement switch to the stuck rod.

the rod out notch position 0 Observes SRM and period response 0 Observes RMCS, RPIS and CAD indications Page 13 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation Events 2 and 3 continued RO Continued

Attempts to withdraw control rod 34-47 per the rod sequence sheet

Diagnoses stuck control rod

Notifies SRO/Crew Note: Numerous steps in the stuck rod procedure

Places 481 Control Rod Movement switch to the are dependent upon how the operator interprets rod out notch position while monitoring RMCS RMCS and CRD indications. and CRD indications

May de-select and re-select rod and re-attempt notch withdrawal Role Play: If dispatched to perform HCU valve

May request HCU valve lineup and re-attempt lineup, wait 1 minute and report that HCU 34-47 notch withdrawal valve lineup is complete (time compression used).

May request operator observe stabilization valve response and re-attempt notch withdrawal

Confirms drive water pressure raised 50 psid Note: Allow enough control rod movement to and re-attempts notch withdrawal evaluate operator's ability to perform the reactivity manipulation, and then move on to event 4. It is not

Notifies the SRO/crew that the control rod is un-necessary to move all rods on page 16 of the startup stuck sequence.

Resumes normal control rod withdrawal BOP

Monitors plant parameters Role Play: If dispatched to observe stabilization

Confirms normal drive water pressure valve response, immediately report that you are on

May request operator observe stabilization valve station. When rod withdrawal is attempted, response and re-attempt notch withdrawal immediately report normal stabilization valve

Raises drive water pressure in 50 psid operation. increments

Returns drive water pressure to normal Page 14 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation Event #4: SRM Upscale Failure Event

A Plant startup is in progress Information

SRM 13 fails upscale

Crew will bypass the SRM

SRO will address Tech Specs When directed by lead examiner, insert CREW malfunction:

Acknowledges/reports annunciators

Diagnoses SRM 13 failed upscale NM01C, SRM CHANNEL 13 FAILURE - UPSCALE TRG3 SRM 13 indicates upscale Expected Annunciators:

F3-4-1, SRM 13-14 F4-4-8, RPS CH 12 REFUEL INST TRIP SRO

Directs execution of ARP F3-4-1

Determines Technical Specification 3.5.1 allows bypassing SRM 13

Determines Technical Specification 3.5.3 does not apply under current plant conditions

Directs bypassing SRM 13 per N 1-0P-38A ATC

Monitors plant parameters Page 15 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation.,

BOP Event 4 continued

Executes ARP F3-4-1

Confirms computer point

Observes E Panel to determine which of the following off-normal conditions exist AND on which channel:

DOWNSCALE OR INOP light

UPSCALE HI COUNT light

UPSCALE HI-HI light

Monitors period meter on G Panel

Monitors count rate meter on G Panel

Verifies correct position of detector in core on E Panel

Bypasses SRM 13 per N 1-0P-38A section H.1.0

Determines operability of all SRMs:

Verifies all SRMs are reading consistent with current plant condition

Verifies Control Room Logs for inoperable SRMs

Observes IF the SRM switch is in bypass

Coordinates with SRO to verify Tech Specs 3.5.1 AND 3.5.3 will be met when desired SRM is bypassed

Places BYPASS switch to bypass position for SRM13 Page 16 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation Events #5 & #6: Loss of all TBCLC Requires Scram and MSIV Isolation, RPS Fails to De-Energize Event

Loss of all TBCLC will require manual scram and MSIV isolation Information

RPS fails to de-energize requiring ARI to insert rods When directed by examiner, insert malfunction: RO

Recognize and report loss of TBCLC Pump 11 CWOSA, Turbine Building Closed Loop Cooling Pump

Recognize and report failure of TBCLC Pump 12 Trip 11, True to auto start TRGS

May recognize TBCLC Pump 12 attempted to TBCLC header pressure drops start and tripped.

TBCLC Pump 12 attempts to start and trips

-H1-1-4, TB COOLING WTR PUMP 11 TRIP I TROUBLE

Recognize and report annunciators H1-1-4 and H1-3-4

-H1-3-4, TURBINE BLDG COOLING WATER PRESS TEMP MAKEUP FLOW RO

Provide a critical parameter update SRO

Acknowledge reports on TBCLC

Verifies execution of ARPs

Directs execution of N1-SOP-24.1, TBCLC Note: The crew is likely to initiate ARI based on the Failures immediate actions of SOP-1, Reactor Scram.

Alternately, the crew may enter EOP-3 for direction to

Acknowledge override requirements from N1-initiate ARI. SOP-24.1

Directs reactor scram CT-1 Note: CRS may just direct the operator to execute

Directs ARI initiated the override steps of N1-SOP-24.1 vice giving CT-2 individual direction for each step.

Directs pressure control on ECs and to shut the MSIVs

Directs all recirc pumps tripped Page 17 of 22 NMPl NRC Scenario 1 February 2017

--Jfl/lf!IP Exelon Generation BOP

Recognizes failure of TBCLC pump 12

Enters N1-SOP-24.1

Informs crew of override requirements to scram the reactor.

Initiates ARI when RPS fails to de-energize CT-2

Initiates ECs

Shuts MSIVs

Trips all recirc pumps RO

Places Mode Switch in Shutdown CT-1

Depresses RPS pushbuttons

Performs scram verification actions of N1-SOP-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places IRMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary

Controls Reactor pressure as directed Page 18 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation",

Events #7 & #8: Un-isolable EC Steam Leak into Secondary Containment Event

The reactor has been scrammed from a low power condition Information

An EC Steam leak occurs whch leads to blowdown.

Verify the following malfunctions are automatically CREW inserted when the mode switch is taken to

Acknowledge/report annunciators SHUTDOWN:

Recognize/report Emergency Condenser 11 EC02, Steam Supply Line Break in RB, FV=20%

steam leak TRG7

Recognize/report failure of Emergency Reactor Building DIP lowers Condenser 11 to isolate Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RBVS isolates Expected Annunciators:

L 1-3-4, REACT. BLDG/ATM DIFF PRESS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL L1-3(4)-6, EMER VENT SYS CHANNEL 11(12) RELAY OPERATE MFP2 2-1-1-7, REAC BLDG 318 LOCAL PNL N0.7 FIRE K1-4-3, EMER COOLING SYSTEM 11 STEAM LEAK AREA THI K1-4-5, EMER COOLING SYSTEM 12 STEAM LEAK AREA THI L 1-3-3, CONTINUOUS AIR RAD MONITOR H1-4-8, AREA RADIATION MONITORS Verify the following malfunctions are preset:

EC07 A, Emergency Condenser 11 Fails to Isolate EC08A, EC Loop 11 Stm IV Fail to Close 111, FV=50 EC08A, EC Loop 11 Stm IV Fail to Close 112, FV=50 Emergency Condenser 11 isolation valves will not close Page 19 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation Events 7 and 8 continued SRO

Acknowledges reports

Enters N1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temps I rad levels, and/or loss of RB D/P

Directs manual isolation of EC11

Directs Reactor Building evacuation

Acknowledges manual isolation failure

Directs dispatching of an operator and RP tech to obtain general area temps and rad levels in the Reactor Building

When Reactor Building Ventilation exhaust radiation exceeds 5 mR/hr, directs verification of RB Vent isolation and RBEVS initiation

Determines area temperatures and/or radiation levels are above setpoints in Tables T and R, and transitions to N 1-EOP-5 circle 27

Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28

May direct anticipatory blowdown with TBVs Note: By this point in the scenario, EC 12 and/or Emergency Condenser 12 with cooldown temperature monitor will likely be in alarm also, due in excess of 100°F/hr to the close proximity of the temperature switches.

Acknowledges reports of Reactor Building Therefore the crew will possibly isolate EC 12 and temperatures and radiation levels not place it in service for the Slowdown.

When report is received that 2 General Areas temperatures are above 135°F, enters N1-EOP-8, RPV Slowdown

Answers "Are all control rods inserted to at least position 04" YES

Answers "Drywell pressure?" <3.5 psig

May direct initiation of Emergency Condenser 12

Answers "Torus water level?" >8 ft

Directs open 4 ERVs CT-3 Page 20 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation Events 7 & 8 continued BOP/ATC Note: No General Area temperature information is

Attempts to isolate Emergency Condenser 11 by available until an Operator has been dispatched to the Reactor Building to monitor area temperatures. closing the following valves per ARP K1 3:

The timeline of field reports may be adjusted by

39-07R, EC STM ISOLATION VALVE 112 examiner as necessary for evaluation purposes.

39-09R, EC STM ISOLATION VALVE 111

39-05, EMERG CNDSR COND RET Role Play: When directed as Operator and RP tech ISOLATION VALVE 11 to obtain General Area temperatures and radiation levels in the Reactor Building:

39-11 R, EMERG CNDSR STM SUPPLY DRAIN IV 111

39-12R, EMERG CNDSR STM SUPPLY Wait approximately 4 minutes and report RB 318' west side temperature is 125°F and rising, radiation DRAIN IV 112 level is 2 mr/hr and rising. Also report that you see

05-01 R, EMERG COND VENT ISOLATION steam coming from the area of the EC steam IV VALVE 111 room.

05-11, EMERG COND VENT ISOLATION VALVE 112 Note: When one general area temperature is

Reports failure of 39-07R and 39-09R to close reported above 135°F and a second general area temperature is reported as approaching 135°F,

Dispatches operator and RP tech to obtain the crew is likely to perform an anticipatory Reactor Building General Area temperatures and blowdown per EOP-2.

radiation levels

Notifies crew of reports on General Area Wait approximately 2 more minutes and report RB temperatures and radiation levels 318' west side temperature is 137°F and rising,

Performs RPV water level control actions of N1-radiation level is 4 mr/hr and rising. Report RB 318' east side temperature is 123°F and rising, radiation SOP-1, Reactor Scram:

level is 2 mr/hr and rising.

Restores RPV level to 53-95" by controlling injection and rejecting through RWCU Wait approximately 3 more minutes and report RB 318' west side temperature is 145°F and rising, radiation level is 6 mr/hr and rising. Report RB 318' east side temperature is 136°F and rising, radiation level is 3 mr/hr and rising.

Page 21 of 22 NMPl NRC Scenario 1 February 2017

Exelon Generation BOP/ATC Continued

Verifies RPV water level above 53"

Verifies 11/12 FWP controllers in MANUAL and set to zero output

Places FWP BYPASS Valve 11or12 in AUTO, sets to 65-70 inches

If RPV level reaches 85 inches and rising, then:

Verifies off all FW Pumps

Secures CRD Pumps not required

May initiate Emergency Condenser 12

Opens 4 ERVs CT-3 Event Termination

RPV water level controlled in assigned band Criteria

RPV Blowdown in progress Page 22 of 22 NMP1 NRC Scenario 1 February 2017

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-2 Op-Test No.: LC1 15-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. ESW Pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking. PB 11 is aligned to reserve power in preparation for cross-tying PB 16.

Turnover: Lower reactor power to 98% using recirc flow. Cross-tie PB 16A to PB 16B with PB 16B supplying. Then, return PB-11 to normal.

Event Malf. Event Event No. No. Type* Description N/A R-ATC, Lower reactor power with recirc.

1 SRO N1-0P-1 N/A N-BOP, Cross-tie PB 16A to PB 16B 2

SRO N1-0P-30 C-ATC, Control Rod 26-35 Drifts Out 3 RD02 SRO N1-SOP-5.2 C-Feedwater Booster Pump 11 Trips with Failure of Feedwater FW02A BOP, 4 Booster Pump 13 to Auto-start SRO Override N1-SOP-16.1, Technical Specifications TS-SRO C-All Respond to trip of Reactor Protection System (RPS) UPS 172 5 RP25 TS-SRO Technical Specification N1 -SOP-40.1 RWCU break in the Secondary Containment requiring scram 6 CU11 M-All N1-EOP-2, N1-EOP-5 Failure of the RWCU Isolation Valves to isolate 7 CU14 C-All N1-EOP-5, N1-EOP-8 C- Mode Switch Fails to Scram 8 Overrides ATC, SRO N1-SOP-1

. (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior

~

~ ExelonGeneration Copy of __

Training Id: NMP1 NRC 2017 Scenario 2 Revision: -0.0 Control Rod Drift, FWBP Trip, Trip of RPS UPS 172, Un-isolable

Title:

RWCU Break in the RB, Mode Switch Fails Signature I Printed Name _

Developed By ? Paul Isham 3/11/16 Validated By Kevin Hines 8/24/16 Josh House Phil Carroll Facility Reviewer --*~*~'---__,_'~-=----~---"-<~~.:'-------P_a_t_O_'B_r_ie_n 7 ~

1?(v-/t6 Page 1 of 24 NMP1 NRC Scenario 2 February 2017

,.=:"!' Exelon Generation, References

1. N1-0P-30, 4.16 KV, 600V, and 48V House Service

2. N1-SOP-5.1, Control Rod Drift

3. N1-SOP-16.1, Feedwater Failures

4. N1-SOP-40.1, Loss of RPS

5. N1-SOP-1 , Reactor Scram

6. N1-EOP-2, RPV Control

7. N1-EOP-5, Secondary Containment Control

8. N1-EOP-1, NMP1 EOP Support Procedure

9. N1-EOP-8, RPV Slowdown

10. Unit 1 Technical Specifications Page 2 of 24 NMPl NRC Scenario 2 February 2017

~ ExelonGeneration Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 100% power. ESW pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking. The crew will start by lowering Reactor power to approximately 98% with Recirculation flow. Then the crew will cross-tie PB 16A to PB 168.

Following the power board transfer, a control rod will begin to drift out. The crew will select the drifting control rod and drive it full in. The crew will dispatch an operator to valve out the affected Hydraulic Control Unit to prevent the control rod from continuing to drift.

Then, Feedwater Booster pump 11 will trip. The standby Feedwater Booster pump will fail to auto-start. The crew will manually start the standby Feedwater Booster pump to restore normal system pressures. The SRO will determine the Tech Spec impact for loss of a redundant HPCI component.

RPS UPS 172 will develop an internal fault and drop out the #12 RPS system and RPS Bus 12. The crew will respond to the trip of UPS per N1-SOP-40.1. The SRO will direct the bus be repowered from l&C Bus 130A and will determine the most limiting Tech Spec condition. The BOP and the RO will reset Y2 scram and Y2 isolations and perform recovery actions after the bus is repowered. The SRO will determine Tech Spec 3.1.2, 3.6.11 and 3.4.4 are the limiting 7 day LCO's applicable with the RPS 12 Bus tripped.

A Reactor Water Cleanup system line break will occur in the Secondary Containment downstream of the Supply Isolation Valves. Reactor Water Cleanup will fail to isolate on high area temperature. The crew will attempt to isolate the system, but the valves will fail to fully close. This break will require a scram (Critical Task) and RPV blowdown (Critical Task) due to exceeding the Maximum Safe Value for general area temperatures. The Mode Switch will fail to scram the Reactor, however either RPS pushbuttons or manual ARI actuation will result in successful control rod insertion.

1. Termination Criteria

a. RPV water level controlled in assigned band, RPV Slowdown in progress Page 3 of 24 NRC Scenario 2 February 2017

~ ExelonGeneration

2. Critical Tasks CT-1, Given an un-isolable RWCU leak outside primary containment and one general area temperature above the maximum safe limit, the crew will insert a manual reactor scram, in accordance with N1-EOP-5.

Justification:

Safety Significance: With an un-isolable primary system discharging outside of Primary Containment resulting in general area temperature above the maximum safe limit, the Reactor must be scrammed. This reduces the rate of energy production and thus the heat input, radioactivity release, and break flow into the Secondary Containment. This also ensures the Reactor is shutdown prior to need for a blowdown.

Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment.

RWCU valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that a general area is above the maximum safe temperature limit. Nt-EOP-5 provides direction to scram the Reactor.

Measurable Performance Indicators: Rotation of the Mode Switch to SHUTDOWN or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.

Performance Feedback: Control rod position and Reactor power indications will provide performance feedback regarding the success of the scram.

CT-2, Given an un-isolable RWCU leak outside primary containment and two general area temperatures above the maximum safe limit, the crew will execute N1-EOP-8, RPV Slowdown, in accordance with N1-EOP-5.

Justification:

Safety Significance: An un-isolable primary system discharging outside of Primary Containment resulting in two general area temperatures above the maximum safe limit indicates a wide-spread problem posing a direct and immediate threat to Secondary Containment. A blowdown minimizes flow through the break, rejects heat to the suppression pool in preference to outside the containment, and places the primary system in the lowest possible energy state.

Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment.

RWCU valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that two general areas is above the maximum safe temperature limit. N1-EOP-5 provides direction to blowdown the Reactor.

Measurable Performance Indicators: The crew will manually open ERVs.

Performance Feedback: ERV instrumentation will provide indication that these valves are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

Page 4 of 24 NRC Scenario 2 February 2017

~ ExelonGeneration .

3. Length

a. -60 minutes

4. Mitigation Strategy Code

a. SC1, Primary System Leak in Secondary Containment, Slowdown Required

5. Technical Specifications

a. TS 3.2.5

b. 3.1.7.e

c. 3.6.3

d. 3.1.8.b (FWBP)

6. EAL Classification

a. Site Area Emergency per EAL FS1 .1 - Loss or potential loss of any two fission product barriers.

(RWCU Isolation Failure and Release Outside Primary Containment)

b. Unusual Event per EAL SU8.1 also occurs during scenario.

7. Special Orders

a. None Page 5 of 24 NRC Scenario 2 February 2017

~

,="1' Exelon Generation B. Initial Conditions

1. IC Number

a. IC-152

2. Presets I With Triggers

a. Malfunctions

1) NM10A, IRM CHANNEL 11 FAILURE- UPSCALE Inserted

2) CW03B, EMERGENCY SERVICE WATER PUMP TRIP 12 Inserted

3) R002R2627, 26-27 Control Rod Failure - Drift Out, Driveable TRG 1

4) R003R2627, 26-27 Control Rod Failure -Accumulator Trouble TRG25

5) FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG2

6) RP25, Loss of Both UPS 172A and 172B TRG3

7) CU11, CU Coolant Leak Outside of Drywell, FV=45 TAGS

8) CU14, CU Isolation Valves Stuck Open Inserted

b. Remotes

1) R007, Reset of Rod Drift Alarm, FV=reset TRG26

2) RP04, RPS Bus 12 Power Source, FV=maint TRG4

3) FW24. Removal of HPCI Fuses FU8/FU9, FV = pulled TRG7

c. Overrides

1) 7543014116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 12 auto-start Inserted failure)

2) 13570014674, POS_ 1 1E67 REAC. SW.-RUN, FV=on Inserted

3) 13570014675, POS_2 1E67 REAC. SW.-SHUTDOWN, FV=off Inserted

d. Annunciators

1) None Page 6 of 24 NRC Scenario 2 February 2017

"~ Exelon Generation

e. Event Triggers Event# Event Action Command TRG 21, Energizes RWCU IV 33-01 green light when zdcu301c==1 ior 9ds51 lo51912 (0 O) control switch is taken to close true TRG 22, Energizes RWCU IV 33-02 green light when zdcu302c==1 ior 9ds531o51914 (0 O) control switch is taken to close true TRG 23, Energizes RWCU IV 33-04 green light when zdcu304c==1 ior 9ds551o5200 (0 0) true control switch is taken to close TRG 29, After scram, allows Mode Switch logic to rd:rpscm(1 )==1 dor 13S70Dl4674 reposition to prevent MSIV closure on low pressure TRG 30, After scram, allows Mode Switch logic to rd:rpscm(1 )==1 dor 13S70Dl4675 reposition to prevent MSIV closure on low pressure

f. Equipment Out of Service

1) ESW Pump 12 in PTL with info tag

2) IRM 11 bypassed with info tag and off normal

g. Support Documentation

1) N1-0P-30 marked up through step H.20.1.2 showing PB-11 is aligned to reserve power.

2) ReMA for power reduction

h. Miscellaneous

1) Protect the following equipment: EDG 103, PB 103

2) Ensure PB-11 aligned to reserve power

3) FWBP 12 is green flagged

4) DW Cooling Fan 11 secured Page 7 of 24 NRC Scenario 2 February 2017

--~ Exelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N ID DATE: -'T'--'o"'""'d=a~y_ __

PARTI: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor power is approximately 100%.

ESW Pump 12 is out of service for maintenance

IRM 11 is bypassed due to spiking

N1-0P-30 is completed up through H.20.1.2 in preparation for transformer maintenance.

Power Board 11 is aligned to reserve power.

PART Ill: Remarks/Planned Evolutions:

Lower Reactor power to approximately 98% (1813MWth) per ReMA

Cross-tie Powerboard 16A to Powerboard 16B in accordance with N1-0P-30, starting at step H.20.1.3. PB 11 is to remain aligned to reserve power.

Page 8 of 24 NRC Scenario 2 February 2017

.a=:-' Exelon Generation Shift Turnover Instructor Actions I Plant Response Operator Actions Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the Crew panels.

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 9 of 24 NRC Scenario 2 February 2017

=--' ExelonGeneration Event #1: Lower Reactor Power with Recirc Flow Event

The crew lowers power with recirc flow with the provided REMA Information

No complications SRO

Directs power reduction with Recirculation flow in accordance with N1-0P-43B and the Reactivity Maneuver Instruction (REMA)

Provides oversight of reactivity maneuver ATC

Acknowledges direction from SRO

Lowers Recirculation flow with master Recirculation flow controller

Monitors APRMs

Monitors Recirculation flow

Monitors Feedwater flow and RPV water level

Observes power-to-flow map restrictions BOP

Monitors individual RRPs for response

Individual MIA-Speed Control stations trending uniformly

Individual RRP indications trending normally for speed decrease

Monitors Feedwater controls for proper response

FWP 13 FCV responding to power change

RPV water level remains within program band (65" - 83")

Page 10 of 24 NRC Scenario 2 February 2017

'~ ExelonGeneration Event #2: Cross-tie PB16A to PB16B Event

PB 11 is aligned to reserve power Information

Crew cross-ties PB16A to PB16B per N1-0P-30 SRO

Direct the crew to cross tie PB 16A to PB 16B, with PB16B supplying per N1 -OP-30 Note: The crew will be informed that loads have been BOP minimized during the pre-job brief.

Acknowledges direction from SRO Note: Crew will be informed during turnover JAF

References N1 -OP-30, Section H.20 notification and S-ODP-OPS-0112, Attachment 4 have been completed BOP Starts at step H.20.1.3

Update crew that annunciator A4-4-4 will alarm

-A4-4-4, POWER BO. 16 BKR BY-PASS SW alarms

Place PB16 SUPPLY-BUS TIE BREAKER INTERLOCK BYPASS SWITCH in BYPASS at panel BS BOP

Close R1042, 16 PB Bus Tie Sect A To Sect B

Open R1041, Supply Bkr To 17 PB (A Section)

-A4-4-4, POWER BO. 16 BKR BY-PASS SW clears

Update crew that annunciator A4-4-4 will clear Note: As soon as A4-4-4 clears proceed to the next

Place PB16 SUPPLY-BUS TIE BREAKER INTERLOCK BYPASS SWITCH in NORMAL at event panel BS (step 20.1.6)

Role Play: If contacted to mark amps on PB-16

Determines PB-11 will remain aligned to reserve per the turnover sheet.

supply transformer, report amps as indicated by the simulator.

Verifies <962 amps on PB-16 supply transformer.

Page 11of24 NRC Scenario 2 February 2017

,. *

Exelon Generation Event #3: Control Rod Drift Event

Reactor power is near rated conditions.

Information

Control Rod drift

Rod will remain inserted when valved out of service When directed by examiner, insert malfunction: CREW

Acknowledges/reports annunciator RD02R2627, 26-27 Control Rod Failure - Drift Out, F3-2-6 Driveable TRG 1

Observes control rod 26-27 drifting outward Reactor power rises Rod 26-27 position indication rises Expected Annunciators:

F3-2-6, CONTROL ROD DRIFT SRO

Acknowledges report from crew

Directs execution of N1-SOP-5.2 and SOP-1.1

Reviews Tech Spec 3.1 .1 RO

Executes N1-SOP-5.2 Note: The first four steps listed for SOP-5.2 are

Identifies drifting rod (IA)

Immediate Actions (IA). These will likely be

Turns on Control Rod Power (IA) performed prior to the RO referencing the procedure.

The procedure should then be referenced to verify

Selects rod 26-27 (IA) correct execution and complete remaining steps.

Inserts rod 26-27 to position 00 using Emergency Rod In (IA)

Role Play: If contacted as station management,

Determines rod can be fully inserted acknowledge report.

Releases emergency rod in switch

Determines rod is drifting out again

Inserts control rod with Emergency Rod In and holds switch

Acknowledges that HCU is valved out

Releases emergency rod in switch

Determines control rod does not drift Page 12 of 24 NRC Scenario 2 February 2017

)J=-" Exelon Generation Role Play: When directed as operator to valve out BOP HCU, acknowledge order and wait 2 minutes, then insert malfunction:

Monitors reactor pressure and level

Peer checks RO RD03R2627, 26-27 Control Rod Failure -

Reduces reactor recirc flow to lower power 85-Accumulator Trouble 90%.

TRG25

Dispatches operator to valve out HCU

Dispatches operator to reset control rod drift Verify the following malfunction is automatically deleted: alarm

If required, dispatches operator to disarm the RD02R2627, 26-27 Control Rod Failure - Drift Out control rod Report HCU for control rod 26-27 is valved out.

Role Play: When directed as operator to reset the control rod drift alarm, wait 1 minute, then insert remote:

RD07, Reset of Rod Drift Alarm, FV=reset TRG26 Then report task completion.

Role Play: If dispatched as operator to disarm the HCU, acknowledge the report and wait one minute, then report the control rod has been disarmed.

Page 13 of 24 NRC Scenario 2 February 2017

.a~ ExelonGeneration Event #4: Feedwater Booster Pump Trip Event

FWBP 11 will trip and FWBP 12 will fail to auto start Information

The crew will respond by starting the standby FWBP

SRO will evaluate tech specs When directed by lead examiner, insert CREW malfunction:

Acknowledge/report annunciator H3-1-6 REACTOR FW BOOSTER P11 TRIP FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG2

Diagnose trip of Feedwater Booster Pump 11 The following override prevents Feedwater Booster Pump 12 from Auto Starting on low header discharge pressure:

OVR-7543014116 POS_3 4H17/51-02A C FRM B, FV=off Inserted RPV water level lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:

H3-1-6, REACTOR FW BOOSTER P11 TRIP H2-3-5, HWC Trouble SRO

Acknowledges report

If BOP does not manually start FWBP 12, directs starting FWBP 12

Enters Tech Spec 3.1.8.b

Determines redundant component inoperable in HPCI train 11, thus 15 day LCO applies

Initiates surveillance requirement 4.1.8.c for redundant component operability verification

Notifies WEC/WWM

Notifies Ops Management Page 14 of 24 NRC Scenario 2 February 2017

~

,,,,__ Exelon Generation Event 4 continued ATC

Monitors plant parameters

May perform Emergency Power Reduction per N1-SOP-1.1 as required to maintain RPV water level BOP Role Play: When dispatched as Operator to investigate, wait 2 minutes, then report:

Report alarm and respond per H3-1-6

Confirms alarm on computer (E049 RX FW

FWBP 11 breaker tripped on overcurrent BOOST PMP 11 TRIP)

No abnormal indications at FWBP 12 breaker

Recognizes/diagnoses failure of the standby

No abnormal indications at FWBP 11 or 12 . pump to automatically start Role Play: When dispatched as Operator to swap

Manually starts FWBP 12 HWC, wait 5 minutes and report that HWC injection

Notifies crew of failure of FWBP 12 to auto start has been transferred from FWBP 11 to FWBP 12.

Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12

May green flag FWBP 11 Page 15 of 24 NRC Scenario 2 February 2017

~* ExelonGeneration Events #5: Trip of RPS UPS 172 Event

The crew will respond to a trip of RPS UPS 172 and swap to the maintenance Information supply

SRO will evaluate Tech Specs When directed by lead examiner, insert malfunction:

RP25, Loss of Both UPS 172A and 172B TRG3 RPS Channel 12 half scram RBEVS initiates CREVS initiates RRP MG Set Scoop Tubes Lock up Multitude of control room annunciators are expected.

RO

Recognize/report loss of RPS Bus 12

Recognize/report half scram .

Recognize/report lock up RRP MG Set Scoop Tubes.

Recognize/report loss of normal R.B. vent and start of RBEVS.

SRO Role Play

Acknowledge report from the crew.

As Elec. Maint., wait five minutes report that a fault

Direct respond to loss of RPS Bus 12 per N1-on the supply breaker to the UPS will prevent SOP-40.1 restoration of the UPSs for a day or two.

Direct EM to investigate UPS 172A .

Page 16 of 24 NRC Scenario 2 February 2017

.a~ ExelonGeneration RO

Acknowledge direction from the SRO .

Enter N1-SOP-40.1 and update crew

Confirms Computer Point G187 Role Play: As in-plant operator, if directed to transfer Restores per N1-0P-40 RPS Bus 12 to the maintenance bus, wait approximately 2 minutes and insert the following

Dispatch in-plant operator to transfer RPS Bus 12 to maintenance bus.

remote:

RP04, RPS BUS 12 POWER SOURCE, MAINT

Acknowledge report from plant operator and update crew TRG4

Discuss priorities with SRO

Reset RPS Channel 12 Containment High Pressure signals (Back panel)

Reset half scram Note: Per N1-0P-40, the following Tech Specs may SRO apply throughout this transient: 3.6.3, 3.1.2, 3.1.6,

Acknowledge report that RPS Bus 12 is re-3.1.8, 3.4.4, and 3.4.5 energized

Direct restoration priorities using N1-SOP-40.1 The plant is in a 14 day LCO per 3.6.3 Note: The SRO may also opt to enter N 1-SOP-16.1 due to the loss of FW Heating.

Page 17 of 24 NRC Scenario 2 February 2017

_,._ Exelon Generation Note: The subsequent actions will be prioritized and may not happen before next event. Lead examiner may move on to next event once half scram is reset.

After RPS Bus 12 is re-energized, the BOP would normally perform the following:

Reset ATWS LOV

Reset ATWS Ch. 12 Trouble per ARP F3-4-3

Restore RPS Bus 12 Loads o Close 77.3-16 (15), Off Gas Vacuum Pump 12(11}FCV o Restore Feedwater Control System 12 to the normal power source o Give 77-03 an open signal o Give close signals to Emergency Cooling CRVs 39-05 and 39-06 o Closes N2 Supply 12 PCV o Reset EC Vent Rad Monitors o Reset Containment Spray Raw Water Rad Monitors o Give SJAE Interstage Blocking Valves on H-Panel an OPEN signal o Resets APRM flow units o Resets LPRM alarms on auxiliary drawers

Restore Reactor Building Ventilation

Reset Reactor Building Vent Radiation Monitors

Restore Normal Control Room Ventilation Page 18 of 24 NRC Scenario 2 February 2017

,.._. Exelon Generation Events #6, #7, and #8: RWCU Leak in the Secondary Containment, Failure of the RWCU Isolation Valves, Failure of Mode Switch to Scram Event

Unisolable RWCU leak into Reactor Building Information

RPV Slowdown will be required

Crew may anticipate blowdown

Mode switch fails to scram When directed by lead examiner, insert CREW malfunction:

Diagnoses/reports leak from RWCU into CU11, CU Coolant Leak Outside of Drywell, FV=45 secondary containment TRG5

Diagnoses/reports RWCU failed to isolate

Recognize/report failure of Mode Switch Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts (if secured from previous event)

RBVS isolates (if restored from previous event)

RWCU /Vs fail to close on isolation signal and manually Expected Annunciators:

H1-4-8, AREA RADIATION MONITORS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL Lt-3(4)-6, EMER VENT SYS CHANNEL 11(12) RELAY OPERA TE (-1 min)

K3-3-4, CLEAN-UP SYS LEAK AREA THI (-5 min)

L1-3-3, CONTINUOUS AIR RAD MONITOR (-1 min)

K3-1-6, CU Pump 12 Trip Later Reactor Building DIP goes to Zero Verify the following malfunctions are preset:

CU14, CU Isolation Valves Stuck Open Verify the following overrides are preset:

13570014674, POS_ 1 1E67 REAC. SW.-RUN, FV=on 13570014675, POS_2 1E67 REAC. SW.-

SHUTDOWN, FV=off Page 19 of 24 NRC Scenario 2 February 2017

~

>~ ExelonGeneration Event 6, 7 and 8 continued SRO

Acknowledges reports

Enters N 1-EOP-5, Secondary Containment Control, on high Reactor Building Vent rad levels, high Reactor Building area temperatures loss of D/P and rad levels

Directs RWCU system isolation

Directs Reactor Building evacuation

Acknowledges report that RWCU failed to isolate both automatically and manually

Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building Note: RBEVS initiation will only be necessary if

When Reactor Building Ventilation exhaust normal RB ventilation was restored following the loss radiation exceeds 5 mR/hr, directs verification of of RPS 12.

RB Vent isolation and RBEVS initiation

Determines area temperatures and radiation levels are above setpoints in Tables T and R, and transitions to N1-EOP-5 circle 27

Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28

Before any area temperature or radiation level reaches 135°F or 8 R/hr, respectively:

Directs manual scram (CT-1.0)

Acknowledges scram report Page 20 of 24 NRC Scenario 2 February 2017

~

...-iw*

~* Exelon Generation Event 6, 7 and 8 continued SRO continued

Enters N1-EOP-2, RPV Control on low RPV water level

Answers "Are all control rods inserted to at least position 04 ?" YES

Directs entry into N1-SOP-1, Reactor Scram

Directs RPV water level control 53-95" using Feedwater/Condensate and CRD

Directs RPV pressure maintained <1080 psig using Emergency Condensers & TBVs Note: Anticipatory blowdown is likely to be directed

May direct anticipatory blowdown with from N1-EOP-2 once one Reactor Building General Area temperature is above 135°F with a second Emergency Condensers with cooldown in excess temperature trending towards 135°F. of 100°F/hr

Acknowledges reports of Reactor Building temperatures and radiation levels

When report is received that 2 General Areas temperatures are above 135°F, enters N1-EOP-8, RPV Slowdown

Answers "Are all control rods inserted to at least position 04" YES

Answers "Drywell pressure?" <3.5 psig

Directs initiation of Emergency Condensers

Answers "Torus water level?" >8 ft

Directs open 4 ERVs (CT-2.0)

Page 21 of 24 NRC Scenario 2 February 2017

~

JJ=:--- Exelon Generation Event 6, 7 and 8 continued RO

Makes evacuation announcements due to steam When control rods insert, verify triggers 29 and 30 leak automatically initiate and delete the following

Places Reactor Mode Switch to SHUTDOWN overrides:

Recognizes/reports failure of Mode Switch to 13$70014674, POS_ 1 1E67 REAC. SW.-RUN scram 13$70014675, POS_2 1E67 REAC. SW.-

Depresses RPS manual scram pushbuttons SHUTDOWN and/or manually initiates ARI

Provides scram report

Performs scram verification actions of N1 -SOP-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places IRMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary

Reduces Recirc Master flow to 25-43 x 106 lbm/hr

Verifies main turbine and generator tripped

Controls RPV pressure as directed using Emergency Condensers or TBVs Page 22 of 24 NRC Scenario 2 February 2017

)i=-" Exelon Generation Event 6, 7 and 8 continued BOP

Attempts to isolate RWCU by closing 33-01 R, 33-Role Play: If dispatched to attempt RWCU valve 02R and 33-04R closures, acknowledge direction and delay action.

Recognizes/reports failure of RWCU IVs (33-01 R,33-02R and 33-04R) to close Note: No General Area temperature information is

Dispatches operator and RP tech to obtain available until an operator has been dispatched to the Reactor Building General Area temperatures and Reactor Building to monitor area temperatures. The radiation levels timeline of field reports may be adjusted by examiner as necessary for evaluation purposes.

Notifies crew of reports on General Area temperatures and radiation levels

Performs RPV water level control actions of N1-SOP-1:

Restores RPV water level to 53-95" by controlling Role Play: When directed as operator and RP tech injection. (unable to reject through RWCU) to obtain General Area temperatures and radiation

Determines #13 FWP was running levels in the Reactor Building:

Determines RPV water level is recovering Wait 4 minutes and report RB 261' east side

Verifies at least one Electric FW Pump running temperature is 125°F and rising, radiation level is 100 mr/hr and rising. Also report that you see steam

Terminates 13 FWP injection as follows:

coming from the area of the RWCU rooms.

Places FWP 13 FCV in manual and closes

Disengages 13 FWP

Gives 29-10, FEEDWATER PUMP 13 Wait 2 more minutes and report RB 261' east side BLOCKING VALVE a CLOSE signal temperature is 137°F and rising, radiation level is 150

Verifies RPV water level above 53" mr/hr and rising. Report RB 261' west side temperature is 123°F and rising, radiation level is 35

Verifies 11/12 FWP controllers in MANUAL and mr/hr and rising. set to zero output

Resets HPCI signal

Places 11 or 12 FWP BYPASS Valve in AUTO, Wait 3 more minutes and report RB 261' east side sets to 65-70" temperature is 145°F and rising, radiation level is 175

If RPV level reaches 85 inches and rising, then:

mr/hr and rising. Report RB 261' west side temperature is 136°F and rising, radiation level is 45

Verifies off all Feedwater Pumps mr/hr and rising.

Secures CRD Pumps not required

Closes FWIVs if required

Closes MSIVs if required Page 23 of 24 NRC Scenario 2 February 2017

~

,;=:-"" Exelon Generation Event 6, 7 and 8 continued BOP continued

Maintains RPV water level in assigned band

Notifies crew of reports on General Area temperatures and radiation levels

When EOP-8, RPV Slowdown, is entered:

Verifies Emergency Condensers in service

Verifies open 39-05

Verifies open 39-06

Opens 4 ERVs (CT-2.0)

Event Termination

RPV Slowdown in progress Criteria Page 24 of 24 NRC Scenario 2 February 2017

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-3 Op-Test No.: LC1 15-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. ESW Pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking.

Turnover: Remove Line 4 from service per N1-0P-33A to support National Grid maintenance.

Event Malf. Event Event No. No. Type* Description N-BOP, Remove Line 4 from Service 1 N/A SRO N 1-0P-33A, Technical Specifications TS-SRO C-BOP, SRO ERV Inadvertently Opens 2 AD05 R-ATC N 1-SOP-1 .4, N 1-SOP-1.1, Technical Specifications TS-SRO C-All Powerboard 11 Electrical Fault 3 ED04 TS-SRO N1-SOP-30.1, N1-SOP-1.3, N1-SOP-1.1, Technical Specifications Steam Leak in Primary Containment 4 EC01 M-All N1-SOP-1, N1-EOP-2, N1-EOP-4, N1-EOP-8 PC10A Torus to Drywell Vacuum Breaker Inadvertently Opens 5 C-All PC10C N1-EOP-4 FW28A C- HPCI Fails to Auto-Initiate, Feedwater Pump 13 Disengages, and FW28B Core Spray Valves Fail to Auto-Open 6 BOP, FW06 SRO N1-EOP-2 CS07 C- Partial Primary Containment Isolation Failure 7 Overrides ATC, SRO N1-SOP-40.2 Containment Spray Pump 111 Trips 8 CT01A C-All N1-EOP-4

. (N)ormal, (R}eactivity, (l}nstrument, (C}omponent, (M}aior

~

,;;:-.. ~ Exelon Generation Copy of __

Training Id: NMP1 NRC 2017 Scenario 3 Revision: -0.0 ----

ERV Inadvertently Opens, Loss of PB 11, Steam Leak in Containment, HPCI & CS Fail to Auto-Initiate, Containment Isolation Partially Fails,

Title:

Containment Spray Pump Trips Signature I Printed Name

~-,d/~~*- ~....:::;, /~..----2

~,,

Developed By ~ Paul Isham 3/11/16 Validated By Kevin Hines 8/24/16 Josh House Phil Carroll

+-1 ,,,_~~__._.*-~_%_:?:?_.,,"--;_. _::_ _ _ _Pa_t_O_'B_r_ie_n 7

Facility Reviewer I"

~ / z/J 116 Page 1of26 NMPl NRC Scenario 3 February 2017

~ Exelon Generation References

1. N1-0P-33A, 115 KV System

2. N1-SOP-1 .4, Stuck Open ERV

3. N1-SOP-1 .1 , Emergency Power Reduction

4. N1-SOP-30.1, Loss of Power Board 11

5. N1-SOP-1 , Reactor Scram

6. N1-SOP-40.2, Vessel/Containment Isolation

7. N1-EOP-2, RPV Control

8. N1-EOP-4, Primary Containment Control

9. N1-EOP-1, NMP1 EOP Support Procedure

10. N1-EOP-8, RPV Slowdown

11. Unit 1 Technical Specifications Page 2 of 26 NMP1 NRC Scenario 3 February 2017

~ ExelonGeneration Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 100% power. ESW pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking. The crew will remove Line 4 from service for maintenance. The SRO will determine the Tech Spec impact.

Next, ERV 111 will inadvertently open. The crew will enter N1-SOP-1.4, Stuck Open ERV. The crew will perform an emergency power reduction to approximately 85% power, then take actions to close ERV 111 (Critical Task). These actions will close the ERV, but leave it inoperable. The SRO will determine the Tech Spec impact.

Next, Powerboard 11 will de-energize due to an electrical fault. This will cause loss of multiple major loads, including a second Recirculation pump, a Service Water pump, and a Circulating Water pump. The crew will respond per N1-SOP-30.1. This will include lowering Reactor power to restore the plant within single Circulating Water pump operating limitations. The SRO will determine the Tech Spec impact of this power loss.

Next, a steam leak will develop inside Primary Containment. The crew will scram the Reactor and execute N 1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. After the scram, Feedwater pump 13 will dis-engage early and Feedwater will fail to automatically shift to the HPCI flow-control mode on low Reactor water level. At lower Reactor pressure, Core Spray Isolation Valves will also fail to automatically open. The crew will be able to restore and maintain Reactor water level by manually injecting with preferred and alternate systems (Critical Task). Multiple primary containment isolation valves will fail to close on either manual or automatic containment isolation. The crew will be able to manually close these valves. Two Torus-to-Drywall vacuum breakers will fail open, resulting in some steam escaping from the Drywall directly into the Torus airspace. When the crew initiates Containment Spray, Containment Spray pump 111 will trip. These failures will further degrade Primary Containment pressure control. The Pressure Suppression Pressure (PSP) will be exceeded. The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).

1. Termination Criteria

a. RPV water level controlled in assigned band

b. RPV Slowdown in progress

c. Primary Containment pressure maintained per N1-EOP-4 Page 3 of 26 NRC Scenario 3 February 2017

~ ExelonGeneration

2. Critical Tasks CT-1, Given an inadvertently open ERV at power, close the ERV or insert a manual scram prior to Torus temperature exceeding 110°F, in accordance with N1-SOP-1.4 Justification:

Safety Significance: A manual Reactor scram is required before Torus temperature exceeds 1 UfF. This reduces the rate of energy production and thus heat input to the Torus. Additionally, this allows evaluating the success of the Reactor scram before boron injection would be required due to Torus temperature in the event of a failure to scram. Closing the ERV prior to the need for the scram avoids the need for these more substantial actions, prevents challenging the plant with a scram, and stops heat input to the Torus.

Cueing: ERV position, ERV acoustic monitors, ERV tailpipe temperature, Torus temperature, Reactor pressure, and steam flow indicate an open ERV. Nt-SOP-1.4 provides direction to close the ERV or scram the Reactor.

Measurable Performance Indicators: Pulling ERV fuses, directing an operator to pull ERV fuses in the field, rotating the Mode Switch to SHUTDOWN, and/or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.

Performance Feedback: ERV position, ERV acoustic monitors, ERV tailpipe temperature, Torus temperature, Reactor pressure, and steam flow will provide performance feedback regarding success of crew actions to close the ERV. Control rod position and Reactor power will provide performance feedback regarding success of crew actions to scram the Reactor.

Page 4 of 26 NRC Scenario 3 February 2017

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--=-"" Exelon Generation CT-2, Given a LOCA in the Drywell and a failure of HPCI to initiate, inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with Nl-EOP-2.

Justification:

Safety Significance: Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence. This protects the integrity of the fuel cladding.

Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level.

Nt-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems.

Measurable Performance Indicators: Manipulation of pumps and/or valves in the preferred or alternate injection system(s) will provide observable actions for the evaluation team.

Performance Feedback: Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.

CT-3, Given a LOCA in the Drywell and degraded Containment Spray capability, execute Nl-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with Nl-EOP-4.

Justification:

Safety Significance: A Blowdown is required to limit further release of energy into the Primary Containment and to ensure that the RPV is depressurized while pressure suppression capability is still available. This protects the integrity of the Primary Containment.

Cueing: Multiple Primary Containment pressure indicators and annunciators will provide indications. Nt-EOP-4 provides direction to monitor the Pressure Suppression Pressure limit and blowdown if required.

Measurable Performance Indicators: The crew will manually open valves to initiate Emergency Condensers. The crew will manually open ERVs.

Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

3. Length

a. -60 minutes Page 5 of 26 NRC Scenario 3 February 2017

~

Ji=-" ExelonGeneration

4. Mitigation Strategy Code

a. PC4, RPV Slowdown due to PSP

5. Technical Specifications

a. TS 3.6.3.b

b. TS 3.1.5.b

c. TS 3.1.8.b

6. Special Orders

a. None Page 6 of 26 NRC Scenario 3 February 2017

~

,.:::""" Exelon Generation B. Initial Conditions

1. IC Number

a. IC-153

2. Presets I With Triggers

a. Malfunctions

1) NM10A, IRM CHANNEL 11 FAILURE- UPSCALE Inserted

2) CW03B, EMERGENCY SERVICE WATER PUMP TRIP 12 Inserted

3) FW28A, HPCI MODE FAILURE TO INITIATE 11 Inserted

4) FW28B, HPCI MODE FAILURE TO INITIATE 12 Inserted

5) CS07, CS Injection Valves Failure to Auto Open Inserted

6) CT01A, CT Pump 111 Trip Inserted

7) ADOS, ERV 111 Failure - Opens Inadvertently TAG 1

8) ED04, PB 11 Electrical Fault TRG2

9) EC01, Steam Supply Line Break in PC, FV=11 % TRG3

10) FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS - DISENGAGES, TRG23 OT =20 seconds

11) PC1 OA, BV 68-01 Fails Open, Delay= 30 sec TRG23

12) PC1 OC, BV 68-03 Fails Open, Delay=30 sec TRG23

b. Remotes

1) AD01 A, ERV 111 Fuses, Pulled TRG27

2) AD07, Acoustic Monitor Alarm Reset, RESET TRG28

c. Overrides

1) 11$33015423, SET 1010 RPS CH.11 BYPASS SW, FV=on (Partial primary Inserted containment isolation failure)

2) 11$34015424, SET 1010 RPS CH.12 BYPASS SW, FV=on (Partial primary Inserted containment isolation failure)

Page 7 of 26 NRC Scenario 3 February 2017

~

ExelonGeneration

d. Annunciators

1) None

e. Event Triggers Event# Event Action Command TRG 23 - Initiates when the mode switch is taken to zdrpstdn==1 imf ec01 (0 0) 30 4:00 11 SHUTDOWN TRG 24 - Initiates when Containment Spray flow is ctfdw>100 imf ec01 (0 0) 45 1:00 30 initiated

f. Equipment Out of Service

1) ESW Pump 12 in PTL with info tag

2) IRM 11 bypassed with info tag and off normal

g. Support Documentation

1) N1-0P-33A Section H.12 marked up to Step H.12.9.

h. Miscellaneous

1) Ensure Drywell cooling fan 11 is secured with control switch in neutral.

2) Protect the following equipment: EDG102, EOG 103, PB 102, PB 103, Line 1, MOD 8106.

Page 8 of 26 NRC Scenario 3 February 2017

--=-"" Exelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N ID DATE: _T_o_d_a_._y_ __

PARTI: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor power is approximately 100%.

ESW Pump 12 is out of service for maintenance

IRM 11 is bypassed due to spiking PART 111: Remarks/Planned Evolutions:

Remove Line 4 from service per N 1-0P-33A Section H.12 to support National Grid maintenance. The procedure has been completed up to Step H.12.9.

Page 9 of 26 NRC Scenario 3 February 2017

~ ExelonGeneration Shift Turnover Instructor Actions I Plant Response Operator Actions Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the Crew panels.

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 10 of 26 NRC Scenario 3 February 2017

.="1!' Exelon Generation Event #1: Remove Line 4 From Service Event

Initial reactor power is -100%

Information

The crew will remove line 4 from service SRO

Directs removing Line 4 from service per N1-0P-33A Section H.12

Provides oversight for evolution

Determines Technical Specification 3.6.3.b requires returning Line 4 to service within 7 days.

Reviews N1-0P-33A Section H.12

(step H.12.9) Verifies Auto Reclosure for R-40 breaker is OFF Role Play: When asked as Operator to confirm R40

Opens breaker R-40 position, immediately report all three phases of R-40

Dispatches Operator to confirm R-40 open locally are open.

on ALL 3 phases Role Play: If requested as Power Control, report the

Notifies SM to review TS for appropriate LCO ow Voltage Post Contingency Alarm is clear.

applicability

Continues at Section H.9.0, Loss of 115 KV Line 4

ATC

Monitors plant parameters

Provides peer checks as needed Page 11 of 26 NRC Scenario 3 February 2017

&~ Exelon Generation Event #2: ERV 111 Inadvertently Opens Event

ERV 111 Inadvertently Opens Information

Operators will respond per SOP-1.4 to attempt to shut the ERV and SOP1 .1 to lower power.

The ERV will shut when fuses are pulled When directed by lead examiner, insert CREW malfunction:

Acknowledges/reports annunciators

Diagnoses ERV 111 has inadvertently opened ADOS, ERV 111 Failure - Opens Inadvertently TRG 1 ERV 111 opens Reactor pressure lowers slightly Reactor power lowers and then rises slightly Torus temperature rises Torus level rises Expected annunciators:

F1-4-8, STEAM LINE DETECTION SYS FLOW OFF NORM F2-4-1, MAIN STM LINE ELECTROMATIC RELIEF VALVE OPEN H3-4-5, PRESS SAFETY/RELIEF VALVES FLOW Page 12 of 26 NRC Scenario 3 February 2017

,.="1"" Exelon Generation SRO Event 2 continued

Acknowledges reports

Directs entry into N1-SOP-1.4, Stuck Open ERV

Directs emergency power reduction to approximately 85% power

Provides oversight for reactivity manipulation

Determines that ERV 111 is inoperable per TS 3.1.5.b, requiring a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown

Directs taking action to close ERV 111 or directs a manual scram prior to Torus temperature exceeding 110°F, in accordance with N1-SOP-1.4 CT-1

Acknowledges that ERV 111 has closed

Enters N1-EOP-4 if Torus temp rises above 85°F or Torus level rises above 11.25'

- Directs Containment Spray to PTL

May direct initiation of Torus Cooling per N 1-EOP-1att16 or N1-SOP-1.4 ATC

Performs emergency power reduction per N1-SOP-1.1

Reduces Recirculation master controller to lower power to approximately 85%

Monitors APRMs

Monitors Recirculation flow

Monitors Feedwater flow and RPV water level

Monitors position on power to flow map

If Torus temperature approaches 110°F, inserts manual Reactor scram CT-1 Page 13 of 26 NRC Scenario 3 February 2017

IJ~ ExelonGeneration Event 2 continued BOP

Enters N1-SOP-1 .4 Role Play: When directed as Operator to go to

Determines ERV 111 is open using:

Auxiliary Control Room and verify ERV 111 is open, - Valve indicating lights on F panel wait one minute and report ERV 111 is open. - Red ERV flow indicating light on F panel Subsequent reports on acoustic monitor status may

Sends an operator to the Aux Control Room to be given immediately, with close attention paid to the actual status of the ERV. verify ERV open using Acoustic Monitor

May send an operator to RB 237' to standby for pulling local ERV fuses

Attempts to close ERV 111 by performing one or Note: Safety glasses, gloves, and long sleeves or a all of the following:

lab coat are required for pulling fuses in F panel. Depresses ADS Timer Reset pushbuttons Cycles Control Switch for ERV 111 Pulls control power fuses F15 and F30 in F panel (ERV 111)

Role Play: If the Operator is directed to pull fuses in o OR the RB wait 3 minutes and insert remote: Directs operator to pull ERV 111 fuses on AD01 A, ERV 111 Fuses, FV=pulled RB 237' CT-1 TRG27

Checks with operator in Aux Control Room to see Report fuses are pulled.

if ERV is still open

Determines/verifies ERV closes

Directs reset of acoustic monitor

Notifies crew that ERV 111 has closed Role Play: When directed as operator to reset the acoustic monitor, wait 1 minute and insert remote:

Monitors Torus temperature AD07, Acoustic Monitor Alarm Reset, FV=reset

Reports if/when Torus temperature exceeds 85°F or Torus level exceeds 11.25' TRG28 Places Containment Spray pumps in PTL if Report acoustic monitor is reset. directed Page 14 of 26 NRC Scenario 3 February 2017

~

~ ExelonGeneration BOP continued

Places Torus cooling in service when directed, per N1-SOP-1.4, att 2 or N1-EOP-1att16:

Close CONT SPRAY BYPASS BV(s) for selected loop Verifies closed 80-115 Verifies closed 80-114 Verifies closed Cont Spray Discharge IV for selected loop Verifies open CONT SPRAY BYPASS BV for selected loop Fully opens80-118 Starts Containment Spray Raw Water pump in selected loop Starts Containment Spray pump in selected loop Page 15 of 26 NRC Scenario 3 February 2017

~ ExelonGeneration Event #3: Powerboard 11 Electrical Fault Event

4160V Power board 11 de-energizes and will not be available for the remainder Information of the scenario.

When directed by lead examiner, insert CREW malfunction:

Diagnose/report loss of PB 11

Recognize/report loss of:

ED04, PB 11 Electrical Fault

Reactor Recirculation Pump 11 /12 TRG2

Drywall Fans 14, 15, 16

Condensate Pump 11

Circulating Water Pump 11 Reactor power lowers due to RRP trips

Service Water Pump 11 Reactor water level rises due to RRP trips

RBCLC Pump 11 Expected Annunciators:

TBCLC Pump 11 A4-1-1, PB 11 R113 TRIP

IAC 11 A4-4-2, POWER BO 16 LOW BUS VOLTAGE

Reactor Building Exhaust Fan 11 L 1-3-4, REACT BLDG/ATM DIFF PRESS

Recognize/report drop in Reactor power

Recognize/report lowering condenser vacuum Also the following equipment trips:

Recognize/report loss of Reactor Building D/P Reactor Recirculation Pump 11112 Drywel/ Fans 14, 15, 16 Condensate Pump 11 Circulating Water Pump 11 Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11

!AC 11 Reactor Building Exhaust Fan 11 Page 16 of 26 NRC Scenario 3 February 2017

~

,._.,., ExelonGeneration SRO

Acknowledges reports from crew

Directs entry into N1-SOP-30.1

Directs Emergency Power Reduction per N1-SOP-1.1 to stabilize condenser vacuum, as necessary

Provides oversight for reactivity manipulation

Directs entry into N 1-SOP-1 .3, Recirculation Pump Trip

Directs RO to re-energize Powerboards 16A and 13A-15A

May enter N1-EOP-5, Secondary Containment Control, on loss of Reactor Building D/P

Directs restoration of Reactor Building D/P with either RBVS or RBEVS

May direct entry into N1-SOP-6.1 for loss of Spent Fuel Pool Cooling, as time permits

Reviews Technical Specifications

Acknowledges that the APRMs are inoperable while the RRP discharge valves are still open

Determines Technical Specification 3.1.7.e limits Note: On the loss of Powerboard 11, Recirc pumps Reactor power to 90% in 3 loop operation 11 and 12 trip. The APRMs are inoperable due to reverse flow through the tripped Recirc loops. The

Determines Core Operating Limits Report APRMs will be declared operable once the discharge (COLR) requires APLHGR and MCPR penalties valves are closed.

Determines Technical Specification 3.1.8.b is entered again for loss of power to Feedwater pump 11 and Condensate pump 11

May enter EOP-4 if OW conditions permit.

Page 17 of 26 NRC Scenario 3 February 2017

4~ Exelon Generation ATC

Acknowledges direction from SRO

Confirms plant is stable by verifying:

- No thermal hydraulic Instability

- 3 Recirc pumps running

- Not operating in the Restricted Zone

Executes N 1-SOP-1.1, Emergency Power Reduction, to lower recirc flow and/or insert CRAM rods to stabilize condenser vacuum, as required

Determines plant operating point on the 3-loop power to flow curves Role Play: BOP If dispatched to investigate Powerboard 11, wait 2

Executes N1-SOP-30.1, Loss of Power Board 11 minutes then report that the normal supply breaker

Starts Service Water pump 12 (R113) tripped on overcurrent.

Coordinates with ATC to monitor APRMs and If dispatched to investigate Powerboard 16A, wait 2 LPRMs minutes then report that there are no problems

Verifies TBCLC pump 12 running evident at Powerboard 16. Report that electrical

Verifies IAC 12 and/or 13 running maintenance has also looked at the Powerboard and

Verifies RBCLC pump 12 running concurs with re-energizing it.

Verifies Steam Packing Exhauster 12 running

Answers "Are A4-4-6, A4-4-7, A4-1-3 OR A5-2-8 Role Play: in alarm" YES If dispatched to lineup Steam Packing Exhauster 12, Determines Power Board 11 is faulted and cannot be wait 4 minutes, then insert remote: reenergized MS09, SPE 12 SUCTION VLV, FV=open Then report task completion.

If asked to also close suction valve to Steam Packing Exhauster, wait 2 minutes, then insert remote:

MSOB, SPE 11 SUCTION VLV, FV=close Then report task completion.

Page 18 of 26 NRC Scenario 3 February 2017

~

~ ExelonGeneration.

Event 3 continued BOP continued

Restores power to Powerboard 16A as follows:

Opens R1041

Closes R 1042

Verifies Power Board 16B amps <962

Dispatches operator to re-energize Power Boards Role Play: As operator when directed to energize 13A, 14A, and 15A Powerboards 13A-15A, acknowledge order. If asked about status during remainder of scenario, report that

Notifies SRO that APRMs are inoperable you are being briefed by the WEC.

Closes Recirc pump 11 and 12 discharge valves

Holds open for 2-3 seconds Recirc pump 11 and 12 discharge valve

Records time when Recirc pump 11 and 12 discharge valve is cracked open

Executes N1-SOP-1.3, Recirc Pump Trip, as time Role Play: As operator when directed to restore permits Offgas vacuum pump, acknowledge order. If called

Dispatches operator to restore Offgas Vacuum for a status on actions, report that you are being Pump briefed by the WEC.

Enters N1-SOP-6.1 for loss of Spent Fuel Pool Cooling, as time permits Role Play: As operator when directed to investigate Dispatches operator to investigate loss of Spent Fuel Spent Fuel Pool Cooling, wait 3 minutes and then Pool Cooling, as time permits report that SFPC pump 11 has tripped.

Page 19 of 26 NRC Scenario 3 February 2017

~

~ ExelonGeneration Event 3 continued BOP continued

Respond to either annunciator (or as directed by SRO) and restore RB D/P:

L1-1-5,RBVENTEXHFAN11-12TRIP-VIB o Verifies closed Reactor Building Exhaust Fan 11 outlet damper o Starts Reactor Building Exhaust Fan 12

L1-3-4, REACT BLDG/ATM DIFF PRESS o Starts RBEVS per OP-10 Possible actions in OP-1 O Section H.1.0 to start RBEVS

Verifies open 202-36, EM VENTILATION FROM REACTOR BLDG BV

Verifies closed the following valves:

202-47, EM VENTILATION TIE BV

202-74, EM VENTILATION LOOP 11 COOLING BV

202-75, EM VENTILATION LOOP 12 COOLING BV

Places 202-37(38), EM VENTILATION LOOP 11 (12) INLET BV control switch to OPEN

Verifies open 202-37(38), EM VENTILATION LOOP 11(12) INLET BV

Starts 202-53(33), EVS FAN 11 (12)

Verifies open 202-34(35), EM VENT EXHAUST FAN 11(12) OUTLET BV

Confirms proper operation of 202-50(51 ), EM VENT EXHAUST FAN 11 (12) INLET FCV, by Role Play: As RP, acknowledge report that RBEVS observing indicating lights and flow indication is in service and RBVS is secured.

Notifies Rad Protection that the Reactor Building Emergency Ventilation system is in service Page 20 of 26 NRC Scenario 3 February 2017

'~ Exelon Generation Event #4, #5, #6, #7, #8: Steam Leak Inside Primary Containment, Vacuum Breaker Fails Open, Failure of HPCI to Auto-Initiate, Partial Primary Containment Isolation Failure, and Trip of Containment Spray Pump 111 Event

A steam leak develops in the Primary Containment Information

The crew will scram the reactor

Feedwater fails to operate in HPCI mode, so the crew will need to operate manually

Primary containment parameters are complicated by Torus to Drywell vacuum breakers opening and the partial failure of the containment to isolate.

The crew will need to blow down the reactor in an attempt to avoid violating PSP.

When directed by the lead examiner, insert CREW malfunction:

Diagnose/report degrading containment parameters EC01, Steam Supply Line Break in PC, FV=11

Acknowledge/report annunciators TRG3

Diagnose failure of HPCI to automatically initiate Drywell humidity, pressure and temperature rise

Diagnose partial failure of primary containment Drywell leakage rises Expected annunciators: isolation H2-1-1, Drywell Floor Drain Level High

Diagnose the trip of Containment Spray pump H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low 111 F1-1-5(4-1-4), RPS Ch 11(12) Drywell Press High Verify the following malfunctions are preset:

FW28A, HPCI Mode Failure to Initiate 11 FW28B, HPCI Mode Failure to Initiate 12 CT01 A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open Feedwater pump 12 running but not injecting RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray IVs do NOT open at 365 psig Expected annunciator:

Page 21 of 26 NRC Scenario 3 February 2017

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&: ::""!' Exelon Generation K1-1-7, Containment Spray Pump 111 Trip Fail to Run Events 4, 5, 6, 7 & 8 continued SRO

Acknowledges reports Verify the following malfunctions automatically

Directs manual scram insert when the mode switch is taken to

Acknowledges scram report SHUTDOWN:

Enters N1-EOP-2 on low RPV water level

Directs N1 -SOP-1 actions FW06, SHAFT DRIVEN FEEDWATER PUMP

Directs RPV water level controlled 53-95" with CLUTCH FAILS - DISENGAGES, Delay=20 Condensate/FW and CRD seconds

When notified of the failure of HPCI to initiate, EC01, Steam Supply Line Break in PC, IV=11, directs manual control of Feedwater RT=4:00, FV=30 (preferred and alternate injection systems)

PC1 OA, BV 68-01 Fails Open, Delay=:30 CT-2 PC1 OC, BV 68-03 Fails Open, Delay=:30 TRG23

Directs RPV pressure controlled 800-1000 psig with Turbine Bypass Valves or Emergency Containment conditions further degrade Condensers Feedwater pump 13 disengages

May direct closure of MSIVs to limit cooldown rate Reactor water level remains low

Enters N 1-EOP-4 due to high drywell pressure Two Torus-to-Drywel/ vacuum breakers indicate open and temperature Expected annunciator: o Direct lockout of Containment Spray pumps

Re-enters N1-EOP-2 due to high drywell K1-4-6, Torus-OW Vac Relief Check Valve Open pressure

Directs execution of N1 -SOP-40.2 for isolation verification

Acknowledges partial failure of primary Verify the following overrides are PRESET to cause containment isolation partial primary containment isolation failure:

Directs/acknowledges manual closure of primary 11S33Dl5423, SET 1010 RPS CH.11 BYPASS SW, containment isolation valves FV=on 11S34Dl5424SET1010 RPS CH.12 BYPASS SW, FV=on Page 22 of 26 NRC Scenario 3 February 2017

~ ExelonGeneration Verify the following malfunction automatically SRO continued inserts when Containment Spray flow is initiated to

When Torus pressure exceeds 13 psig or the Drywall:

Drywall temperature approaches 300°F:

EC01, Steam Supply Line Break in PC, IV=30,

Answers "Below the Containment Spray RT =1 :00, FV=45 Initiation Limit?" - Yes

Verifies all Recirc pumps tripped

Directs trip of all Drywall cooling fans

Directs operation of Containment Spray per N 1-EOP-1 attachment 17

Evaluates/monitors position on Pressure Suppression Pressure curve

Acknowledges report of Containment Spray pump 111 trip

May direct rapid depressurization with ECs in anticipation of RPV Slowdown

Determines Torus pressure cannot be maintained within Pressure Suppression Pressure limit

Enters N1-EOP-8, RPV Slowdown CT-3

Answers "Are all control rods inserted to at Note: Core Spray injection will only be prevented if least 04 ?" YES not needed for core cooling. If the crew has not yet

Answers "Drywall pressure?" At or above 3.5 re-established RPV injection when this step is psig evaluated, the Core Spray jumpers may not be installed until later. EOP-2 step P-1 provides

May direct prevention of Core Spray injection per N1-EOP-1 attachment 4 continuous guidance for this consideration.

Directs EC initiation

Answers "Torus water level?" Above 8.0 ft

Directs open 4 ERVs Page 23 of 26 NRC Scenario 3 February 2017

~ ExelonGeneration Events 4, 5, 6, 7 & 8 continued ATC

Monitors plant parameters

When directed, places Mode Switch in Shutdown

Provides scram report

Performs N1-SOP-1, Reactor Scram, scram verification actions

Places IRMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary to monitor power decrease

If recirc pumps have not yet tripped, reduces recirc flow to 25-43 Mlbm/hr

Maintains RPV pressure below 1080 psig and in assigned band

Executes N1-SOP-40.2

Recognizes/reports failure of multiple primary containment isolation valves to automatically close

Manually closes the following valves:

201.7-01 & 02, 201.2-110 & 111, 201.2-109 & 112 (11 H202)

201.2-23 & 24, 201.2-29 & 30 (12 H202)

The failed primary containment isolation valves are

201.7-08 & 09, 201.7-10 & 11 (Drywell controlled by three control switches. CAM)

Reports primary containment isolation valves have been manually closed Page 24 of 26 NRC Scenario 3 February 2017

,a~ ExelonGeneration Events 4, 5, 6, 7 & 8 continued BOP

Monitors/reports degrading Containment parameters

Performs RPV water level control actions of N1-SOP-1, Reactor Scram:

Restores RPV level to 53-95" by controlling injection and rejecting through RWCU

Determines #13 FWP was running

Determines RPV water level is recovering

Terminates 13 FWP injection as follows:

Closes 13 FWP VALVE CONTROL

Disengages 13 FWP

Closes 29-10, Feedwater Pump 13 Note: Feedwater level control actions will vary Blocking Valve depending on when the operator diagnoses the

Verifies RPV water level above 53" failure of HPCI to automatically control injection

Verifies 11/12 FWP controllers in MANUAL through Feedwater flow control valves 11 and 12.

and set to zero output

Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches

If RPV level reaches 85 inches and rising, then:

Verifies off all FW Pumps

Secures CRD Pumps not required

Diagnoses failure of HPCI to automatically initiate

Notifies SRO/Crew of HPCI failure

Manually controls RPV injection to restore and maintain level CT-2 Page 25 of 26 NRC Scenario 3 February 2017

=-"' Exelon Generation Events 4, 5, 6, 7 & 8 continued ATC/BOP

Places Containment Spray pumps in PTL

Closes MSIVs, as directed

Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F

Verifies Recirc pumps tripped

Trips Drywell cooling fans

Initiates Containment Spray per N1-EOP-1 attachment 17

Diagnoses/reports Containment Spray pump 111 trip

Verifies started Containment Spray pumps 121 and 122 Note: Core Spray pumps may be placed in PTL if

If 80-118 is open for Torus Cooling:

needed before EOP-1 attachment 4 jumpers can be

Opens 80-35 installed due to scenario progression and resource

Closes80-118 limitations. If Core Spray pumps are placed in PTL,

Verifies open 80-40 and 80-45 at least one Core Spray pump should be restarted

Prevents Core Spray injection installing N 1-EOP-after jumper installation for App J water seal. Core 1 attachment 4 jumpers (17, 18, 19, 24, 25, 26), if Spray may also be used as an alternate injection directed source.

Initiates both ECs

Opens 4 ERVs CT-3 Event

RPV water level controlled in assigned band Termination

RPV Slowdown in progress Criteria

Primary Containment pressure maintained per N 1-EOP-4 Page 26 of 26 NRC Scenario 3 February 2017

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-4 Op-Test No.: LC1 15-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 95% power. ESW Pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking.

Turnover: Start TBCLC Pump 12 and secure TBCLC Pump 11. Then, raise Reactor power to 98%

with Recirculation flow.

Event Malf. Event Event No. No. Type* Description N- Swap Running TBCLC Pumps 1 N/A BOP, SRO N1-0P-24 R- Raise Reactor Power with Recirculation Flow 2 N/A ATC, SRO N 1-0P-1, N 1-0P-43B I-ATC, APRM #13 fails upscale, half scram, bypass.

3 NM19A SRO ARP Tech Spec TS-SRO RD36A C-BOP, Control Rod Drive Flow Control Valve 44-151 fails closed, requiring 4 SRO shifting to the alternate FCV TS-SRO N1-SOP-5.1, Tech Spec C-BOP, Service Water Adams Strainer 11 High D/P 5 CW16A SRO N1-0P-18, ARP H1-3-2 C-ATC, Loss of main condenser vacuum 6 MC01 SRO N1-SOP-25.1, N1-SOP-1.1, N1-SOP-1 ATWS 7 RD33 M-ALL N1-EOP-2, N1-EOP-3 All Turbine Bypass Valves Fail Closed 8 TC12 C-ALL N1-EOP-8 FW03A Motor Driven Feedwater Pumps Fail 9 C-ALL FW03B N1-EOP-8

. (N)ormal, (R)eactivitv, (l)nstrument, (C)omponent, (M)ajor

~

~~ "" Exelon Generation.

Copy of __

Training Id: NMP1 NRC 2017 Scenario 4 Revision: 0.0 Swap TBCLC Pumps, APRM Upscale Failure, CRD FCV Failure, Adams

Title:

Strainer Clogging, Loss of Condenser Vacuum, ATWS without TBVs re Printed Name Developed By ~--------

_,,. ~ Paul Isham 3/11/16 Validated By Kevin Hines 8/24/16 Josh House Phil Carroll Facility Reviewer Pat O'Brien Page 1of29 NMPl NRC Scenario 4 February 2017

ExelonGeneration References

1. N1-0P-24, TBCLC Water System

2. N1-0P-1, NSSS

3. N1-0P-18, Service Water System

4. N1-0P-43B, Normal Power Operations

5. N1-SOP-1 .1 , Emergency Power Reduction

6. N1-SOP-5.1, Loss of Control Rod Drive

7. N1-SOP-1 , Reactor Scram

8. N1-SOP-25.1, Unplanned Loss of Condenser Vacuum

9. N1-EOP-2, RPV Control

10. N1-EOP-3, Failure to Scram

11. N1-EOP-1, NMP1 EOP Support Procedure

12. N1-EOP-8, RPV Slowdown

13. Unit 1 Technical Specifications Page 2 of 29 NMP1 NRC Scenario 4 February 2017

Ji=-- Exelon Generation Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 95% power. ESW pump 12 is out of service for maintenance. IRM 11 is bypassed due to spiking. The crew is to start TBCLC pump 12 and secure TBCLC pump 11 per N1-0P-24 section F.1. After the TBCLC pumps are successfully shifted, the crew will raise reactor power with recirc.

Then, APRM 13 will fail upscale causing a half scram. The crew will bypass the APRM and reset the half scram.

The US will make a Tech Spec call. When the half scram is reset, the Control Rod Drive Flow Control Valve fails closed, requiring shifting to the alternate FCV. After CRD flow is returned to normal, Service Water Adams Strainer 11 will clog, resulting in a high D/P annunciator in the control room. The crew will dispatch an Operator to manually backwash the strainer. When this is unsuccessful at clearing the alarm, the crew will place Service Water pump 12 in service.

Main condenser vacuum will begin to degrade as a result of air in-leakage. The crew will enter N1-SOP-25.1.

Power will be lowered per N1-SOP-1.1 and the reactor will be scrammed before vacuum lowers to 22.1" Hg.

When the scram is inserted, control rods will only partially insert. The crew will enter N1-EOP-3 to respond to the failure to scram. The crew will terminate and prevent all injection except boron and CRD (Critical Task).

The ATWS will be complicated with the failure of TBVs to open. The crew will initiate liquid poison injection and/or take actions in accordance with N1-EOP-3.1 to insert control rods (Critical Task).

1. Termination Criteria

a. RPV water level controlled in assigned band above -109"

b. RPV Slowdown in progress, Liquid Poison injection or control rod insertion in progress Page 3 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration

2. Critical Tasks CT-1, Given a failure of the Reactor to scram with power above 6% and RPV water level above -41 inches, the crew will terminate and prevent all injection except boron and CRD, in accordance with N1-EOP-3.

Justification:

Safety Significance: High Reactor power after a scram is attempted indicates a challenge to nuclear fuel and to plant heat sinks. In the event of a loss of the normal heat sink, this may result in adding heat to the Torus and challenging the Primary Containment. Lowering Reactor power reduces these challenges.

Cueing: Control rod position and Reactor power indications will indicate a failure to scram with Reactor power above 6%.

Nt-EOP-3 provides direction to terminate and prevent injection based on Reactor power.

Measurable Performance Indicators: Manipulation of Feedwater system components and Core Spray jumpers will provide observable actions for the evaluation team.

Performance Feedback: Feedwater flow, Reactor water level, and Reactor power will provide performance feedback regarding the success of crew actions.

CT-2, Given a failure of the reactor to scram with power above 6%, the crew will lower reactor power by inserting control rods or injecting boron, in accordance with N1-EOP-3.

Justification:

Safety Significance: Inserting control rods lowers Reactor power, which reduces challenges to the plant during a failure to scram. Additionally, inserting control rods ultimately provides a long-term, stable core shutdown. Boron injection will lower power, however, alone may not provide a stable shutdown condition.

Cueing: Control rod position and Reactor power indications will indicate a failure to scram. Nt-EOP-3 provides direction to insert control rods or inject Boron.

Measurable Performance Indicators: Manipulation of RPS, CRD, liquid poison, and RMCS controls will provide observable actions for the evaluation team.

Performance Feedback: Control rod position and Reactor power will provide performance feedback regarding success of crew actions to insert control rods or inject poison .

Page 4 of 29 NRC Scenario 4 February 2017

--~ ExelonGeneration CT-3, Given a failure to scram and the inability to restore and maintain RPV water level above -109 inches with the preferred ATWS injection systems, the crew will execute N1-EOP-8, RPV Slowdown and restore and maintain RPV water level above -109 inches with preferred and alternate ATWS injection systems, in accordance with N1-EOP-3.

Justification:

Safety Significance: Reactor water level must be maintained above limits to ensure adequate core cooling. With only low pressure systems available to inject and Reactor pressure above the pressure limits of these systems, Reactor pressure must be quickly lowered to allow injection. This protects the integrity of the fuel cladding.

Cueing: Multiple Reactor water level and pressure indications and annunciators will indicate low Reactor water level with Reactor pressure too high for available injection systems to inject. Nt-EOP-3 provides direction to initiate a blowdown.

Measurable Performance Indicators: Manipulation of Emergency Condenser valve and ERV control switches will provide observable actions for the evaluation team.

Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown. Multiple level indications will provide feedback of the success of the A TWS low pressure injection systems.

3. Length

a. -60 minutes

4. Mitigation Strategy Code

a. AT2, High Power ATWS, RPV Slowdown due to Low Reactor Water Level

5. Technical Specifications

a. TS 3.1.6 CRD

b. 3.1.7.e

c. 3.1.8

6. EAL Classification

a. FS1.1

7. Special Orders

a. None Page 5 of 29 NRC Scenario 4 February 2017

--=' ExelonGeneration B. Initial Conditions

1. IC Number

a. IC-154

2. Presets I With Triggers

a. Malfunctions

1) NM10A, IRM CHANNEL 11 FAILURE- UPSCALE Inserted

2) CW038, EMERGENCY SERVICE WATER PUMP TRIP 12 Inserted

3) RD33A, Control Rod Bank Blocked Bank 1, FV=24 Inserted

4) RD33B, Control Rod Bank Blocked Bank 2, FV=18 Inserted

5) RD33C, Control Rod Bank Blocked Bank 3, FV=22 Inserted

6) RD33D, Control Rod Bank Blocked Bank 4, FV=18 Inserted

7) RD33E, Control Rod Bank Blocked Bank 5, FV=24 Inserted

8) TC12, All Bypass Valves Fail Closed (0-100%) Inserted

9) FW03A, Feedwater Pump Trip 11 Inserted

10) FW038, Feedwater Pump Trip 12 Inserted

11) NM19C, APRM Channel 13 Failure - Upscale TRG 1

12) RD36A, CRD FCV 44-151 FAILURE-CLOSED TRG2

13) CW16A, SW Pump 11 Strainer 72-05 Clogging, FV=10% TRG4

14) MC01, Main Condenser Air lnleakage, FV=13.5 TRG5

15) FW06, Shaft Driven Feedwater Pump Clutch Fails - Disengage TRG6

b. Remotes

1) FW24, Removal of HPCI Fuses FU8/FU9, FV=pulled TRG 10

2) ROOS, CRD FLOW CONTROL VALVE ISOL, FINAL VALUE=nc30b TRG 16

c. Overrides

1) None Page 6 of 29 NRC Scenario 4 February 2017

~

*

Exelon Generation

d. Annunciators

1) None

e. Event Triggers Event# Event Action Command TRG 6, Activates 13 FWP disengage action when zarrlc11 <0.37 Blank Reactor water level is below -41 inches.

TRG 16, Swaps CAD FCV when operator operates zdrdfcvb==1 Blank switch in Control room

f. Equipment Out of Service

1) ESW Pump 12 in PTL with info tag

2) IRM 11 bypassed with info tag and off normal

g. Support Documentation

1) ReMA for raising power with recirc

h. Miscellaneous

1) None Page 7 of 29 NRC Scenario 4 February 2017

~

ExelonGeneration SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N ID DATE: _;T:. .;:o:;. ;:d=a:. 1-v_ __

PARTI: To be performed by the oncoming Operator before assuming the shift.

Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

LCO Status (SRO)

Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:

Reactor power is approximately 95%.

ESW Pump 12 is out of service for maintenance

IRM 11 is bypassed due to spiking PART Ill: Remarks/Planned Evolutions:

Start TBCLC pump 12 and secure TBCLC pump 11, per N1-0P-24 section F.1. An operator is standing by at the pump. Three Heat Exchangers are in service. Pump venting is not required.

Raise reactor power with recirc per the ReMA Page 8 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration Shift Turnover Instructor Actions I Plant Response Operator Actions Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

Verify annunciator sound turned on

If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown the Crew panels.

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 9 of 29 NRC Scenario 4 February 2017

'!" Exelon Generation Event #1

Swap TBCLC Pumps Event

Crew will start TBCLC Pump 12 and secure TBCLC pump 11 Information NOTE: The crew may hesitate to perform the pump SRO swap based on the notes outlining TBCLC and SW

Directs starting TBCLC pump 12 and securing parameters in the beginning of the procedure. If TBCLC pump 11 per N1-0P-24, Sect F.1.0 asked, report that the parameters are within

Provides oversight for evolution acceptable range.

RO

Monitors plant parameters BOP

Reviews N 1-0P-24, Sect F.1.0

Starts TBCLC pump 12

May direct operator to vent TBCLC pump 12 and Role Plays: If directed to vent TBCLC pump 12, wait close the vent when venting is complete 30 seconds and report that the pump has been

Monitors system pressure and pump amps vented.

Stops TBCLC Pump 11 and place its control switch in Auto-Start If asked about TBCLC pump starts/stops,

Notifies the SRO/Crew that TBCLC pump 12 is in immediately report SAT pump starts/stops. service and TBCLC pump 11 in standby Page 10 of 29 NRC Scenario 4 February 2017

,Ji=-- Exelon Generation Event #2: Raise Reactor Power with Recirculation Flow Event

Crew will raise power per the provided ReMA Information SRO

Directs power ascension with Recirculation flow in accordance with N1-0P-438 and the ReMA

Provides oversight of reactivity maneuver ATC Note: When sufficient reactivity change has been

Acknowledges direction from SRO observed, move on to the next event per the lead

Raises Recirculation flow with master examiner's discretion. Recirculation flow controller

Monitors APRMs

Monitors Recirculation flow

Monitors Feedwater flow and RPV water level

Observes power-to-flow map restrictions BOP

Monitors individual RRPs for response

Individual MIA-Speed Control stations trending uniformly

Individual RRP indications trending normally for speed increase

Monitors Feedwater controls for proper response

FWP 13 FCV responding to power change

RPV water level remains within program band (65" - 83")

Page 11 of 29 NRC Scenario 4 February 2017

-' Exelon Generation Event #3

APRM 13 Upscale Failure Event

APRM 13 fails upscale Information

Crew bypasses APRM and resets half scram IAW ARPs When directed by examiner, insert malfunction: ATC NM19C APRM CHANNEL 13 FAIL UPSCALE

Recognize/report RPS Channel 11 trip TRG 1

Reports APRM 13 Upscale APRM 13 Fails Upscale The following annunciators alarm F2-1-6APRM 11-14 F1-1-1 RPS CH 11 REACT NEUTRON MONITOR F1-2-1 RPS CH 11 REACTOR AUTO TRIP F3-4-4 ROD BLOCK Role Play: As WEC/Mgmt. acknowledge report from SRO SRO. Advise that you will provide requested assistance.

Acknowledges report from RO

Directs RO/BOP to follow ARPs for failed APRM, Half-SCRAM and ROD BLOCK The APRM will not be repaired during the scenario.

Contacts WEC/Management and informs them of failed instrument. Requests assistance in correcting problem.

Reviews Technical Specifications for impact of failed instrument.

0 TS 3.6.2.a requires 2 operable trip systems and 3 operable channels per Note: Technical Specification requirements from system to cause a SCRAM on High Flux Tables 3.6.2.a and 3.6.2.g are satisfied with only one APRM failed. 0 TS 3.6.2.g requires 2 operable trip systems and 3 operable channels per system to initiate a ROD BLOCK on High Flux

Determines that APRM 13 may be bypassed

Directs RO to bypass APRM 13 and reset RPS Channel 11 trip.

Page 12 of 29 NRC Scenario 4 February 2017

..~ ExelonGeneration Event 3 continued BOP

Acknowledges direction from SRO

Obtains ARP F2-1-6 and executes 0 Verifies alarm computer points B183 (ROD BLOCK) and D052 (UPSCALE HIHI FLUX) 0 Observes LPRM-APRM Auxiliaries Drawer (Panel "G") and determines that APRM 13 has an upscale condition 0 If required, bypass APRM per N1-0P-38C.

Obtains/reviews ARP F1 1 0 Confirm RPS Channel 11 tripped 0 Confirms other channel readings are normal/

0 Obtains/reviews ARP F1 1 0 Determines that failed APRM caused trip 0 When cause is corrected (APRM is bypassed), reset RPS Channel 11

Obtains/reviews ARP F3-4-4 0 Confirms alarm by observing computer point C067 RWM ROD BLOCK 0 Determines caused by failed APRM

When directed to verify APRM 13 bypassed, observes APRM 13 bypass light on Panel "G" (LPRM-APRM AUXILIARIES DRAWER)

Note: When APRM 13 is bypassed F2-1-6, F3-4-4 ATC and F1 1 should all clear.

Completes RO actions for ARP F2-1-6 The LPRM-APRM Auxiliaries drawer will indicate the

Determines that APRM 13 has UPSCALE/HI-HI HIHI condition until the APRM is bypassed then the condition BYPASS indicating light will also be illuminated.

Monitors other APRM channels to determine that power is stable/unchanged Following the bypassing of APRM 13 and the reset of the half-scram, all annunciators will be clear.

Verifies proper power to flow ratio on 5-Loop Operating Curve Page 13 of 29 NRC Scenario 4 February 2017

~

~** Exelon Generation Event 3 continued BOP

Bypasses APRM 13 per N 1-0P-38C Bypass APRM

Places APRM BYPASS joystick on Panel "E" to "APRM 13" position

Confirm APRM BYPASS light lit on E Panel.

Confirm APRM BYPASS light lit on LPRM-APRM auxiliaries drawer (G Panel).

Confirm computer printout "APRM BYPASS YES".

Reset RPS Channel 11 Trip ATC

After APRM bypassed reset RPS Channel 11 trip

Verifies F1-1-1 clear

Depress SCRAM RESET pushbutton on "E"

Verifies F1 1 clear and resets annunciators

Report APRM 13 bypassed and ARP actions completed to SRO Page 14 of 29 NRC Scenario 4 February 2017

,.::"""' Exelon Generation Event #4: CRD Flow Control Valve Failure Event

Crew will swap to alternate FCV in accordance with N1-SOP-5.1 Information

SRO will determine tech specs When actions for the voltage regulator failure are CREW complete and when directed by the examiner, insert

Acknowledge/report annunciator F3-1-5, CRD malfunction: CHARGING WTR PRESS HI/LO

Diagnose CRD FCV 11 is closed RD36A, CRD FCV 44-151 FAILURE- CLOSED TRG2 CRD charging water pressure rises SRO CRD drive water pressure lowers CRD cooling water pressure and flow lower

Acknowledge report from the crew Expected Annunciator:

Direct entry into N1-SOP-5.1, LOSS OF CRD F3-1-5, CRD CHARGING WTR PRESSURE HI/LO

Acknowledge report that CRD FCV has failed

Acknowledge report that CRD FCV has been shifted and is in AUTO

Enter Technical Specifications 3.1.6.c while CRD flow less than 50 gpm.

ATC

Monitor plant parameters Page 15 of 29 NRC Scenario 4 February 2017

~

,.~ ExelonGeneration BOP

Acknowledge direction from SRO Role Play: As PO, when directed to transfer CRD

Execute N 1-SOP-5.1 FCV, wait 1 minute and inform the control room that

Answers "Is a CRD pump operating" YES you are standing by

Determines need to switch CRD Flow Control Valves per N1-0P-5 Section F.5.0:

Role Play: As PO, when directed to open 44-148

Dispatch PO to report to RB 237' and establish and 44-152, wait 1 minute and report task completion communications (Step 5.4.1)

Place CRD Flow Control in MAN and 0 demand

Direct PO open 44-148 and 44-152

Direct PO to count-down to place RB air transfer switches in UP position while you place CRD FCV transfer switch in VAL VE 12 position at F Role Play: As PO, when directed to countdown and panel swap transfer switch, give simulated countdown and

Places CRD FCV transfer switch in VALVE 12 report task completion (see note below), as required position

Direct PO close 44-150 and 44-153 Note: When the control room operator takes the

Monitor flow CRD Flow Control Transfer Switch to "VALVE 12"

Place CRD Flow Control in AUTO TRG 16 will automatically insert remote:

RD05, CRD FLOW CONTROL VALVE ISOL, FINAL VALUE=nc30b TRG16 This precludes the console operator from having to time the insertion of this remote.

Role Play: As PO, when directed to close 44-150 and 44-153, wait 1 minute and report task completion. (Step 5.4.3)

Page 16 of 29 NRC Scenario 4 February 2017

,:-". Exelon Generation Events #5: Service Water Adams Strainer Clogging Event

Service Water Adams Strainer begins clogging.

Information

Backwashing does not fix the problem.

Crew will start a second SWP When directed by examiner, insert malfunction:

CREW CW16A, SW Pump 11 Strainer 72-05 Clogging,

Acknowledge/respond to annunciator H1-3-2, FV=10% SERVICE WTR P STR 11-12 TRIP-LO VOLT TRG4 DIFF PRESS Expected Annunciator:

H1-3-2, SERVICE WTR P STR 11-12 TRIP-LO VOLT DIFF PRESS SRO

Acknowledges report

Directs entry into ARP for H1-3-2

Acknowledges report that SW strainer BV 408, Backwash Valve is open and that D/P is not lowering

Determines the alarm cannot be cleared

Directs shifting to SWP 12 per N1 -OP-18 section F.2.0

Acknowledges report that SWP 12 has been started

Acknowledges report of current D/P ATC

Monitors plant parameters Page 17 of 29 NRC Scenario 4 February 2017

1

Exelon Generation BOP Role Play: When directed as PO to investigate, wait

Enters ARP for H1-3-2 two minutes, then report that Service Water pump 11

Directs an PO to the Intake area to check the SW Strainer D/P is 10 psid and slowly rising due to a Pump Strainer small amount of grass coming in the intake.

IF strainer D/P is high perform the following:

Confirms BV-72-408, ADAMS STRNR 11 Role Play: When directed as PO to verify strainer Backwash VLV open backwash valve, 72-408 open, immediately report

Determines the alarm cannot be cleared that 72-408 is open, backwash is in progress, but it

Starts SWP 12 per N1-0P-18, Sect. F.

does not appear to be lowering D/P

Places the SERVICE WTR PUMP 12 control switch at H Panel in Start Role Play: If directed to perform SWP start actions,

Observes normal motor running current, system acknowledge report and report completion.

flow, and discharge pressure Role Play: When directed as PO to report on pump start, immediately report that SWP 12 is operating normally Role Play: When requested as PO after start of Service Water Pump 12, report Service Water Pump 12 Adams Strainer D/P is 3 psid, and report that Service Water Pump 11 Adams Strainer D/P is 9 psid (if still running)

Page 18 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration Event #6: Loss of Main Condenser Vacuum Event

Loss of Condenser Vacuum leads to a reactor Scram Information When directed by examiner, insert malfunction: CREW MC01, Main Condenser Air lnleakage, FV=13.5

Recognize/report lowering main condenser TRG5 vacuum Main condenser vacuum slowly Jowers

Acknowledge/report annunciators:

Offgas flow rises Expected Annunciator:

A1-3-4, CONDENSER VACUUM BELOW 24" A 1-3-4, CONDENSER VACUUM BELOW 24" HG HG SRO

Acknowledges reports

Directs execution of N1-SOP-25.1, Unplanned Loss of Condenser Vacuum

Directs Emergency Power Reduction per N1-SOP-1.1 to stabilize condenser vacuum

Provides oversight for reactivity manipulation

Determines condenser vacuum can NOT be maintained above 22.1" Hgv

Directs a Reactor Scram

When vacuum approaches 7.0" Hgv, direct closing the MSIVs Page 19 of 29 NRC Scenario 4 February 2017

"* * *

Exelon Generation Event 6 continued RO

Monitor plant parameters

Lower recirc flow and insert cram rods per N1-SOP-1.1 to stabilize vacuum

When directed to manually scram:

Places Reactor Mode Switch in SHUTDOWN

Recognizes control rods did NOT fully insert

Pushes manual scram pushbuttons

Reports failure to scram Role Play: If dispatched as operator to check for BOP condenser leaks, acknowledge order. If asked about

Executes N1-SOP-25.1, Unplanned Loss of status, report that you have not found any leaks yet. Condenser Vacuum

Verifies proper operation of the following:

Gire Water System

SJ A Es

Off Gas System

Condensate System

Turbine Gland Seal System

Dispatches operator to check for condenser leakage

Attempts manual initiation of ARI Page 20 of 29 NRC Scenario 4 February 2017

'~ ExelonGeneration Events #7 & #8: ATWS with a Failure of All TBVs to Open Event

High Power ATWS with no TBVs and no High Pressure Injection Information

Ultimately leads to Slowdown The following malfunctions are preset: CREW

Diagnose failure of control rods to insert RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=24

Diagnose loss of all HP Injection RD33B, CONTROL ROD BANK BLOCKED BANK 2,

May recognize/report failure of TBVs to open FV=18 RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=22 RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=18 RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=24 Control rods partially insert Reactor power remains > 6%

Verify the following malfunction is automatically inserted when Reactor water level lower below -41 inches or manually initiated when directed by the examiner:

FW06, Shaft Driven Feedwater Pump Clutch Fails -

Disengage TRG6 Feedwater flow lowers Reactor water level lowers Page 21 of 29 NRC Scenario 4 February 2017

..-it

~ ExelonGeneration Events 7 and 8 continued SRO

Acknowledges report of failure to scram

Enters N 1-EOP-2 due to reactor power above 6%

when scram required

Answers "All rods in to at least 04" NO

Answers Will the reactor stay shutdown without boron" NO

Exits N 1-EOP-2, enters N 1-EOP-3

Directs ADS bypassed

Directs prevention of Core Spray injection per N1-EOP-1Att4 EOP-3 Level Leg Actions (Initial)

Directs bypass of the low-low RPV water level MSIV isolation per N1-EOP-1 Att 2

Determines Reactor power is above 6% and RPV water level is above -41 inches

Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1Att24 CT-1.0

Directs RPV water level lowered to at least -41 inches EOP-3 Pressure Leg Actions

If an ERV is cycling:

Directs initiation of Emergency Condensers

Directs open ERVs to lower RPV pressure to less than 965 psig

Directs RPV pressure controlled below 1080 psig Note: Turbine Bypass Valves are not available.

using Emergency Condensers, and ERVs

Monitors Figure M, Heat Capacity Temperature Limit Page 22 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration Events 7 and 8 continued SRO continued EOP-3 Power Leg Actions

Directs initiation of ARI

Answers "Turbine Generator on-line?" NO

Answers "Reactor power?" Above 6%

Verifies Recirc Pumps tripped

Directs execution of N1-EOP-3.1

If power oscillates more than 25% or before Torus water temperature reaches 110°F:

Records Liquid Poison tank level

Directs Liquid Poison injection CT-2.0 EOP-3 Level Leg Actions (Subsequent)

Acknowledges RPV water level below -41 inches

If Torus temperature is above 110°F, then directs level lowered until:

Power drops below 6%, OR

Level drops to -84 inches (TAF)

Records final actual level

Directs RPV injection with Condensate/Feedwater and CRD

Acknowledges report that Condensate/Feedwater Note: The most likely high-capacity injection system is not available for injection is Condensate and Feedwater Booster pumps with

When RPV water level cannot be maintained N1-EOP-1 Att 25 and/or 26. If SRO determines above -109 inches, enters N1-EOP-8, RPV inadequate level response is observed with these Slowdown systems, Core Spray is available with N1-EOP-1 Att

Answers "Are all control rods inserted to at least 4.

position 04 ?" NO

Answers 'Will the reactor stay shutdown without boron?" NO/UNKNOWN

Directs terminate and prevent of all RPV injection except boron and CRD per N1-EOP-1Att24

Directs initiation of Emergency Condensers Page 23 of 29 NRC Scenario 4 February 2017

~

~** ExelonGeneration Events 7 and 8 continued SRO continued

Answers "Torus water level?" Above 8 feet

Directs open 4 ERVs CT-3.0

Returns to N1-EOP-3 at circle 10

Answers "Is any ERV open?" YES

Waits until RPV pressure is below 264 psig

Answers "Was level intentionally lowered before you entered N1-EOP-8?" YES

Returns to circle 9

Directs RPV injection between -109 inches and previous final actual level with preferred and alternate ATWS injection systems CT-3.0

Acknowledges report of RPV water level restored above-109inches N1-EOP-4. Primary Containment Control, Actions Note: Since TBVs are not available, Pressure control will be on the ECs and ERVs. Use of the

Acknowledges degrading Primary Containment ERVs will cause torus temperature to rise toward parameters EOP entry conditions.

Enters N1-EOP-4 on high Torus Water temperature

Answers "Has Containment Spray Initiated?

o If NO, directs Containment Spray pumps placed in PTL

May eventually direct action to initiate Torus Cooling Page 24 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration RO

Provides scram report

Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N (17, 18, 19, 24, 25, 26)

Bypass low-low MSIV isolation per N1-EOP-1 Att 2 by installing four jumpers inside Panel N (1, 2, 8, 9)

Note: Control rods will successfully insert using

When directed, performs N1-EOP-3.1, Section RMCS 3 (driving rods) and/or 4 (manual scrams)

(See actions below)

Reports when APRMs <6%

Reports status of control rod insertion

Injects Liquid Poison, if directed CT2.0 Page 25 of 29 NRC Scenario 4 February 2017

~ ExelonGeneration Events 7 and 8 continued RO Continued Possible N1-EOP-3.1 Section 3 Actions:

Verifies a CRD Pump running Note: RO will likely have to fully open the CRD flow

Places Reactor Mode Switch in REFUEL control valve and/or close 44-04 in order to achieve

Places ARI OVERRIDE switch in OVERRIDE rod movement via RMCS; these methods are

Installs RPS jumpers (5, 6, 12, 13) preferential to closing 44-167 due to ability to perform

Resets the scram from the control room and not preventing further

Inserts rods to 00 using EMER ROD IN scram attempts by blocking the charging water starting with high power regions of core (use header LPRM indications)

CT-2.0

If more drive pressure is required, then perform one or more of the following:

Fully open CRD Flow Control Valve (F panel)

Close 44-04, Control Rod Drive Water Cont V (F Panel)

Close 44-167, Charging Water Header Blocking Valve (RB 237')

Possible N 1-EOP-3.1 Section 4 Actions:

Places ARI OVERRIDE switch in OVERRIDE

Installs RPS jumpers (5, 6, 12, 13)

Resets the scram

Verify open 44-167, Charging Water Header Blocking Valve (RB 237')

When the SDV is drained, then initiate a manual scram Page 26 of 29 NRC Scenario 4 February 2017

~

,;::-"" Exelon Generation Events 7 and 8 continued BOP

Bypasses ADS

Terminates and prevents all injection except boron and CRD per N1-EOP-1Att24:

CT-1.0

Closes both Feedwater Isolation Valves 11 and 12 OR places Feedwater pumps 11 and 12 in PTL

Selects Manual on 11, 12 and 13 FWP Valve Control selector switches

Closes 11 , 12 and 13 Feedwater FCV (Knurled Knob) full counterclockwise

Places FW LVL SETPOINT SETDOWN to OVERRIDE Role Play

Directs operator to remove fuses FU-8 and If directed to pull HPCU fuses FU-8 and FU-9 from FU-9 from Panel IS34 in the Aux Control Panel IS34 in the Aux Control Room, wait Room approximately 2 minutes and insert remote:

Verifies closed, FEEDWATER PUMP 13 BLOCKING VALVE FW24, Removal of HPCI Fuses FU8/FU9, FV=pulled

Verifies in MAN, FWP 11 BYPASS VALVE, TRG 10 AND set to zero output

Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output

May re-open Feedwater Isolation Valve

Informs SRO when RPV water level reaches -41 inches Page 27 of 29 NRC Scenario 4 February 2017

=: -" Exelon Generation Events 7 and 8 continued BOP continued

If any ERV is cycling:

Initiates Emergency Condensers

Manually opens ERVs to lower RPV pressure

<965 psig

Controls RPV pressure below 1080 psig with Emergency Condensers and ERVs

Initiates ARI

Verifies all Recirc Pumps tripped

Initiates Liquid Poison as directed

Reports initial tank level

Starts Liquid Poison pump 11 or 12 CT-2.0

Verifies RWCU isolated

Places Containment Spray pumps in PTL (Either before they initiate, or once Drywall pressure lowers to below 3.5 psig)

Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD

Attempts to re-inject with Condensate/Feedwater per EOP-1 Att 24:

Reopens at least one Feedwater Isolation Valve 11 and I or 12, if closed

Reports no high pressure Feedwater pumps are available for injection

Determines Feedwater Booster Pump 12 is available Page 28 of 29 NRC Scenario 4 February 2017

)=:""!" Exelon Generation Events 7 and 8 continued BOP continued

Re-terminates RPV injection per EOP-1 Att 24 o Verifies closed 11, 12, and 13 Feedwater FCVs

Verifies ECs are initiated

Opens 4 ERVs CT-3.0

Re-establishes RPV injection using Feedwater Booster Pump and/or Core Spray per N1-EOP-1 Att 4, 24, 25, or 26 CT-3.0

Reports RPV water level restored above -109 inches Event Termination

RPV water level controlled in assigned band above -109" Criteria

RPV Slowdown in progress

Liquid Poison injection or control rod insertion in progress Page 29 of 29 NRC Scenario 4 February 2017

ML17101A468

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