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Nine Mile Point Station, Unit 1 - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML15110A397
Person / Time
Site:	Nine Mile Point
Issue date:	02/18/2015
From:	Fish T H; Operations Branch I
To:	Isham P; Exelon Generation Co
Shared Package
ML14238A301	List: ML14246A018; ML15110A382; ML15110A384; ML15110A385; ML15110A387; ML15110A388; ML15110A390; ML15110A393; ML15110A395; ML15110A397; ML15121A834; ML15169A595;
References
	TAC U01905
	Download: ML15110A397 (270)
	v • d • e

Exelon Generation Training Id: 2015 NRC RO Admin C001 Revision:

0.0 Title: Nl-ST-DO DAILY CHECKS (Partial)

Approvals:

Developed By P ,.?/J/ Paul Isham 5/28/14 Validated By Leigh Mason, Dave Ballard 08/21/2014 Facility Reviewer Greg Elkins Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

_________

_ Date: NRC JPM RO COOl Page 1of9 March 2015 Exelon Generation References

1. Nl-ST-DO, Daily Checks 2. NUREG 1123, 2.1.7 (4.4) NRC JPM RO COOl Page 2 of 9 March 2015

Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to record and interpret plant surveillance data and identify inoperable equipment.

Control room RPV water level readings are taken for Nl-ST-DO.

Out of spec readings and inoperable equipment are identified by the operator.

2. Task Information:

a. NS-REL-01001, Perform System Surveillances.

b. K/A 2.1.7 (4.4), Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

3. Evaluation

/Task Criteria Perform Classroom No No Yes 4. Recommended Start Location

a. Simulator

1) Simulator will be in 'Freeze'.

Therefore this cannot be performed in conjunction with a simulator JPM. NRC JPM RO COOl Page 3 of 9 March 2015 Exelon Generation

5. JPM Setup (if required)

a. Provide copies of Nl-ST-DO.

b. Initialize simulator to IC-166 c. Plant is operating

"'15% power d. Verify the following overrides are set: 1) 5M80A03550

= 73.00 2) 5M81A03560

= 75.00 3) 5M118A03860

= 76.00 4) 5M116A03840

= 68.00 5) 5AR1TS1A031000

= 68.00 6) 13M1A042680

= 69.00 7) 9M53A051270

= 70.50 e. Take the simulator to Run, and then back to Freeze f. Verify average Drywell temperature is less than 130°F g. Verify total Recirc flow is 38 Mlbm/hr h. Verify FWLC is selected to column 11 i. Turn off PI monitor NRC JPM RO COOl Page 4 of 9 March 2015 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.

NRC JPM RO COOl Page 5 of 9 March 2015

1. 2. 3. Exelon Generation Given:

The plant is operating at approximately 15% power.

Nl-ST-DO, Daily Checks, is in progress.

The provided printout shall be used to determine computer point and PI data.

The process computer is unavailable Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure.

When completed, report findings and provide completed sections to SRO. Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper communications correction if necessary.

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

STD: Nl-ST-DO

Obtained, sections 5.0 and 6.0 Note: Completed Nl-ST-DO is attached as p referenced.

JPM key. Small differences in recorded values may occur due to instrument interpolation.

Records section 5.0 readings SAT/ UNSAT p STD: Records Reactor Recirc Pump Inlet Temperature readings on Attachment 4 Section 5.0 NRC JPM RO C001 Page 6 of 9 March 2015

4. Compare Recirc Pump Inlet Temperature SAT/ UNSAT readings and determines readings within 15°F p STD: Compares readings and determines readings within l5°F of each other PASS I FAIL p STD: Checks YES block in Section 5.0, indicating the maximum difference in loop temperatures is < l5°F 5. Record section 6.0 readings SAT/ UNSAT Cue: Another operator has completed the p STD: Records RPV water level required Independent Verifications.

readings on Attachment 4 section 6.0 6. Record Total Recirc Flow SAT I UNSAT p STD: Records total recirc flow in the correct box on Attachment 4 section 6.0 7. Determines average Drywell temperature SAT I UNSAT /NA Note: Since Yarway level indicator deviation p STD: Observes average Drywell is less than 4 inches, Drywell temperature temperature is less than 125°F reading is not necessary for task completion.

8. Analyzes Yarway level indicator deviation PASS/ FAIL Note: This may be evidenced by the lack of p STD: Determines Yarway level a report to the contrary.

indicator deviation is less than the 6 inch limit 9. Analyzes GEMAC level indicator deviation PASS/ FAIL p STD: Determines GEMAC level indicator deviation is greater than the 6 inch limit NRC JPM RO COOl Page 7 of 9 March 2015

10. 11. Exelon Generation Determines GEMAC level indicators are PASS/ FAIL inoperable p STD: Checks INOP option in step 8.4 Provides completed sections to SRO and SAT/ UNSAT informs of out of spec readings p STD: Proper communications used. Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

NRC JPM RO COOl Page 8 of 9 March 2015

=::""Exelon Generation NRC JPM RO C001 JPM Handout Given:

The plant is operating at approximately 15% power.

Nl-ST-DO, Daily Checks, is in progress.

The provided printout shall be used to determine computer point and PI data.

The process computer is unavailable (Operators Name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure.

When completed, report findings and provide completed sections to SRO. Page 9 of 9 March 2015

Generation Training Id: 2015 NRC RO Admin JPM EP Revision:

0.0 Title: Perform CRO Firefighting Checklist Approvals:

Developed By Paul Isham 5/28/14 Validated By Leigh Mason 8/21/14 Facility Reviewer Greg Elkins Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM RO EP Page 1 of 8 March 2015 Exelon Generation References

1. EPIP-EPP-28, Firefighting

2. NU REG 1123, 2.4.27 (3.4) NRC JPM RO EP Page 2 of 8 March 2015 Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to carry out control room actions for a fire in the plant. The operator will execute the CRO Firefighting Checklist.

2. Task Information:

a. Nl-286000-01023, Respond to a Plant Fire b. K/ A 2.4.27 (3.4 ), Knowledge of "fire in the plant" procedures

3. Evaluation/

Task Criteria Perform Classroom No No Yes 4. Recommended Start Location

a. Simulator

5. JPM Setup (if required)

a. None NRC JPM RO EP Page 3 of 8 March 2015

&=r-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.

NRC JPM RO EP Page 4 of 8 March 2015

=::"Exelon Generation

1. 2. 3. Given:

The plant is operating at approximately 100% power.

You are the CRO.

You have just received a report from site electricians that there is a significant fire in EDG 102 room.

The OSC has NOT been activated.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), perform EPIP-EPP-28 Attachment 1, CRO Firefighting Checklist.

Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of the reference procedure and review/ utilize the correct section of the procedure.

Place the GAitronics in the "Merge" Mode. p p p SAT/ UNSAT STD: Proper communications used. SAT I UNSAT STD: Obtains a copy of EPP-28. References attachment 1, CRO Firefighting Checklist SAT/ UNSAT STD: Places the GAitronics in the "MERGE" mode by placing the switch on the Communications Console in the Control Room to the "MERGE" position.

NRC JPM RO EP Page 5 of 8 March 2015

S: rExelon Generation

4. Sound the fire alarm for 10 seconds and PASS I FAIL announce the fire event. STD: Sounds the fire alarm and Cue: As the Fire Brigade Leader reply that, makes the following announcement:

"The Fire Brigade is on the way to the 'Attention, Attention, this is a assembly area and I will report on the p drill. A fire has been detected situation as soon as I arrive on the scene." at Unit! in the EOG 102 room The Nine Mile Point Fire Brigade shall report to the Unit 1 assembly area. All other personnel are to remain clear of the EDG 102 room area.' 5. Announce evacuation of EDG 102 room. SAT/ UNSAT STD: Continues on from previous announcement:

p 'This is a C02 protected area. All personnel shall immediately evacuate the EDG 102 room and all areas adjacent to and below this location.'

6. Take the GAitronics system out of the Merge SAT/ UNSAT Mode STD: Takes GAitronics out of Cue: As the Fire Brigade Leader, report the p 'Merge' using the fire is confirmed and you request off-site fire communications console.

assistance.

7. Notify the SM of the confirmed fire. SAT/ UNSAT p STD: Proper communicatiOons Role Play: As SM, acknowledge report of used. confirmed fire. 8. Turn up volume on station radio base SAT/ UNSAT console, including Oswego County fire p frequency STD: Volume adjusted appropriately.

NRC JPM RO EP Page 6 of 8 March 2015

=::"Exelon Generation Control room actions for the CRO Firefighting Checklist are complete.

NRC JPM RO EP Page 7 of 8 March 2015

=:rExelon Generation NRC JPM RO EP JPM Handout Given:

The plant is operating at approximately 100% power.

You are the CRO.

You have just received a report from site electricians that there is a significant fire in EDG 102 room.

The OSC has NOT been activated.

(Operators Name), perform EPIP-EPP-28 Attachment 1, CRO Firefighting Checklist.

Page 8 of 8 March 2015 Training Id: 2015 NRC SRO Admin C001 Revision:

0.0 Title: Review N1-ST-DO Daily Instrument Checks (Partial)

Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name Isham Pat O'Brien Greg Elkins 20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM SRO COOl Page 1 of 8 5/21/14 8/19/2014 2/n/1.1 March 2015 Exelon Generation References

1. Nl-ST-00, Daily Checks 2. Unit 1 Technical Specifications

3. NUREG 1123, 2.1.7 (4.7) NRC JPM SRO C001 Page 2 of 8 March 2015 Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the senior operator's ability to evaluate plant surveillance data and determine applicable tech spec actions for failed equipment.

2. Task Information:

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

b. K/A 2.1.7 (4.7), Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

3. Evaluation

/Task Criteria Perform Classroom No No Yes 4. Recommended Start Location

a. Training Classroom NRC JPM SRO COOl Page 3 of 8 March 2015

=:r-Exelon Generation

5. JPM Setup (if required)

a. Provide copy of Nl-ST-DO with Attachment 4 section 6.0 and step 8.4 completed with the following values: Attachment 4 section 6.0: Low-Low Level Alarms -Checked "NO" Feedwater Level Column -Checked "11" E-Panel Vessel Level Indicator

-72" K-Panel Vessel Level Indicator

-72" K-Panel Flange Level Indicator

-DOWNSCALE Reactor Vessel Level Recorder

-71" Wide Range Level Indicator

-7' GEMAC Level Column (Ch 11/12) -71" I 79" GEMAC Level Computer Points (Ch 11/12) -71.344" / 79.051" Pi Calculated GEMAC level column difference

-7.680" RPS Level Column (Ch 11/12) -73"/76" Yarway (RPS) Level Column -73.125"/75.

763" Pi Calculated Yarway level column difference

-2. 770" GEMAC variance

-8" Computer point variance

-7. 707" Total Recirc Flow -38.0 Mlbm/hr Step 8.4: Check "Pi-Calculated GEMAC Level Delta" Check "Acceptable Range" b. If multiple operators are going to perform the JPM at the same time, ensure each operator has a copy of Nl-ST-DO.

NRC JPM SRO COOl Page 4 of 8 March 2015 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.

NRC JPM SRO COOl Page 5 of 8 March 2015

1. 2. 3. 4. Exelon Generation Given:

The plant is operating at approximately 67% power.

Nl-ST-DO, Daily Checks, is in progress.

Operators have completed the RPV water level instrument readings.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), perform SRO review of the following section of ST-DO:

Attachment 4 section 6.0

Step 8.4 When completed, report findings to the Examiner.

Provide repeat back of initiating cue Cue: Acknowledge repeat back providing p correction if necessary.

Obtain a copy of the reference procedure and review / utilize the correct section of the p procedure.

Review Attachment 4 section 6.0 readings and Step 8.4 p Identifies error in Step 8.4 p SAT/ UNSAT STD: Proper communications used. SAT/ UNSAT STD: N1-ST-DO Obtained SAT/ UNSAT STD: Reviews Attachment 4 section 6.0 and step 8.4 readings PASS/ FAIL STD: Identifies that GEMAC Level Column Variance is in the !NOP range NRC JPM SRO C001 Page 6 of 8 March 2015

5. 6. 7. Exelon Generation If Candidate asks for prior readings for comparison, or for Engineering evaluation, report that plant data indicates GEMAC 11 is trending normally and GEMAC 12 indicates higher than expected.

Determines GEMAC 12 level indicator is inoperable Determines Technical Specification impact Provides completed sections to Examiner and informs of out of spec readings p p p PASS/ FAIL STD: Determines GEMAC 12 level indicator is inoperable PASS I FAIL STD: Determines a 15 day LCO applies per Technical Specification 3.1.8 SAT/ UNSAT STD: Proper communications used Control room RPV water level instrument surveillance per Nl-ST-DO is reviewed.

Out of spec results are identified and the appropriate Technical Specification is determined.

NRC JPM SRO COOl Page 7 of 8 March 2015 Exelon Generation NRC JPM SRO COOl JPM Handout Given:

The plant is operating at approximately 67% power.

Nl-ST-DO, Daily Checks, is in progress.

Operators have completed the RPV water level instrument readings.

(Operators Name), perform SRO review of the following section of ST-DO:

Attachment 4 section 6.0

Step 8.4 When completed, report findings to the Examiner.

Page 8 of 8 March 2015

=::rExelon Generation Training Id: 2015 NRC RO-SRO Admin C002 Revision:

0.0 Title: Determine Personnel Overtime Availability IAW CNG-SE-1.01-1002 Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name Pau/Isham Pat O'Brien Greg Elkins Approximate Duration:

20/30 minutes (RO/SRO)

Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM RO-SRO C002 Page 1of13 5/21/14 8/19/2014 z/t J Its-March 2015

Generation References

1. CNG-SE-1.01-1002

2. NUREG 1123, 2.1.5 (2.9/3.9)

NRC JPM RO-SRO C002 Page 2 of 13 March 2015 Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to evaluate plant surveillance data and determine applicable tech spec actions for failed equipment.

2. Task Information:

3. 4. a. GAP-FFD02-00002, Maintain working hours within overtime guidelines.

b. GAP-FFD02-00004,

Initiate, review and approve an overtime waiver with Empcenter unavailable.

c. K/A 2.1.5 (2.9/3.9),

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Evaluation

/Task Criteria Perform Classroom No No Yes Recommended Start Location

a. Training Classroom NRC JPM RO-SRO C002 Page 3 of 13 March 2015

=:r-Exelon Generation

5. JPM Setup (if required)

a. Provide copy of CNG-SE-1.01-1002.

b. If multiple operators are going to perform the JPM at the same time, ensure each operator has a copy of CNG-SE-1.01-1002.

c. Provide extra copies of CNG-SE-1.01-1002, attachment

1. NRC JPM RO-SRO C002 Page 4 of 13 March 2015 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.

NRC JPM RO-SRO C002 Page 5 of 13 March 2015

=:r-Exelon Generation

1. 2. Given:

The plant is shutdown for a refueling outage.

Current time is 2200 on November 27, 2014.

An Operator scheduled to work the day shift on November 28, 2014 has called in sick for that shift.

In order to support minimum control room staffing requirements, personnel overtime will be required for the day shift on November 28, 2014 from 0630-1830.

All the overtime hours will be spent performing control room activities.

November 14, 2014 through November 28, 2014 is a fixed 15-day period for work hour rule considerations.

EmpCenter is NOT available.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operator Name), 1. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift beginning at 0630 on November 28 without exceeding the limits of CNG-SE-1.01-1002.

2. If a Work Hour Limits Waiver would be required for any individual(s),

state the work hour limit(s) which would be exceeded IAW CNG-SE-1.01-1002.

Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of the reference procedure and review / utilize the correct section of the procedure.

p p SAT I UNSAT STD: Proper communications used. SAT/ UNSAT STD: CNG-SE-1.01-1002 Obtained NRC JPM RO-SRO C002 Page 6 of 13 March 2015 Exelon Generation

3. Reviews work hours for Reactor Operators

1 through #3 4. SRO Only -Completes CNG-SE-1.01-1002 Attachment 1 Section 1 for RO #2 Cue: Give SRO additional cue sheet and blank CNG-SE-1.01-1002 Attachment 1 Section 1. Direct the SRO to complete CNG-SE-1.01-1002, Attachment 1 for RO #2. Note: Only items 1) and 2) of CNG-SE-1.01-1002 Attachment 1 Section 1 are deemed critical for evaluation of this step. p p PASS/ FAIL STD: Determines the following:

RO #1 -Not Eligible

-Would work more than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period OR <10 hours between shifts. (step 5.2.A.2.a)

RO #2 -Not Eligible

-Would work more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period RO #3 -Eligible PASS I FAIL STD: Completes CNG-SE-1.01-1002 Attachment 1 Section 1 for RO #2, per attached key JPM Attachment B completed.

For SROs, CNG-SE-1.01-1002 Attachment 1 Section 1 completed for RO #2. NRC JPM RO-SRO C002 Page 7 of 13 March 2015 Exelon Generation RO-SRO JPM Handout Given:

The plant is shutdown for a refueling outage.

Current time is 2200 on November 27, 2014.

An Operator scheduled to work the day shift on November 28, 2014 has called in sick for that shift.

In order to support minimum control room staffing requirements, personnel overtime will be required for the day shift on November 28, 2014 from 0630-1830.

All the overtime hours will be spent performing control room activities.

November 14, 2014 through November 28, 2014 is a fixed 15-day period for work hour rule considerations.

EmpCenter is NOT available.

(Operator Name), NRC JPM RO-SRO C002 1. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift beginning at 0630 on November 28 without exceeding the limits of CNG-SE-1.01-1002.

2. If a Work Hour Limits Waiver would be required for any individual(s),

state the work hour limit(s) which would be exceeded IAW CNG-SE-1.01-1002.

Page 8 of 13 March 2015

=::'"Exelon Generation SRO ONLY Additional JPM Handout Given:

ROs #1 and #3 have not been able to be contacted.

RO #2 is the only operator available and will be required to work. (Operator Name), Complete CNG-SE-1.01-1002, Attachment 1, 10 CFR 26 Work Hour Limits Waiver, Section 1, for RO #2 to cover this shift on November

28. NRC JPM RO-SRO C002 Page 9 of 13 March 2015 Exelon Generation Attachment A -Work Hours RO#l 11/10 11/11 11/12 11/13 11/14 11/15 11/16 11/17 11/18 11/19 11/20 11/21 11/22 11/23 11/24 11/25 11/26 11/27 11/28 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 OFF --OFF OFF ----OFF OFF -OFF -----? 1830 1830 1830 1830 1830 2030 1830 1830 1830 1830 1530 2130 R0#2 11/10 11/11 11/12 11/13 11/14 11/15 11/16 11/17 11/18 11/19 11/20 11/21 11/22 11/23 11/24 11/25 11/26 11/27 11/28 0630 0730 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 OFF --OFF OFF -----OFF OFF ------? 2130 1730 1830 1830 1830 2030 1830 1830 1830 1830 1830 1830 1830 R0#3 11/10 11/11 11/12 11/13 11/14 11/15 11/16 11/17 11/18 11/19 11/20 11/21 11/22 11/23 11/24 11/25 11/26 11/27 11/28 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 0630 --OFF -OFF OFF -----OFF OFF ----OFF ? 1830 1830 1830 1830 1830 1630 2030 1830 1830 2030 1830 1830 NRC JPM RO-SRO C002 Page 10 of 13 March 2015 Exelon Generation Attachment B -Answer Sheet Eligible to work without a If No, what work hour Work Hour Limits Waiver? limit(s) would be exceeded (Yes/No)

IAW CNG-SE-1.01-1002?

RO #1 RO #2 RO #3 NRC JPM RO-SRO C002 Page 11of13 March 2015 Exelon Generation Training Id: 2015 NRC RO-SRO Admin EC Revision:

0.0 -----Title: Perform Daily Thermal Limit Surveillance Approvals:

ature Printed Name Developed By

.r.,,,,,

r Paul Isham 5/21/14 Validated By Pat O'Brien 8/19/14 Facility Reviewer Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM RO-SRO EC Page 1 of 8 March 2015 Exelon Generation References

1. Nl-RESP-lA, Daily Thermal Limit Surveillance Short Form 2. 30 Monicore

3. NU REG 1123, 2.2.12 (3. 7 /4.1) NRC JPM RO-SRO EC Page 2 of 8 March 2015 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.

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 Perform Classroom No No Yes 4. Recommended Start Location

a. Training Classroom

5. JPM Setup (if required)

a. Provide two 30 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 NRC JPM RO-SRO EC Page 3 of 8 March 2015

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.

NRC JPM RO-SRO EC Page 4 of 8 March 2015

1. 2. Exelon Generation Given:

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 30 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 = O. 9990 LEFM Flow correction factor from CRC Book -East= 0.9907 Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), perform the Daily Thermal Limit Surveillance in accordance with N1-RESP-1A, section 8.2. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of the reference procedure and review / utilize the correct section of the procedure.

p p SAT/ UNSAT STD: Proper communications used. SAT/ UNSAT STD: N1-RESP-1A and 30 Monicore cases obtained Provide copies of N1-RESP-1A and 30 monicore case edits (current and previous day). Only provide N1-0P-16, attachment 4 if requested.

NRC JPM RO-SRO EC Page 5 of 8 March 2015

3. 4. 5. Exelon Generation Complete Nl-RESP-lA section 8.2 Note: Refer to KEY for completed surveillance.

The items circled in blue are the critical steps (8.2.5, 8.2.6, 8.2.7, and 8.2.9). 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. Identify discrepancy in Nl-RESP-lA section 8.2 SRO Only Cue: Once the SRO Candidate has identified MFLCPR/MCPR violation, direct them to determine the required action for this condition.

SRO Only -Determine required action for MFLCPR/MCPR violation NRC JPM RO-SRO EC Page 6 of 8 p p p p PASS/ FAIL STD: Nl-RESP-lA completed per the key PASS/ FAIL STD: Identifies that MFLCPR/MCPR have exceeded the limit PASS/ FAIL STD: Determines Technical Specification 3.1. 7 .c is not met. PASS/ FAIL 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. March 2015

=:rExelon Generation NRC JPM RO-SRO EC Daily thermal limit surveillance completed in accordance with N1-RESP-1A section 8.2, with all discrepancies identified.

For SRO Candidates, required actions identified.

Page 7 of 8 March 2015 Exelon Generation NRC JPM RO-SRO EC JPM Handout Given:

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 (Operators Name), perform the Daily Thermal Limit Surveillance in accordance with N1-RESP-1A, section 8.2. Page 8 of 8 March 2015 Exelon Generation Training Id: 2015 NRC SRO Admin RC Revision:

0.0 -----Determine Radiation Controls

-Emergency Exposure for Local MSIV Title: Closure Approvals:

Developed By Paul Isham 5/21/14 Validated By Pat O'Brien 8/19/2014 Facility Reviewer Greg Elkins z/;7 ft-Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM SRO RC Page 1of10 March 2015

Generation References

1. GAP-RPP-07, Internal and External Dosimetry Program 2. S-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits 3. CNG-EP-1.01-1014, Emergency Exposures and KI 4. NUREG 1123, 2.3.4 (3.7) NRC JPM SRO RC Page 2 of 10 March 2015

Generation Instructor Information A. JPM Information

1. Description

a. This JPM is used to test generic knowledge in calculation of overall dose and control mechanisms to allow the selection of individuals to continue or perform work in high dose areas. This JPM tests basic mathematics and understanding of stay times and remaining dose limitations under normal operating conditions given normal quarterly dose limitations.

2. Task Information:

a. GAP-RPP07-00002, Comply with administrative exposure limits b. K/A 2.3.4 (3.7), Knowledge of radiation exposure limits under normal or emergency conditions.

3. Evaluation/

Task Criteria Perform Classroom No No Yes 4. Recommended Start Location

a. Training Classroom NRC JPM SRO RC Page 3 of 10 March 2015 Exelon Generation

5. JPM Setup (if required)

a. Ensure sufficient copies of the following procedures are available in the exam area:

GAP-RPP-07

S-RAP-RPP-0703

CNG-EP-1.01-1014

EP-Form-ALL08 (2 per applicant)

NRC JPM SRO RC Page 4 of 10 March 2015 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.

NRC JPM SRO RC Page 5 of 10 March 2015 Exelon Generation NRC JPM SRO RC Given:

The plant is at 15% power.

A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage.

Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation.

Job conditions are as follows:

o Two individuals are required to complete the job. o Each worker is expected to receive 575 mR in transit to the Main Steam line access door AND the same amount again while exiting the plant. o Each worker is expected to spend 2 minutes in an 800 mR/hr field in transit from the Main Steam line access door to the job site. o The job site is against the outer Containment Wall in a 1.9 R/hr field. o The job will take 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the job site with both workers working the full time. o Each worker is expected to spend 3 minutes in an 800 mR/hr field in transit from the job site to the Main Steam line access door.

Two workers are briefed to complete the task. o Technician 1 -John Technician

-Maintenance

-SS # 123-45-6789 -TLD # 145678 o Technician 2 -James Worker -Operations

-SS# 987-65-4321

-TLD# 235699

During an initial entry under a modified RWP the workers received the following dose: o Technician 1 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. o Technician 2 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year.

The TSC has not been staffed and the RAC is in route to the site.

Emergency exposure controls have not been implemented.

Evaluator:

Ask trainee if he/she has any questions presenting initial conditions (Operators Name), Anticipate dose to be accumulated by each worker. Authorize work using the appropriate exposure limits to allow completion of the required task per CNG-EP-1.01-1014 and GAP-RPP-07.

Page 6 of 10 March 2015 Exelon Generation

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

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

STD: CNG-EP-1.01-1014 and GAP-RPP-07 Obtained

3. For each worker: 3a Determine anticipated dose from task SAT I UNSAT performance in the work area. p STD: Dose Rate *Time= Task Dose 1900 mR/hr

2hr = 3800 mR 3b Determine anticipated dose from transit to p SAT I UNSAT and from the Main Steam chase STD: 2 x Transit dose (To and From) 2*575mR = 1150mR 3c Determine anticipated dose from transit to p SAT I UNSAT the work area in the steam chase. STD: Dose Rate *Time=Transit Dose 800mR/hr*

(2min/60)=26.

7mR 3d Determine anticipated dose from transit from p SAT/ UNSAT the work area in the steam chase. STD: Dose Rate *Time=Transit Dose 800mR/hr

(3min/60)=40mR 3e Determine the total dose for each worker p PASS/ FAIL from 3a through 3d. STD: Add 3a-3d = 5016.7mR NRC JPM SRO RC Page 7 of 10 March 2015

=;:r Exelon Generation

4. Determine that task performance is not p SAT I UNSAT allowable per normal controls.

STD: Determines that total dose is greater than the annual 4000 mR administrative limit for radiation exposure per GAP-RPP-07 and the 5000 mR federal limit 5. Determines that emergency exposure PASS/ FAIL controls are required per CNG-EP-1.01-1014, STD: Evaluates the total step 5.1.A expected dose and recognizes p that emergency exposure controls are required to raise the limit above 5 R for each individual per CNG-EP-1.01-1014 6. Verifies workers are allowed to receive p SAT/ UNSAT emergency exposure per step 5.1.C STD: Using currently identified workers verifies workers:

are not declared pregnant Cue: If asked, neither worker meets any of workers have not received a the exclusion criteria.

previous emergency exposure have not received a planned special exposure.

7. Determines EP-Form-All08 is required per p PASS/ FAIL step 5.1.E. STD: Determines EP-Form-All08 is required due to Cue: When the applicant determines EP-anticipated exposure

>SR Form-All08 is required, provide the form. 8. Completes EP-Form-All08 for technician

1. p PASS/ FAIL STD: Completes section A of Note: Acceptable range of authorized EP-Form-All08 for technician

1. exposure:

Anywhere between 5.016Rem to 25 Rem with be accepted for full credit. Employer is not a critical component of this step. NRC JPM SRO RC Page 8 of 10 March 2015

=:r-Exelon Generation

9. Completes EP-Form-All08 for technician

2. Note: Acceptable range of authorized exposure:

Anywhere between 5.016Rem to 25 Rem with be accepted for full credit. Employer is not a critical component of this step. p PASS/ FAIL STD: Completes section A of EP-Form-AllOS for technician

2. "You may stop here, you have met the termination criteria for this JPM" NRC JPM SRO RC Page 9 of 10 March 2015 Exelon Generation NRC JPM SRO RC JPM Handout Given:

The plant is at 15% power.

A Site Area Emergency has been declared due to a steam line rupture with significant fuel damage.

Entry is required into the MSIV Room to close the outboard MSIVs to prevent event escalation.

Job conditions are as follows:

o Two individuals are required to complete the job. o Each worker is expected to receive 575 mR in transit to the Main Steam line access door AND the same amount again while exiting the plant. o Each worker is expected to spend 2 minutes in an 800 mR/hr field in transit from the Main Steam line access door to the job site. o The job site is against the outer Containment Wall in a 1.9 R/hr field. o The job will take 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the job site with both workers working the full time. o Each worker is expected to spend 3 minutes in an 800 mR/hr field in transit from the job site to the Main Steam line access door.

Two workers are briefed to complete the task. o Technician 1 -John Technician

-Maintenance

-SS # 123-45-6789 -TLD # 145678 o Technician 2 -James Worker -Operations

-SS# 987-65-4321

-TLD# 235699

During an initial entry under a modified RWP the workers received the following dose: o Technician 1 received 900 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1678 mR for the year. o Technician 2 received 600 mR on his Electronic Dosimeter from his first entry, resulting in a total exposure of 1399 mR for the year.

The TSC has not been staffed and the RAC is in route to the site.

Emergency exposure controls have not been implemented.

(Operators Name), Anticipate dose to be accumulated by each worker. Authorize work using the appropriate exposure limits to allow completion of the required task per CNG-EP-1.01-1014 and GAP-RPP-07.

Page 10 of 10 March 2015

_.,, Exelon Generation Training Id: 2015 NRC SRO Admin EP Revision:

0.0 -----Title: Classify Emergency Event and Perform Initial Notifications Approvals:

Si Developed By 5/21/14 Validated By Pat O'Brien 8/19/2014 Facility Reviewer Greg Elkins b/11 la Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM SRO EP Page 1of9 March 2015 Exelon Generation References

1. NUREG 1123, 2.4.41 (4.6) 2. EPIP-EPP-01 EAL Matrix 3. CNG-EP-1.01-1013, Emergency Classification and PAR 4. CNG-EP-1.01-1015, Emergency Notifications

5. CNG-EP-1.01-1019, Site Emergency Operations

6. EPMP-EPP-0101, Unit 1 Emergency Classification Technical Bases NRC JPM SRO EP Page 2 of 9 March 2015

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

1. Description

a. This JPM tests the senior operator's knowledge of emergency action thresholds by giving a series of plant conditions and requiring the operator to classify the event and complete a part 1 notification.

2. Task Information:

3. 4. 5. a. NS-EPlOl-03005, Classify emergency events requiring emergency plan implementation.

b. K/A 2.4.41 (4.6), Knowledge of emergency action level thresholds and classifications.

Evaluation

/Task Criteria Perform Classroom Yes No Yes Recommended Start Location

a. Training Classroom JPM Setup (if required)

a. Provide copy of EPIP-EPP-01, UNIT 1 EAL MATRIX b. Ensure sufficient copies of the SM/ED checklist packages are available.

NRC JPM SRO EP Page 3 of 9 March 2015 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.

NRC JPM SRO EP Page 4 of 9 March 2015

1. 2. Exelon Generation Given: 1. You are the Unit 1 Shift Manager.

2. Unit 1 was operating at 100% power. 3. Unit 2 is operating at 100% power. 4. The following events have occurred at Unit 1:

EDG 103 was removed from service for corrective maintenance and will not be available for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

A loss of both offsite power lines has occurred.

EDG 102 automatically started and supplied Powerboard 102

Power control estimates several hours until an offsite power line can be restored.

The ERO has not been activated.

Unit 1 is currently still in an operating condition.

Instructor

/ Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), based on the above conditions, determine the event classification per CNG-EP-1.01-1013 and complete steps 1 through 1.3.2.A of EP-Chlst-MCROl, Shift Manager Checklist.

This is a time critical task. Time starts now. -.. "ACr*CODE'"

. :

. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary.

Obtain a copy of the reference procedure and review / utilize the correct section of the procedure.

Note: Each SRO applicant will be provided with a partial Shift Manager ERO Guidebook and a copy of the EAL Flowchart.

p p SAT/ UNSAT STD: Proper communications used. SAT I UNSAT STD: Shift Manager ERO forms obtained.

EAL Flowchart obtained.

NRC JPM SRO EP Page 5 of 9 March 2015

3. 4. 5. 6. 7. Exelon Generation Print name and date on Shift Manager Checklist.

(step 1.1.2) Call the Shift Communicator and Dose Assessors to the Control Rooms. (step 1.1.3) If entry is due to a security event, the concurrently perform the station specific procedure.

Using CNG-EP-1.01-1013, classify the event. (step 1.2.2) Note: The classification, NOT the use of the references provided in the standard, is used for the pass/fail grading criteria.

Cue: If applicant requests a peer check, respond that peer checks are not available.

Declare the event by announcing, "I am declaring an Alert, EAL SAl.1, at (time) due to only having 1 power source available to the emergency 4160V powerboards, and assuming the role as Emergency Director."

Notes: Similar announcements are acceptable provided all the information listed in step 1.2.2.B is announced.

The time difference must be 15 minutes or less. NRC JPM SRO EP Page 6 of 9 ACT. CODE*** P IS:l i-4Jt' .* p p p p SAT/ UNSAT STD: Step 1.1.2 complete with applicant name and date. SAT/ UNSAT STD: Proper communications used SAT I UNSAT STD: Determine there is no indication of a security threat. PASS I FAIL STD: Determines Alert, SA1 .1 due to:

AC power capability to 4.16 kV emergency buses reduced to a single power source for > 15 min. AND

ANY additional single power source failure will result in a loss of all 4.16 kV emergency bus power. PASS/ FAIL STD: Event declared in the control room. Declaration occurred within 15 minutes of JPM start time. JPM Start Time ___ _ Declaration time ___ _ March 2015

Generation

8. 9. 10. 11. Determine if protective actions for onsite personnel are necessary using ALL12, Onsite Protective Measures Flowchart (step 1.2.3) Note: EP-Form-ALL12 will advise to "Consider" implementing protected area evacuation, but does not require it. Announce or direct PA announcements, for station personnel as necessary using Form-ALL36.

(step 1.2.4) Cue: When EP-Form-ALL36 is completed, inform the applicant another operator will make the PA announcement.

Determine appropriate PAR per CNG-EP-1.01-1013, Emergency Classification and PAR. (step 1.2.5) Complete ERONS notification Details Form, EP-Form-ALL28 (step 1. 3 . 1 ) Cue: When EP-Form-ALL28 is completed, inform the applicant the Shift Communicator with inform the ERO. NRC JPM SRO EP Page 7 of 9 p p SAT I UNSAT STD: Determine there is no need to perform protected area evacuation and accountability.

PASS I FAIL STD: Completes ALL36 per the attached key with step (3) being the only critical step. SAT/ UNSAT STD: Determine no PARs for the Alert condition.

SAT I UNSAT STD: Completes ALL28 per the attached key. March 2015 Exelon Generation

12. Complete station specific initial notification form (Part 1) (step 1.3.2) Note: The time difference must be 15 minutes or less. Your task is complete.

P / srNA'

)'."* PASS/ FAIL STD: Completes ALL31 per the attached key with steps (3), (4), (5),

(6), and (7)being the only critical steps. Declaration time ___ _ Part 1 Notification Fact Sheet is complete:

__ _ Alert is declared and Part 1 notification is complete.

NRC JPM SRO EP Page 8 of 9 March 2015 200' 200' 200' 30' Exelon Generation Date: JPM Handout Given: 1. You are the Unit 1 Shift Manager.

2. Unit 1 was operating at 100% power. 3. Unit 2 is operating at 100% power. 4. The following events have occurred at Unit 1:

EOG 103 was removed from service for corrective maintenance and will not be available for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

A loss of both offsite power lines has occurred.

EOG 102 automatically started and supplied Powerboard 102

Power control estimates several hours until an offsite power line can be restored.

The ERO has not been activated.

Unit 1 is currently still in an operating condition.

{Operators Name), based on the above conditions, determine the event classification per CNG-EP-1.01-1013 and complete steps 1 through 1.3.2.A of EP-ChLst-MCROl, Shift Manager Checklist.

This is a time critical task. Time starts now. Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System XX/XX/XXXX Time (Local):

XX:XX:XX Elevated Ground Wind Speed (Main) 40 (mph) 30' Wind Speed (Main) 35 (mph) Wind Dir From (Main) 45 (deg) 30' Wind Dir From (Main) 60 (deg) Delta Temperature

-1.56 (deg F) 100' Delta Temperature

-0.81 (deg F) Stability Class D Stability Class D Air Temperature 80 (deg F) Precipitation (15 min) 0 (in) NRC JPM SRO EP Page 9 of 9 March 2015

=::'"Exelon Generation Training Id: 2015 NRC JPM S-1 Revision:

0.0 -----Title: Place 11 Shutdown Cooling Loop in Service (Alternate Path) Approvals:

Developed By Validated By Facility Reviewer Signature I Printed Name Paul Isham Leigh Mason Greg Elkins Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM 5-1 Page 1of13 03/17/14 8/20/14 March 2015 References

1. Nl-OP-4, Shutdown Cooling System 2. NUREG 1123 K/A 205000, A4.01, (3.7/3.7)

NRC 2015 JPM S-1 Page 2 of 13 March 2015

Generationoo Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate the SDC system. The operator will attempt to put SDC system 11 in service.

b. This JPM is considered alternate path because shortly after a SDC pump is started, it will trip. The operator will be expected to make a recommendation to place 12 SDC loop in service.

2. Task Information:

a. Nl-205000-01002

b. K/A 205000, A4.01, (3.7/3.7)

3. Evaluation/

Task Criteria Perform Simulator No Yes Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-1 Page 3 of 13 March 2015

=:rExelon Generation

5. a. b. c. d. Simulator Setup (if required)

Initialize Simulator to IC-161. Verify SOC temperature recorder on. Update 70-49, 70-54, and 70-58 status to "4". Verify recirc suction temperature is displayed (computer point A427). e. Verify SOC is removed from service (TCVs closed, pumps secured, IVs closed, inlet BVs closed).

f. g. h. i. j. k. Verify SOC Pump 13 in PTL and yellow tagged Verify SOC 13 suction valve is yellow tagged (38-05) Verify Malfunction SCOlC inserted Verify Malfunction SCOlA on TRG 1 with 60 second TD Verify TRG 1 condition is "ZDSCPSTR(l)==l" Verify the following remotes are preset:

SCOl = close

SC02 = installed

SC03 = close I. Verify remotes SC04A(B)(C)

= 100% are preset. 6. JPM Setup (if required)

a. Nl-OP-4, E.3.1 marked complete.

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.

NRC 2015 JPM S-1 Page 4 of 13 March 2015

Generation

1. 2. 3. Given:

The Reactor is shutdown with all rods in.

Reactor pressure is less than 120 psig.

Nl-OP-4 has been completed through step E.3.1 for placing Shutdown Cooling in service.

Shutdown Cooling has been filled and vented within the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and does not require further filling or venting.

Shutdown Cooling IV fuses/breakers have been installed.

SOC pump 13 is OOS for maintenance.

Reactor water level is being monitored by another operator.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), place Shutdown Cooling loop 11 in service per OP-4 starting at step E.3.2. Provide repeat back of initiating cue SAT I UNSAT p STD: Proper Cue: Acknowledge repeat back providing communications used correction if necessary Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the procedure p STD: Nl-OP-4 obtained, precautions

& limitations

reviewed,

& section E.3.0 referenced Open the following valves: (Step 3.2) NRC 2015 JPM S-1 Page 5 of 13 March 2015

Generation 3a. 38-03, SDC VALVE 11 PUMP SUCTION PASS/ FAIL (Step E.3.2) p STD: Opens 38-03 by rotating control switch CW to OPEN 3b. 38-04, SDC VALVE 12 PUMP SUCTION PASS/ FAIL (Step E.3.2) p STD: Opens 38-04 by rotating control switch CW to OPEN 3c. 38-05, SDC VALVE 13 PUMP SUCTION SAT I UNSAT Note: Candidate may request a Technical STD: Recognizes 38-05 Procedure Step Deletion be processed before is tagged closed proceeding.

p Cue: If Technical Procedure Step Deletion is requested, inform the Operator that the step has been deleted and to proceed.

4. Fill AND vent the SDC System by performing SAT/ UNSAT the following:

(Step 3.3) p STD: Determines fill and vent not required due to initial conditions

5. Verify all rods inserted UNLESS directed by SAT/ UNSAT EOPs (Step 3.4) p STD: Determines all rods are inserted per initial conditions or simulator setup NRC 2015 JPM S-1 Page 6 of 13 March 2015 Exelon Generatione<

6. IF SDC IV fuses AND breakers have NOT SAT/ UNSAT been installed, THEN perform the following:

(Step 3.5) STD: Determines SDC IV p fuses and breakers have been installed per initial conditions or simulator setup 7. Open IV-38-02, SDC SYSTEM IN IV 12 PASS/ FAIL (OUTSIDE)

(Step 3.6) p STD: Opens 38-02 by rotating control switch CW to OPEN 8. WHEN Reactor pressure is less than 120 SAT I UNSAT psig, un-isolate Shutdown Cooling System as follows:

(Step 3. 7) p STD: Determines Reactor pressure is less than 120 psig per initial conditions or simulator setup 8a Monitor Reactor vessel level SAT/ UNSAT (Step 3.7.1) p STD: Determines another operator is monitoring Reactor water level per initial conditions 8b IF Reactor vessel level begins to go down SAT/ UNSAT WHILE un-isolating Shutdown Cooling System, THEN isolate Shutdown Cooling p STD: Determines Reactor System AND determine cause of reduction in water level is stable in Reactor Vessel level subsequent steps 8c Open 38-13, SDC SYSTEM OUT IV 1 PASS/ FAIL (INSIDE)

(Step 3. 7 .3) p STD: Opens 38-13 by rotating control switch CW to OPEN NRC 2015 JPM S-1 Page 7 of 13 March 2015

Generation 8d Open 38-01, SDC SYTEM IN IV 11 (INSIDE)

PASS/ FAIL (Step 3.7.4) p STD: Opens 38-01 by rotating control switch CW to OPEN 9. Vent Shutdown Cooling pumps using the SAT/ UNSAT following valves: (step 3.8) p STD: Determines venting not required due to initial conditions

10. Vent heat exchangers using the following SAT I UNSAT valves: (Step 3.9) p STD: Determines venting not required due to initial conditions

11. Verify open the following valves: SAT I UNSAT (Step 3.10) STD: Observes green

38-134, SDC PUMP RECIRC VALVE 11 light off, red light on for all

38-131, SDC PUMP RECIRC VALVE 12

38-128, SDC PUMP RECIRC VALVE 13 Note: Candidate may disregard 38-128 because the associated pump is tagged out. 12. Start 11 SDC Pump as follows:

(Step 3.11) Note: Pump Seal was NOT discovered de-staged (Step 3.11.1) NRC 2015 JPM S-1 Page 8 of 13 March 2015 Exelon Generation 12a Verify SD COOLING TCV 11 manual controller selected for zero output demand (Step 3.11.2) 12b Using local indication, verify closed FCV-38-09, SDC 11 FCV (step 3.11.2.b)

Role Play: Acknowledge direction and report the appropriate loop FCV is closed. p p SAT/ UNSAT STD: Observes SD COOLING TCV 11 manual controller selected for zero output demand SAT/ UNSAT STD: Dispatches operator to verify closed FCV-38-09 Role Plays: For each of these dPIS steps, acknowledge direction and then report the appropriate valve position.

Candidate may just provide direction to perform actions by procedure step number. 12c Verify closed Gl, Instrument HP Blocking Valve -SDC Loop 11 (step 3.11.2.c) 12d Verify open G3, Instrument Equalizing Valve -SDC Loop 11 (step 3.11.2.d) 12e Verify closed G2, Instrument LP Blocking Valve -SDC Loop 11 (step 3.11.2.e) 12f Place 11 SDC Pump Control Switch in START UNTIL 11 SDC PUMP running light is lit (step 3.11.2.f)

NRC 2015 JPM S-1 Page 9 of 13 p p p p SAT I UNSAT STD: Dispatches operator to verify closed Gl SAT/ UNSAT STD: Dispatches operator to verify open G3 SAT/ UNSAT STD: Dispatches operator to verify closed G2 PASS/ FAIL STD: Starts SDC pump 11 by rotating control switch CW to START March 2015

Generation 12g Open G2, Instrument LP Blocking Valve -SDC Loop 11 (step 3.11.2.g) 12h Close G3, Instrument Equalizing Valve -SDC Loop 11 (step 3.11.2.h) 12i Open Gl, Instrument HP Blocking Valve -SDC Loop 11 (step 3.11.2.i)

13. Open respective SD Cooling TCV approximately 10% for selected SDC Loop:

38-09, SD COOLING TCV 11 NOTE: 1 minute after 11 SDC pump in service, verify tripped 11 SDC pump (event trigger).

Alarm K3-1-1, SDC Pump 11 trip, comes in on the pump trip. The alarm response procedure gives direction to start another pump. Cue: If applicant does not make a recommendation to place another SDC pump in service, ask "What would you recommend?".

Role Play: If candidate asks about normalizing SDC loop 11, tell them to leave SDC loop 11 as is. NRC 2015 JPM S-1 Page 10 of 13 p p p p SAT/ UNSAT STD: Dispatches operator to open G2 SAT/ UNSAT STD: Dispatches operator to close G3 SAT/ UNSAT STD: Dispatches operator to open Gl PASS I FAIL I NA STD: Opens 38-09 by rotating knurled knob CW Note: Step may be NA if pump trips prior to executing.

March 2015

Generation

14. Start 12 SDC Pump as follows:

(Step 3.11) Note: Pump Seal was NOT discovered de-staged (Step 3.11.1) 14a Verify SD COOLING TCV 12 manual controller SAT/ UNSAT selected for zero output demand p STD: Observes SD COOLING TCV 12 manual controller selected for zero output demand 14b Using local indication, verify closed FCV-38-SAT I UNSAT 10, SOC 12 FCV p STD: Dispatches Role Play: Acknowledge direction and operator to verify closed report the appropriate loop FCV is closed. FCV-38-10 Role Plays: When directed to operate valves in steps 3.11.2.1, m, and n, report the valves have been repositioned as directed.

14c Place 12 SDC Pump Control Switch in START PASS/ FAIL UNTIL 12 SOC PUMP running light is lit (Step 3.11.2.o) p STD: Starts SOC pump 12 by rotating control switch CW to START Role Plays: When directed to operate valves in steps 3.11.2.p, q, and r, report the valves have been repositioned as directed.

15. Open respective SD Cooling TCV PASS/ FAIL approximately 10% for selected SDC Loop: p STD: Opens 38-10 by 38-10, SD COOLING TCV 12 rotating knurled knob CW (step 3.11.3) NRC 2015 JPM S-1 Page 11of13 March 2015 Exelon Generation

16. If reactor water flashing occurs in SDC SAT I UNSAT System, reduce reactor water flow via selected SDC cooling TCV and maximize p STD: Pump amp RBCLC cooling water flow. indicator observed as steady. Cue: No flashing observed.

17. Adjust SDC COOLING TCV 12 for gradual SAT I UNSAT warmup of the system. STD: Rotate knob on NOTE: Operator will monitor temperatures controller 38-10 CW or on panel recorder.

CCW as required for a gradual warmup as NOTE: Operator may choose not to make p indicated on 38-136B.

any further adjustments based on the rate at which the loop is warming up with 38-10 10% open. Cue: Tell operator no further adjustments in the system are required.

18. Inform SM SDC Loop 12 in service SAT/ UNSAT p Cue: Acknowledge report Cue: Your task is complete.

Shutdown Cooling Loop 12 placed in service.

NRC 2015 JPM S-1 Page 12 of 13 March 2015 Exelon Generation NRC 2015 JPM S-1 JPM Handout Given:

The Reactor is shutdown with all rods in.

Reactor pressure is less than 120 psig.

Nl-OP-4 has been completed through step E.3.1 for placing Shutdown Cooling in service.

Shutdown Cooling has been filled and vented within the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and does not require further filling or venting.

Shutdown Cooling IV fuses/breakers have been installed.

SDC pump 13 is OOS for maintenance.

Reactor water level is being monitored by another operator.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), place Shutdown Cooling loop 11 in service per OP-4 starting at step E.3.2. Page 13 of 13 March 2015

Generation Training Id: 2015 NRC JPM S-2 Revision:

0.0 Title: Vent the Drywell Prior to Personnel Entry <212F Per Nl-OP-9 Approvals:

Developed By Validated By Facility Reviewer I Printed Name 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: NRC 2015 JPM S-2 Page 1of9 03/17/14 8/20/14 March 2015

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)

NRC 2015 JPM S-2 Page 2 of 9 March 2015 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. 2. Task Information:

a. Nl-223003-01004

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

3. Evaluation/

Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-2 Page 3 of 9 March 2015 Exelon

5. Simulator Setup (if required)

a. The reactor is in a shutdown condition.

b. Initialize simulator to IC-161. 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.2.6.2.

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.

NRC 2015 JPM S-2 Page 4 of 9 March 2015

_..,, Exelon Generation

1. 2. 3. 3a. Given:

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.2.6.2.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), vent the Drywell in accordance with Nl-OP-9, starting at step G.2.6.3.

Secure venting when Drywell pressure is below 0 psig. Provide repeat back of initiating cue SAT/ UNSAT p STD: Proper Cue: Acknowledge repeat back providing communications used correction if necessary Obtain a copy of the reference procedure and SAT I UNSAT review / utilize the correct section of the procedure p STD: Nl-OP-9 obtained, precautions and limitation

reviewed, section G.2.0 referenced Open the following valves: (Step 2.6) 201-10, DW AIR VENT & PURGE ISOLATION PASS/ FAIL VALVE 11 p STD: Rotates 201-10 control switch CW NRC 2015 JPM S-2 Page 5 of 9 March 2015

Generation 3b. 201-08, TOR AIR VENT & PURGE ISOLATION VALVE 11 3c. 201-32, DW N2 VENT & PURGE ISOLATION VALVE 11 3d. 201-16, TORUS N2 VENT & PURGE ISOLATION VALVE 11 4. 5. 6. Applicant should determine from initial conditions, a full de-inert is required for personnel entry to the Drywell and should select "Approximately 19.5%". (Step 2. 7) Note: Step 2.8 is N/ A Notify Chemistry that a Drywell purge is about to commence.

Start 201-35, DRYWELL & TORUS VENT & PURGE (Step 2.10) NRC 2015 JPM S-2 Page 6 of 9 p PASS/ FAIL STD: Rotates 201-08 control switch CW PASS/ FAIL P STD: Rotates 201-32 control switch CW PASS/ FAIL P STD: Rotates 201-16 control switch CW p SAT I UNSAT STD: Determines 19.5% oxygen per the initial conditions.

SAT/ UNSAT P STD: Proper communications used p PASS/ FAIL STD: Rotates 201-35 control switch CW March 2015

7. 8. Sa. 9. 9a. Exelon Generation Verify open the following valves: (Step 2.11)

201-21, DW & TOR VENT & PURGE FAN INLET BV

201-22, DW & TOR VENT & PURGE FAN OUTLET BV Throttle open 201-31, DW N2 VENT & PURGE ISOLATION VALVE 12 (Step 2.12) Throttle open 201-17, TORUS N2 VENT & PURGE ISOLATION VALVE 12 (Step 2.13) Cue: After 201-17 is opened, report drywell and torus pressure is below 0 psig for purposes of this JPM (time compression used). NRC 2015 JPM S-2 Page 7 of 9 p p p SAT/ UNSAT STD: Observes red light on, green light off for both PASS I FAIL STD: Rotates 201-31 control switch CW SAT/ UNSAT STD: Throttles 201-31 by using pull-to-stop feature of control switch PASS/ FAIL STD: Rotates 201-17 control switch CW SAT I UNSAT STD: Throttles 201-17 by using pull-to-stop feature of control switch March 2015 Exelon Generation

10. When drywell and Torus pressures drops BELOW 0 psig, open the following valves: lOa 201-09, DW AIR VENT & PURGE ISOLATION VALVE 12 lOb 201-07, TOR AIR VENT & PURGE ISOLATION VALVE 12 Cue: Another operator will complete this procedure.

Cue: Your task is complete.

SAT I UNSAT P STD: Continues the JPM based on examiner cue. PASS/ FAIL P STD: Rotates 201-09 control switch CW p PASS/ FAIL STD: Rotates 201-07 control switch CW Drywell vented to atmospheric pressure in accordance with Nl-OP-9.

NRC 2015 JPM S-2 Page 8 of 9 March 2015 Exelon Generation NRC 2015 JPM S-2 JPM Handout Given:

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.2.6.2.

(Operators Name), vent the Drywell in accordance with Nl-OP-9, starting at step G.2.6.3.

Secure venting when Drywell pressure is below O psig. Page 9 of 9 March 2015

Generation Training Id: 2015 NRC JPM S-3 Revision:

0.0 Title: MSIV Stroke Test and Limit Switch Test (N1-ST-Q26)

Approvals:

Signature I Printed Name Developed By /'J/ Paul Isham 03/17/14 Validated By Pat O'Brien 8/20/14 Facility Reviewer 15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM S-3 Page 1of10 March 2015 Exelon Generation References

1. Nl-ST-Q26

2. NUREG 1123 K/A 239001 A4.01, (4.2/4.1)

NRC 2015 JPM 5-3 Page 2 of 10 March 2015

=:rExelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate MSIV controls for a surveillance test and verify proper indications.

b. This JPM is NOT considered alternate path. 2. Task Information:

a. Nl-239001-01026

b. K/A 239001 A4.01, (4.2/4.1)

3. Evaluation I Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-3 Page 3 of 10 March 2015 Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in an operating condition

b. Initialize simulator to IC 162 6. JPM Setup (if required)

a. Section 7, prerequisites, and section 8.1 marked complete.

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.

NRC 2015 JPM S-3 Page 4 of 10 March 2015 Exelon Generation Given:

The plant is operating at 100% power.

All prerequisites for N1-ST-Q26 are complete.

Section 8.1 has been completed.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), test Main Steam Line Isolation Valve 112 in accordance with N1-ST-Q26, Section 8.2. 1. 2. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary Obtain a copy of the reference procedure and review/ utilize the correct section of the procedure

3. Prepare to initiate a Half-Scram on CHANNEL 11: (Step 8.2.1) 3a. Verify NO RPS Half-Scram signals exist 3b. Notify CRO that the following steps will initiate a Half-Scram NRC 2015 JPM S-3 Page 5 of 10 p p p p :':<'."'

:,}* ,, SAT/ UNSAT STD: Proper communications used SAT I UNSAT STD: N 1-ST-Q26

obtained, precautions

& limitations reviewed SAT/ UNSAT STD: Observes all scram solenoid lights energized SAT/ UNSAT STD: Proper communications used March 2015 Exelon Generation 3c. Verify all four MSIV SOV continuity ammeters indicate greater than lOOmA 4. 5. 6. Role Play: If dispatched to the Aux Control Room, acknowledge the request and report all four MSIV SOV continuity ammeters indicate greater than lOOmA Place Main Steam Isolation Valve 7% Test Switch to the 112 position (Step 8.2.2) Confirm 01-03 MSIV 112 white test light ON (Step 8.2.3) Confirm 01-03 MSIV 112 yellow light OFF (Step 8.2.4) Note: Step 8.2.5 will be N/A. p SAT I UNSAT STD: Dispatch another operator to the Aux Control Room to perform the verification PASS/ FAIL P STD: Test switch is rotated to the 112 position p p SAT/ UNSAT STD: White test light for MSIV 112 is verified SAT I UNSAT STD: Yellow light for MSIV 112 is verified energized Note: JPM steps 7 to 11 will occur in rapid sequence; expect annunciators Fl-1-7 and Fl-2-1. 7. Cue: Notify the candidate that you will be monitoring the valve mimic board for MSIV 112. Momentarily place 01-03 MSIV-112 control switch to CLOSE position (Step 8.2.6) p PASS/ FAIL STD: Rotates control switch for MSIV 112 momentarily CCW to CLOSE, then releases NRC 2015 JPM S-3 Page 6 of 10 March 2015

Generation

8. 9. Confirm RPS Channel 11 Half-Scram indications Cue: If Fl-1-7 is cleared before candidate completes verification, report that Fl-1-7 alarmed and cleared as expected.

Confirm 01-03, MSIV-112 automatic partial closure indications Cue: The MSIV 112 mimic light came on and went off as expected.

10. Confirm 01-03 MSIV-112 yellow light illuminated BRIGHT NRC 2015 JPM S-3 Page 7 of 10 p p SAT I UNSAT STD: Observes:

CHANNEL 11 SCRAM SOLENOID GROUPS 1, 2, 3, 4, white light off

CHANNEL 11 B.U. SCRAM S.D.V. VENT & DRAIN VALVE red light off

Annunciator Fl-1-7, RPS CH 11 MN STM LINE 11 ISOL VALVE CLOSED, alarms

Annunciator Fl-2-1, RPS CH 11 AUTO REACTOR TRIP, alarms SAT/ UNSAT STD: Observes:

01-03 MSIV-112 Green Light ON momentarily

01-03 MSIV-112 Red Light ON

01-03 MSIV-112 Mimic Light ON momentarily SAT I UNSAT P STD: Observes 01-03 MSIV 112 yellow test light ON brightly March 2015

=:rExelon Generation

11. Confirm 01-03 MSIV-112 automatic opening indications

12. Place MSIV 7% Test Switch to the OFF position Cue: Inform candidate that another operator has completed the Independent Verification.

13. Confirm 01-03 MSIV 112 White Test Light OFF 14. Confirm 01-03 MSIV 112 Yellow Light OFF 15. Depress REACTOR TRIP RESET at Panel E Fl-2-1 clears NRC 2015 JPM S-3 Page 8 of 10 p p SAT I UNSAT STD: Observes:

01-03 MSIV-112 Green Light OFF

01-03 MSIV-112 Red Light ON

01-03 MSIV-112 Mimic Light OFF PASS/ FAIL STD: Rotates Test Switch to OFF SAT/ UNSAT P STD: Observes White Test Light for MSIV-112 is OFF SAT/ UNSAT P STD: Observes Yellow Light for MSIV-112 is OFF PASS/ FAIL STD: Depresses Rx Trip RESET Button on Console March 2015

Generation

16. Confirm RPS Channel 11 Half-Scram indications clear Cue: Your task is complete.

Nl-ST-Q26 completed for MSIV 01-03. NRC 2015 JPM S-3 Page 9 of 10 SAT I UNSAT STD: Observes:

CHANNEL 11 SCRAM SOLENOID Groups 1,2,3,4 White Light ON

CHANNEL 11 BACKUP SCRAM VALVE S.D.V. VENT ND DRAIN VALVE Red Light ON

Annunciator Fl-1-7, RPS CH 11 MN STM LINE 11 ISOL VALVE CLOSED, clear

Annunciator Fl-2-1, RPS CH 11 AUTO REACTOR TRIP, clear March 2015 Exelon Generation NRC 2015 JPM 5-3 JPM Handout Given:

The plant is operating at 100% power.

All prerequisites for Nl-ST-Q26 are complete.

Section 8.1 has been completed.

(Operators Name), test Main Steam Line Isolation Valve 112 in accordance with Nl-ST-Q26, Section 8.2. Page 10 of 10 March 2015

=:""Exelon Generation Training Id: 2015 NRC JPM S-4 Revision:

0.0 Title: Transfer House Loads from Reserve to Normal -N 1-0P-30 Approvals:

Printed Name Developed By llh au s am 03/17/14 Validated By Leigh Mason 8/20/14 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: NRC 2015 JPM 5-4 Page 1of10 March 2015 Exelon Generation References

1. Nl-OP-30, 4.16KV, 600V, and 480V House Service 2. NUREG 1123 K/A 262001 A4.04, (3.6/3.7)

NRC 2015 JPM S-4 Page 2 of 10 March 2015

Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to manipulate electrical system controls to parallel two AC sources.

The operator will shilt house service loads from the reserve transformers to the normal transformers, as is done during a plant start up. b. This JPM is NOT considered alternate path. 2. Task Information:

a. Nl-262001-01001

b. K/ A 262001 A4.04, (3.6/3. 7) 3. Evaluation I Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM 5-4 Page 3 of 10 March 2015 Exelon Generation

5. Simulator Setup (if required)

a. The reactor is in a power operating condition

b. Initialize simulator to IC 162 c. Verify Powerboards 11 and 12 are ready to be transferred to the normal transformer.

6. JPM Setup (if required)

a. Provide copy of Nl-OP-30 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.

NRC 2015 JPM S-4 Page 4 of 10 March 2015

1. 2. 3. Exelon Generation Given:

The reactor is in an operating condition after a recent plant startup

The reserve transformers are supplying house loads

Main Generator load is stable

S-ODP-OPS-112 Attachment 4 has been completed for transferring House loads Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), transfer normal house service from the reserve transformers to normal in accordance with Nl-OP-30, section E.15. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary Obtain a copy of the reference procedure and review / utilize the correct section of the procedure Confirm Main Generator load stable (Step 15.1) p p SAT/ UNSAT STD: Proper communications used SAT I UNSAT STD: Nl-OP-30 obtained.

Precautions

& limitations reviewed

& section E.15 referenced SAT/ UNSAT STD: Observes main p generator megawatts stable (meters on Panels E or A7, digital indication on Panel K). Or determines stable from initial conditions.

NRC 2015 JPM S-4 Page 5 of 10 March 2015

=:r-Exelon Generation NRC 2015 JPM S-4 Page 6 of 10 March 2015 Exelon Generation

8. Close Breaker R113 AND immediately open R112 (Step 15.6) 9. Leave R112 control switch in neutral position (Step 15.7) 10. Place Sync Key in OFF position (Step 15.8) 11. Remove Sync Key from R113 (Step 15.9) 12. Insert Sync Key in R122 AND perform the following:

(Step 15.10) 12a Turn Sync Key ON 12b Confirm incoming voltage slightly above running voltage NRC 2015 JPM S-4 Page 7 of 10 .. P,/S. p p p p p PASS/ FAIL STD: Rotates Rl 13 control switch CW to CLOSE, observes red light on and green light off. When Rl 13 is closed, rotates Rl 12 control switch CCW to TRIP, observes green light on and red light off SAT/ UNSAT STD: Releases Rl 12 control switch to NEUTRAL SAT I UNSAT STD: Rotates Sync. Key in Breaker R113 CCW to OFF SAT/ UNSAT STD: Removes Sync. Key from Breaker R113 SAT I UNSAT STD: Positions Sync. Key in Breaker R122 PASS/ FAIL P STD: Rotates Sync. Key for Breaker R122 CW to ON p SAT/ UNSAT STD: Observes INCOMING and RUNNING voltages March 2015 Exelon Generation 12c IF required, THEN make voltage adjustment with Tap Changer on Transformer

10. 13. Close Breaker R122 AND immediately open R123 (Step 15.11) 14. Leave R123 control switch in neutral position (Step 15.12) 15. Place Sync Key in OFF position (Step 15.13) 16. Remove Sync Key from R122 (Step 15.14) 17. Adjust Power Boards 11 AND 12 voltages to 4160 volts using Tap Changer on Transformer

10. (Step 15.15) NRC 2015 JPM S-4 Page 8 of 10 SAT I UNSAT STD: Adjusts TAP CHGR P CONT TRANS 10 to match incoming and running voltages, if required p p p p p PASS/ FAIL STD: Rotates R122 control switch CW to CLOSE, observes red light on and green light off. When R122 is closed, rotates R123 control switch CCW to TRIP, observes green light on and red light off SAT/ UNSAT STD: Releases R123 control switch to NEUTRAL SAT I UNSAT STD: Rotates Sync. Key in Breaker R122 CCW to OFF SAT I UNSAT STD: Removes Sync. Key from Breaker R122 SAT I UNSAT I NA STD: Adjusts TAP CHGR CONT TRANS 10, if required March 2015

Generation

18. Notify Electrical Maintenance to complete Attachment 12 of Nl-0P-43A to confirm Auto transfer capability.

(Step 15.16) Cue: Your task is complete.

p SAT I UNSAT STD: Proper communications used House loads are supplied by the normal transformer

-T-10. NRC 2015 JPM S-4 Page 9 of 10 March 2015

=:r-Exelon Generation NRC 2015 JPM 5-4 JPM Handout Given:

The reactor is in an operating condition after a recent plant startup

The reserve transformers are supplying house loads

Main Generator load is stable

S-ODP-OPS-112 Attachment 4 has been completed for transferring House loads {Operators Name), transfer normal house service from the reserve transformers to normal in accordance with Nl-OP-30, section E.15. Page 10 of 10 March 2015 Exelon Generation Training Id: 2015 NRC JPM S-5 Revision:

0.0 -----Shift Reactor Building Operating Exhaust and Supply Fans From Title: #11 to #12 (Faulted)

Approvals:

Developed By Paul Isham 03/17/14 Validated By Pat O'Brien 8/20/14 Facility Reviewer Greg Elkins Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM S-5 Page 1of9 March 2015

References

1. Nl-OP-10, Reactor Building

Heating, Cooling, and Ventilating System 2. NUREG 1123 K/A 288000 A4.01, (3.1/2.9)

NRC 2015 JPM S-5 Page 2 of 9 March 2015

,1118ar*

Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate the Reactor Building Ventilation System. b. This JPM is not considered alternate path, but it is faulted, because one of the newly started fans displays abnormal operating parameters which should prompt the operator to restore reactor building ventilation back to a functioning lineup. 2. Task Information:

a. Nl-288001-01002

b. K/A 288000 A4.01, (3.1/2.9)

3. Evaluation

/Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-5 Page 3 of 9 March 2015

=::rExelon Generation

5. Simulator Setup (if required)

a. Initialize simulator to IC-163 b. RX Building Supply and Exhaust Fans #11 in service.

c. RB VENT JPM SETUP

Event trigger -set TRG 3 to ZDHVF02T==O

Overrides assigned to TRG 3 (Delete overrides when Supply Fan 12 switch is taken to STOP.)

11S68DI54912, RB Supply Fan 12 & Inlet Damper, ON

11M4A052590, React Bldg supply Fan 12 AMP, Analog Value 1

11DS229L05624, Reactor Bldg Supply Fan 12 Green light OFF

11DS230L05625, Reactor Bldg Supply Fan 12 SLOW Red light ON

11DS216L05617, Reactor Bldg Supply Fan 12 Inlet Damper Green light OFF DT=lSsec

11DS217L05618, Reactor Bldg Supply Fan 12 Inlet Damper Red light ON 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.

NRC 2015 JPM S-5 Page 4 of 9 March 2015

1. 2. 3. 4. Exelon Generation(,

Given:

Reactor Building Exhaust Fan #11, and Reactor Building Supply Fan # 11 are in service.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Place Reactor Building Exhaust and Supply Fans #12 in service IAW Nl-OP-10 Section F.1.0 and F.2.0. '*' '.' Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper communications correction if necessary used Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the procedure p STD: Nl-OP-10 obtained.

Precautions

& limitations reviewed

& section F.1.0 and F.2.0 referenced.

Verify operating RX Building supply and SAT I UNSAT exhaust fans in SLOW. (Step 1.2.1) STD: Visually observe p REACTOR BLDG SUPPLY FAN 11 and REACTOR BLDG EXHAUST FAN 11 fans in SLOW red slow light illuminated.

Start REACTOR BLDG EXHAUST FAN 12 on PASS/ FAIL SLOW (Step 1.2.2) STD: Rotate REACTOR BLDG p EXHAUST FAN 12 control switch CW to the slow position observe red slow light illuminated, green light off. NRC 2015 JPM S-5 Page 5 of 9 March 2015 Exelon Generation

\

' 5. Confirm damper 202-07, REACTOR BLDG SAT/ UNSAT EXHAUST FAN 12 OUTLET DAMPER open. p (Step 1.2.3) STD: Observe 202-07 open red light on, green light off. 6. Stop REACTOR BLDG EXHAUST FAN 11. PASS/ FAIL (Step 1.2.4) p STD: Rotate REACTOR BLDG EXHAUST FAN 11 control switch CCW to the Off position.

7. Confirm damper 202-08, REACTOR BLDG SAT/ UNSAT EXHAUST FAN 11 OUTLET DAMPER closed. (Step 1.2.5) p STD: Observe REACTOR BLDG EXHAUST FAN 11 OUTLET DAMPER closed green light on, red light off. 8. Confirm normal system flow. SAT I UNSAT (Step 1.3) p STD: Observe annunciator Ll-2-5 RB VENT EXH FLOW LOW is clear. 9. Start REACTOR BLDG SUPPLY FAN 12 on PASS/ FAIL SLOW. (Step 2.2.2) STD: Rotate REACTOR BLDG p SUPPLY FAN 12 control switch CW to the Slow position observe red slow light illuminated, green light off. 10. Confirm damper FCV 202-04, REACTOR SAT I UNSAT / NA BLDG SUPPLY FAN 12 INLET DAMPER open. p (Step 2.2.3) STD: Observe 202-04 open red light on, green light off NRC 2015 JPM S-5 Page 6 of 9 March 2015 Exelon Generation Note: Candidate may not notice amps low and continue in procedure to secure Fan 11. There are 2 success paths. 1. Low amps identified after Supply Fan 12 start. Candidate performs steps 11,12,13 and 18, with step 13 a critical step. 2. Low amps not identified after Supply Fan 12 start. Candidate performs steps 14,15,16,17,18, with steps 16 and 17 as critical step. 11. Identify low amps on REACTOR BLDG SUPPLY FAN 12. 12. Inform SM of low amps on REACTOR BLDG SUPPLY FAN 12. Cue: As SM, concur and allow Fan 11 to remain in service.

13. Secure REACTOR BLDG SUPPLY FAN 12. Note: Booth operator, delete all overrides when Supply Fan 12 is secured.

14. Secure REACTOR BLDG SUPPLY FAN 11 Cue: If directed from Ll-2-4 report the following:

Heating Unit is tripped

Inlet Filter differential pressure is normal NRC 2015 JPM S-5 Page 7 of 9 SAT I UNSAT I NA p STD: Observe low amps on Fan 12 (5-10 amps) with Fan 11 amps remaining at normal ( ,,,30 amps). p p p SAT I UNSAT / NA STD: Recommend Fan 11 remains in service and Fan 12 be shutdown.

PASS / FAIL / NA STD: Rotate REACTOR BLDG SUPPLY FAN 12 control switch CCW to the Off position.

SAT/ UNSAT I NA STD: Rotate REACTOR BLDG SUPPLY FAN 11 control switch CCW to the Off position and observe red slow light off, green light illuminated.

Observe annunciator Ll-3-4 and Ll-2-4 alarm Observe RB dp indication rises indicating high negative dp March 2015

Generation

15. Report abnormal indication to SM Cue: As SM, concur and allow Fan 11 to be returned to service and Fan 12 to be shutdown.

16. Start REACTOR BLDG SUPPLY FAN 11 on SLOW. Annunciators Ll-3-4 and Ll-2-4 clear RB dp indication returns to normal 17. Secure REACTOR BLDG SUPPLY FAN 12 Note: Booth operator, delete all overrides when Supply Fan 12 is secured.

18. Notify CRS/SM that REACTOR BLDG SUPPLY FAN 11 has been returned to service with normal dp and REACTOR BLDG supply FAN 12 is secured.

Cue: Acknowledge report. Cue: Your task is complete.

p SAT I UNSAT I NA STD: Recommend returning Fan 11 to service and securing Fan 12 PASS I FAIL I NA STD: Rotate REACTOR BLDG SUPPLY FAN 11 control switch CW to the Slow position observe red slow light illuminated, green light off. PASS / FAIL I NA STD: Rotate REACTOR BLDG SUPPLY FAN 12 control switch CCW to the Off position and observe red slow light off, green light illuminated.

SAT I UNSAT I NA STD: Proper communications used. Misoperation identified on Supply Fan 12. Supply Fan 11 is running with either Exhaust Fan 11 or 12 running.

NRC 2015 JPM S-5 Page 8 of 9 March 2015 Exelon Generation NRC 2015 JPM S-5 JPM Handout Given:

Reactor Building Exhaust Fan #11, and Reactor Building Supply Fan # 11 are in service.

(Operators Name), Place Reactor Building Exhaust and Supply Fans #12 in service IAW Nl-OP-10 Section F.1.0 and F.2.0. Page 9 of 9 March 2015

Generation Training Id: 2015 NRC JPM S-6 Revision:

0.0 Title: Control Rod Exercising Operability Test N1-ST-W1 (Alternate Path) Approvals:

Si rinted Name Developed By Isham 01/29/2015 Validated By Kerry Henderson 02/03/15 Facility Reviewer Greg Elkins Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: JPM S-6 Page 1of12 NRC March 2014 Exelon Generation References

1. Nl-ST-Wl, Control Rod Exercising Operability Test 2. Nl-OP-5, Control Rod Drive System JPM S-6 Page 2 of 12 NRC March 2014

=::--Exelon Generation Instructor Information A. JPM Information

1. Description

2. 3. 4. a. This JPM tests the operator's ability to perform the weekly control rod exercise surveillance, N 1-ST-Wl.

b. This JPM is considered alternate path because rod position indication will be lost while exercising rods, requiring the operator to take actions prescribed in the Control Rod Drive Operating Procedure.

Task Information:

a. Nl-214000-01001, Monitor RPIS b. K/A 214000, A4.02 (3.8/3.8)

Evaluation I Task Criteria Perform Simulator No Yes Yes Recommended Start Location

a. Unit 1 Simulator JPM S-6 Page 3 of 12 NRC March 2014

Generation

5. Simulator Setup (if required)

a. Initialize simulator to IC-163 b. Verify RD08R0231 is assigned to trigger 1 c. Verify Event Trigger #1 hzlrdin==l&hzlrdself(72)==1

d. Ensure process computer is not available

6. JPM Setup (if required)

a. Prepare a copy of Nl-ST-Wl, marked with step 6.1 -6.2.4 complete.

JPM 5-6 Page 4 of 12 NRC March 2014 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.

JPM S-6 Page 5 of 12 NRC March 2014

&:r'Exelon Generation

1. 2. 3. JPM S-6 Given:

The plant is online.

Weekly Control Rod exercising is in progress.

The process computer is unavailable.

Nl-ST-Wl is complete through step 6.2.4.

No rods are expected to double notch. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Complete Nl-ST-Wl, starting at step 6.2.5. Begin with rod 02-35 and continue with the sequence outlined in attachment

1. Document applicable rod movement information on attachment

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

used. Obtain a copy of Nl-ST-Wl and review/ p SAT I UNSAT utilize the correct section of the procedure STD: Obtains copy of Nl-ST-Wl. Section 6.2 is referenced Depress the rod select pushbutton for p SAT I UNSAT Control Rod to be tested on Rod Map Display STD: Depresses pushbutton for at E panel. (Step 6.2.5) control rod 02-35. Observes white light lit. Page 6 of 12 NRC March 2014

4. 5. 6. 7. 8. 9. Exelon Generation RECORD selected control rod's initial position on Attachment 1, Control Rod Exercising Data Sheet. (Step 6.2.6) Cue: If the applicant requests status of V138 (step 6.2. 7), report V138 has a normal response.

Confirm the following:

(Step 6.2.8)

Rod select pushbutton back lighted on Rod Map Display

Select light illuminated for appropriate Control Rod at F Panel Step 6.2.9 -"IF Control Rod is expected to double notch ... " PLACE 4S1, CONTROL ROD MOVEMENT switch to ROD IN position UNTIL ROD IN light illuminates.

(Step 6.2.10) Determines steps 6.2.11, 6.2.12, 6.2.14, and 6.2.15 are NA Record the following on Attachment 1:

New control rod position

Drive-To-Reactor d/p (step 6.2.13) 10 Withdraw control rod to initial position as follows:

(step 6.2.16) JPM S-6 Page 7 of 12 p p p p p p SAT/ UNSAT STD: Records position 48 for control rod 02-35 SAT/ UNSAT STD: Observes both white lights lit. SAT I UNSAT STD: Determine step is NA per initial conditions.

PASS I FAIL STD: Places control rod movement switch to the Rod In position.

Observes rod settle at position

46. SAT/ UNSAT SAT/ UNSAT STD: Records position 46 for control rod 02-35. And approximately 250 psi differential pressure.

NRC March 2014

=::""Exelon Generation 10.a Confirm the following:

p SAT/ UNSAT STD: Observes both white

Rod select pushbutton back lighted on lights lit. Rod Map Display

Select light illuminated for appropriate Control Rod at F Panel 10.b PLACE CONTROL ROD MOVEMENT switch in p PASS I FAIL ROD OUT NOTCH, UNTIL ROD IN light STD: Places control rod illuminates.

movement switch to the Rod Out Notch position.

Observes rod settle at position

48. 10.c CONFIRM next higher even position p SAT I UNSAT illuminates at F Panel. STD: Observes rod settle at position

48. 10.d Verify final position equals initial position and p SAT/ UNSAT record final position on attachment

1. STD: Records final position on attachment 1 and confirms Examiner note: Withdraw to position 48 initial and final positions are the same. may be performed concurrently with the coupling check. 11. Perform coupling check (step 6.2.17):

11.a SIMULTANEOUSLY PLACE 4Sl to ROD OUT p PASS/ FAIL NOTCH AND 4S3, CONTROL ROD N STD: Simultaneously places OVERRIDE switch to NOTCH OVERRIDE.

Control Rod Movement Switch to Rod Out Notch and the Control Rod N Override Switch to Notch Override.

11.b CONFIRM the following:

p SAT I UNSAT STD: Observes position 48 and

Position 48 illuminates with red red backlighting while holding backlighting remains illuminated for switches.

Control Rod selected at F Panel

CONTROL ROD OVERTRAVEL annunciator, F3-1-6, does NOT alarm JPM S-6 Page 8 of 12 NRC March 2014

=::"Exelon Generation°'

11.c RECORD Withdrawal Stall Flow on Attachment

1. 11.d Record Satisfactory coupling check 12. Select next rod to be exercised 12.a Depress the rod select pushbutton for Control Rod to be tested on Rod Map Display at E panel. (Step 6.2.5) 12.b RECORD selected control rod's initial position on Attachment 1, Control Rod Exercising Data Sheet. (Step 6.2.6) 13. 14. 15. JPM S-6 Cue: If the applicant requests status of V138 (step 6.2. 7), report V138 has a normal response.

Confirm the following:

(Step 6.2.8)

Rod select pushbutton back lighted on Rod Map Display

Select light illuminated for appropriate Control Rod at F Panel Step 6.2. 9 -"IF Control Rod is expected to double notch ... " PLACE 4Sl, CONTROL ROD MOVEMENT switch to ROD IN position UNTIL ROD IN light illuminates.

(Step 6.2.10) Page 9 of 12 p p p p p p p SAT I UNSAT STD: Observes stall flow on F Panel. Records on att 1. SAT/ UNSAT STD: Checks appropriate block in attachment

1. SAT/ UNSAT STD: Depresses pushbutton for control rod 02-31. Observes white light lit. SAT/ UNSAT STD: Records position 48 for control rod 02-31 on attachment

1. SAT/ UNSAT STD: Observes both white lights lit. SAT I UNSAT STD: Determine step is NA per initial conditions.

PASS/ FAIL STD: Places control rod movement switch to the Rod In position.

Observes rod start to move. NRC March 2014 Exelon Generation When the rod is moved in, RPIS will fail initiating the alternate path. The applicant should determine rod position is unknown and references Nl-OP-5, Off Normal section to respond to the loss of rod position indication.

16. Verify indicating light NOT burnt out at F Panel. (Nl-OP-5 Step H.10.1) Cue: Another operator verified the light was not burnt out. Note: The applicant may make the determination that a light is not burnt out since all position indication for the rod was lost. 17. Notify Reactor Engineering.

(Nl-OP-5 Step H.10.2) Cue: When contacted as Reactor Engineering, acknowledge report. 18. IF control rod lacks position indication, THEN perform the following:

(Nl-OP-5 Step H.10.3) 18.a Insert control rod one notch. JPM S-6 Page 10 of 12 p p p SAT I UNSAT STD: Determines lights not burnt out. SAT I UNSAT STD: Reports loss of rod position indication to Reactor Engineering PASS/ FAIL STD: Momentarily places control rod movement switch to Rod In. NRC March 2014 18.b 19. 20. JPM S-6 Exelon Generation Confirm the following:

p SAT I UNSAT

ROD IN light illuminates for STD: Observes proper response approximately three seconds.

from RMCS timer lights. Observes next lower rod

ROD OUT SETTLE light illuminates for position does not display.

approximately four seconds AFTER ROD IN light extinguishes.

Next lower even position illuminates

. IF control rod lacks position indication at more than one position AND position CANNOT be determined by other means, THEN perform following:

(Nl-OP-5 Step H.10.4) Fully insert control rod. p PASS/ FAIL STD: Places and holds control rod movement sw. to Rod In. Once control rod 02-31 is being fully inserted, provide the following Cue: Cue: Time compression.

The rod is fully inserted.

Your task is complete, another operator will complete the remainder of the ARP actions.

Control Rod 02-31 is being fully inserted.

Page 11of12 NRC March 2014 JPM S-6 Exelon Generation JPM Handout Given:

The plant is online.

Weekly Control Rod exercising is in progress.

The process computer is unavailable.

Nl-ST-Wl is complete through step 6.2.4.

No rods are expected to double notch. (Operators Name), Complete Nl-ST-Wl, starting at step 6.2.5. Begin with rod 02-35 and continue with the sequence outlined in attachment

1. Document applicable rod movement information on attachment

1. Page 12 of 12 NRC March 2014 Exelon Generation Training Id: 2015 NRC JPM S-7 Revision:

0.0 -----Title: Place a Second RWCU Pump in Service Approvals:

Si Developed By 03/17/14 Validated By Leigh Mason 8/21/14 Facility Reviewer Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM S-7 Page 1of9 March 2015

S: 'r'Exelon Generation References

1. Nl-OP-3, RWCU 2. NUREG 1123 K/A 204000 A4.01, (3.1/3.0)

NRC 2015 JPM 5-7 Page 2 of 9 March 2015 Exelon Generationoo Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to operate the RWCU system. The operator will place a second RWCU pump in service and stabilize parameters.

b. This JPM is NOT considered alternate path. 2. Task Information:

a. Nl-204000-01039

b. K/A 204000 A4.01, (3.1/3.0)

3. Evaluation/

Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-7 Page 3 of 9 March 2015 Exelon Generation

5. Simulator Setup (if required)

a. Initialize simulator to IC 164 b. Verify RWCU pump 12 is running c. Verify 33-39, Cleanup PCV 12 (HP) is in AUTO or BAL d. Verify 33-40, Cleanup Sys Flow, is in MANUAL e. Verify system flow is between 180 -220 x 103 lbm/hr f. Verify NRHX outlet temperature (F359) is displayed

g. Verify RHX outlet temperature (F363) is displayed

h. Verify nuisance annunciators failed off: 1) Al-4-6 2) A2-3-2 3) A2-4-4 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.

NRC 2015 JPM 5-7 Page 4 of 9 March 2015

Generation

1. 2. Given:

The plant has scrammed

The Reactor Water Cleanup System is to be lined up to support further plant shutdown

NRHX outlet temperature (F359) and RHX outlet temperature (F363) are displayed on the R-time screen. Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), place a second Reactor Water Cleanup Pump in service in accordance with Nl-OP-3, section E.7. Establish system flow at 325-350 X 103 lbm/hr. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary Obtain a copy of the reference procedure and review/ utilize the correct section of the procedure p p SAT/ UNSAT STD: Proper communications used SAT I UNSAT STD: Nl-OP-3 obtained Precautions

& limitations reviewed Section E.7.0 referenced NRC 2015 JPM S-7 Page 5 of 9 March 2015

3. 4. 5. 6. 7. Exelon Generation Monitor NON-REGENERATIVE HX outlet temp and REGENERATIVE HX inlet temp (Step 7.1) Cue: F359 and F363 are indicated on time display Verify adequate margin exists to core thermal power limits to prevent exceeding design or administrative limits when a second cleanup pump is started and flow is raised (8-12 MWth) (Step 7.3) Verify closed 33-15 CLEANUP PUMP 1 DISCHARGE VALVE (Step 7.4.1) Adjust 33-40, CLEANUP SYS FLOW, using RMC-33-151 to establish cleanup system flow between 180 x 103 and 220 x 103 lbm/hr (360 -440 gpm) (Step 7.4.2) Verify Open 33-160, CLEANUP PUMP RECIRC VALVE 11 (Step 7.4.3) NRC 2015 JPM S-7 Page 6 of 9 p p SAT I UNSAT STD: Monitor REGERATIVE HX outlet temp (F359) and REGENERATIVE HX initial temp (F363) during the performance of this section UNTIL system parameters stabilize, AND ensure temperatures do not exceed 120°F as indicated on computer points F359 and F363 SAT/ UNSAT STD: Verifies core power is less than 1842 MWth SAT/ UNSAT STD: Observes green light P on, red light off for 33-15 Cleanup Pump 1 Discharge Valve p p SAT/ UNSAT STD: Verifies system flow on chart recorder 35-150 or MA station 33-151 SAT/ UNSAT STD: Observes red light on March 2015

Generation@

8. Verify system pressure as indicated on PI-35-131A is being maintained 80 -100 psig (Step 7.4.4) 9. START Cleanup Pump 11 (Step 7.4.5) 10. Perform simultaneously:

(Step 7.4.6) lOa Slowly jog open 33-15, CLEANUP PUMP 11 DISCHARGE VALVE Note: This valve must be opened in small increments to maintain proper system pressure lOb Verify system pressure maintained between 80 -100 psig Note: System pressure may momentarily drop below 80 psig while the PCV responds lOc Maintain pump discharge pressure less than 1400 psig by opening 33-40, CLEANUP SYS FLOW, using RMC-33-151 NRC 2015 JPM S-7 Page 7 of 9 p p p p p SAT/ UNSAT STD: Observes system pressure on PI-35-131A is 80 -100 psig PASS/ FAIL STD: Rotates control switch for Cleanup Pump 11 CW to start and observes red flag in window, red light on, green light off, and motor amps increase PASS/ FAIL STD: Rotates CLEANUP PUMP 11 DISCHARGE VALVE control switch CW to open, until red light is on and green light is off SAT/ UNSAT STD: Observes proper response of in-service PCV in AUTO OR adjusts service PCV in MANUAL while jogging open 33-15 to maintain system pressure 80 -100 psig SAT I UNSAT STD: Adjusts RMC-33-151 as required to maintain discharge pressure below 1400 psig March 2015

Generation

11. When 33-15, CLEANUP PUMP 11 DISCHARGE VALVE, is fully open, adjust 33-40 using RMC-33-151, CLEANUP SYS FLOW, to maintain desired flow 250 x 103 -380 x 103 lbm/hr (500 -760 gpm) (Step 7.4.7) Note: 325-350 x 103 lbm/hr given in initiating cue Cue: Your task is complete.

p PASS/ FAIL STD: Rotates knob CW to raise system flow to approximately 325-350 x 103 lbm/hr Second Reactor Water Cleanup Pump is in service and system flow adjusted to approximately 325-350 x 103 lbm/hr. NRC 2015 JPM S-7 Page 8 of 9 March 2015 Exelon Generation NRC 2015 JPM S-7 JPM Handout Given:

The plant has scrammed

The Reactor Water Cleanup System is to be lined up to support further plant shutdown

NRHX outlet temperature (F359) and RHX outlet temperature (F363) are displayed on the R-time screen. (Operators Name), place a second Reactor Water Cleanup Pump in service in accordance with Nl-OP-3, section E.7. Establish system flow at 325-350 X 103 lbm/hr. Page 9 of 9 March 2015 Exelon Generation Training Id: 2015 NRC JPM S-8 Revision:

0.0 Title: Initiate Liquid Poison Injection, RWCU Fails To Isolate Approvals:

Signature I Printed Name Developed By 03/07/14 Validated By Pat O'Brien 8/21/14 Facility Reviewer

__ ..,..., ___ ____________

z/{J/a Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM 5-8 Page 1of9 March 2015

=:r-Exelon Generation References

1. Nl-EOP-HC Attachment 10 2. NUREG 1123 K/A 211001 Al.08, (3.7/3.8)

NRC 2015 JPM S-8 Page 2 of 9 March 2015 Exelon Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to initiate liquid poison and verify proper isolations occur. b. This JPM is not considered alternate path. 2. Task Information:

a. Nl-211000-01006

b. K/A 262001 211001 Al.08, (3.7/3.8)

3. Evaluation

/ Task Criteria Perform Simulator No No Yes 4. Recommended Start Location

a. Unit 1 Simulator NRC 2015 JPM S-8 Page 3 of 9 March 2015

Generation

5. Simulator Setup (if required)

a. The reactor is in a failure to scram b. Initialize simulator to IC 165 c. Verify the following malfunctions are inserted

RD33A, RD33C, and RD33E at position 48

RD33B and RD33D at position 06

CU12 and CU13 to establish RWCU isolation failure d. Verify Mode Switch in shutdown

e. Verify ADS bypassed

f. Allow conditions to stabilize.

6. JPM Setup (if required)

a. No steps need to be marked up. B. Read Before Every l PM Perform a nee 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.

NRC 2015 JPM S-8 Page 4 of 9 March 2015

1. 2. 3. Exelon Generation Given:

The plant was operating at 100% power

A failure to scram has occurred Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), inject Liquid Poison into the Reactor Vessel with Liquid Poison pump 11 in accordance with Nl-EOP-HC, Attachment

10. Provide repeat back of initiating cue Cue: Acknowledge repeat back providing correction if necessary Obtain a copy of the reference procedure and review/ utilize the correct section of the procedure Place Liquid Poison System keylock selector switch to SYS 11 (Step 1.0) p p p SAT I UNSAT I NA STD: Proper communications used SAT I UNSAT I NA STD: Nl-EOP-HC, Attachment 10 obtained.

PASS/ FAIL STD: Keylock selector switch is rotated CW to SYS 11 NRC 2015 JPM S-8 Page 5 of 9 March 2015 Exelon Generation

4. Confirm:

(Step 2.0) 5.

Both explosive valves fire

Liquid Poison pump 11 Starts

RWCU System isolates Note: RWCU will fail to isolate Notify CRS that the RWCU system failed to isolate Role Play: Acknowledge RWCU System failed to isolate NRC 2015 JPM S-8 Page 6 of 9 p p SAT/ UNSAT STD:

Observes squib valves 11 and 12 continuity lights off SAT/ UNSAT

Observes Liquid Poison pump 11 red light ON, green light OFF, amps and pressure rise PASS/ FAIL

Diagnoses failure of RWCU to isolate:

RWCU system isolation valves remain open with green lights OFF, red lights ON, RWCU pump in service SAT I UNSAT STD: Proper communication used OPS-01) March 2015

=="'Exelon Generation

6. 7. 8. 9. IF RWCU does NOT automatically isolate THEN manually isolate the RWCU system IAW Nl-OP-3 Note: The Operator may immediately close RWCU isolation valves 33-0lR,33-02R and 33-04R and/or trip the running RWCU pump. This satisfies JPM steps 7, 8 and/or 12, and is acceptable to be performed prior to referencing the procedure, as it is a backup to a failed automatic operation.

Provide close signal to both valves below at H panel (Step H.11.1)

Close 33-02R

Close 33-04 Secure all operating cleanup pumps (Step H.11.2) Open ONE of the following valves

33-10, Cleanup to Waste Disposal BV

33-11, Cleanup to Condenser BV (Step H.11.3) p p p p SAT/ UNSAT STD: Refers to Nl-OP-3, Section H.11 PASS/ FAIL STD: Closes33-02R & 33-04 by rotating individual control switches CCW SAT/ UNSAT STD: Secures RWCU pump 12 by rotating control switch CCW to STOP SAT/ UNSAT STD: Opens ONE of the listed valves using common control switch Role Play: When asked, state that Rapid Depressurization is NOT required and that RWCU system is to remain pressurized

10. Marks step 11.4, N/A, rapid depressurization NOT required NRC 2015 JPM S-8 Page 7 of 9 p SAT/ UNSAT STD: Step 11.4 marked N/A March 2015

11. 12. 13. 14. Exelon Generation If high pressure system is to remain SAT/ UNSAT pressurized, THEN close 33-41, AO Blocking p Valve. STD: Closes 33-41, AO (Step H.11.5) Blocking Valve by rotating control switch CCW Provide close signal at H Panel to 33-0lR, CU PASS/ FAIL Return Isolation Valve 1 (inside)

(Step H.11.6) STD: Provides close signal p at H Panel to 33-0lR, CU Return Isolation Valve 1 (inside),

by rotating control switch CCW Adjust in-service PCV AND 33-165, Cleanup SAT/ UNSAT to Cond & Waste Flow, as required to maintain Cleanup system pressure less than STD: Adjusts in-service PCV AND 33-165, Cleanup 110 psig AND minimize reject flow p to Cond & Waste Flow, as (Step H.11.7) required to maintain Cleanup system pressure less than 110 psig AND minimize reject flow Verify closed the following valves SAT I UNSAT (Step H.11.8)

IV-33-02R p STD: Verifies closed the

IV-33-04 listed valves (green light ON, red light OFF)

IV-33-0lR Cue: Your task is complete.

Liquid Poison pump 11 injecting into the Reactor Vessel and Reactor Water Cleanup isolated.

NRC 2015 JPM S-8 Page 8 of 9 March 2015 Exelon Generation NRC 2015 JPM 5-8 JPM Handout Given:

The plant was operating at 100% power

A failure to scram has occurred (Operators Name), inject Liquid Poison into the Reactor Vessel with Liquid Poison pump 11 in accordance with Nl-EOP-HC, Attachment

10. Page 9 of 9 March 2015 Exelon Generation Training Id: 2015 NRC Plant P-1 Revision:

0.0 Title: Air Start the Diesel Fire Pump Approvals:

Si nature Printed e Developed By Paul Isham 03/18/14 Validated By Leigh Mason 8/19/14 Facility Reviewer Approximate Duration:

20 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM P-1 Page 1 of 7 March 2015 Exelon Generation References

1. N 1-0P-21A, Fire Protection System -Water 2. NUREG 1123 K/A 286000, A3.01 (3.4/3.4)

NRC JPM P-1 Page 2 of 7 March 2015

Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to locally start the diesel fire pump with a loss of control power. b. This JPM is not considered alternate path 2. Task Information:

a. Nl-286000-04039

b. K/ A 286000, A3.0l (3.4/3.4)

3. Evaluation/

Task Criteria Simulate Plant No No Yes 4. Recommended Start Location

a. Unit 1 Turbine Building

5. JPM Setup (if required)

a. Provide a copy of Nl-OP-21A NRC JPM P-1 Page 3 of 7 March 2015

=:rExelon 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.

NRC JPM P-1 Page 4 of 7 March 2015

1. 2. 3. 4. Exelon Generation Given:

The plant is shutdown

A total loss of DC power has occurred Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), start the diesel fire pump per Nl-OP-21A, Section H.6 Provide repeat back of initiating cue SAT/ UNSAT Cue: Acknowledge repeat back providing p STD: Proper correction if necessary.

communications used Obtain a copy of the reference procedure and SAT/ UNSAT review / utilize the correct section of the procedure p STD: Nl-OP-21A obtained.

Precautions Cue: Step 6.1 is complete and limitations reviewed.

Section H.6 referenced.

Place Diesel Fire Pump Control Switch to SAT I UNSAT OFF. s STD: Local Control Switch rotated CW to OFF in Diesel Fire Pump Room Manually open 100-1211, Solenoid Operated PASS/ FAIL Inlet Valve, to the Woodward Governor.

s STD: Manually opens 100-1211 by rotating override lever CW NRC JPM P-1 Page 5 of 7 March 2015 Exelon Generation The Diesel Fire Pump has been manually started.

NRC JPM P-1 Page 6 of 7 March 2015

=:r-Exelon Generation NRC JPM P-1 JPM Handout Given:

The plant is shutdown

A total loss of DC power has occurred (Operators Name), start the diesel fire pump per Nl-0P-21A, Section H.6 Page 7 of 7 March 2015

Generation Training Id: 2015 NRC Plant P-2 Revision:

0.0 OATC Actions For Control Room Evacuation

{Nl-SOP-21.2)

Title: {Alternate Path) Approvals:

Developed By Validated By 08/19/2014 Facility Reviewer z;f 1/1;--25 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC JPM P-2 Page 1of10 March 2015 Exelon Generation References

1. Nl-SOP-21.2

2. NUREG 1123 K/A 295016 AAl.04 (3.1/3.2)

NRC JPM P-2 Page 2 of 10 March 2015

Instructor Information A. JPM Information

1. Description

2. 3. 4. 5. a. This JPM tests the operator's ability to execute OATC actions for a control room abandonment.

The actions are primarily associated with local operation of electrical distribution components.

b. This JPM is considered alternate path because after reporting to the Emergency Diesel Generators, a loss of offsite power will occur causing both EDGs to load. The operator will be required to execute override actions for the loss of offsite power and the subsequent Hot EDG. Task Information:

a. Nl-296000-01003-01

b. K/A 295016 AAl.04 (3.1/3.2)

Evaluation I Task Criteria Simulate Plant No Yes Yes Recommended Start Location

a. Unit 1 Turbine Building JPM Setup (if required)

a. Provide a copy of Nl-SOP-21.2 NRC JPM P-2 Page 3 of 10 March 2015

=:r-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.

NRC JPM P-2 Page 4 of 10 March 2015

Generation

1. 2. 3. Given:

You are the OATC.

A Control Room Evacuation has been ordered due to a fire.

The Reactor has been scrammed and all control rods are fully inserted.

The Main Turbine has just been tripped.

Feedwater Pump 13 could NOT be disengaged from the control room.

Powerboard 11 and 12 are energized.

Evaluator:

Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), perform OATC actions of Nl-SOP-21.2, Control Room Evacuation, starting at*." Provide repeat back of initiating cue SAT I UNSAT Cue: Acknowledge repeat back providing p STD: Proper correction if necessary.

communications used Obtain a copy of the reference procedure and SAT/ UNSAT review/ utilize the correct section of the procedure p STD: Nl-SOP-21.2 obtained Section 'C' referenced IF Main Turbine NOT tripped, WHEN Reactor SAT/ UNSAT has been scrammed, THEN Trip Main Turbine by rotating AND pulling MASTER TRIP at STD: Determines step is Front Standard

{TB EL 300') p N/ A per initial conditions NRC JPM P-2 Page 5 of 10 March 2015

Generation

4. 5. 6. IF Feedwater Pump 13 NOT disengaged, THEN Disengage Feedwater Pump 13 locally Note: Once the Candidate has identified the FWP actuator junction boxes, relocate to a quieter, lower dose area. Present the Candidate with a picture of the controls including the stop button and have them show what they would do. Cue: Indicated button pushed. The actuator motors have been stopped.

Proceed to PB 11 and 12 Is Offsite Power available (voltage on PB 11/12)? 7. At PB 11 and 12, verify the following:

7a 7b Breaker R122 open Cue: Breaker R122 green light ON and red light OFF. Breaker R113 open Cue: Breaker R113 green light ON and red light OFF. NRC JPM P-2 Page 6 of 10 s p PASS/ FAIL STD: FWP actuator junction boxes identified.

Stop buttons depressed.

SAT I UNSAT STD: Travels to PB 11 and 12 (TB 261' South) SAT/ UNSAT STD: Determines offsite P power is available per initial conditions or by checking volt meters on PB 11/12. s s SAT/ UNSAT STD: Breaker R122 verified open by observing local indications SAT/ UNSAT STD: Breaker Rl 13 verified open by observing local indications March 2015 Exelon Generation NRC JPM P-2 Page 7 of 10 March 2015 Exelon

9. IF D/G loaded due to Loss of Offsite Power (LOOP), THEN: 9a Place D/G Control in LOCAL PASS/ FAIL Note: D/G Control switch is labeled s STD: D/G 103 Control "REMOTE AUTO" and "LOCAL START". switch placed in LOCAL START 9b Monitor D/G voltage AND HOT ENGINE light SAT/ UNSAT Cue: DG 103 HOT ENGINE light is p STD: D/G 103 voltage extinguished, DG 103 voltage is normal. AND HOT ENGINE light monitored

10. Proceed to Diesel Generator/PB rooms (TB SAT I UNSAT 261') p STD: Travels to Diesel Generator Room 102 (TB 261' East) 11. IF D/G loaded due to Loss of Offsite Power (LOOP), THEN: lla Place D/G Control in LOCAL PASS/ FAIL Note: D/G Control switch is labeled s STD: D/G 102 Control "REMOTE AUTO" and "LOCAL START". switch placed in LOCAL START llb Monitor D/G voltage AND HOT ENGINE light SAT I UNSAT Cue: DG 102 HOT ENGINE light is LIT, DG p STD: D/G 102 voltage 102 voltage is normal. AND HOT ENGINE light monitored

12. IF D/G Control Circuit damage detected SAT/ UNSAT as indicated by HOT ENGINE light s STD: CRS notified illuminated, THEN notify CRS and shutdown EDG 102 as follows:

NRC JPM P-2 Page 8 of 10 March 2015

Generation Cue: Your task is complete.

OATC actions of Nl-SOP-21.2 are complete.

NRC JPM P-2 Page 9 of 10 March 2015

Generation NRC JPM P-2 JPM Handout Given:

You are the OATC.

A Control Room Evacuation has been ordered due to a fire.

The Reactor has been scrammed and all control rods are fully inserted.

The Main Turbine has just been tripped.

Feedwater Pump 13 could NOT be disengaged from the control room.

Powerboard 11 and 12 are energized.

(Operators Name), perform OATC actions of Nl-SOP-21.2, Control Room Evacuation, starting at *." Page 10 of 10 March 2015

=:r-Exelon Generation Training Id: 2015 NRC JPM P-3 Revision:

0.0 -----Emergency Condenser Initiation From the Remote Shutdown Panel Title: {Alternate Path) Approvals:

Si nature Printed Name Date Developed By /Paul Isham 03/07/2014 Validated By 08/19/2014 Facility Reviewer bl,Gb f Lf<'IJ<:

7 Approximate Duration:

15 minutes Documentation of Performance:

Performer:

Evaluator:

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

Evaluators Signature:

Date: NRC 2015 JPM P-3 Page 1of8 March 2015

=:r-Exelon Generation References

1. Nl-SOP-21.2, Attachment 20 2. NUREG 1123 K/A 295016 AAl.09, (4.0/4.0)

NRC 2015 JPM P-3 Page 2 of 8 March 2015

Generation Instructor Information A. JPM Information

1. Description

a. This JPM tests the operator's ability to initiate Emergency Condensers from outside the control room in the event of Control Room Abandonment.

b. This JPM is considered alternate path due to a failure of the automatic EC level control.

This requires executing an override step that would not normally be necessary to complete the task. 2. Task Information:

a. Nl-207000-01019

b. K/A 295016 AAl.09, (4.0/4.0)

3. Evaluation/

Task Criteria Perform Plant No Yes Yes 4. Recommended Start Location

a. Unit 1 Turbine Building Elevation 261' 5. Simulator Setup (if required)

a. N/A 6. JPM Setup (if required)

a. Provide a copy of Nl-SOP-21.2, Control Room Evacuation.

NRC 2015 JPM P-3 Page 3 of 8 March 2015 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.

NRC 2015 JPM P-3 Page 4 of 8 March 2015

1. 2. 3. Given:

A control room evacuation has occurred

All control room actions were completed

All control rods are in

RPV Pressure is 900 psig and slowly rising

RPV Level is 72" and stable

The Remote Shutdown Keys (VA-1) have been obtained

You are the CRO

Offsite Power is available

FW and CRD are available

Other operators are performing the manual vessel isolation and removing ERV fuses Evaluator:

Ask trainee if he/she has any questions presenting initial conditions (Operators Name), Place Emergency Cooling Loop 11 in service in accordance with Nl-SOP-21.2 CRS/CRO actions and commence normal RPV cooldown.

Provide repeat back of initiating cue SAT I UNSAT STD: Proper Cue: Acknowledge repeat back providing p communications used correction if necessary Obtain a copy of the reference procedure and SAT/ UNSAT review/ utilize the correct section of the p STD: Nl-SOP-21.2 procedure.

obtained and reviewed.

Go to Remote Shutdown Panel #11 SAT I UNSAT p Cue: The EC System has NOT isolated STD: Proceed to RSP 11, TB 250' South NRC 2015 JPM P-3 Page 5 of 8 March 2015

=::'"Exelon Generation

4. 5. 6. 7. 8. 9. Place the Channel 11 CONTROL TRANSFER keylock switch in EMERG position to transfer control to the RSP. Verify open 39-07 and 39-09 Cue: 39-07 and 39-09 are open (if necessary).

Control RPV cooldown by cycling open and closed 39-05, EMERGENCY CONDENSER COND RTN IV 11 Cue: 39-05 is open. Reactor Pressure is 900 psig and slowly lowering.

RPV water level is 72" and stable. s s s PASS/FAIL STD: Rotate the control switch to the emergency position SAT I UNSAT STD: Observe red lights on, green lights off. PASS/FAIL STD: Rotate control switch for valve 39-05 CW to the open position, observe red light energized, green light out. Note: The following cue indicates that AUTO shell level control has failed. Cue: If the candidate references EC shell water level indicator, inform them that EC shell water level is 5.5' and slowly lowering Place EC 111/112 Level Control Transfer Switch to Local Verify AUTO control by observing "A" on status panel Cue: EC shell water level is 5.0' and slowly lowering.

Depress A/M key pad s s PASS/FAIL STD: Rotate control switch CW to the Local position.

SAT/ UNSAT STD: Observe "A" illuminated on status panel PASS/FAIL S STD: Manual mode selected by depressing the A/M key pad NRC 2015 JPM P-3 Page 6 of 8 March 2015

Generation

10. Verify M is displayed SAT I UNSAT Cue: M is illuminated s STD: Observe "M" is illuminated on status panel 11. Control level by depressing arrows on key PASS/FAIL pad STD: Level is raised in s the EC Condenser Shell Cue: EC Condenser Shell is 6.4' and stable. by depressing the key Reactor Pressure is 850 psig and slowly pad arrows. lowering.

12. Report that # 11 EC Condenser in service and SAT I UNSAT EC shell level control is in manual. p STD: Proper communications used. (GAP-OPS-01)

Cue: Your task is complete.

Emergency Cooling Loop 11 placed in service in accordance with Nl-SOP-21.2, and EC Shell level is controlled in manual. NRC 2015 JPM P-3 Page 7 of 8 March 2015

Generation NRC 2015 JPM P-3 JPM Handout Given:

A control room evacuation has occurred

All control room actions were completed

All control rods are in

RPV Pressure is 900 psig and slowly rising

RPV Level is 72" and stable

The Remote Shutdown Keys (VA-1) have been obtained

You are the CRO

Offsite Power is available

FW and CRD are available

Other operators are performing the manual vessel isolation and removing ERV fuses (Operators Name), Place Emergency Cooling Loop 11 in service in accordance with Nl-SOP-21.2 CRS/CRO actions and commence normal RPV cooldown.

Page 8 of 8 March 2015

Generation Copy of __ Training Id: NRC 2015 Scenario 2 Revision:

0.1 -----Recirc Flow Unit Failure, EC Initiation, Fuel Failure, Un-isolable MSL Break, PB 12 Fails to Fast Transfer, FW Pump 11 Trip, Turbine Title: Building Ventilation Trips Si nature Printed Name Date Developed By Paul Isham 6/2/14 Validated By Pat O'Brien 8/20/14 .. Leigh Mason 8/20/14 Dave Ballard 8/20/14 Facility Reviewer L;;:C_ Greg Elkins 2/t,)r iY Page 1 of 23 NRC Scenario 2 March 2015 Exelon Generation References

1. N 1-0P-19, Circulating Water System 2. N1-0P-1, NSSS 3. N1-SOP-1, Reactor Scram 4. N1-SOP-1.1, Emergency Power Reduction

5. N1-SOP-25.2, Fuel Failure or High Activity in Reactor Coolant or Off Gas 6. N1-SOP-30.2, Loss of PB 12 7. N1-EOP-1, NMP1 EOP Support Procedure

8. N1-EOP-2, RPV Control 9. N1-EOP-6, Radioactivity Release Control 10. N1-EOP-8, RPV Slowdown

11. Unit 1 Technical Specifications Page 2 of 23 NRC Scenario 2 March 2015 Exelon Generation Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 50-55% power. Containment Spray pump 112 and Reactor Building Exhaust Fan 12 are out of service for maintenance.

Circulating Water pump 11 is out of service following maintenance.

The crew will start Circulating Water pump 11, then raise Reactor power with recirculation flow. Then, Recirculation flow unit 11 fails upscale.

The crew will respond per the alarm response procedure and the CRS will determine the Tech Spec impact. Then, an inadvertent EC initiation occurs. The crew will respond to isolate the EC and the CRS will determine the Tech Spec impact. Next, fuel failure will occur due to the previous transients.

The crew will respond per N1-SOP-25.2, Fuel Failure or High Activity in Rx Coolant or Off-Gas.

This includes performing an emergency power reduction per N1-SOP-1.1, and eventually scramming the Reactor per N1-SOP-1 (Critical Task). When the Generator trips after the scram, Powerboard 12 will fail to transfer to reserve power. The crew will execute N1-SOP-30.2, Loss of Powerboard 12, to re-energize the powerboard.

Feedwater Pump 11 will trip shortly after the reactor scram. Following the scram, a Main Steam line break will occur. The MSIVs will fail to close both automatically and manually, leading to an un-isolable leak into the Turbine Building.

The running Turbine Building ventilation exhaust fan will trip. The crew will start the standby Turbine Building ventilation exhaust fan, however it will trip after a short time delay. This will allow an un-monitored, ground level release from the Turbine Building.

The crew will enter N1-EOP-6, Radioactivity Release Control.

Field reports will indicate off-site release rates approaching the General Emergency level. The crew will perform an RPV Slowdown per N1-EOP-8 (Critical Task). 1. Termination Criteria

a. RPV water level controlled in assigned band, RPV Slowdown in progress Page 3 of 23 NRC Scenario 2 March 2015 Exelon Generation@

2. Critical Tasks CT-1, Given fuel failure causing Main Steam Line radiation levels to approach and/or exceed 3.75 times normal full power background, scram the Reactor, in accordance with N1-SOP-25.2.

Justification:

Safetv Significance: High Main Steam Line radiation levels indicate fuel failure and release of fission products to the Reactor coolant.

A Reactor scram reduces the rate of energy production and thus the heat input, radioactivity

release, and flow down the Main Steam Lines. Scramming the Reactor also allows further mitigating

actions, such as Reactor isolation and depressurization.

Cueing: Multiple annunciators and radiation monitors will provide indications of fuel failure.

N1-SOP-25.

2 directs scramming 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 primary system discharging outside of primary and secondary containments and off-site release rate approaching the General Emergency level, perform an RPV Slowdown, in accordance with N1-EOP-6.

Justification:

Safety Significance:

An un-isolable primary system discharging outside of Primary and Secondary Containments resulting in off-site release rates approaching the General Emergency limit indicates a significant problem posing a direct and immediate threat to the health and safety of the public. 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. This will lower the release of radioactivity to the environment and lower the dose received by the public. Cueing: Multiple annunciators will provide indications of a primary system discharging into the Turbine Building.

MSIV valve position indicators will provide indication that the system is un-isolable.

Field reports will provide indication that site release rate approaches the General Emergency level. N1-EOP-6 provides direction to blowdown the Reactor. Measurable Performance Indicators:

The crew will manually initiate Emergency Condensers and 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.

Page 4 of 23 NRC Scenario 2 March 2015 Exelon Generation

3. Length a. -60 minutes 4. Mitigation Strategy Code a. RR4, Primary system leak outside of primary and secondary containment, RPV Blowdown required due to General Emergency release rate approached

5. Technical Specifications

a. TS 3.6.2.a and g b. TS 3.1.3.b 6. EAL Classification

a. Site Area Emergency EAL RS1 .2 ->1 OOmRem TEDE at site boundary

7. Special Orders a. None Page 5 of 23 NRC Scenario 2 March 2015 Exelon Generation

8. Initial Conditions

1. IC Number a. IC-152 2. Presets I With Triggers

a. Malfunctions

1) CT01 B, CT Pump 112 Trip 2) HV01 B, Reactor Building Exhaust Fan Trip 12 3) E027, PB 12 Auto Transfer Failure 4) NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE -UPSCALE 5) EC038, EC RETURN VALVE FAILS OPEN(IV 39-06) 6) RX01, FUEL CLADDING

FAILURE, FV=34, IV=10, RT=5:00 7) M501, Steam Line Break Outside PC Area, FV=12, IV=5, RT=4:00 8) FW03A, FEEDWATER PUMP TRIP 11 9) M513A, MSIV FAILS OPEN MS01-01(111),

FV=10% 10) M513C, MSIV FAILS OPEN MS01-03(112),

FV=10% b. Remotes 1) E040A, l&C Bus 130 NC Supply Breaker from IC XFMR (PB 13B), Open 2) E0408, l&C Bus 130 NO Supply Breaker from PB 167A, Closed, DT=5sec c. Overrides

1) 115300154110, POS_11L9/203-01APOSA, FV=on, DT=2:00 2) 115300154111, POS_2 1L9/203-01A POS C, FV=off, DT=2:00 (Turbine Building Ventilation exhaust fan 11 trips) 3) 115310154112, POS_11L9/203-01APOSA, FV=on, DT=1:00 4) 115310154113, POS_2 1L9/203-01A POS C, FV=off, DT=1:00 (Turbine Building Ventilation exhaust fan 12 trips) Page 6 of 23 NRC Scenario 2 Inserted Inserted Inserted TRG 1 TRG2 TRG4 TRG5 Inserted Inserted Inserted TRG15 TRG 15 TRG5 TRG5 TRG6 TRG6 March 2015 Exelon Generation@

d. Annunciators

1) None e. Event Triggers

. . Sv4tnt ActiOR ,) comm*nd Event# ., . ' . :.' ,, TRG 6, Initiates Turbine Building exhaust fan 12 is started zdhvtbft(6)==0 Blank TRG 10, Ramps up fuel failure once the stack isolates hzlog002g==1 imf rx01 (0 0) 45 8:00 34 f. Equipment Out of Service 1) Containment Spray Pump 112 in PTL with yellow tag 2) Containment Spray suction isolation valve 112 closed with yellow tag 3) Reactor Building Exhaust Fan 12 secured with yellow tag 4) Circulating Water Pump 11 secured with no tag g. Support Documentation

1) RMI for power ascension with recirc flow 2) Markup N1-0P-19 Section E.2.0 up to step E.2.7 3) Markup N1-0P-43B Section F.3.0 to the appropriate steps for 50% power level (up to F.3.25 with steps 3.20 and 3.23 still open) h. Miscellaneous

1) Ensure TB Exhaust Fan 11 is in service 2) Protect the following equipment:

EOG 103, PB 103, PB 12, Gire Water pump 12 3) Update Divisional Status Board 4) DW Cooling Fan 11 secured Page 7 of 23 NRC Scenario 2 March 2015 Exelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: I N ID DA TE: _;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 55%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Reactor Building Exhaust Fan 12 is out of service for maintenance.

PART Ill: Remarks/Planned Evolutions:

Start Circulating Water pump 11 per N1-0P-19 Section E.2.0. The section is complete up to step E.2. 7. In step E.2.11, it is desired to stop both Circulating Water Priming pumps. A Plant Operator is standing by in the screen house.

Continue Reactor power ascension with Recirculation flow per the provided RMI and N1-0P-43B.

N1-0P-43B Section F.3.0 is in progress.

Page 8 of 23 NRC Scenario 2 March 2015

_.,.,, Exelon Generation ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

Power Ascension from 55% Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I RE presence required in the Control Room? Yes_ No ,/ If YES above, RE presence not required for steps_. Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range Actual CTP 1030-1070 MWth Description of Step: Raise Reactor power to approximately 65% with Recirculation flow per N1-0P-43B.

Critical parameters to be monitored DURING Step: Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency Recirc Flow 67.5 RO Continuous Stop evolution and consult RE. Mlbm/hr CTP 1850 MWth RO Continuous Lower power to less than 1850 MWth with Recirculation flow. Rod line 108% RO 15 minutes Stop evolution and consult RE. RMI evaluated against approved power profile:*

N/A D. I I Other Comments:

I Step Prepared by: Alex Reed I Today Step Reviewed by: Jack Dean I Today RE/STA Date RE/STA/SRO Date Approval to perform Step John Aaron I Today Step Completed by: I Shift Manager Date SRO Date Page 9 of 23 NRC Scenario 2 March 2015 Exelon Generation Shift Turnover Plant Response o ratC>rActtcms'

I* *pe:* . *. :*:* .* .. . . : .. * . 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 23 NRC Scenario 2 March 2015 Exelon Generation Event #1: Start Circulating Water Pump 11

The Plant is operating approximately 55% power

The crew will start Gire Water Pump 11 per N1-0P-19 SRO

Directs starting Circulating Water pump 11 per N1-0P-19 Section E.2.0

Provides oversight for evolution BOP

Reviews N1-0P-19 Section E.2.0 Role Play:

Verifies running CRD Pump flow greater than 60 When requested, report a good start on Circulating GPM Water pump 11.

Starts 74-01, CONDSR CIRCULATING WATER PUMP 11

Closes 74-20, FISH SCREEN DRAIN VALVE 11 Role Play: Contacts Operator to confirm normal circulating

When requested, report normal circulating water water pump discharge pressure in Screen House pump discharge pressure in Screen House.

Verifies the following pumps are stopped per SM direction:

Role Play:

75-09, COND. WATER BOX PRIMING If asked as Shift Manager, direct securing both Water PUMP NO. 11 Box Priming pumps.

75-08, COND. WATER BOX PRIMING PUMP NO. 12 ATC

Monitors plant parameters Page 11 of 23 NRC Scenario 2 March 2015 Exelon Generation Event #2: Power Ascension With Recirculation Flow

The crew will raise power with recirc flow per the RMI SRO

Directs power ascension with Recirculation flow in accordance with N1-0P-43B and the Reactivity Maneuver Instruction (RMI)

Provides oversight of reactivity maneuver ATC N1-0P-43B includes the following power-to-flow map

Acknowledges direction from SRO restrictions:

Raises Recirculation flow with master

PRIOR to exceeding 65% flow, verify greater than 50% Rod Line OR that RIP region will NOT be entered.

PRIOR to 100% rod line raise recirc flow to greater than 59% flow (approximately 40 x 106 lb/hr) to avoid the flow biased control rod block line. Note: Recommend initiating the next event when Reactor power is between 55-60% power. 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 12 of 23 NRC Scenario 2 March 2015 Exelon Generation Event #3: Recirculation Flow Unit Fails Upscale 'Event .. *

Recirc flow unit 11 fails upscale .

Crew responds per ARP F2-2-6 -no manipulations made.

CRS makes Tech Spec determination.

When directed by lead examiner, insert CREW malfunction:

Recognize/report Recirculation flow unit 11 failed upscale NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE-UPSCALE TRG 1 Comparator trip occurs resulting in a Rod Block. The "FLOW COMPARATOR" lamps on the Rod Block Display (PANEL E) will light. The upscale light on Flow Converter 11 (G Panel) will light Expected Annunciators:

F2-2-6, APRM FLOW UNIT 11 F3-2-1, APRM FLOW UNIT 12 F3-4-4, ROD BLOCK SRO

Acknowledges reports from crew

Directs response with ARP F2-2-6

Consults Tech Spec Tables 3.6.2.a and 3.6.2.g

Declares APRMs 11-14 inoperable for the upscale scram and rod block functions

Determines a half scram must be placed on RPS channel 11 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Contacts l&C Department for troubleshooting ATC

Verifies proper power to flow ratio on Power Flow Map on E Panel Page 13 of 23 NRC Scenario 2 March 2015 Exelon Generation Event 3 continued BOP

Executes ARP F2-2-6

Confirms alarm by observing the following:

o Computer Printout o APRM Flow Comparator on G Panel o LPRM/APRM Trip Auxiliary Panels on G Panel o Rod Block Monitor on E Panel Page 14 of 23 NRC Scenario 2 March 2015 Exelon Generation Event #4: Inadvertent Initiation of Emergency Condenser 12

Emergency Condenser 12 goes into service inadvertently

The crew will isolate the EC per the ARPs

CRS makes Tech Spec determination.

When directed by lead examiner, insert CREW malfunction:

Recognize/report Emergency Condenser 12 EC03B, EC RETURN VALVE FAILS OPEN (IV 39-initiation

06)

Recognize/report Reactor power and water level TRG2 rising EC 12 Condensate Return Valve (39-06) opens

Recognize/report no valid Emergency Condenser Reactor power rises initiation signal Reactor water level initially rises Expected Annunciators:

K1-1-5, EMER COND CONDEN RET /SOL VALVE 12 OPEN SRO

Acknowledges reports from crew Role Play: If dispatched to investigate 39-06, wait 2 minutes and

Directs response with ARP K1-1-5 then report that there is a significant air leak on the

Directs securing Emergency Condenser 12 air supply line to 39-06.

Declares Emergency Condenser 12 inoperable but available

Enters a 7 day LCO per Tech Spec 3.1.3.b

May direct entry into N1-SOP-1.5, Unplanned Reactor Power Change Note: BOP The next event should NOT be inserted until Reactor

Executes ARP K1-1-5 water level has stabilized from this event.

Closes: 0 39-08R EC STM ISOLATION VALVE 122, and/or 0 39-10R EC STM ISOLATION VALVE 121 Page 15 of 23 NRC Scenario 2 March 2015 Exelon Generation Events #5 and #6: Fuel Failure, PB 12 Fails to Fast Transfer.

A fuel failure occurs due to the power ascension earlier.

The crew will manually scram the reactor.

PB 12 will not fast transfer but will be available

FWP 11 will trip CREW When directed by the lead examiner, insert malfunction:

RX01, FUEL CLADDING

FAILURE, FV=34, IV=10, RT=S:OO

Acknowledges/reports annunciator H1-1-7, OFF GAS HIGH RADIATION Rising off-gas radiation levels Rising main steam line radiation levels Expected Annunciators:

H1-1-7, OFF GAS HIGH RADIATION TRG4 H1-2-7, OFF GAS RAD MON 11-12 FILTER IJ.P SAMPLE FLOW H1-3-7, MAIN CNDSR OG TIMER STARTED /SOL TD 15 M H1-4-8, AREA RADIATION MONITORS F1-2-7, MAIN STEAM RAD MONITOR CH 11 HI/LO (later) F4-2-2, MAIN STEAM RAD MONITOR CH 12 HI/LO (later) Verify the following malfunctions are preset: ED27, PB 12 Auto Transfer Failure FW03A, FEEDWATER PUMP TRIP 11 Powerboard 12 voltage drops to zero after Generator trip Feedwater pump 11 starts and then immediately trips

Recognizes rising offgas and main steam line radiation levels

Diagnoses fuel failure Page 16 of 23 NRC Scenario 2 March 2015 Exelon Generation Note: Normal Full Power Background (NFPB) Main Steam Line (MSL) radiation levels are approximately 410 mR/hr at this power level. Any value between 400-500 mR/hr is reasonable.

This makes a reasonable range of 1500-1875 mR/hr for the 3. 75 times NFPB benchmark.

The crew may establish a lower threshold for executing the scram and vessel isolation.

Alternately, if the crew scrams and closes MSIVs early, 3.75 times NFPB may not be reached.

Note: High pressure Feedwater will be unavailable until Powerboard 12 is re-energized.

Note: Emergency Condenser 12 is inoperable from a previous event, however, it is still available for pressure control if the crew opts to use it. Note: Recommend initiating the next event once the crew has stabilized the plant post-scram and PB 12 is energized.

SRO

Acknowledges reports

Directs entry into N 1-SOP-25.2, Fuel Failure/High Activity

May direct emergency power reduction per N1-SOP-1.1 as necessary to control radiation levels

Provides oversight for reactivity manipulation

Directs Reactor scram CT-1

Acknowledges scram report

Enters N1-EOP-2, RPV Control, on low Reactor water level

Answers "Are all control rods inserted to at least position 04?" Yes

Directs entry into N1-SOP-1, Reactor Scram

Directs Reactor water level control 53-95" using Feedwater/Condensate and CRD

Directs Reactor pressure control 800-1000 psig on Turbine Bypass Valves or Emergency Condenser 11

May direct MSIVs closed

Directs manual vessel isolation and entry into N 1-SOP-40.2 if Main Steam Line radiation levels reach 3.75 x Normal Full Power Background (NFPB)

Enters N 1-EOP-5, Secondary Containment

Control, on high area radiation levels

Acknowledges failure of Powerboard 12 to transfer to reserve power

Directs entry into N1-SOP-30.2, Loss of Powerboard 12 Page 17 of 23 NRC Scenario 2 March 2015 Exelon Generation Events 5 & 6 continued ATC

If directed, performs emergency power reduction Note: All CRAM rods are already inserted and E per N1-SOP-1.1 Console indication of recirc flow is lost due to earlier malfunctions, thus limiting the ability of N 1-SOP-1.1.

Places Mode Switch in Shutdown CT-1

Performs scram verification actions of N 1-SOP-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places I RMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary

Controls Reactor pressure as directed

May perform a manual vessel isolation by placing both Vessel Isolation Ch 11 and Ch 12 Control Switches on the E Panel to ISOLATION, if necessary Role Play: When dispatched as Chemistry to take BOP samples, acknowledge request.

Executes N1-SOP-25.2

Notifies Chemistry to sample offgas and reactor Role Play: When directed to close Turbine Building coolant for gross activity Roof Vents, Sidewall Vents and Roll Doors, wait 2

Directs operator to close Turbine Building Roof minutes then report the Turbine Building Roof Vents, Vents, Sidewall Vents and Roll Doors Sidewall Vents and Roll Doors are CLOSED. Also report that RP is with you, and they have detected

Monitors ARMs and rad monitors to determine higher than normal rad levels near the offgas piping. plant radiation levels

Notifies CRS/Crew of rising Main Steam Line Note: Normal Full Power Background (NFPB) Main Radiation Monitor levels Steam Line (MSL) radiation levels are approximately

Notifies CRS if MSL Rad Monitors 410 mR/hr at this power level. Any value between approach/exceed 3.75 X Normal Full Power 400-500 mR/hr is reasonable.

This makes a reasonable range of 1500-1875 mR/hr for the 3. 75 Background (NFPB) times NFPB benchmark.

Page 18 of 23 NRC Scenario 2 March 2015 Exelon Generation Event 5 & 6 continued BOP continued

Performs Reactor water level control actions of N1-SOP-1:

Attempts to restore RPV water level to 53-95" by controlling injection and rejecting through Note: RWCU, as necessary High pressure Feedwater will be unavailable until

Determines both electric Feedwater pumps Powerboard 12 is re-energized.

NOT running

May close MSIVs

May verify Vessel Isolation per N1-SOP-40.2 ATC/BOP

Executes N1-SOP-30.2 N1-SOP-30.2 Actions:

Verifies Reactor scram due to less than 3 operating Recirculation loops

Verifies Service Water pump 11 running

Continuously monitors for thermal hydraulic instability

Verifies:

TBCLC pump 11 running

IAC 11 running

RBCLC system running Note:

Re-energizes Powerboard 12: At the examiner's discretion, move on to next event

Answers "Are A5-4-1, A5-4-2, A5-1-8, OR when PB 12 has been re-energized.

A5-2-8 in alarm?" No

Obtains SRO permission to re-energize Powerboard 12

Verifies open Breaker R 122

Inserts Sync. Key into R123 AND rotates clockwise to ON

Closes Breaker R 123

Rotates Sync. Key counterclockwise to OFF AND removes

Closes Breakers R124 and R121 Page 19 of 23 NRC Scenario 2 March 2015

/118111r' Exelon Generation Events #7, #8, and #9: Main Steam Line Break in Turbine Building, MSIVs Fail to Close, Turbine Building Ventilation Exhaust Fan Trips

Fuel failure is complicated by a MSL break in the TB

Two MSIVs fail to isolate

Lose TB Exhaust ventilation leading to unmonitored ground level release, When directed by the lead examiner, insert malfunctions:

M501, Steam Line Break Outside PC Area, FV=12, IV=5, RT=4:00 Main Steam tunnel temperatures rise Turbine Building radiation levels rise Expected Annunciators>>

F1-2-2, RPS CH 11 MAIN STM LINE BREAK TRG5 F2-3-2, MAIN STM LINE BREAK AREA TEMP HIGH F4-2-7, RPS CH 12 MAIN STM LINE BREAK H1-4-8, AREA RADIATION MONITORS The following overrides also insert on TRG 5: 115300154110, P05_11L9/203-01A P05 A, FV=on, OT=2:00 115300154111, P05_21L9/203-01A P05 C, FV=off, OT=2:00 Turbine Building exhaust fan 11 trips on a time delay CREW

Acknowledges/reports annunciators H1-1-7, OFF GAS HIGH RADIATION

Diagnoses Main Steam Line break Page 20 of 23 NRC Scenario 2 March 2015

_.., Exelon Generation Events 7, 8, & 9 continued Verify the following overrides are automatically inserted when Turbine Building exhaust fan 12 is started:

115310154112, POS_11L9/203-01A POSA, OT=30, FV=on, OT=1 :00 115310154113, POS_2 1L9/203-01A POS C, OT=30, FV=off, OT=1 :00 Turbine Building exhaust fan 12 trips Verify the following malfunctions are preset: TRG6 MS13A, MSIV FAILS OPEN MS01-01(111),

FV=10% MS13C, MSIV FAILS OPEN MS01-03(112),

FV=10% Two MS/Vs fail mid-position on closure Page 21 of 23 NRC Scenario 2 March 2015 Exelon Generation Events 7, 8, & 9 continued Role Plays: When the crew has determined both Turbine Building exhaust fans are inoperable, or when requested as RP/Chemistry to assess dose, wait 2 minutes then report as Off-Site Dose Assessment Manager that dose at the site boundary is 50 mr/hr TEDE and rising. Three minutes later, report that dose at the site boundary is 500 mrem TEDE and rising. Evaluator Cue: After the report is made to the crew that dose at the site boundary exceeds 1 OOmrem TEDE, inform the CRS that the Shift Manager is declaring a Site Area Emergency per EAL RS1 .2 due to offsite release rate. Three minutes after previous field report, report that dose at the site boundary is 800 mrem TEDE and rising. Three minutes later, report that dose at the site boundary is 950 mrem TEDE and rising. Three minutes later, report that dose at the site boundary is 1100 mrem TEDE and rising. SRO

Acknowledges reports

Directs MSIVs closed

Directs Turbine Building evacuation

Acknowledges failure of two MSIVs to close

May direct cooldown using Turbine Bypass Valves or Emergency Condensers

<100°F/hr

Acknowledges trip of Turbine Building exhaust fan 11

Directs start of Turbine Building exhaust fan 12

Acknowledges trip of Turbine Building exhaust fan 12

Dispatches personnel to monitor on-site/off-site radiation levels

Acknowledges off-site release rate reports

Enters N 1-EOP-6 due to off-site release rate above Alert level

May direct rapid depressurization with Emergency Condenser 11 >100°F/hr

Determines off-site release rate is approaching the General Emergency level

Enters N1-EOP-8, RPV Blowdown

Directs initiation of EC 11

Directs open 4 ERVs If asked for an update between reports, give an CT-2 extrapolated value for dose at the site boundary.

If dispatched into the plant for any other task, wait 2 minutes and then report that there is excessive steam in the Turbine Building and you have backed out. Page 22 of 23 NRC Scenario 2 March 2015 Exelon Generation NRC Scenario 2 ATC/BOP

Reports failure of MSIVs to automatically close on high steam tunnel temperature

Attempts to manually close MSIVs

Reports failure of two MSIVs to close

Makes Turbine Building evacuation announcement

May open Turbine Bypass Valves or initiate Emergency Condenser 11 to cooldown

<100°F/hr

Reports trip of Turbine Building exhaust fan 11

Starts Turbine Building exhaust fan 12

Reports trip of Turbine Building exhaust fan 12

Dispatches personnel to monitor on-site/off-site radiation levels

Acknowledges/reports off-site release rate reports

May perform rapid depressurization with Emergency Condenser 11 > 100°F /hr

Initiates EC 11

Open 4 ERVs

Controls Reactor water level 53-95" using Condensate/Feedwater and CRD CT-2

RPV water level controlled in assigned band

RPV Slowdown in progress Page 23 of 23 March 2015 Exelon Generation Copy of __ Training Id: NRC 2015 Scenario 3 Revision:

0.1 Condensate Pump S/D, Sequence

Exchange, MSL Rad Monitor Failure, RBCLC TCV Failure, RPS MG Set Trip, Instrument Air Leak, Title: ATWS, Feedwater IVs Stick Developed By Validated By Facility Reviewer NRC Scenario 3 Signature I Printed Name Pat O'Brien Leigh Mason Dave Ballard Greg Elkins Page 1 of 28 6/2/14 8/20/14 8/20/14 8/20/14 z/11/1r March 2015 Exelon Generation References

1. N1-0P-5, Control Rod Drive System 2. N1-0P-15A, Condensate System 3. N 1-0P-48, Motor Generator Sets 4. N1-SOP-11.1, RBCLC Failure 5. N 1-SOP-1, Reactor Scram 6. N1-SOP-16.1, FeedwaterSystem Failures

7. N1-SOP-20.1, Instrument Air Failure 8. N1-EOP-2, RPV Control 9. N1-EOP-3, Failure to Scram 10. N1-EOP-1, NMP1 EOP Support Procedure

11. Unit 1 Technical Specifications Page 2 of 28 NRC Scenario 3 March 2015 Exelon Generation Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The crew assumes the shift at approximately 85% power. Containment Spray pump 112 and Reactor Building Exhaust Fan 12 are out of service for maintenance.

The crew is directed to remove Condensate Pump 11 from service immediately for maintenance due to a motor oil leak. After the pump has been removed from service, the crew will conduct a rod pattern exchange.

During the rod pattern exchange, a Main Steam Line Rad monitor will fail inoperable.

The SRO will address Tech Specs. Next, the Reactor Building Closed Loop Cooling (RBCLC) Temperature Controller will fail such that RBCLC temperatures rise. This failure will require placing the RBCLC controller in manual and restoring the effected equipment to normal temperatures.

Then, RPS MG set 141 will trip. The crew will enter SOP-16.1 due to the resulting partial loss of Feedwater heating.

The crew must recover the RPS trip bus by shifting to its alternate supply. Next, an Instrument Air leak will occur in the piping to the CRD system. The crew will insert a manual Reactor scram as CRD air pressure lowers below 60 psig (Critical Task). When the scram occurs the control rods will not fully insert. The crew must terminate and prevent injection (Critical Task). When the operator attempts to close Feedwater Isolation Valves 11 and 12, the valves will fail to isolate Feedwater flow. The crew must diagnose the failure and place the Feedwater pumps in Pull-To-Lock to terminate feeding the RPV. The crew will lower Reactor power by inserting control rods per EOP-3.1 and/or using Liquid Poison (Critical Task).

1. Termination Criteria

a. RPV water level controlled in assigned band, Reactor power < 6%, Control rod insertion in progress or complete Page 3 of 28 NRC Scenario 3 March 2015 Exelon Generation

2. Critical Tasks CT-1, Given lowering CRD system air pressure, the crew will insert a manual reactor scram before control rods begin drifting, in accordance with N1-ARP-F3 and/or N1-SOP-20.1.

Justification:

Safety Significance:

Lowering CRD system air pressure can result in various rods drifting to unpredictable locations in the core. This can lead to an unanalyzed rod pattern and localized power peaking resulting in fuel damage. Cueing: Annunciators on L 1 and F3 will provide indication for lowering plant air pressures.

Procedures direct inserting a manual reactor scram for lowering CRD system air pressure.

Measurable Performance Indicators:

Inserting a manual reactor scram 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. Page 4 of 28 NRC Scenario 3 March 2015 Exelon Generation CT-2, 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 represents 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%. N1-EOP-3 provides direction to trip Recirculation pumps and terminate and prevent injection based on Reactor power. Measurable Performance Indicators:

Manipulation of Recirculation pump control switches, Feedwater system components, and Core Spray jumpers will provide observable actions for the evaluation team. Performance Feedback:

Lowering Recirculation flow, Feedwater flow, Reactor water level, and Reactor power will provide performance feedback regarding the success of crew actions.

CT-3, 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 mav not provide a stable shutdown condition.

Cueing: Control rod position and Reactor power indications will indicate a failure to scram. N1-EOP-3 provides direction to insert control rods. Measurable Performance Indicators:

Manipulation of RPS, CRD, 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 lower power by inserting control rods or injecting Boron. Page 5 of 28 NRC Scenario 3 March 2015 Exelon Generation

3. Length a. -60 minutes 4. Mitigation Strategy Code a. AT1, A TWS requiring RPV water level to be lowered, no Blowdown

5. Technical Specifications

a. TS 3.1.8 (b), TS 3.6.2 (h) 6. EAL Classification

a. Site Area Emergency per EAL SS3.1 -An automatic Scram failed to shut down the reactor as indicated by reactor power >6% AND Manual actions taken at the reactor control console failed to shut down the reactor as indicated by reactor power >6% 7. Special Orders a. None Page 6 of 28 NRC Scenario 3 March 2015 Exelon Generation B. Initial Conditions

1. IC Number a. IC-153 2. Presets I With Triggers

a. Malfunctions

1) CT01 B, CT Pump 112 Trip 2) HV01 B, Reactor Building Exhaust Fan Trip 12 3) RM51A, PRM Steam Line Rad Mon 111, Norm Malfunction, FV=O 4) CW19, RBCLC Temperature Controller

Failure, FV=minimum cooling 5) RP01 B, Reactor Trip Bus Motor Generator Trips 141 6) RD34, Loss of CRD Instrument Air Pres., RT=5:00, FV=20 7) IA01, Loss of Instrument Air, RT=5:00, FV=40 8) RD33A, Control Rod Bank Blocked Bank 1, FV=12 9) RD33B, Control Rod Bank Blocked Bank 2, FV=12 10) RD33C, Control Rod Bank Blocked Bank 3, FV=18 11) RD33D, Control Rod Bank Blocked Bank 4, FV=12 12) RD33E, Control Rod Bank Blocked Bank 5, FV=12 b. Remotes 1) FW01A, Condensate Pump 11 Discharge Valve 50-10, FV=close

2) RP02, Rx Trip Bus 141 Pwr Source, FV=maint

3) MS05, FW Htr String 12 Reset, FV=reset

4) MS02, HP FW Htr 125 Reset, FV=reset

5) FW24, Removal of HPCI Fuses FU8/FU9, FV=pulled Page 7 of 28 NRC Scenario 3 Inserted Inserted TRG 1 TRG2 TRG4 TRGG TRGG Inserted Inserted Inserted Inserted Inserted TRG25 TRG27 TRG 30 TRG30 TRG23 March 2015

_..,,,, Exelon Generation

c. Overrides

1) OVR-5s5di307 POS_ 1 1F10/31-03A PULL OU, On (FWIV Failure)

2) OVR-5s6di3010 POS_ 1 1F10/31-03A PULL OU, On (FWIV Failure)

d. Annunciators

1) F1-1-8, Fail Off 2) F3-1-4, Fail Off 3) F4-1-1, Fail Off e. Event Triggers TRG10 TRG10 TRG10 Inserted Inserted TRG 20 -Activates when ARI is overridden, RPS has been reset and SDV has drained to allow a hzlrp12g1

==1 &&zdrrarov==1

&&anx bat n15scen3trg20.bat manual scram to achieve full inward rod movement

f. Equipment Out of Service stat2(177)==0

1) Containment Spray Pump 112 in PTL with yellow tag 2) Containment Spray suction isolation valve 112 closed with yellow tag 3) Reactor Build Exhaust Fan 12 secured with yellow tag g. Support Documentation

1) N1-0P-15A section H.9.0, completed through step 9.3 2) RMI and Rod Movement Sheets for sequence exchange

h. Miscellaneous

1) Protect the following equipment:

EDG 103, PB 103 2) Update Divisional Status Board 3) Secure DW Cooling fan 11 4) Ensure batch file "n15scen3trg20.bat" is in the root batch file directory with the following commands:

a. dmf rd33a b. dmf rd33b c. dmf rd33c d. dmf rd33d e. dmf rd33e Page 8 of 28 NRC Scenario 3 March 2015

=::rExelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: I N ID DA TE:

__ _ 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 85%.

A rod sequence exchange is in progress and has been placed on hold due to an oil leak from Condensate pump 11 motor.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Reactor Building Exhaust Fan 12 is out of service for maintenance.

PART Ill: Remarks/Planned Evolutions:

Shutdown Condensate pump 11 per N1-0P-15A section H.9.0. Then place the control switch in PTL.

Continue the Control Rod Sequence Exchange per RMI. Page 9 of 28 NRC Scenario 3 March 2015 Exelon Generation ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

Rod Sequence Exchange Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I RE presence required in the Control Room? Yes_ No ,/ If YES above, RE presence not required for steps_. Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range Actual Recirc Flow 54 -58 Mlbm/hr 56 Mlbm/hr Description of Step: Complete attached rod movement sheets. Critical parameters to be monitored DURING Step: Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency CTP 1850 MWth RO Continuous Lower recirculation flow or insert last notch RMI evaluated against approved power profile:*

N/A o. Other Comments:

Power may rise to as high as 90% on highest reading APRM by the end of the rod withdrawals.

Step Prepared by: Alex Reed I Today Step Reviewed by: Jack Dean I Today RE/STA Date RE/STA/SRO Date Approval to perform Step John Aaron I Today Step Completed by: I Shift Manager Date SRO Date Page 10 of 28 NRC Scenario 3 March 2015

@ c 0 *-+-J m L (]) c (]) C) c: 0 ...,J w ,,, Insert FROM: 48 TO: 12 Control Rod From lntttals I Mow Ccrnplete To 14-27 48 12 PR 38-27 48 12 PF! . .l!lllill PFI ,.... .. lndlvidual confirms rod position by rods iorby using 00-7 printout by Alex Reed Vatted 11y Jake Darrow NMP1 ROD MOVEMENT SHEET NIChedc:

Coopilg (as Expected)

Chedc: "" NIA " NIA 51 47 43 39 35 31 27 23 19 15 11 De* Tooay 07 Date To<ISll Step: .l FulOut Comments ug,t NIA NIA ""' uti 1C 14 18 ;i:;i: "'O .:JU 34' J8 4;i: "'llO :Kl 1 2 02 06 10 14 18 22 26 30 34 38 42 46 50 51 47 43 39 35 31 27 23 19 15 11 07 03 co N ...... 0 'l"4 'l"4 Q) Ol ro 0. U') r-1 0 N ..c ro :a: !"") 0 "i: ro c Q) u (/) u er: z

c 0 -I-' m L (]) c (]) C) c: 0 ...J w llt Insert FROM: 12 TO: 08 Cont'OI Rod From lnlials I Mew Canplete To 14-27 12 08 38-27 12 08 lndlvidu!I confirms rod pogftion oy rods Of' by ushg 00-7 printout Pl8Jl.-d by Alex Reed vade<I by Jake Darrow NMP1 ROD MOYEME'NT SHEET NJ Check Cooping (as Expected)

Check NIA NIA 51 47 43 39 35 31 27 23 19 15 11 De* Today 01 03 Data To<IB)' Step: 1 Full Out Comments NIA NIA u.:: 00 1C 14 18 .::.:: .::u .ru 34 42 46 :ru 1 2 02 06 10 14 18 22 26 30 34 38 42 46 50 51 47 43 39 35 31 21 23 19 15 11 07 03 00 N ...... 0 N .... Q) Ol ro a.. U1 .-i 0 N ..c ro M 0 *;:: ro c Q) u (/) u er:: z

@ c 0 +-J m L Q) c Q) C) c: 0 ..J w * Withdrawal FROM: 04 TO: 08 Control Rod F1u111 Initials I Mo'1e Complete Tc 18-35 04 08 34-35 04 08 34-19 04 08 18-19 04 08 1>ila1uona1 uua11ne1 1na1v1aua1 conrrms roo (}'.'ISitinn by ff!SP.IP.r.ting roOS p: by using 00-7 printout Frepared by Alex Reed Varifiad 03TOW NMP1 ROD lllO\IEMENT SHEET NI Check CoupliflD (as ::xpectec)

Check N/A NIA N/A N/A 47 43 39 35 31 27 23 19 15 11 Date Tooay 07 -**-Ono Tomy Step: 1 Full OJt Ligtl: NIA N/A N/A NIA U2 U> U 14 18 LL 2.6 3U 34 jt1 42 46 !JO 1 2 4 3 02 00 10 14 18 22 26 10 3.t 38 .42 .46 50 b1 47 43 39 35 31 27 23 19 15 11 07 03 GO N ...... 0 M 'l"'I Q) Ol ro a_ LI) .-i 0 N ..s::: ro M 0 *;: ro c Q) u (/) u a:: z

Generation Shift Turnover 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 panels. Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 14 of 28 NRC Scenario 3 March 2015 Exelon Generation Event #1: Shutdown Condensate Pump 11

The crew will shutdown Condensate Pump 11 and places in PTL SRO

Directs shutdown of Condensate pump 11 per N1-0P-15A, Section H.9.0

Provides oversight for evolution

Enters T.S. 3.1.8.b for removal of a redundant HPCI component from service, 15 day LCO RO

Monitors plant parameters BOP

Acknowledges direction to shutdown Condensate pump 11 Role Play: When directed to slowly close 50-10,

Notifies SRO to enter LCO for HPCI acknowledge order, wait approximately 1 minute and

Monitors Feedwater Booster pump suction insert remote: pressure (computer point D454 -123 psig)

Directs operator in field to slowly close 50-10, BV FW01A, Condensate Pump 11 Discharge Valve 50--COND PMP 11 DISCHARGE 10, FV=close

WHEN the Condensate Pump 11 discharge valve TRG25 is 90% closed, places the pump control switch in PTL Then report 50-10 is 90% closed.

Verifies:

Maximum Condensate pump motor current :5 135 amps

Minimum FW Booster pump suction pressure Role Play: If contacted as operator to report local within the acceptable range of curve shown in FW pump suction pressure, immediately report FW OP-15C attachment 4 (minimum pressure at pump suction pressure based on simulator value of 85% flow (-6 mlbs/hr) is 72 psig) FWBP discharge pressure minus 50 psig (-300 psi).

Minimum FW pump suction pressure 200 psig Role Play: When directed to fully close 50-10,

Directs operator in field to fully close 50-10, BV -acknowledge order, wait approximately 15 seconds COND PMP 11 DISCHARGE and report valve is fully closed.

Verifies no abnormal Main Condenser air in-leakage is occurring Page 15 of 28 NRC Scenario 3 March 2015 Exelon Generation

The crew will perform a rod sequence exchange SRO Note: Lead examiner may move to the next event

Directs performance of Control Rod Sequence once sufficient action is observed on the reactivity Exchange per RMI and N1-0P-5 manipulation.

Provides oversight for reactivity manipulation RO

Acknowledges direction from SRO Note: RMI includes rods 14-27, 38-27, 18-35, 34-35,

Obtains copy of RMI 34-19, and 18-19 Withdraws control rods per rod movement sheets

and N1-0P-5

Turns control rod power on

Selects rod

Uses CONTROL ROD MOVEMENT switch to notch rod

Monitors APRM indications BOP

Monitors Feedwater controls for proper response

FWP 13 FCV responding to power change

RPV water level remains within program band (65" -83") Page 16 of 28 NRC Scenario 3 March 2015 Exelon Generation Event #3: Main Steam Line Radiation Monitor Failure

A MSL Rad monitor will fail inoperable

The CRS will address Tech Specs When directed by the examiner, insert malfunction:

CREW

Acknowledge/report Annunciator F1-2-7, MAIN RM51A, PRM Steam Line Rad Mon 111, Norm STEAM RAD MONITOR CH 11 HI/LO Malfunction, FV=O TRG 1

Diagnose failure of MSL Rad Monitor 111 Expected Annunciator:

F1-2-7, MAIN STEAM RAD MONITOR CH 11 HI/LO SRO

Acknowledges report of MSL Rad Monitor alarm

Directs execution of ARP for F1-2-7

Acknowledges MSL Rad Monitor has failed

Informs WEC, requests investigation of the failure Role Play: When requested to investigate the MSL

Enters TS Table 3.6.2.h (requires placing channel rad monitor failure, report that you will begin an in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or immediate investigation verifying Mechanical Vacuum pump isolated)

Briefs crew on failure of MSL Rad Monitor RO

Monitors plant parameters BOP

Executes ARP for F1-2-7

Goes to back panel or checks PPC and determines the other MSL Rad Monitors indicate normal readings

Observes downscale light on MSL Rad Monitor Ch 11 and diagnoses the Monitor is INOP

Notifies crew MSL Rad Monitor Ch 11 is INOP Page 17 of 28 NRC Scenario 3 March 2015

Generation Event #4: RBCLC Temperature Control Valve Failure

RBCLC TCV fails to minimum cooling

Crew responds per N1-SOP-11.1 As directed by lead examiner, insert malfunction:

CREW

Recognize/report rising RBCLC temperatures CW19, RBCLC Temperature Controller

Failure,

Diagnose failure of RBCLC automatic FV=minimum cooling temperature control TRG2 TCV 70-137 closes and bypass opens RBCLC water temperature rises Temperatures of components cooled by RBCLC rise Expected Annunciator:

H1-4-1, R BUILDING COOLING WATER PRESS TEMP MAKEUP FLOW (-4.5 minutes)

SRO

Acknowledges report of RBCLC TCV failure

Directs execution of ARP H 1-4-1

May direct entry into SOP-11.1, RBCLC Failure

Directs manual control of RBCLC temperature RO

Monitor plant parameters

Monitor RRPs and other components cooled by RBCLC Page 18 of 28 NRC Scenario 3 March 2015 Exelon Generation Event 4 continued Note: Crew may recognize failure of TBCLC temperature controller prior to the annunciator

alarming, and may take manual control without referencing the ARP. BOP

Executes ARP H1-4-1

May enter N1-SOP-11.1, RBCLC Failure

Monitors equipment cooled by RBCLC

Places RBCLC Temperature Controller 70-238 in manual (N1-0P-11, Section H.13 may be referenced)

Depress the AIM Button until red LED is illuminated next to "M"

Turns knurled knob as required to open/close RBCLC TCV

Manually adjust RBCLC Temperature Controller to maintain RBCLC temp between 57°F and 95°F Page 19 of 28 NRC Scenario 3 March 2015 Exelon Generation Event #5: RPS MG Set 141 Trip

RPS MG Set 141 trips causing a half scram on RPS 12. As directed by the examiner, insert malfunction:

CREW

Recognize/report RPS 12 half scram RP01 B, Reactor Trip Bus Motor Generator Trips 141

Diagnose trip of RPS MG set 141 TRG4 Scram solenoid lights for RPS 12 de-energize SRO Feedwater temperature slowly lowers Acknowledges reports Reactor power slowly rises

Expected annunciators:

(Immediate)

Directs execution of ARP F4-3-2 F4-3-2, RX. TRIP BUS M-G SET 141 TROUBLE Directs entry into OP-48, H.5 F4-3-8, RPS CH 12 MAN REACTOR TRIP

F4-2-8, RPS CH 12 AUTO REACTOR TRIP

Directs entry into SOP-16.1 for loss of Feedwater heating

May direct emergency power reduction per SOP-1.1 if needed to control Feedwater temperatures or Reactor power

Provides oversight of reactivity changes RO

Monitors plant parameters

Lowers power per SOP-1.1 as required to control Feedwater temperatures or Reactor power

Resets half scram Role Play: When dispatched as operator to BOP investigate problem with MG Set 141, wait two

Executes ARP F4-3-2 minutes then report that you can smell burnt insulation in the vicinity of MG Set 141 motor. Report

Dispatches an operator to investigate MG Set that the drive motor breaker tripped on overcurrent.

If 141 asked, report no overvoltage trip occurred.

Determines I & C Bus 130A is available

Obtains SRO permission to perform dead bus transfer of Reactor Trip Bus 141 Page 20 of 28 NRC Scenario 3 March 2015 Exelon Generation Event 5 Continued Role Play: When dispatched as operator to transfer Reactor Trip Bus 141 to l&C Bus 130A, wait 2 minutes and insert remote: RP02, Rx Trip Bus 141 Pwr Source, FV=maint TRG27 Then report Reactor Trip Bus 141 has been energized from l&C Bus 130A, and that half scram and Feedwater heaters can be reset. Role Play: When dispatched as operator to reset Feedwater

heaters, wait 2 minutes and insert remotes:

MS05, FW Htr String 12 Reset, FV=reset MS02, HP FW Htr 125 Reset, FV=reset TRG 30 Then report 12 Feedwater heaters have been reset. BOP Continued

Dispatches an operator to perform dead bus transfer of Reactor Trip Bus 141 per OP-48 section H.5.0

Enters SOP-16.1 due to loss of Feedwater heating

Monitors Feedwater temperatures

Acknowledges that Reactor Trip Bus 141 is energized

Coordinates with RO to reset half scram

Dispatches operator to reset Feedwater heaters Page 21 of 28 NRC Scenario 3 March 2015 Exelon Generation Event #6: Instrument Air Leak

Lowering Instrument Air pressure and CRD air pressure leads to a manual reactor Scram. As directed by lead examiner, insert malfunctions:

CREW

Recognizes/reports lowering instrument air RD34, Loss of CRD Instrument Air Pres, RT=5:00, FV=20 pressure IA01, Loss of Instrument Air, RT=5:00, FV=40

Observes start of standby IAC TRG6 Instrument air pressure lowers SRO Backup Instrument Air Compressor

(/AC) loads Acknowledges reports Standby Instrument Air Compressor

(/AC) starts

CRD air pressure lowers -Reaches 60# at -4 minutes

Directs execution of ARP F3-3-2 Expected Annunciators:

May direct entry into SOP-20.1 L1-4-7, INST AIR BACK-UP VALVE OPEN

F3-3-2, CRD CONTROL AIR PRESSURE HI-LO (-2 min)

May direct execution of ARP L 1-4-7

Acknowledges CRD air pressure

< 60 psig

Directs manual Reactor scram (CT-1.0)

Acknowledges scram report RO

Monitors plant parameters

Places Mode Switch in SHUTDOWN (CT-1.0)

Provides scram report BOP Role Play: When directed as operator check for air

Executes ARP F3-3-2 leaks, acknowledge order. Wait 2 minutes and report If directed executes ARP L 1-4-7 air leakage on Reactor Building 237' West, near the

HCUs and it cannot be isolated.

Dispatches Operator to check for air leaks

Monitors CRD air pressure

Reports when CRD air pressure lowers below 60 psig Page 22 of 28 NRC Scenario 3 March 2015

/11811r Exelon Generation Events #7 and #8: ATWS with Failure of FW Isolation Valves to Isolate

ATWS with Failure of FW Isolation Valves to Isolate

Crew responds per N1-EOP-3 Verify the following malfunctions are preset: CREW RD33A, Control Rod Bank Blocked Bank 1, FV=12

Diagnose failure of control rods to insert RD33B, Control Rod Bank Blocked Bank 2, FV=12

Diagnose Reactor power above 6% RD33C, Control Rod Bank Blocked Bank 3, FV=18 RD33D, Control Rod Bank Blocked Bank 4, FV=12 RD33E, Control Rod Bank Blocked Bank 5, FV=12 Control rods partially insert Reactor power remains > 6% SRO

Enters EOP-2, RPV Control, due to Reactor power above 6% when scram required

Answers "Are all rods inserted to at least position 04?" NO

Answers "Will the reactor stay shutdown without boron?" NO

Exits EOP-2, enters EOP-3, Failure to Scram

Directs ADS bypassed

Directs prevention of Core Spray injection per EOP-1 att 4

May enter EOP-4 on high torus temperature

Directs lockout of Containment Spray pumps except pump(s) used for torus cooling Page 23 of 28 NRC Scenario 3 March 2015

=::"Exelon Generation Events 7 and 8 continued SRO Continued EOP-3 Level Leg Actions:

Directs bypass of low-low RPV water level MSIV isolation per EOP-1 att 2

Determines Reactor power is above 6% and RPV water level is above -41 inches

Directs terminate and prevent of all RPV injection except boron and CRD per EOP-1 att 24 (CT-2.0)

Directs RPV level lowered to at least -41 inches

Directs RPV water level controlled

-109 to -41 inches with Condensate/FW and CRD EOP-3 Pressure Leg Actions:

If any ERV is cycling:

Directs initiation of Emergency Condensers

Directs ERVs opened to lower RPV pressure to less than 965 psig

Directs RPV pressure controlled below 1080 psig using TBVs, ECs and/or ERVs

Monitors Figure M, Heat Capacity Temperature Limit Page 24 of 28 NRC Scenario 3 March 2015

_..,.. Exelon Generation Events 7 and 8 continued SRO continued EOP-3 Power Leg Actions:

Directs initiation of ARI

Answers "Is the Turbine Generator On-line?"

NO

Answers "Reactor power?" Above 6%

Directs Recirc pumps verified tripped

Directs execution of EOP-3.1, Alternate Rod Insertion (CT-3.0)

If power is oscillating more than 25% or before Torus temperature reaches 110°F:

Records Liquid Poison tank level

Directs Liquid Poison injection (CT-3.0)

Acknowledges first Liquid Poison pump injecting RO

Depresses RPS pushbuttons

Initiates ARI

Bypasses Core Spray IV interlocks per N1-EOP-1 Att4 by installing six jumpers (17, 18, 19, 24, 25, 26) inside Panel N

Bypasses low-low RPV water level MSIV isolation per EOP-1 att 2 by installing four jumpers (1, 2, 8, 9) inside Panel N

Performs EOP-3. 1, Section 3 (driving rods) and/or 4 (manual scrams) (see actions below)

Inserts SRMs

Inserts IRMs

Controls IRM recorders and range switches as required to monitor power

Reports when APRMs are < 6%

Reports status of control rod insertion Page 25 of 28 NRC Scenario 3 March 2015 Events 7 and 8 continued Note: Control rods will successfully insert using RMCS. RO Continued Possible EOP-3.1 Section 3 Actions:

Verify a CRD Pump running *

Place Reactor Mode Switch in REFUEL Place ARI OVERRIDE switch in OVERRIDE

Installed RPS jumpers (5, 6, 12, 13) Note: RO will likely have to fully open the CRD flow

Reset the scram control valve and/or close 44-04 in order to achieve

Insert rods to 00 using EMER ROD IN starting rod movement via RMCS; these methods are preferential to closing 44-167 due to ability to perform from the control room and not preventing further scram attempts by blocking the charging water header. Note: When ARI is overridden, the scram is reset, and annunciator F4-1-1 clears, then TRG 20 will activate.

Verify this occurs and the RD33 malfunctions all delete. This allows all control rods to insert on the next manual scram attempt.

As directed by the examiner, if it's desired to 'time compress' scramming to all rods in, insert TRG 10 to fail off appropriate annunciators and insert TRG 20 to remove A TWS malfunctions all AFTER verifying the scram is reset. with high power regions of core (use LPRM indications) (CT-3.0)

If more drive pressure is required, then perform one of 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 EOP-3.1 Section 4 Actions:

Place ARI OVERRIDE switch in OVERRIDE

Installed RPS jumpers (5, 6, 12, 13)

Reset the scram

Verify open 44-167, Charging Water Header Blocking Valve (RB 237')

When the SDV is drained, then initiate a manual scram (CT-3.0)

Page 26 of 28 NRC Scenario 3 March 2015 Exelon Generation Events 7 and 8 continued Role Play: When directed as PO to pull HPCI fuses FU-8 and FU-9, wait one minute and insert remote: FW24, Removal of HPCI Fuses FU8/FU9, FV=pulled TRG23 Then report that HPCI fuses FU-8 and FU-9 have been pulled BOP

Bypasses ADS

Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24 (CT-2.0):

Attempts to close both FEEDWATER ISOLATION Valves 11 and 12

Determines FWIVs will not close and places FWPs 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

Directs PO to remove fuses FU-8 and FU-9 from Panel IS34 in the Aux Control Room

Verifies closed, FEEDWATER PUMP 13 BLOCKING VALVE

Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output

Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output Informs SRO when RPV water level reaches -41 inches Page 27 of 28 NRC Scenario 3 March 2015

Generation Copy of __ Training Id: NRC 2015 Scenario 4 Revision:

0.0 Restore RRP to Service, Loss of Reactor Building Ventilation, RRMG M/ A Station Failure, Steam Line Break in the Drywell, Failure of Title: HPCI, Containment Spray Pump Trip Developed By Validated By Facility Reviewer NRC Scenario 4 Signature I Printed Name Isham Pat O'Brien Leigh Mason Dave Ballard Greg Elkins Page 1 of 25 6/2/14 8/20/14 8/20/14 8/20/14 March 2015

_.,,..,.

Exelon Generation References N1-0P-1, Nuclear Steam Supply System N1-0P-43B, Normal Power Operations N1-0P-10, Reactor Building

Heating, Cooling, and Ventilation System N1-SOP-1.3, Recirc Pump Trip at Power N 1-SOP-1 , Reactor Scram N1-EOP-2, RPV Control N1-EOP-4, Primary Containment Control N 1-EOP-5, Secondary Containment Control N1-EOP-1, NMP1 EOP Support Procedure N1-EOP-8, RPV Slowdown Unit 1 Technical Specifications NRC Scenario 4 Page 2 of 25 March 2015 Exelon Generation Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The crew assumes the shift with the plant operating at 90% power and four recirculation loops in service.

Containment Spray pump 112 and Reactor Building Exhaust Fan 12 are out of service for maintenance.

Immediately after assuming the shift the crew will be directed to restore Recirculation Pump 11 to service and return to full power. The crew will assess plant conditions and lower power with Recirculation Flow until flow is less than 50 Mlbm/hr.

They will then return Recirculation Pump 11 to service.

After the crew has placed the recirc pump in service,

11 RB exhaust fan will trip. The crew will diagnose the fan trip and a positive RB pressure.

With #12 RB exhaust fan OOS, the crew will start the Reactor Building Emergency Ventilation System (RBEVS) to restore a negative RB pressure.

Entry into N1-EOP-5, Secondary Containment Control is required.

SRO determines the secondary containment TS is still satisfied.

Next, RRP 15 flow rises due to a blind controller failure.

The crew will take the M/A station to manual, and the rise will stop. RRMG 15 will develop a high slot temperature, requiring the crew to remove it from service.

A steam leak will then develop in the Primary Containment.

The crew will insert a scram. Following the scram, HPCI will fail to initiate, requiring manual action to establish injection with preferred and/or alternate injection systems to maintain RPV water level (Critical Task). When the crew attempts to spray the Containment, Containment Spray pump 111 will trip. The two remaining Containment Spray pumps will be insufficient to avoid violating PSP, and the crew will perform an RPV Blowdown (Critical Task). 1. Termination Criteria

a. RPV water level controlled in assigned band, RPV Blowdown in progress, Primary Containment pressure controlled per N1-EOP-1 attachment 17 Page 3 of 25 NRC Scenario 4 March 2015 Exelon Generation

2. Critical Tasks CT-1, Given a LOCA in the Drywell and a failure of HPCI to initiate, the crew will inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with N1-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. N1-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-2, Given a LOCA in the Drywell and degraded Containment Spray capability, the crew will execute N1-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with N1-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.

N1-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 4 of 25 NRC Scenario 4 March 2015 Exelon Generation

4. Mitigation Strategy Code a. PC4, RPV Slowdown due to PSP 5. Technical Specifications

a. TS 3.2.5 b. TS 3.6.2 Tables a and g c. TS 3.1.7.e 6. EAL Classification

a. Alert, EAL FA 1.1 -Any loss or any potential loss of either fuel clad barrier or RCS barrier.

7. Special Orders a. None Page 5 of 25 NRC Scenario 4 March 2015 Exelon Generation B. Initial Conditions

1. IC Number a. IC-154 2. Presets I With Triggers

a. Malfunctions

1) CT01 B, CT Pump 112 Trip 2) HV01 B, Reactor Building Exhaust Fan Trip 12 3) HV01A, Reactor Building Exhaust Fan Trip 11 4) RR65E, RR Pump 15 Blind Controller Input Signal Failure, FV=95, RT=5min 5) RR09E, RR PUMP 15 MG Slot Temperature

Increase, DT=30sec, RT=10min, FV=60 6) EC01, Steam Supply Line Break in PC, FV=11 7) PC10A, BV 68-01 Fails Open 8) PC10C, BV 68-03 Fails Open 9) FW28A, HPCI MODE: FWP 11 AUTO-START FAIL 10) FW288, HPCI MODE: FWP 12 AUTO-START FAIL 11) CT01A, CT Pump 111 Trip 12) CS07, CS Injection Valves Failure to Auto Open b. Remotes 1) c. Overrides None d. Annunciators None Page 6 of 25 NRC Scenario 4 Inserted Inserted TRG 1 TRG2 TRG3 TRG5 TRG 23 TRG 23 Inserted Inserted Inserted Inserted March 2015 Exelon Generation

e. Event Triggers TRG 3, Initiates when RRP 15 M/A station is taken to manual to initiate slot temperature rise. TRG 22, Initiates when RRP 15 M/A station is taken to manual to delete M/A station oscillations TRG 23, Initiated when Mode Switch is taken to Shutdown to increase the size of the leak. TRG 24, Initiates when Containment Spray flow is initiated to increase size of the leak. TRG 25, Delete slot temperature rise malfunction when the recirc pump is secured.

f. Equipment Out of Service zdrrmam(5)==1 zdrrmam(5)==1 zdrpstdn==1 ctfdw>100 zdrrmgpl(5)==1

1) Containment Spray Pump 112 in PTL with yellow tag 2) Containment Spray suction isolation valve 112 closed with yellow tag 3) Reactor Build Exhaust Fan 12 secured with yellow tag 4) Recirc Pump 11 secured, ready for start g. Support Documentation

1) N1-0P-1 marked up through step H.4.4 2) N1-0P-43B marked up through step 2.6 3) RMI for lowering recirc flow to 50 Mlbm/hr h. Miscellaneous

1) Protect the following equipment:

EDG 103, PB 103 2) Update Divisional Status Board Blank dmf rr65e imf ec01 (0 0) 30 4:00 11 imf ec01 (0 0) 45 1 :00 30 dmf rr09e 3) Ensure LPRM downscale pushbuttons are depressed on rod block monitor 4) DW Cooling Fan 11 Secured Page 7 of 25 NRC Scenario 4 March 2015

Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: . I N ID DATE:

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 90%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Reactor Building Exhaust Fan 12 is out of service for maintenance.

RRP 11 removed from service for repairs and is ready to be returned to service.

TS 3.1. 7.e. Four loop operation.

PART Ill: Remarks/Planned Evolutions:

Start RRP 11 per N1-0P-1, H.4.0, and return to five-loop operation.

N1-0P-1, H.4.0, signed off up to step H.4.5. N1-0P-43B signed off up to step 2.7.

Reactor power is at 90% and must be lowered until recirc flow <50 Mlbm/hr to support starting RRP 11.

After starting Recirc Pump 11 MG set, operate it on the master flow controller for one hour while maintenance takes readings before returning to 100% power. Page 8 of 25 NRC Scenario 4 March 2015 Exelon Generation ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

Recirc Pump Restoration Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I RE presence required in the Control Room? Yes_ No ./ If YES above, RE presence not required for steps_. Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range Actual Recirc Flow 51-54 Mlbm/hr Description of Step: 1. Lower recirculation flow to 49-50 Mlbm/hr.

2. Start 11 RRP per N 1-0P-1 3. Raise reactor Power to 98% with recirc flow 4. Raise reactor Power to 100% with recirc flow over one hour Critical parameters to be monitored DURING Step: Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency CTP 1850 MWth RO Continuous Lower recirculation flow or insert cram rods RMI evaluated against approved power profile:*

N/A D. Other Comments:

After Starting recirc pump 11 MG set and placing it on the master controller, operate it for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to returning to 100% power. Step Prepared by: Alex Reed I Today Step Reviewed by: Jack Dean I Today RE/STA Date RE/STA/SRO Date Approval to perform Step John Aaron I Today Step Completed by: I Shift Manager Date SRO Date Page 9 of 25 NRC Scenario 4 March 2015

=::"Exelon Generation Shift Turnover 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 panels. Page 10 of 25 NRC Scenario 4 Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift March 2015

__.,. Exelon Generation Event #1: Power Reduction with Recirc Flow for RRP Restoration

The crew will reduce reactor power with recirc flow in order to restore recirc pump 11 to service following repairs SRO Note: Reactivity brief and procedure review will be

Directs RO to lower core flow to <50 Mlbm/hr conducted prior to the crew entering the simulator.

IAWRMI

Supervises reactivity maneuver RO

Reduces recirc flow IAW RMI

Continuously observes the following:

-APRMs lowering

-Recirc flow lowering

-Steam and feedwater flow lowering

-Vessel level normal

Lower recirc flow until <50 Mlbm/hr

Report when recirc flow is <50 Mlbm/hr BOP

Monitors individual RRP for response

-Individual MIA-Speed Control stations trending uniformly

-Individual RRP indications trending normally for lowering speed

Monitors feed water controls for proper response

-FWP 13 FCV responding to power change

RPV Water Level remains within program band (65" -83") Page 11 of 25 NRC Scenario 4 March 2015

Generation

The plant is operating in 4 loop operation

The crew will restore RRP 11 to service Note: Crew directed to start RRP 11 in pre-brief, SRO starting at N1-0P-1, step H.4.5.

Direct start up of RRP 11, using N 1-0P-1, starting at step H.4.5

Supervise reactivity manipulation

Acknowledge report that RRP 11 is in service

Determine TS 3.1. 7.e no longer applies and the LCO Actions can be exited RO

Continuously observe the following:

-APR Ms -Recirc flow

Monitor P/F map and transfer from 4 loop to 5 loop map when the startup is performed Page 12 of 25 NRC Scenario 4 March 2015 Exelon Generation Event 2 Continued CAUTIONS from N1-0P-1

Failure to raise Recirc Pump speed during opening of discharge valve may result in stalled rotor and pump trip due to reverse flow.

To Prevent backflow thru the RRP, discharge valve should be opened before MG frequency lowers to 20 Hz. Frequency will raise, then drop quickly, then raise again before SLOWLY lowering.

Discharge BV should be opened when frequency is slowly lowering.

Role Play: As PO sent to Aux Control Room, wait one minute then report you have reset 50SR Pump Motor Stalled Rotor Target Role Play: As PO, when requested report MG set oil temperature is 120°F and stable. Page 13 of 25 NRC Scenario 4 BOP

Verify recirculation flow < 50 x 106 lb/hr

Verify RRP 11 GEMAC in MAN and matched with other four GEMACs but no greater than 50%

Verify RRP 11 discharge valve closed

Verify RRP 11 suction and discharge bypass valves are open

Make a plant announcement for start of RRP 11

Place RRP 11 control switch to START and observe indications

MG MOTOR starts, Amp Meter Amps increase then decrease

MG Generator accelerates to proper speed (approx 50 -60 Hz)

Generator Field Bkr closes

Generator slows toward 20% speed (Approximately 11.5 Hz)

WHEN speed (Frequency Meter) is between 30 and 25 Hz, open REACTOR R PUMP DISCH VALVE

Verify RRP 11 maintained less than or equal to OP limits

Adjust pump speed to match other pumps

Null RRP 11 controller and shift to BAL or AUTO

Verify power/flow map updated to five loop requirements

Dispatch PO to reset 50SR Pump Motor Stalled Rotor Target (Aux Control Room)

Dispatch PO to check MG set oil temperature locally

May perform N 1-ARP-F2-1-1 action to depress PUMP MOTOR VIBRATION RESET pushbutton on F Panel, clearing annunciator F2-1-1 March 2015 Exelon Generation Event #3: Loss of Normal Reactor Building Ventilation

A trip of RB Exhaust Fan 11 occurs with RB Exhaust Fan 12 OOS for maintenance.

The crew will need to re-establish negative RB DIP with RBEVS As directed by lead examiner, insert malfunction:

CREW

Recognize/report L 1-3-4, REACT BLDG/ATM HV01A, Reactor Building Exhaust Fan Trip 11 DIFF PRESS, in alarm. TRG 1

Recognize/report L 1-1-5, RB VENT EXH FAN 11-12 TRIP -VIB, in alarm.

Recognize/report exhaust fan 11 tripped . L1-1-5, RB VENT EXH FAN 11-12 TRIP-V/B SRO L 1-2-4, RB VENT SUP SYSTEM Acknowledge report L 1-3-4, REACT BLDG/ATM L 1-2-5, RB VENT EXH FLOW LOW

L 1-3-4, REACT BLDG/ATM DIFF PRESS DIFF PRESS, in alarm. RB dP drops to O"

Acknowledge report L 1-1-5, RB VENT EXH FAN 11-12 TRIP -VIB, in alarm.

Acknowledge report exhaust fan 11 tripped .

Direct actions of L 1-3-4andL1-1-5 to be performed.

Acknowledge reactor building negative pressure is degraded low.

Recognize entry condition for N1-EOP-5, Secondary Containment Control.

Determine no emergency exists (activation of emergency plan not required).

i. Per SC-3, ensure RBEVS started and RB ventilation isolated

Determine that with the reactor building isolated and RBEVS running and maintaining reactor building negative pressure within the limit, entry into Tech Spec actions for Secondary Containment IS NOT REQUIRED.

0 TS 3.4.2 and TS 3.4.4 requirements are met Page 14 of 25 NRC Scenario 4 March 2015 Exelon Generation Event 3 Continued Page 15 of 25 NRC Scenario 4 BOP

Acknowledge direction to perform actions of L 1-3-4, L 1-1-5

Monitor Reactor Building DIP

Inform SRO D/P is zero

Start RBEVS per N1-0P-10 o Verify open 202-36, EM VENTILATION FROM REACTOR BLDG BV o Verify closed 202-47, EM VENTILATION TIE BV o Verify closed 202-74, EM VENTILATION LOOP 11 COOLING BV o Verify closed 202-75, EM VENTILATION LOOP 12 COOLING BV If starting RBEVS 11

Place 202-37, EM VENTILATION LOOP 11 INLET BV control switch to OPEN

Verify open 202-37, EM VENTILATION LOOP 11 INLET BV

Start 202-53, EVS FAN 11

Verify open 202-34, EM VENT EXHAUST FAN 11 OUTLET BV

Confirm proper operation of 202-50, EM VENT EXHAUST FAN 11 INLET FCV, by observing flow indication and Rx Bldg DP If starting RBEVS 12

Place 202-38, EM VENTILATION LOOP 12 INLET BV control switch to OPEN

Verify open 202-38, EM VENTILATION LOOP 12 INLET BV

Start 202-33, EVS FAN 12

Verify open 202-35, EM VENT EXHAUST FAN 12 OUTLET BV

Confirm proper operation of 202-51, EM VENT EXHAUST FAN 12 INLET FCV, by observing flow and Rx Bldg DP March 2015

Generation Event 3 Continued Page 16 of 25 NRC Scenario 4 BOP Continued

Isolate reactor building ventilation per N1-0P-10 o Place REACTOR BLDG SUPPLY FANS 11and12 in OFF o Place REACTOR BLDG EXHAUST FANS 11 and 12 in OFF o Place control switch for 202-31, REACTOR BLDG EXHAUST ISOLATION VALVE 12 and 202-32, REACTOR BLDG EXHAUST ISOLATION VALVE 11 in CLOSE o Place control switch for 202-15, REACTOR BLDG SUPPLY ISOLATION VALVE 11 and 202-16, REACTOR BLDG SUPPLY ISOLATION VALVE 12 in CLOSE

Report RBEVS in service and reactor building ventilation isolated March 2015 Exelon Generation Event #4: Recirc Pump 15 M/A Failure and High Temperature Trip

The plant is operating with 5 recirc loops in service at less than rated power.

RRP15 flow rises due to a blind controller

failure, but stops when placed in Manual

RRP15 runs a high slot temperature and must be tripped As directed by lead examiner, insert malfunction:

CREW RR65E, RR Pump 15 Blind Controller Input Signal

Diagnose/report Recirc pump 15 parameters are Failure, FV=95, RT=5min elevated.

TRG2 APRMs, MWth, MWe, all rise SRO

Acknowledges report of power rising

May direct entry into N1-SOP-1.5

May direct entry into N1-0P-1, Sect H for Recirculation System Failures

Directs taking manual control of RR Pump 15 M/A station

Acknowledges report that RR Pump 15 is in manual and able to be controlled RO

Monitors plant parameters BOP

Recognizes and reports RR Pump 15 controller rising

Nulls deviation meter on RR Pump 15 (may reference N1-0P-1, Sect. F.1.0)

Places RR Pump 15 MIA station in MAN

Verifies failure stops

Notifies SRO/Crew that RR Pump 15 is in manual and that the malfunction has stopped Page 17 of 25 NRC Scenario 4 March 2015

Generation Verify the following malfunction is automatically CREW inserted when the RRP 15 MIA station is taken to

Acknowledge/report Annunciator F2-2-5 MAN:

Observe computer points A 130 and 8399 in alarm RR09E, RR Pump 15 MG Slot Temperature

Increase, DT=30sec, RT=10:00, FV=60 TRG3 Expected Annunciator:

F2-2-5, REACT REC/RC MG SET 15 -6 min Expected Computer Points: 8399 RRMG 15 GEN SLOT TEMP C -5min A130 RRMG 15 GEN SLOT TEMP HIGH-6 min 8404 RRP 15 MTR Slot Temp High SRO Note: If the crew does not take action to secure the

Acknowledges RRMG 15 high slot temperature pump after a reasonable time trip RR Pump 15 by

Directs execution of ARP F2-2-5 inserting malfunction RR01 E.

Directs a reactor power reduction

Provides oversight of reactivity manipulation Note: N1-0P-1 directs lowering power per N1-0P-* May direct a trip of RR Pump 15 and entry into 438. However, due to the emergent nature of this N1-SOP-1.3 event, the crew will likely lower power using the guidance of N 1-SOP-1.1, Emergency Power

May direct entry into N1-SOP-1.5 after the trip Reduction.

May direct removing RR Pump 15 from service using N1-0P-1, Sect H.1.0 Role Play: If contacted as the Ops Director regarding

Enter T.S. 3.6.2 for inoperable APRMs while RR the high temperature, direct the crew to remove the Pump 15 Discharge Valve is open if the pump is MG Set from service.

tripped

Enters T.S. 3.1.7.e for partial loop operation RO

Monitors plant parameters

When directed, lowers power with recirculation flow

Verifies P/F Map updated for 4 loop operation

Lowers Recirc flow as necessary to remain within flow limits for 4 loop operation

Monitors plant limits for 4 loop operation Page 18 of 25 NRC Scenario 4 March 2015

=:r-Exelon Generation Role Play: If requested to check Turbine Building Ventilation and MG Set Ventilation, wait 3 minutes, then report that everything is normal with the ventilation.

Report that the generator end of RRMG 15 is very hot to the touch. Note: N1-0P-1 directs lowering power per N1-0P-43B. However, due to the emergent nature of this event, the crew will likely lower power using the guidance of N 1-SOP-1.1, Emergency Power Reduction.

Note: Verify TRG 25 inserts to automatically delete RR09E when the recirc pump is tripped.

Page 19 of 25 NRC Scenario 4 BOP

Enters ARP F2-2-5

Enters N1-0P-1, Sect F.4

Dispatches operator to verify proper operation of MG Set Area Ventilation, TB Track Bay AND Roll door position(s),

and MG Set Area Coolers.

Verifies Reactor Recirc Pump parameters are within the following limits:

Generator MW 0.790 MW

Generator Amps 240 A

RRP Flow 16.8 X 106 lbm/hr

Generator Frequency 11.5 Hz to 56 Hz

Verifies total recirculation flow is evenly balanced between all operating RRPs

When Generator slot temperature continues to rise and approaches or exceeds 120°C, reduces loading on affected RRMG by lowering power per N1-0P-43B If directed to trip RR Pump 15:

Places RR Pump MOTOR 15 MG SET switch to STOP

Enters N1-SOP-1.3

Notifies SRO the APRMs are inop

Close RR Pump 15 Discharge Valve

Holds Discharge Valve in OPEN position for 2 to 3 seconds

Records time

Notifies SRO the APRMs are operable If directed, removes RR Pump 15 from service using N1-0P-1, Sect H.1

Verifies open RR Pump 15 Bypass Valve

Lowers flow on RR Pump 15 to 6 to 8 x 106 lbm/hr

Closes RR Pump 15 Discharge Valve

When the Discharge Valve is closed, places RR Pump MOTOR 15 MG SET switch to STOP

Holds Discharge Valve in OPEN position for 2 to 3 seconds March 2015 Exelon Generation Events #5, #6, #7, and #8: Steam Leak Inside Drywell, Vacuum Breaker Fails Open, Failure of HPCI and Core Spray to Initiate, Trip of Containment Spray Pump 111

EC Steam line Break in the Drywell with multiple system failures When directed by the lead examiner, insert malfunction:

EC01, Steam Supply Line Break in PC, FV=11 TRG5 Drywel/ humidity, pressure and temperature rise Drywel/ /eakage rises Expected annunciators:

H2-1-1, Drywell Floor Drain Level High H2-4-7, Drywel/ Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5(4-1-4),

RPS Ch 11(12) Drywel/ Press High Verify the following malfunctions are preset: FW28A, HPCI Mode Failure to Initiate 11 FW28B, HPCI Mode Failure to Initiate 12 CT01A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray /Vs do NOT open at 365 psig Expected annunciator:

K1-1-7, Containment Spray Pump 111 Trip Failto Run Page 20 of 25 NRC Scenario 4 CREW

Diagnose/report degrading containment parameters

Acknowledge/report annunciators

Diagnose failure of HPCI to automatically initiate

Diagnose the trip of Containment Spray pump 111 March 2015 Exelon Generation Events 5, 6, 7, and 8 continued Verify the following malfunctions automatically insert when the mode switch is taken to SHUTDOWN:

EC01, Steam Supply Line Break in PC, IV=11, RT=4:00, FV=30 PC10A, BV 68-01 Fails Open PC10C, BV 68-03 Fails Open Containment conditions further degrade TRG23 Two Torus-to-Drywel/

vacuum breakers indicate open Expected annunciator:

K1-4-6, Torus-OW Vac Relief Check Valve Open Verify the following malfunction automatically inserts when Containment Spray flow is initiated to the Drywell:

EC01, Steam Supply Line Break in PC, IV=30, RT=1 :00, FV=45 TRG24 Page 21 of 25 NRC Scenario 4 SRO

Acknowledges reports

Directs manual scram

Acknowledges scram report

Enters N 1-EOP-2 on low RPV water level

Directs N1-SOP-1 actions

Directs RPV water level controlled 53-95" with Condensate/FW and CRD

When notified of the failure of HPCI to initiate, directs manual control of Feedwater (preferred and alternate injection systems)

CT-1

Directs RPV pressure controlled 800-1000 psig with Turbine Bypass Valves (if available) or Emergency Condensers

May direct closure of MSIVs to limit cooldown rate

Enters N1-EOP-4 due to high drywell pressure and temperature o Direct lockout of Containment Spray pumps

Re-enters N1-EOP-2 due to high drywell pressure and low RPV water level March 2015 Exelon Generation Events 5, 6, 7, and 8 continued Role Play: If directed to perform in-plant actions to line up Containment Spray Raw Water to Containment Spray, acknowledge order, but delay any field actions.

Note: Core Spray injection will only be prevented if not needed for core cooling.

If the crew has not yet re-established RPV injection when this step is evaluated, the Core Spray jumpers may not be installed until later. N1-EOP-2 step P-1 provides continuous guidance for this consideration.

Page 22 of 25 NRC Scenario 4 SRO continued

When torus pressure exceeds 13 psig or drywell temperature approaches 300°F:

Answers "Below the Containment Spray Initiation Limit?" -Yes

Verifies all Recirc pumps tripped

Directs trip of all Drywell cooling fans

Directs operation of Containment Spray per 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-2

Answers "Are all control rods inserted to at least 04?" YES

Answers "Drywell pressure?"

At or above 3.5 psig

May direct prevention of Core Spray injection per EOP-1 attachment 4

Directs EC initiation

Answers "Torus water level?" Above 8.0 ft

Directs open 4 ERVs March 2015

Generation Events 5, 6, 7, and 8 continued RO Page 23 of 25 NRC Scenario 4

Monitors plant parameters

When directed, places Mode Switch in Shutdown

Provides scram report

Performs N 1-SOP-1, Reactor Scram, scram verification actions

Places I RMs 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 March 2015

Generation Events 5, 6, 7, and 8 continued BOP

Monitors/reports degrading Containment parameters

Performs RPV water level control actions of SOP-1, Reactor Scram: Note: Feedwater level control actions will vary

Restores RPV level to 53-95" by controlling depending on when the operator diagnoses the failure of HPCI to automatically control injection through Feedwater flow control valves 11 and 12. Page 24 of 25 NRC Scenario 4 injection and rejecting through RWCU

Starts 11 or 12 MDFWP

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 Blocking Valve

Verifies RPV water level above 53"

Verifies 11/12 FWP controllers in MANUAL 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-1 March 2015 Events 7, 8, and 9 continued Note: Core Spray pumps may be placed in PTL if needed before N1-EOP-1 attachment 4 jumpers can be installed due to scenario progression and resource limitations.

If Core Spray pumps are placed in PTL, at least one Core Spray pump should be restarted after jumper installation for App J water seal. Core Spray may also be used as an alternate injection source.

RPV Slowdown in progress RO/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 If 80-118 is open for Torus Cooling:

Opens 80-35

Closes80-118

Verifies open 80-40 and 80-45 Prevents Core Spray injection installing EOP-1 attachment 4 jumpers (17, 18, 19, 24, 25, 26), if directed

Initiates both ECs

Opens 4 ERVs CT-2

Primary Containment pressure controlled per N1-EOP-1 attachment 17 Page 25 of 25 NRC Scenario 4 March 2015

_.,,., Exelon Generation Copy of __ Training Id: NRC 2015 Scenario 5 Revision:

0.0 -----ERV Inadvertently Opens, Powerboard 16A Fault, Loss of All RBCLC, Loss of High Pressure Feedwater, Coolant Leak Inside Primary Containment, Title: RPV Flooding Developed By Validated By Facility Reviewer NRC Scenario 5 Signature I Printed Name Isham Pat O'Brien Leigh Mason Dave Ballard Greg Elkins Page 1 of 25 6/2/14 8/20/14 8/20/14 8/20/14

Generation References

1. N1-0P-33A, 115 KV System 2. N 1-SOP-1.4, Stuck Open ERV 3. N 1-SOP-1.1, Emergency Power Reduction

4. N1-SOP-11.1, RBCLC Failure 5. N1-SOP-1, Reactor Scram 6. N1-EOP-2, RPV Control 7. N1-EOP-4, Primary Containment Control 8. N1-EOP-1, NMP1 EOP Support Procedure

9. N1-EOP-7, RPV Flooding

10. Unit 1 Technical Specifications Page 2 of 25 NRC Scenario 5

=:rExelon Generation Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The scenario begins at approximately 100% power. Containment Spray pump 112 and Reactor Building Exhaust Fan 12 are out of service for maintenance.

The crew will remove Line 4 from service for maintenance.

The CRS 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 CRS will determine the Tech Spec impact. Next, Powerboard 16A will develop an electrical fault. This will cause a loss of power to three Drywell cooling fans. The crew will start an additional Drywell cooling fan to stabilize Drywell temperature and pressure.

The electrical loss will also affect EDG 103 auxiliary equipment.

The CRS will determine the Tech Spec impact. Next, the running RBCLC pumps will trip. The standby RBCLC pump will trip upon being started.

The crew will enter N1-SOP-11.1, RBCLC Failure.

The crew will scram the Reactor, trip Recirculation pumps, initiate Emergency Condensers, and shut the MSIVs. The high pressure Feedwater pumps will fail to operate on the scram, complicating Reactor water level control.

Once the crew stabilizes the plant after the scram, a coolant leak will develop inside the Primary Containment.

The crew will re-enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control.

Containment parameters will degrade and the crew will initiate Containment Sprays (Critical Task). The elevated Containment temperature will cause the Fuel Zone level indications to become erratic.

With all other Reactor water level indicators downscale, the crew will execute N1-EOP-7, RPV Flooding, to lower Reactor pressure and flood the Reactor to the Main Steam lines (Critical Task). 1. Termination Criteria

a. RPV Flooding in progress

b. Reactor water level on scale or upscale c. Containment pressure and temperature controlled in accordance with N1-EOP-4 Page 3 of 25 NRC Scenario 5

Exelon Generation

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 110° F. 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. N1-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 25 NRC Scenario 5

Generation CT-2, Given a LOCA in the Drywell, initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4 Justification:

Safetv Significance:

Initiating Containment Sprays reduces Primary Containment pressure.

This reduces stresses on the Drywell and Torus, assists in avoiding "chugging" that may cause fatigue failure of the LOCA downcomers, and avoids the need for a blowdown.

These benefits reduce challenges to the fuel cladding, the RPV, and the Primary Containment.

Cueing: Multiple Primary Containment pressure and temperature indications and annunciators will indicate degrading conditions.

N1-EOP-4 provides direction to initiate Containment Sprays. Measurable Performance Indicators:

Manipulation of Containment Spray pump control switches will provide observable actions for the evaluation team. Performance Feedback:

Containment Spray flow and lowering Primary Containment pressure and temperature indications will provide performance feedback regarding success of crew actions to initiate Containment Sprays. CT-3, Given the plant with RPV water level unknown, execute N1-EOP-7, RPV Flooding, in accordance with N1-EOP-2.

Justification:

Safety Significance:

With Reactor water level unknown, the status of core cooling is unknown.

RPV flooding is required to establish conditions to cool the core. This protects the fuel cladding integrity.

Cueing: Multiple Reactor water level indications will indicate either downscale or invalid.

N1-EOP-2 provides direction to implement N1-EOP-7, RPV Flooding.

Measurable Performance Indicators:

Manipulation of ERVs, MS/Vs, EC/Vs, and injection system controls provide observable actions for the evaluation team. Performance Feedback:

ERV, MSIV, and EC/V position indications, Reactor pressure, ERV tailpipe temperatures, and ERV acoustic monitors provide performance feedback regarding success of RPV flooding actions.

3. Length a. -60 minutes Page S of 25 NRC Scenario 5

=:r-Exelon Generation

4. Mitigation Strategy Code a. RL4, loss of all RPV level indication (non-ATWS),

RPV Slowdown, RPV Flooding.

5. Technical Specifications

a. TS 3.6.3 (b) b. TS 3.1.5 (b) 6. EAL Classification

a. Site Area Emergency per FS1 .1 -Loss or potential loss of ANY two fission product barriers.

7. Special Orders a. None Page 6 of 25 NRC Scenario 5

Generation

8. Initial Conditions

1. IC Number a. IC-155 2. Presets I With Triggers

a. Malfunctions

1) CT01B, CT Pump 112 Trip 2) HV01 B, Reactor Building Exhaust Fan Trip 12 3) ADOS, ERV 111 Failure -Opens Inadvertently

4) ED12A, PB 16A Electrical Fault 5) CW04A, RBCLC Pump 11 Trip 6) CW04B, RBCLC Pump 12 Trip 7) CW04C, RBCLC Pump 13 Trip 8) FW03A, FEEDWATER PUMP TRIP 11 9) FW03B, FEEDWATER PUMP TRIP 12 10) FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH DISENGAGES

11) CU01, CU COOLANT LEAK INSIDE OF DRYWELL, FV=70, RT=5:00 12) EC01, Steam Supply Line Break in PC, FV=5, RT=5:00 13) VICP20168_FE CP-201-68, Fuel Zone Erratic Failure 14) VICP20169_FE CP-201-69, Fuel Zone Erratic Failure b. Remotes 1) AD01 A, ERV 111 Fuses, FV=pulled

2) AD07, Acoustic Monitor Alarm Reset, FV=reset

3) FW24. Removal of HPCI Fuses FU8/FU9, FV = pulled Page 7 of 25 NRC Scenario 5 Inserted Inserted TRG 1 TRG3 TRG4 TRG4 TRG4 TRG5 TRG5 TRG5 TRG6 TRG6 TRG7 TRG7 TRG27 TRG 28 TRG9

_.,,,, Exelon Generation

c. Overrides

1) OVR-5M76A03510 1F1/36-20 FV= -33.84 (LLL downscale indication)

2) OVR-5M75A03500 1 F1/36-19 FV= -33.84 (LLL downscale indication)

d. Annunciators

1) None e. Event Triggers TRG 5 -Activates on Reactor zdrpstdn==1 scram to insert loss of Feedwater.

TRG 7 -Activates on DW hzarrl19<0.075&&hzarrl20<0.075&&pctdw8 temp >200°F, LLL level below >200&&ctfdw>100

-20", and Containment Spray flow to Drywell >100 gpm to insert Fuel Zone erratic indication.

f. Equipment Out of Service 1) Containment Spray pump 112 in PTL with yellow tag Blank Blank 2) Containment Spray suction isolation valve 112 closed with yellow tag 3) Reactor Building Exhaust fan 12 OOS with yellow tag 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.

TRG7 2) Protect the following equipment:

EDG102, EDG 103, PB 102, PB 103, Line 1, MOD 8106. 3) Update Divisional Status Board. Page 8 of 25 NRC Scenario 5

Exelon Generation SHIFT TURNOVER INFORMATION ON COMING SHIFT: I N ID DATE: -=Tc..:::oo...=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%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Reactor Building Exhaust Fan 12 is out of service for maintenance.

PART Ill: Remarks/Planned Evolutions:

Remove Line 4 from service per N1-0P-33A Section H.12 to support National Grid maintenance.

The procedure has been completed up to Step H.12.9. Page 9 of 25 NRC Scenario 5

Exelon Generation Shift Turnover 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 panels. NRC Scenario 5 Crew

Walkdown panels

Conduct shift turnover brief

Assume the shift Page 10 of 25

Generation Event #1: Remove Line 4 From Service Role Play:

Initial reactor power is -100%

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. BOP

Reviews N1-0P-33A Section H.12

Verifies Auto Reclosure for R-40 breaker is OFF

Opens breaker R-40

Dispatches Operator to confirm R-40 open locally on ALL 3 phases When asked as Operator to confirm R40 position,

Notifies SM to review TS for appropriate LCO immediately report all three phases of R-40 are open. applicability NRC Scenario 5

Continues at Section H.9.0, Loss of 115 KV Line 4 ATC

Monitors plant parameters

Provides peer checks as needed

Line 4 removed from service Page 11 of 25

,..,.,,,

Exelon Generation Event #2: ERV 111 Inadvertently Opens

ERV 111 Inadvertently Opens

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 malfunction:

ADOS, ERV 111 Failure -Opens Inadvertently ERV 111 opens Reactor pressure lowers slightly Reactor power lowers and then rises slightly Torus temperature rises Torus level rises Expected annunciators:

TRG 1 F1-4-8, STEAM LINE DETECTION SYS FLOW OFF NORM F2-4-1, MAIN STM LINE ELECTROMA TIC RELIEF VALVE OPEN H3-4-5, PRESS SAFETY/RELIEF VALVES FLOW NRC Scenario 5 CREW

Acknowledges/reports annunciators

Diagnoses ERV 111 has inadvertently opened Page 12 of 25

Generation SRO Event 2 continued

Acknowledges reports

Directs entry into N 1-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 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 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 N1-EOP-1 att 16 or N1-SOP-1.4 ATC

Performs emergency power reduction per N 1-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 25 NRC Scenario 5

Exelon Generation Event 2 continued Role Play: When directed as Operator to go to Auxiliary Control Room and verify ERV 111 is open, wait one minute and report ERV 111 is open. Subsequent reports on acoustic monitor status may be given immediately, with close attention paid to the actual status of the ERV. Note: Safety glasses, gloves, and long sleeves or a lab coat are required for pulling fuses in F panel. Role Play: If the Operator is directed to pull fuses in the RB wait 3 minutes and insert remote: AD01A, ERV 111 Fuses, FV=pulled TRG27 Report fuses are pulled. Role Play: When directed as operator to reset the acoustic

monitor, wait 1 minute and insert remote: AD07, Acoustic Monitor Alarm Reset, FV=reset TRG28 Report acoustic monitor is reset. BOP

Enters N1-SOP-1.4

Determines ERV 111 is open using: -Valve indicating lights on F panel -Red ERV flow indicating light on F panel

Sends an operator to the Aux Control Room to 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 all of the following:

Depresses ADS Timer Reset pushbuttons Cycles Control Switch for ERV 111 Pulls control power fuses F15 and F30 in F panel (ERV 111) o OR Directs operator to pull ERV 111 fuses on RB 237' CT-1

Checks with operator in Aux Control Room to see if ERV is still open

Determines/verifies ERV closes

Directs reset of acoustic monitor

Notifies crew that ERV 111 has closed

Monitors Torus temperature

Reports if/when Torus temperature exceeds 85°F or Torus level exceeds 11.25' Places Containment Spray pumps in PTL if directed Page 14 of 25 NRC Scenario 5

Exelon Generation NRC Scenario 5 BOP continued

Places Torus cooling in service when directed, per N1-SOP-1.4, att 2 or N1-EOP-1 att 16: 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 25

=:rExelon Generation Event #3: Powerboard 16A Electrical Fault

The plant experiences an electrical fault on PB 16A

The crew will take action to mitigate further degradation to the plant. When directed by examiner, insert malfunction:

CREW

Recognize/report loss of Powerboard 16A ED12A, PB 16A Electrical Fault

Recognize/report trip of three Drywell cooling TRG3 fans Three Drywell cooling fans de-energize

Recognize/report trip of RBCLC pump 11 Drywel/ pressure and temperature rise Spent Fuel Pool Cooling pump 11 trips

Recognize/report Spent Fuel Pool trouble alarm RBCLC pump 11 trips Expected Annunciators:

L4-3-6, DRYWELL COOLING FAN TRIP-VIB A4-3-1, POWER BO. 16 R1041 TRIP A4-4-2, POWER BO. 16 LOW BUS VOLTAGE L 1-4-5, FUEL POOL ANNUNCIATOR SRO

Directs execution of ARPs

Directs start of Drywell cooling fan 11

May direct lowering RBCLC temperature

May direct Reactor power reduction per N1-SOP-1.1

If Drywell average temperature exceeds 150°F, enters N1-EOP-4

Directs placing Containment Spray pumps in PTL

Directs entry into N1-SOP-6.1, Loss of SFP/Rx Cavity Level/Decay Heat Removal

May direct start of RBCLC pump 12 Page 16 of 25 NRC Scenario 5

Exelon Generation Event 3 continued ATC

Monitors plant parameters

If directed, lowers Reactor power per N1-SOP-1.1 BOP

Executes ARPs

Dispatches operator/maintenance to investigate Powerboard 16A Role Play:

Dispatches operator to investigate Spent Fuel If requested to investigate Powerboard 16A, wait 2 Pool alarm minutes, then report the feeder breaker is tripped and

Acknowledges/reports Powerboard 16A is faulted there is an acrid odor in the area. Electrical

Starts Drywell cooling fan 11 Maintenance does NOT recommend re-energizing

May green flags Drywell cooling fans 14, 15, and Powerboard 16A. 16

May start RBCLC pump 12

May green flag RBCLC pump 11 Role Play:

If directed, lowers RBCLC temperature per N1-If requested to investigate SFPC trouble, wait 2 OP-11: minutes, then report SFPC pump 11 tripped.

If 0 Places RBCLC TCV in manual: directed to restore SFPC, acknowledge order, but 0 Depresses the AIM Button UNTIL red delay any action for rest of scenario.

LED is illuminated next to "M" 0 Verifies70-238.V is displayed in the LED readout 0 IF 70-238.V is NOT displayed, THEN depresses the "D" button UNTIL the display shows70-238.V 0 Adjusts RBCLC temperature as desired 0 May lower RBCLC TCV automatic setpoint per N1-0P-11 Section H.24.0 Page 17 of 25 NRC Scenario 5

Generation Event 3 continued NRC Scenario 5 BOP continued o May place RBCLC TCV back in automatic:

o Depresses the AIM Button UNTIL green LED is illuminated next to "A" o Verifies70-238. P is displayed in the LED readout o IF 70-238.P is NOT displayed, THEN depresses the "D" button UNTIL the display shows70-238. P o Verifies TCV-70-137 is responding properly to automatic control

If directed, places Containment Spray pumps in PTL Page 18 of 25 Exelon Generation Events #4 and #5 : All RBCLC Pumps Trip, Feedwater Pumps Fail to Operate

A trip of the running RBCLC pumps occurs with no standby pump available.

The crew will execute the override actions of N 1-SOP-11.1.

A loss of all HP feed water occurs on the scram. When directed by lead examiner, insert malfunction:

CW04A, RBCLC Pump 11 Trip CW048, RBCLC Pump 12 Trip CW04C, RBCLC Pump 13 Trip RBCLC pumps trip RBCLC pressure lowers RBCLC temperature Expected Annunciators:

TRG4 H1-1-1, REACTOR BLDG COOL PUMP 11 TRIP-V-SUCT H1-2-1, REACTOR BLDG COOL PUMP 12 TRIP-V-SUCT H1-3-1, REACTOR BLDG COOL PUMP 13 TRIP-V-SUCT H1-4-1, R BUILDING COOLING WATER PRESS TEMP MAKEUP FLOW K2-4-3, DRYWELL PRESSURE HIGH-LOW K3-4-4, CLEAN-UP SYSTEM /SOLA TION CREW

Recognize/report trip of all RBCLC pumps

Later: o Recognize/report Feedwater pump 11 and 12 trips o Recognize/report Feedwater pump 13 disengages o Recognize/report low Reactor water level Page 19 of 25 NRC Scenario 5

=:rExelon Generation Events 4 and 5 continued Verify the following malfunctions are automatically inserted when the Reactor scrams: FW03A, FEEDWATER PUMP TRIP 11 FW038, FEEDWATER PUMP TRIP 12 FW06, FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS -DISENGAGES TRG5 Feedwater pumps 11 and 12 trip immediately after starting, Feedwater pump 13 disengages Reactor water level remains lower than normal Expected Annunciators:

H3-1-7, REACTOR FWPUMP 11 TRIP OVERLOAD SUCTION HI-LEVEL H3-2-7, REACTOR FW PUMP 12 TRIP OVERLOAD SUCTION HI-LEVEL H3-4-8, REACTOR FW SHAFT P13 CLUTCH TROUBLE F2-3-3, REACT VESSEL LEVEL HIGH-LOW Note: Expected initial RPV water level control band SRO

Acknowledges reports

Directs entry into N1-SOP-11.1

Direct start of standby RBCLC pump

Acknowledges trip of all RBCLC pumps

Directs execution of override, including:

o Manual Reactor scram o Trip Recirculation pumps o Initiate Emergency Condensers o Close MSIVs o Trip RWCU pump

Acknowledges scram report

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 N 1-SOP-1, Reactor Scram

Acknowledges trip of Feedwater pumps

Directs RPV water level controlled between -84" is narrower (ex. O" to 95"). and 95" using CRD and/or Liquid Poison NRC Scenario 5

Directs RPV cooldown

<100°F/hr using Emergency Condensers

Enters N1-EOP-4, Primary Containment

Control, on high Drywell temperature o Directs lockout of Containment Spray pumps Page 20 of 25 Exelon Generation Events 4 and 5 continued ATC

Places Reactor Mode Switch to SHUTDOWN

Provides scram report

Performs scram verification actions of N 1-SOP-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places I RMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary

Verifies main turbine and generator tripped

Controls RPV pressure as directed using Emergency Condensers BOP

Executes N 1-SO P-11 . 1

Attempts to start standby RBCLC pump Note: Depending on timing, Lo-Lo Reactor water

Informs crew of need to execute override level may trip Recirculation pumps, initiate

Enters N1-SOP-1 Emergency Condensers, and close MSIVs before

Informs crew of Feedwater pump trips and low operator action. Reactor water level

Trips Recirculation pumps Note: RWCU will likely trip on high temperature

Initiates Emergency Condensers before operator action.

Closes MSIVs

Verifies RWCU pump tripped

May maximize CRD flow by starting second CRD pump and/or taking FCV to manual and opening Note: Recommend initiating next event shortly after further the reactor is scrammed.

May start Liquid Poison

Places Containment Spray pumps in PTL Page 21 of 25 NRC Scenario 5

Exelon Generation Events #6 and #7: Coolant Leak Inside Primary Containment and Fuel Zone Level Instrument Erratic Indication

A reactor coolant leak develops in the drywell

When containment parameters degrade sufficiently, fuel zone level instrumention will begin to give erratic indication and drive the crew into RPV Flooding.

When directed by examiner, insert malfunctions:

CU01, CU Coolant Leak Inside of Drywell, RT=5:00, FV=70 EC01, Steam Supply Line Break in PC, RT=5:00, FV=5 CREW

Recognize/report degrading Containment parameters TRG6 Containment parameters degrade RPV water level lowers Expected annunciators:

H2-4-7, DRYWELL WATER LEAK DETECTION SYS K2-4-3, DRYWELL PRESSURE HIGH-LOW L 1-4-4, DRYWELL -TORUS TEMP HIGH F1-1-5, RPS CH 11 DRYWELL PRESS HIGH F4-1-4, RPS CH 12 DRYWELL PRESS HIGH F1-2-3, RPS CH 11 REACTOR LEVEL LOW-LOW F4-2-6, RPS CH 12 REACTOR LEVEL LOW-LOW F1-3-3, RPS CH 11 REACTOR LEVEL LOW-LOW-LOW F4-3-6, RPS CH 12 REACTOR LEVEL LOW-LOW-LOW NRC Scenario 5 Page 22 of 25

Generation Events 6 and 7 continued Note: Due to an already low RPV water level when Drywell pressure reaches 3.5 psig, Containment Spray may auto-start before the crew can prevent it. In accordance with the EOPs, the crew will then verify proper operation per N1-EOP-1attachment17.

In this case, Critical Task 2 shall be evaluated as "Not Applicable".

Verify the following malfunction is automatically inserted when DW temp is above 200°F, LLL level indicates below -20", and Containment Spray has been initiated:

VICP20168_FE CP-201-68, Fuel Zone Erratic Failure VICP20169_FE CP-201-69, Fuel Zone Erratic Failure TRG7 Fuel Zone indications give sporadic numbers All other RPV water level instruments are either downscale or below minimum usable levels SRO * * * * * *

Acknowledges reports from the crew Re-enters N1-EOP-4 on high Drywell pressure Re-enters N1-EOP-2 on high Drywell pressure Transitions to Alternate Level Control leg of N1-EOP-2 Direct ADS bypassed Verifies EC initiation If either Drywell temperature approaches 300°F or Torus pressure exceeds 13 psig: o Answers "Below the Containment Spray Initiation Limit?" Yes o Verifies all Recirc pumps tripped o Directs trip of all Drywell cooling fans o Direct Containment Sprays per N1-EOP-1 attachment 17 CT-2

Monitors location on Pressure Suppression Pressure curve

Acknowledges sporadic readings of Fuel Zones

Acknowledges RPV water level is unknown

Exits N1-EOP-2, enters N1-EOP-7, RPV Flooding CT-3 Page 23 of 25 NRC Scenario 5

Exelon Generation SRO continued Events 6 and 7 continued

Answers "Are all control rods inserted to at least position 04?" Yes

Answers "Torus water level?" Above 8.0 ft

Directs open 4 ERVs

Directs injection to flood the RPV to the main steam lines using low pressure Feedwater, CRD, Core Spray or Alternate Injection Systems

Answers "Can any ERV be opened?"

Yes

Directs MSIVs and EC steam IVs verified closed

Acknowledges RPV water level rising ATC/BOP

Places Containment Spray pumps in PTL, or verifies proper operation per N1-EOP-1 attachment 17

Bypasses ADS

Verifies EC initiation

Monitors Containment parameters

Reports if either Drywell temperature approaches 300°F or Torus pressure exceeds 13 psig Page 24 of 25 NRC Scenario 5

=:--Exelon Generation ATC/BOP Continued Events 6 and 7 continued

If Containment Spray did not auto-start earlier:

NRC Scenario 5

RPV Flooding in progress

Verifies all Recirc pumps tripped

Trips all Drywell cooling fans

Initiates Containment Sprays per N1 -EOP-1 attachment 17:

Verifies

started, two Containment Spray pumps CT-2

IF required to lower Containment

pressure, start additional Containment Spray Pumps

Reports Containment pressure and temperature lowering

Recognizes/reports sporadic Fuel Zone values

Recognizes/reports RPV water level is unknown

Opens 4 ERVs

Injects to flood the RPV to the main steam lines using low pressure Feedwater, CRD, Core Spray or Alternate Injection Systems CT-3

Verifies MSIVs and EC steam IVs closed

Monitors for indications of successful flooding

Reports RPV water level rising

Reactor water level on scale or upscale

Containment pressure and temperature controlled in accordance with N1-EOP-4.

Page 25 of 25

=::"Exelon Generation NRC Scenario 3 BOP continued

If any ERV is cycling:

Initiates Emergency Condensers

IF initiating EC Loop 11, places 39-05, EMERG CNDSR COND RET ISOLATION VALVE 11 control switch in OPEN

IF initiating EC Loop 12, places 39-06, EMERG CNDSR COND RET ISOLATION VALVE 12 control switch in OPEN

Subsequently controls EC valves per EOP-HC att 9

Manually opens ERVs to lower RPV pressure to 965 psig

Controls RPV pressure below 1080 psig with TBVs, ECs and/or ERVs

Verifies all Recirc Pumps tripped

Initiates Liquid Poison as directed

Reports initial tank level

Starts Liquid Poison pump 11 or 12

Verifies RWCU isolated

RPV water level controlled in assigned band

Reactor power < 6%

Control rod insertion in progress or complete Page 28 of 28 March 2015

ML15110A397: Difference between revisions

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