Text

Ja Fitzpatrick - Final Operating Test (Sections a, B, and C) (Folder 3)
	ML20087G852
Person / Time
Site:	FitzPatrick
Issue date:	03/27/2020
From:	Todd Fish; Operations Branch I
To:	Fitzpatrick J; Entergy Nuclear Operations
	Fish T
Shared Package
ML19105A122	List: ML20043C809; ML20087G852; ML20087H514; ML20260H150; ML20260H151; ML20260H152; ML20260H153; ML20260H154; ML21056A284; ML21056A285; ML21056A306; ML21056A307;
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James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC S/RO TASK TITLE: Core Thermal Heat Balance Verification Using COO1 Turbine Steam Pressure APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.1.19 (3.9/3.8)

ESTIMATED COMPLETION TIME: 12/20 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Perform Completion Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

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James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC S/RO TASK TITLE: Core Thermal Heat Balance Verification Using COO1 Turbine Steam Pressure APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-65, Startup and Shutdown Procedure B. RAP-7.3.03, Core Thermal Power Evaluation III. TOOLS AND EQUIPMENT A. Calculator B. Steam Tables IV. SET UP REQUIREMENTS A. Provide a copy of RAP-7.3.03 ready to perform section 9.3 and Attachment 2.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. A plant startup has just been completed.

B. Verification of Core Thermal Power is required.

C. The required plant data is given in the provided handouts.

-2 of 12-

S/RO 18-1 NRC S/RO COO1 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure VII. INITIATING CUE Inform the candidate, Verify Core Thermal Power per RAP-7.3.03 Attachment 2.

EVALUATION /

STEP STANDARD COMMENT

1. Obtain and review procedure. Candidate obtains and reviews RAP-7.3.03. Candidate SAT / UNSAT determines that the start point is Attachment 2.

EVALUATOR:

Hand candidate a copy of RAP-7.3.03 ready to perform Section 9.3 and Attachment 2. Provide the EPIC screenshot and 3D Monicore case.

2. Obtain and record Turbine first Obtains a value of ~688.1 psig for EPIC point 1299 and CRITICAL STEP stage pressure from EPIC 1299. records on Attachment 2. SAT / UNSAT

3. Calculate and record Reactor Calculates ~103% power and records on Attachment 2. CRITICAL STEP power calculated from Turbine SAT / UNSAT first stage pressure.

4. Obtain and record Reactor power Obtains a value of ~97.1% for Reactor power and records CRITICAL STEP calculated from heat balance. on Attachment 2. SAT / UNSAT

5. Determine if the two methods are Determines the two methods differ by more than 5%. CRITICAL STEP within 5% of rated power of each SAT / UNSAT

-3 of 12-

S/RO 18-1 NRC S/RO COO1 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure EVALUATION /

STEP STANDARD COMMENT other.

6. Determine need to initiate Indicates that an investigation must be initiated. CRITICAL STEP investigation. SAT / UNSAT NOTE: This step may be satisfied by direct report, notification to Shift Manager, notification to Reactor Engineering, initiating a Incident Report, or similar.

7. Determine need to notify General Indicates that the General Manager Plant Operations must SAT / UNSAT Manager Plant Operations. be notified if the difference cannot be explained.

NOTE: This step may be satisfied by direct report, notification to Shift Manager, notification to Reactor Engineering, initiating a Condition Report, or similar.

EVALUATOR: Terminate the task at this point for RO candidates. For SRO candidates, provide the additional SRO Only Conditions and Cue, along with the SRO Only Worksheet.

Additional SRO Only Conditions:

Investigation has revealed the following:

The 3D Monicore Core Thermal Power calculation is erroneous.

Turbine first stage bowl pressure accurately reflects plant power level.

Operation at the current power level has been ongoing for three hours.

-4 of 12-

S/RO 18-1 NRC S/RO COO1 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure EVALUATION /

STEP STANDARD COMMENT Additional SRO Only Cue:

Complete the provided SRO Only Worksheet regarding requirements associated with the Licensed Power Level.

8. SRO ONLY SRO ONLY CRITICAL STEP Determine the procedure that Determines RAP-7.3.16 contains the specific guidance on SAT / UNSAT contains the specific guidance on both 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thermal power averages.

both 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thermal power averages.

9. SRO ONLY SRO ONLY CRITICAL STEP Determine requirements for 2 Determines requirement for 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thermal power average SAT / UNSAT hour thermal power average is:

If the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months average exceeds RTP, take timely action to ensure that thermal power is less than or equal to RTP (or similar).

10. SRO ONLY SRO ONLY CRITICAL STEP Determine requirement for Determines requirement for average Reactor power level SAT / UNSAT average Reactor power level for for each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift is:

each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift

The average reactor power level for each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift shall not exceed Rated Thermal Power (or similar).

-5 of 12-

S/RO 18-1 NRC S/RO COO1 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure EVALUATION /

STEP STANDARD COMMENT EVALUATOR: Terminate the task at this point for SRO candidates.

Task Standard: Core thermal heat balance determined to be out of tolerance in relation to Turbine steam pressure. For SRO candidates, procedural requirements of RAP-7.3.16, Plant Power Changes, for control of core thermal power determined.

-6 of 12-

SRO Only Key

1. Identify the plant procedure that contains the specific guidance on both of the questions below.

RAP-7.3.16

2. Describe the specific requirement(s) regarding 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thermal power average, in accordance with plant procedure.

If the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months average exceeds RTP, take timely action to ensure that thermal power is less than or equal to RTP (or similar).

3. Describe the specific requirement(s) regarding the average Reactor power level for each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift, in accordance with plant procedure.

The average reactor power level for each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift shall not exceed Rated Thermal Power (or similar).

SRO Only Key

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HANDOUT

A plant startup has just been completed.

Verification of Core Thermal Power is required.

The required plant data is given in the provided handouts.

Verify Core Thermal Power per RAP-7.3.03 Attachment 2.

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HANDOUT

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HANDOUT

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ADDITIONAL SRO ONLY HANDOUT Investigation has revealed the following:

The 3D Monicore Core Thermal Power calculation is erroneous.

Turbine first stage bowl pressure accurately reflects plant power level.

Operation at the current power level has been ongoing for three hours.

Complete the provided SRO Only Worksheet regarding requirements associated with the Licensed Power Level.

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SRO Only Worksheet

1. Identify the plant procedure that contains the specific guidance on both of the questions below.

2. Describe the specific requirement(s) regarding 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thermal power average, in accordance with plant procedure.

3. Describe the specific requirement(s) regarding the average Reactor power level for each 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift, in accordance with plant procedure.

-12 of 12-

James A. Fitzpatrick JOB PERFORMANCE MEASURE RO 18-1 NRC RO TASK TITLE: Perform RCIC Lineup Verification Per ST-24A COO2 APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.1.31 (4.6)

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Performed Completion Location: Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

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James A. Fitzpatrick JOB PERFORMANCE MEASURE RO 18-1 NRC RO TASK TITLE: Perform RCIC Lineup Verification Per ST-24A COO2 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-24A, RCIC Monthly Operability Test III. TOOLS AND EQUIPMENT

None IV. SET UP REQUIREMENTS A. Provide a copy of ST-24A completed up to step 8.2.

B. Reset the simulator to an IC (IC-227) with RCIC in a normal standby lineup, except for the following:

a. Set RCIC FLOW CNTRL setpoint dialed to approximately 315 gpm.

b. Close PMP DISCH VLV 13MOV-20.

c. Close STM LINE DRN TO RADW 13AOV-35.

V. EVALUATOR NOTES A. If the candidate informs you that the ST cannot be continued due to issues, inform the candidate the deviation has been noted and for them to continue with the rest of the ST.

VI. TASK CONDITIONS A. ST-24A, RCIC Monthly Operability Test, is in progress.

B. Other operators have completed ST-24A thru Section 8.1.

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18-1 NRC RO COO2 TASK TITLE: Perform RCIC Lineup Verification Per ST-24A VII. INITIATING CUE Inform the candidate, Complete ST-24A Section 8.2, RCIC Valve Lineup.

EVALUATION /

STEP STANDARD COMMENT

1. Record RCIC FLOW CNTRL output Records RCIC FLOW CNTRL SAT/UNSAT at panel 09-4. output as greater than or equal to 100%.

2. Verify the following lineup at Verifies the following lineup at CRITICAL STEP panel 09-4: panel 09-4 and documents in ST- (bolded items only) 24A:

RCIC FLOW CNTRL setpoint - SAT/UNSAT 410 gpm

RCIC FLOW CNTRL setpoint -

approximately 315 gpm

RCIC FLOW CNTRL - AUTO

RCIC FLOW CNTRL - AUTO

TURB GOV VLV 13HOV Open

TURB GOV VLV 13HOV Open

TURB TRIP & THROTTLE VLV 13HOV Open

TURB TRIP & THROTTLE VLV 13HOV Open

TURB TEST 13A-S20 - NORMAL

TURB TEST 13A-S20 - NORMAL

TEST PWR - OFF

TEST PWR - OFF

TEST SPEED ADJUST - Full counter clockwise

TEST SPEED ADJUST - Full counter clockwise

TURB STM SUPP VLV 13MOV-131 - Closed

TURB STM SUPP VLV 13MOV-131 - Closed

OUTBD STM SUPP VLV 13MOV Open

OUTBD STM SUPP VLV 13MOV Open

INBD STM SUPP VLV 13MOV-15 - Open

INBD STM SUPP VLV 13MOV-15 - Open EVALUATOR NOTE: The bolded item above is out-of-spec. Should Candidate inform that ST cannot be continued due to the out of spec value, inform Candidate the deviation has been noted, continue with the ST and the deviation will be corrected by another Operator.

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18-1 NRC RO COO2 TASK TITLE: Perform RCIC Lineup Verification Per ST-24A EVALUATION /

STEP STANDARD COMMENT CRITICAL STEP (bolded items only)

CST SUCT VLV 13MOV

CST SUCT VLV 13MOV Open Open SAT/UNSAT

MIN FLOW VLV 13MOV

MIN FLOW VLV 13MOV Closed Closed

PMP DISCH VLV 13MOV

PMP DISCH VLV 13MOV Open Closed

STM LINE DRN TRAP BYP VLV

STM LINE DRN TRAP BYP VLV 13AOV AUTO 13AOV AUTO

INJ VLV 13MOV Closed

INJ VLV 13MOV Closed

INBD TORUS SUCT VLV

INBD TORUS SUCT VLV 13MOV Closed 13MOV Closed

TEST VLV TO CST 13MOV

TEST VLV TO CST 13MOV Closed Closed

OUTBD TORUS SUCT 13MOV-

OUTBD TORUS SUCT 13MOV-39 - Closed 39 - Closed

OIL CLR WTR SUPP 13MOV-132

OIL CLR WTR SUPP 13MOV-132

- Closed - Closed

COND PMP DISCH TO RADW

COND PMP DISCH TO RADW 13AOV AUTO 13AOV AUTO

STM LINE DRN TO RADW

STM LINE DRN TO RADW 13AOV Open 13AOV Open EVALUATOR NOTE: The bolded item above is out-of-spec. Should Candidate inform that ST cannot be continued due to the out of spec value, inform Candidate the deviation has been noted, continue with the ST and the deviation will be corrected by another Operator.

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18-1 NRC RO COO2 TASK TITLE: Perform RCIC Lineup Verification Per ST-24A EVALUATION /

STEP STANDARD COMMENT

3. Verify the following lineup at Verifies the following lineup at CRITICAL STEP panel 09-3: panel 09-3 and documents in ST- (bolded items only) 24A (cont.): SAT/UNSAT

COND PMP DISCH TO RADW 13AOV Open

COND PMP DISCH TO RADW 13AOV Open

STM LINE DRN TO RADW 13AOV Open

STM LINE DRN TO RADW 13AOV Closed

RCIC EXH VAC BKR 13MOV130

- Open

RCIC EXH VAC BKR 13MOV130

- Open EVALUATOR NOTE: The bolded item above is out-of-spec. Should Candidate inform CRS that ST cannot be continued due to the out of spec value, inform Candidate the deviation has been noted, continue with the ST and the deviation will be corrected by another Operator.

EVALUATOR: Terminate the task at this point.

Task Standard: ST-24A performed with deficiencies in controller setpoint and two valve lineups identified.

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HANDOUT

ST-24A, RCIC Monthly Operability Test, is in progress.

Other operators have completed ST-24A thru Section 8.1.

Complete ST-24A Section 8.2, RCIC Valve Lineup.

-6 of 6-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.2.41 (3.5/3.9)

ESTIMATED COMPLETION TIME: 15/25 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Perform Completion Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

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James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. Electrical Print 1.60-17 (GE 865E365 Sheet 3)

B. Electrical Print 1.67-97 (GE 791E456 Sheet 7)

C. Electrical Print 1.67-99 (GE 791E456 Sheet 9)

D. Electrical Print 1.67-101 (GE 791E456 Sheet 11)

E. Technical Specification 3.3.1.1 F. OP-27A III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. None

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SRO/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings VII. INITIATING CUE Inform the candidate of the following:

Using the provided station electrical prints, explain how an upscale failure of Reactor pressure instrument 02-3PT-55A results in an RPS half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

For SRO candidates, also provide the following:

Additionally, explain the Technical Specification impact if Reactor pressure instrument 02-3PT-55A fails downscale with the plant operating at 100% power.

STEP STANDARD EVALUATION / COMMENT EVALUATOR: Provide working copy of referenced prints.

1. Identifies 02-3PT-55A corresponds to Identifies 02-3PT-55A and relay 5A-K101A on CRITICAL STEP relay 5A-K101A on electrical print electrical print 1.60-17 (near locations A-2, B-2, and SAT / UNSAT 1.60-17. C-2).

EVALUATOR NOTE: This, and all other items in this JPM, may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

2. Identifies contact 5A-K101A on Identifies contact 5A-K101A on electrical print 1.67- CRITICAL STEP electrical print 1.67-97. 97 (near location C-4). SAT / UNSAT

-3 of 9-

SRO/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION / COMMENT

3. Identifies relay 5A-K5A on electrical Identifies relay 5A-K5A on electrical print 1.67-97 CRITICAL STEP print 1.67-97. (near location E-4). SAT / UNSAT

4. Identifies contacts 5A-K5A on Identifies contacts 5A-K5A on electrical print 1.67-99 CRITICAL STEP electrical print 1.67-99. (near location H-2/3). SAT / UNSAT

5. Identifies relays 5A-K14A and 5A- Identifies relays 5A-K14A and 5A-K14E on electrical CRITICAL STEP K14E on electrical print 1.67-99. print 1.67-99 (near location L-2/3). SAT / UNSAT

6. Identifies contacts 5A-K14A and 5A- Identifies contacts 5A-K14A and 5A-K14E on CRITICAL STEP K14E on electrical print 1.67-101. electrical print 1.67-101 (near locations A-3, A-6, A-9, SAT / UNSAT and A-11).

EVALUATOR NOTES:

The candidate does not have to identify all four contacts on this sheet, as long as a representative sample is identified and some indication is given that there are multiple contacts.

-4 of 9-

SRO/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION / COMMENT

7. Identifies relays 3-13-117 (or 03SOV- Identifies solenoids/relays 3-13-117 (or 03SOV-117) CRITICAL STEP 117) on electrical print 1.67-101. on electrical print 1.67-101 (near locations C-2/3, C-4, SAT / UNSAT C-5, C-6, C-8, C-9, C-11, and C-12).

EVALUATOR NOTES:

The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.

-5 of 9-

SRO/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION / COMMENT

8. Describes how upscale failure of Describes the following: SAT / UNSAT Reactor pressure instrument 02-3PT-

Relay 5A-K101A de-energizes.

55A results in an RPS half scram

Relay 5A-K5A de-energizes.

Relay 5A-K14A and 5A-K14E de-energize

Solenoids/relays 3-13-117 de-energize at each HCU.

EVALUATOR NOTE: This is a summary of previous critical steps. The candidate does not have to match this description word-for-word, but must include all concepts in their description.

-6 of 9-

SRO/RO 18-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION / COMMENT

9. SRO Only SRO Only SRO Only Determines and reports the Technical Reports that Technical Specification Table 3.3.1.1-1 Specification impact of Reactor Function 3 is not met. CRITICAL STEP pressure instrument 02-3PT-55A SAT / UNSAT failing downscale while at 100%

power Reports that Technical Specification 3.3.1.1 Condition A must be entered and requires either placing a channel in trip or placing the trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

EVALUATOR NOTE: The candidate may also reference Technical Specification Table 3.6.1.1-1 Function 6a and Technical Specification 3.3.6.1 Conditions A & F, but this is not critical since at 100% power the required actions are already completed (SDC penetration is isolated).

EVALUATOR: Terminate the task at this point.

Task Standard: Operation of half scram from 02-3PT-55A explained using electrical prints, including identification of related electrical components. For SRO candidates, Technical Specification 3.3.1.1 impact of inoperable Reactor pressure instrument determined.

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RO HANDOUT Using the provided station electrical prints, explain how an upscale failure of Reactor pressure instrument 02-3PT-55A results in an RPS half scram.

You may mark the provided prints and/or write the explanation on this sheet.

Identify the electrical components that accomplish this action.

-8 of 9-

SRO HANDOUT Using the provided station electrical prints, explain how an upscale failure of Reactor pressure instrument 02-3PT-55A results in an RPS half scram.

You may mark the provided prints and/or write the explanation on this sheet.

Identify the electrical components that accomplish this action.

Additionally, explain the Technical Specification impact if Reactor pressure instrument 02-3PT-55A fails downscale with the plant operating at 100% power.

-9 of 9-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC TASK TITLE: Determine Worker Exposure for Emergent S/RO RC Work APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.3.4 (3.2/3.7)

ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Perform Completion Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

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James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC TASK TITLE: Determine Worker Exposure for Emergent S/RO RC Work APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. RP-AA-203, Exposure Control and Authorization III. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure adequate copies of the procedures referenced above are available.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Two operators are required to enter a locked high radiation area to support an emergent job.

C. The job is expected to take 45 minutes.

D. The job site dose rate is 1500 mRem/hr.

E. Operator #1 has received 1147 mRem of dose so far this year.

F. Operator #2 has received 450 mRem of dose so far this year.

G. Neither operator has received any dose extensions so far this year.

H. Neither operator has any undocumented quarters for this year.

I. No other Operators are available to perform this job.

J. No means of reducing area dose rates are available.

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SRO/RO 18-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work VII. INITIATING CUE Inform the candidate, Determine the expected dose that each operator will receive while performing this job. Determine if each operator will need a dose extension in order to receive this dose. Report your results on the provided worksheet.

EXAMINER: Provide the candidate with the first handout and worksheet.

STEP STANDARD EVALUATION

/ COMMENT

1. Obtain required references. Obtains and utilizes required SAT / UNSAT references, which may include:

RP-AA-203 EXAMINER NOTE: See provided key for remaining steps.

2. Determine the expected dose that Calculates that each operator will CRITICAL each operator will receive while receive 1125 mRem while STEP performing this job performing this job. SAT / UNSAT (45 minutes/60 minutes per hour) x (1500 mRem/hour) = 1125 mRem

3. Determine if Operator #1 will need a Determines that Operator #1 will CRITICAL dose extension in order to receive need dose extension in order to STEP this dose. receive this dose. SAT / UNSAT 1147 mRem + 1125 mRem = 2272 mRem > 2000 mRem normal dose limit

4. Determine if Operator #2 will need a Determines that Operator #2 will CRITICAL dose extension in order to receive NOT need dose extension in order to STEP this dose. receive this dose. SAT / UNSAT 450 mRem + 1125 mRem = 1575 mRem < 2000 mRem normal dose limit

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SRO/RO 18-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work EXAMINER: If the candidate correctly complete JPM steps 2-4, provide them with the extra handout, with the following information:

Operator #1 has been granted a dose extension to 2500 mRem. Operator #2 has NOT been granted a dose extension.

Determine the maximum time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their full administrative dose limits. Document your results in the worksheet below.

5. Determine the maximum time Calculates the maximum time for CRITICAL allowed for Operator #1 such that full Operator #1 is approximately 54 STEP administrative dose limit is NOT minutes. SAT / UNSAT exceeded.

(2500 mRem - 1147 mRem) / 1500 mRem/hr = 0.902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months x (60 minutes per hour) = 54.12 minutes

6. Determine the maximum time Calculates the maximum time for CRITICAL allowed for Operator #2 such that full Operator #2 is approximately 62 STEP administrative dose limit is NOT minutes. SAT / UNSAT exceeded.

(2000 mRem - 450 mRem) / 1500 mRem/hr = 1.033 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months (60 minutes per hour) = 62 minutes EVALUATOR: Terminate the task at this point for RO candidates.

EXAMINER: For SRO candidates, continue JPM by providing SRO Only cue sheet:

INITIATING CUE for SRO Candidates Only:

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SRO/RO 18-1 NRC S/RO RC TASK TITLE: Determine Worker Exposure for Emergent Work Inform the candidate, Determine the required actions necessary for Operator #1 to be allowed to receive a dose of 2500 mRem. Report your results below.

STEP STANDARD EVALUATION

/ COMMENT

7. [RP-AA-203 Step 4.2.1] Candidate indicates that Attachment CRITICAL 1 of RP-AA-203 (or computerized STEP USE Attachment 1, Dose Control Level Extension Form, or a equivalent) must be filled out. SAT / UNSAT computerized equivalent, to authorize exposures for adult Note: The candidate may list individuals in excess of 2000 mrem individual items from RP-AA-203 and routine TEDE in a year. Attachment 1, but the only critical requirement is to identify the procedure and attachment.

EVALUATOR: Terminate the task at this point for SRO candidates.

Task Standard: Expected dose, maximum allowable time, and dose extension determined based on given radiological conditions. For SRO candidates, procedural requirement for dose extension identified.

-5 of 14-

EVALUATORS KEY

1. Expected dose that each operator will receive while performing this job:

1125 mRem

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

-6 of 14-

EVALUATORS KEY EVALUATORS KEY

1. Maximum time allowed for Operator #1 (record final answer in minutes):

54 minutes

2. Maximum time allowed for Operator #2 (record final answer in minutes):

62 minutes

-7 of 14-

EVALUATORS KEY

-8 of 14-

HANDOUT Initial Conditions:

The plant is operating at 100% power.

Two operators are required to enter a locked high radiation area to support an emergent job.

The job is expected to take 45 minutes.

The job site dose rate is 1500 mRem/hr.

Operator #1 has received 1147 mRem of dose so far this year.

Operator #2 has received 450 mRem of dose so far this year.

Neither operator has received any dose extensions so far this year.

Neither operator has any undocumented quarters for this year.

No other Operators are available to perform this job.

No means of reducing area dose rates are available.

Initiating Cue:

Determine the expected dose that each operator will receive while performing this job.

Determine if each operator will need a dose extension in order to receive this dose.

Report your results on the provided worksheet.

-9 of 14-

WORKSHEET

1. Expected dose that each operator will receive while performing this job:

2. Will Operator #1 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

3. Will Operator #2 need a dose extension in order to receive the dose calculated above? (circle one)

Yes No

-10 of 14-

-11 of 14-EXTRA HANDOUT Operator #1 has been granted a dose extension to 2500 mRem.

Operator #2 has NOT been granted a dose extension.

Determine the maximum time allowed for both Operator #1 and for Operator #2, such that they do NOT exceed their full administrative dose limits. Document your results in the worksheet below.

EXTRA WORKSHEET

1. Maximum time allowed for Operator #1 (record final answer in minutes):

2. Maximum time allowed for Operator #2 (record final answer in minutes):

-12 of 14-

-13 of 14-SRO Candidates Only:

Determine the required actions necessary for Operator #1 to be allowed to receive a dose of 2500 mRem.

Report your results below.

-14 of 14-

James A. Fitzpatrick JOB PERFORMANCE MEASURE SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and APPL. TO JPM NUMBER Initiate Event Notification (Time Critical)

REV: DATE: NRC K/A SYSTEM NUMBER: 2.4.40 (4.5)

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Perform Completion Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

-1 of 8-

James A. Fitzpatrick JOB PERFORMANCE MEASURE SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and APPL. TO JPM NUMBER Initiate Event Notification (Time Critical)

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-AA-1014 B. EAL Matrix C. EP-CE-114-100-F-05 D. EP-AA-114-F-08 E. EP-CE-111-F-05 III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available, including extra copies of the Part 1 notification form.

V. EVALUATOR NOTES A. None

-2 of 8-

James A. Fitzpatrick JOB PERFORMANCE MEASURE SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and APPL. TO JPM NUMBER Initiate Event Notification (Time Critical)

VI. TASK CONDITIONS A. The plant is initially operating at 100% power.

B. Severe thunderstorm activity has been occurring in the area.

C. A spurious Main Generator lockout occurs.

D. Lines 3 and 4 de-energize immediately after the Main Generator lockout.

E. EDGs A and C fail to start.

F. EDGs B and D start and re-energize the 10600 bus.

G. Then, the 10600 bus de-energizes due to a significant electrical fault.

H. Maintenance is estimating it will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to restore power to either the 10500 or 10600 bus.

I. Power Control is estimating it will take 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore either Line 3 or Line 4.

J. The following conditions exist now:

All control rods are full in.

Reactor pressure is 850 psig and slowly lowering on SRVs.

Reactor water level is 190 and stable on RCIC.

NO elevated radiation levels have been detected.

200 elevation wind speed is 10 mph from 190o.

30 elevation wind speed is 5 mph from 190o.

Stability class is E.

Nine Mile Point Units 1 and 2 and both operating at 100% power.

-3 of 8-

SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

VII. INITIATING CUE Inform the candidate of the following:

Classify the event and complete the Part 1 Notification Fact Sheet. This is a time critical JPM. Your time clock starts once you acknowledge this task.

STEP STANDARD EVALUATION / COMMENT

1. Obtain applicable reference Obtains a copy of applicable reference documents, SAT / UNSAT documents as needed:

EP-AA-1014

EAL Matrix

EP-CE-114-100-F-05

EP-AA-114-F-08

EP-CE-111-F-05 EVALUATOR: Ensure sufficient copies of these documents are available.

2. Classify the event Classifies the event as General Emergency MG1 CRITICAL STEP within 15 minutes of JPM start time SAT / UNSAT JPM start time: __________

Time of classification: __________

Time difference: __________

-4 of 8-

SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

STEP STANDARD EVALUATION / COMMENT

3. Completes Part 1 Notification Fact Completes Part 1 Notification Fact Sheet per CRITICAL STEP Sheet. attached key within 15 minutes of classification time SAT / UNSAT Time of classification: __________

Time of offsite notification: __________

Time difference: __________

EVALUATOR NOTES:

Only item 3, 4, 5, 6, and 7 of the Part 1 Notification Fact Sheet are deemed critical for this JPM.

These items are individually graded in the JPM steps below.

All other items are non-critical.

See attached key.

4. Completes Part 1 Notification step 3 Indicates GENERAL EMERGENCY in Part 1 CRITICAL STEP Notification step 3 (see attached key) SAT / UNSAT

5. Completes Part 1 Notification step 4 Records todays date and time of declaration in Part CRITICAL STEP 1 Notification step 4 (see attached key) SAT / UNSAT

-5 of 8-

SRO 18-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification (Time Critical)

STEP STANDARD EVALUATION / COMMENT

6. Completes Part 1 Notification step 5 Indicates No Release in Part 1 Notification step 5 CRITICAL STEP (see attached key) SAT / UNSAT

7. Completes Part 1 Notification step 6 Indicates EVACUATE and IMPLEMENT the KI CRITICAL STEP plan for ERPAs 1, 2, 3, 26, and 27 in Part 1 SAT / UNSAT Notification step 6 (see attached key)

8. Completes Part 1 Notification step 7 Indicates EAL # MG1 in Part 1 Notification step 7 CRITICAL STEP (see attached key) SAT / UNSAT EVALUATOR: Terminate the task at this point.

Task Standard: The emergency event is classified and the Part 1 Notification form is filled out correctly.

-6 of 8-

EVALUATORS KEY EVALUATORS KEY

-7 of 8-

HANDOUT Initial Conditions:

The plant is initially operating at 100% power.

Severe thunderstorm activity has been occurring in the area.

A spurious Main Generator lockout occurs.

Lines 3 and 4 de-energize immediately after the Main Generator lockout.

EDGs A and C fail to start.

EDGs B and D start and re-energize the 10600 bus.

Then, the 10600 bus de-energizes due to a significant electrical fault.

Maintenance is estimating it will take 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to restore power to either the 10500 or 10600 bus.

Power Control is estimating it will take 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore either Line 3 or Line 4.

The following conditions exist now:

All control rods are full in.

Reactor pressure is 850 psig and slowly lowering on SRVs.

Reactor water level is 190 and stable on RCIC.

NO elevated radiation levels have been detected.

200 elevation wind speed is 10 mph from 190o.

30 elevation wind speed is 5 mph from 190o.

Stability class is E.

Nine Mile Point Units 1 and 2 and both operating at 100%

power.

Initiating Cue:

Classify the event and complete the Part 1 Notification Fact Sheet.

This is a time critical JPM.

Your time clock starts once you acknowledge this task.

-8 of 8-

James A. Fitzpatrick JOB PERFORMANCE MEASURE SRO 18-1 NRC SRO TASK TITLE: Determine Reportability Requirements -

COO2 Technical Specification Shutdown and Group I APPL. TO JPM NUMBER Isolation REV: DATE: NRC K/A SYSTEM NUMBER: 2.1.18 (3.8)

ESTIMATED COMPLETION TIME: 25 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE LOGIN ID:

NAME:

JPM Perform Completion Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

-1 of 6-

James A. Fitzpatrick JOB PERFORMANCE MEASURE SRO 18-1 NRC SRO TASK TITLE: Determine Reportability Requirements -

COO2 Technical Specification Shutdown and Group I APPL. TO JPM NUMBER Isolation I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. 10 CFR 50.72 B. NUREG 1022 C. LS-AA-1400 III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available.

V. EVALUATOR NOTES A. Note VI. TASK CONDITIONS A. The plant was initially operating at 100% power.

B. A shutdown was performed to meet Technical Specification requirements.

C. All control rods were fully inserted with RMCS.

D. The Reactor mode switch was then placed in SHUTDOWN per OP-65 and OP-18.

E. Then, a Main Steam leak developed.

F. A Group I isolation occurred due to high Main Steam tunnel temperature.

G. All systems responded per design.

H. Condensate Booster pumps were used to control Reactor water level.

I. SRVs were used to control Reactor pressure.

-2 of 6-

SRO/RO 18-1 NRC SRO COO2 TASK TITLE: Determine Reportability Requirements - Technical Specification Shutdown and Group I Isolation VII. INITIATING CUE Inform the candidate of the following:

List the applicable 10 CFR 50.72 reportability requirements and the associated time limitations for reporting under that category. Record your findings on the sheet provided.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a applicable reference Obtains a copy of applicable reference documents: SAT / UNSAT documents

10 CFR 50.72

NUREG 1022

LS-AA-1400 EVALUATOR: Ensure sufficient copies of these documents are available.

2. Locate and identify applicability of Identifies reportability per 10 CFR 50.72(b)(2)(i) CRITICAL STEP 10 CFR 50.72(b)(2)(i) SAT / UNSAT EVALUATOR NOTE: This may also be identified as due to the initiation of any nuclear plant shutdown required by the plant's Technical Specifications.

3. Determine notification time Determines 10 CFR 50.72(b)(2)(i) requires notification CRITICAL STEP requirement for 10 CFR 50.72(b)(2)(i) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SAT / UNSAT

-3 of 6-

SRO/RO 18-1 NRC SRO COO2 TASK TITLE: Determine Reportability Requirements - Technical Specification Shutdown and Group I Isolation STEP STANDARD EVALUATION / COMMENT

4. Locate and identify applicability of 10 Identifies reportability per 10 CFR 50.72(b)(3)(iv)(A) CRITICAL STEP CFR 50.72(b)(3)(iv)(A) SAT / UNSAT EVALUATOR NOTE: Candidate may alternately refer to 10CFR 50.72(b)(3)(iv)(B)(2) for this reportability requirement.

EVALUATOR NOTE: This may also be identified as due to the valid actuation of the Group I isolation.

5. Determine notification time Determines 10 CFR 50.72(b)(3)(iv)(A) requires CRITICAL STEP requirement for 10 CFR notification within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months SAT / UNSAT 50.72(b)(3)(iv)(A)

EVALUATOR NOTE: Candidate may alternately refer to 10CFR 50.72(b)(3)(iv)(B)(2) for this reportability requirement.

EVALUATOR: Terminate the task at this point.

Task Standard: NRC reportability requirements and associated time limits are determined.

-4 of 6-

HANDOUT

The plant was initially operating at 100% power.

A shutdown was performed to meet Technical Specification requirements.

All control rods were fully inserted with RMCS.

The Reactor mode switch was then placed in SHUTDOWN per OP-65 and OP-18.

Then, a Main Steam leak developed.

A Group I isolation occurred due to high Main Steam tunnel temperature.

All systems responded per design.

Condensate Booster pumps were used to control Reactor water level.

SRVs were used to control Reactor pressure.

List the applicable 10 CFR 50.72 reportability requirements and the associated time limitations for reporting under that category.

-5 of 6-

Attachment 2 JPM Scorecard for Candidate Use List the applicable 10 CFR 50.72 reportability requirements and the associated time limitations for reporting under that category.

-6 of 6-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC A TASK TITLE: Isolate Control Room and Relay Room Ventilation APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 290003 A4.01 (3.2/3.2)

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-55B, Control Room Ventilation and Cooling III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Initialize the simulator to IC-227.

B. Control Room Ventilation Train A in service.

C. Relay Room Ventilation Train B in service.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. An accident at Nine Mile Point has resulted in rising radiation levels in the Control Room ventilation air supply header.

-2 of 8-

VII. INITIATING CUE Inform the candidate, "Isolate Control Room and Relay Room ventilation per OP-55B section G.1.

NOTE: All actions performed at Panel 09-75 STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-55B. SAT / UNSAT OP-55B, Control Room Ventilation and Cooling.

2. (OP-55B step G.1.1) Place Control Places Control Room Ventilation ISOL & PURGE CRITICAL STEP Room Ventilation ISOL & PURGE CNTRL switch in ISOL.

SAT / UNSAT CNTRL switch in ISOL.

Evaluator Note: These controls are in the Control Room Vent area of the 09-75 panel.

3. (OP-55B step G.1.2) Verify closed Observes red light off, green light on for the SAT / UNSAT the following dampers and valves: following:

EXH 70MOD-109

EXH 70MOD-109

INLET 70MOD-105

INLET 70MOD-105

EXH ISOL 70MOV-107

EXH ISOL 70MOV-107

INLET ISOL 70MOV-108

INLET ISOL 70MOV-108

-3 of 8-

STEP STANDARD EVALUATION / COMMENT

4. (OP-55B step G.1.3) Verify open the Observes red light on, green light off for the SAT / UNSAT following dampers: following:

RECIRC A 70MOD-110A

RECIRC A 70MOD-110A

RECIRC B 70MOD-110B

RECIRC B 70MOD-110B

5. (OP-55B step G.1.4) Verify one of Observes red light on, green light off for FRESH AIR SAT / UNSAT the following control room SUPP SUPP 70FN-6A emergency air supply fans is running with its discharge damper open:

Observes red light on, green light off for DISCH Supply Fan 70MOD-112A FRESH AIR SUPP 70FN-6A FRESH AIR SUPP 70FN-6B Discharge Damper DISCH 70MOD-112A DISCH 70MOD-112B

6. (OP-55B step G.1.5) Close Direct field operator to close 70DMPR-105. CRITICAL STEP 70DMPR-105 (control room vent Evaluator Cue: 70DMPR-105 is closed. SAT / UNSAT supply isol 70MOD-105 manual bypass damper) (located near 70MOV-108).

-4 of 8-

STEP STANDARD EVALUATION / COMMENT

7. (OP-55B step G.1.6) Ensure closed Acknowledges cue. SAT / UNSAT all access doors to Control Room.

Evaluator Cue: All access doors to the Control Room are closed.

8. (OP-55B step G.1.7) IF differential Observes CNTRL RM DIFF PRESS 70DPI-063 SAT / UNSAT pressure is LESS THAN +0.125 indicates greater than +0.125 inches water gauge.

inches water gauge on CNTRL RM DIFF PRESS 70DPI-063, THEN ensure Office Area Ventilation is in normal operation or shutdown per OP-59B.

9. (OP-55B step G.1.8) WHILE control Acknowledges step. SAT / UNSAT room ventilation is operating in Evaluator Cue: Another operator will record isolate mode, perform the following:

Control Room dP in the narrative log.

a. Record control room dP in the narrative log once per shift.

Evaluator Note: A Note in the procedure allows

b. Notify system engineer if LESS JPM steps 9 and 10 to be performed after the THAN +0.2 inches water gauge.

subsequent JPM steps.

-5 of 8-

STEP STANDARD EVALUATION / COMMENT

10. (OP-55B step G.1.9) Hang copy (6 Acknowledges step. SAT / UNSAT total) of Attachment 5 on the Evaluator Cue: Another operator has hung the following sets of doors (one copy required signs.

facing outside on outer fire door, other facing inside on inner vestibule door):

76FDR-300-13 MAIN CONTROL ROOM FIRE DOOR and associated inner vestibule door 76FDR-300-10 MAIN CONTROL ROOM CORRIDOR FIRE DOOR and associated inner vestibule door 76FDR-300-26 CONTROL ROOM ACCESS DOOR FROM NEW ADMIN/SUPPORT FACILITY and associated inner vestibule door

11. (OP-55B step G.1.10) IF Control Evaluator Note: These controls are in the Relay Room Ventilation is being isolated as Room area of the 09-75 panel.

a result of high radiation in the air supply header, OR by direction of AOP-39 OR AOP-40, THEN isolate Places ISOL & PURGE CNTRL A in ISOL.

CRITICAL STEP Relay Room Ventilation as follows:

SAT / UNSAT Place the following Relay Room Ventilation control switches in ISOL:

ISOL & PURGE CNTRL A Places ISOL & PURGE CNTRL B in ISOL. CRITICAL STEP

ISOL & PURGE CNTRL B SAT / UNSAT

-6 of 8-

STEP STANDARD EVALUATION / COMMENT

12. (OP-55B step G.1.10.b) Verify Observes red light off, green light on for the SAT / UNSAT closed the following dampers and following:

valves:

EXH ISOL 70MOV-105

EXH ISOL 70MOV-105

INLET ISOL 70MOV-106

INLET ISOL 70MOV-106

RR VENT DAMPER 70MOD-115

RR VENT DAMPER 70MOD-115

13. (OP-55B step G.1.10.c) IF either Determines step is N/A and moves on in procedure. SAT / UNSAT 70MOV-105 or 70MOV-106 failed to close

14. (OP-55B step G.1.10.d) IF RR VENT Determines step is N/A and moves on in procedure. SAT / UNSAT DAMPER 70MOD-115 is not closed

15. (OP-55B step G.1.10.e) Verify open Observes red light on, green light off for the SAT / UNSAT the following dampers: following:

RECIRC A 70MOD-104A

RECIRC A 70MOD-104A

RECIRC B 70MOD-104B

RECIRC B 70MOD-104B

16. (OP-55B step G.1.10.f) Ensure Acknowledges cue. SAT / UNSAT closed all access doors to Relay Evaluator Cue: All access doors to the Relay Room.

Room are closed.

EVALUATOR: Terminate the task at this point.

Task Standard: Control Room and Relay Room ventilation are isolated per OP-55B section G.1.

-7 of 8-

HANDOUT

An accident at Nine Mile Point has resulted in rising radiation levels in the Control Room ventilation air supply header.

Isolate Control Room and Relay Room ventilation per OP-55B section G.1.

-8 of 8-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO NRC 18-1 B TASK TITLE: Transfer Feedwater Level Control to Master-Auto, Level Drifts Low APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 259001 A4.01 (3.6/3.5)

ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-2A, Feedwater System III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Plant in a startup condition near 5% power (IC-227).

B. Ensure Feedwater pump A is operating and pump B is secured.

C. Ensure 34MOV-100A and 34MOV-100B are closed.

D. Ensure Reactor water level is being maintained in the green band and controlled with 34FCV-137 in MAN and open as needed to stabilize level and other Feedwater controllers in MAN.

E. Place FDWTR screen on EPIC slave 1 monitor.

F. Ensure simulator is programmed to insert malfunction FW08 to 60 on event 1.

G. Ensure simulator is programmed for event 1 = zdi683(3)==1.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. A plant startup is in progress.

B. Reactor power is approximately 5%.

C. Feedwater pump A is running and Feedwater pump B is secured.

D. FDWTR STARTUP VLV (34FCV-137) 06FIC-130 is in MAN and throttled open.

E. RFP A FLOW CNTRL 06-84A is in MAN.

F. RX WTR LVL CNTRL 06LC-83 is in MAN.

-2 of 7-

VII. INITIATING CUE Inform the candidate, "Transfer RFP A FLOW CNTRL 06-84A to master-manual and then master-auto per OP-2A Section D.2.

The procedure is in progress up to step D.2.27. Maintain Reactor water level 196.5-206.5.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-2A. SAT / UNSAT OP-2A.

Evaluator Note: The candidate may make adjustments to Feedwater controllers throughout the JPM that are not scripted in order to maintain Reactor water level in band.

2. (OP-2A step D.2.27) WHEN Observes RX WTR LVL CNTRL 06LC-83 is in MAN. SAT / UNSAT RFPT A speed is GREATER THAN 2000 rpm, perform the following at the Shift Manager's discretion to transfer RFP A FLOW CNTRL 06-84A to master-manual:

Line up RX WTR LVL CNTRL 06LC-83 as follows:

Verify controller is in MAN.

3. (OP-2A step D.2.27.a.2) Ensures RX WTR LVL CNTRL 06LC-83 setpoint is between SAT / UNSAT Ensure setpoint is BETWEEN 55 AND 65% (197 and 203 inches).

55 AND 65% (197 and 203 inches).

-3 of 7-

STEP STANDARD EVALUATION / COMMENT

4. (OP-2A step D.2.27.b) Adjust Rotates 06LC-83 manual control knob to balance RFP A SAT / UNSAT / NA RX WTR LVL CNTRL 06LC- FLOW CNTRL 06-84A, as necessary.

83 manual control knob to balance RFP A FLOW CNTRL 06-84A.

5. (OP-2A step D.2.27.c) Place Places RFP A FLOW CNTRL 06-84A in BAL. CRITICAL STEP RFP A FLOW CNTRL 06-84A SAT / UNSAT in BAL.

6. (OP-2A step D.2.27.d) Control Controls RFPT A speed by adjusting RX WTR LVL CNTRL SAT / UNSAT / NA RFPT A speed by adjusting 06LC-83 manual control knob, as necessary.

RX WTR LVL CNTRL 06LC-83 manual control knob.

7. (OP-2A step D.2.28) Transfer Determines 34FCV-137 is NOT in automatic (BAL) and SAT / UNSAT / NA RFP A FLOW CNTRL 06-84A moves to next step.

to master auto as follows:

IF 34FCV-137 is in automatic (BAL), THEN place FDWTR STARTUP VLV (34FCV-137) 06FIC-130 in manual as follows

-4 of 7-

STEP STANDARD EVALUATION / COMMENT

8. (OP-2A step D.2.28.b) Place Balances RX WTR LVL CNTRL 06LC-83 by adjusting SP SAT / UNSAT RX WTR LVL CNTRL 06LC- ADJUST knob as necessary.

83 in automatic (BAL) as follows:

Balance controller by adjusting SP ADJUST knob.

9. (OP-2A step D.2.28.b.2) Place Places RX WTR LVL CNTRL 06LC-83 in BAL. CRITICAL STEP controller in BAL. SAT / UNSAT Note: The alternate path is automatically triggered when the candidate completes JPM step #9. Reactor water level will begin drifting low.

10. Recognize / report failure of Recognizes / reports failure of RX WTR LVL CNTRL 06LC- SAT / UNSAT RX WTR LVL CNTRL 06LC- 83 in automatic.

83 in automatic.

Evaluator cue: If asked for direction, tell candidate to make a recommendation and then carry out that recommendation.

11. Stabilize Reactor water level Places RX WTR LVL CNTRL 06LC-83 in MAN CRITICAL STEP by taking manual control of OR SAT / UNSAT Feedwater level control.

Places RFP A FLOW CNTRL 06-84A in MAN Adjusts as necessary to stabilize Reactor water level.

-5 of 7-

STEP STANDARD EVALUATION / COMMENT

12. Maintain Reactor water level Maintains Reactor water level within a band of 177-222.5 CRITICAL STEP within a band of 177-222.5 throughout the evolution. SAT / UNSAT throughout the evolution.

EVALUATOR NOTE: This step is used to designate that a critical aspect of the entire JPM is to maintain Reactor water level within a band of 177-222.5. Many of the other steps are partially critical, in that if the candidate makes a significant enough of an error, a Reactor water level transient will occur. If a scram is received on low Reactor water level or a Feedwater pump trip occurs on high Reactor water level, at any point in the JPM, that is considered grounds for failing this critical step.

EVALUATOR: Terminate the task at this point.

Task Standard: RFP A FLOW CNTRL 06-84A is transferred to master-manual and then master-auto per OP-2A Section D.2.

Failure of master-auto is detected and Reactor water level is stabilized. Reactor water level is maintained within a band of 177-222.5 throughout the evolution.

-6 of 7-

HANDOUT

A plant startup is in progress.

Reactor power is approximately 5%.

Feedwater pump A is running and Feedwater pump B is secured.

FDWTR STARTUP VLV (34FCV-137) 06FIC-130 is in MAN and throttled open.

RFP A FLOW CNTRL 06-84A is in MAN.

RX WTR LVL CNTRL 06LC-83 is in MAN Transfer RFP A FLOW CNTRL 06-84A to master-manual and then master-auto per OP-2A Section D.2.

The procedure is in progress up to step D.2.27.

Maintain Reactor water level 196.5-206.5.

-7 of 7-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC C TASK TITLE: Shutdown Core Spray Following Terminate/Prevent and Subsequent Injection APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 209001 A4.01 (3.8/3.6)

ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-5, Termination and Prevention of RPV Injection B. OP-14, Core Spray System III. TOOLS AND EQUIPMENT A. None.

IV. SET UP REQUIREMENTS A. Reset the simulator to IC-229.

B. Ensure Core Spray has had an automatic start signal and that signal is now clear.

C. Ensure Core Spray A has been terminated and prevented per EP-5.

D. Ensure Core Spray A has been realigned for injection per EP-5 with 14MOV-12A throttled partially open.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. The plant is shutdown following a significant transient.

B. Core Spray A was previously terminated/prevented.

C. Core Spray A is now running and aligned for injection.

-2 of 5-

VII. INITIATING CUE Inform the candidate, "Secure Core Spray Loop A per EP-5 section 5.1.3.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-5. SAT / UNSAT EP-5.

2. (EP-5 step 5.1.3.A) Perform Obtains a controlled copy of OP-14 and selects section F.1. SAT / UNSAT Core Spray Loop A Shutdown per Section F of OP-14.

3. (OP-14 step F.1.1) Ensure Rotates 14MOV-12A control switch counterclockwise until CRITICAL STEP closed INBD INJ VLV 14MOV- green light on, red light off. SAT / UNSAT 12A.

4. (OP-14 step F.1.2) Ensure Observes MIN FLOW VLV 14MOV-5A green light off, red SAT / UNSAT open MIN FLOW VLV light on.

14MOV-5A.

5. (OP-14 step F.1.3) Stop PMP Rotates PMP 14P-1A control switch counterclockwise to CRITICAL STEP 14P-1A. STOP. SAT / UNSAT

6. (OP-14 step F.1.4) IF Core Depresses LOGIC RESET 14A-S15A pushbutton. CRITICAL STEP Spray auto initiated, AND SAT / UNSAT Core Spray initiation conditions are no longer present, THEN reset Core Spray Loop A initiation logic as follows:

Depress LOGIC RESET 14A-S15A pushbutton.

-3 of 5-

STEP STANDARD EVALUATION / COMMENT

7. (OP-14 step F.1.4.b) Verify Observes SYS A LOGIC ACTUATED 14A-DS27A light is SAT / UNSAT white SYS A LOGIC off.

ACTUATED 14A-DS27A light is off.

8. (OP-14 step F.1.5) Ensure Acknowledges cue and returns to EP-5 section 5.1.3. SAT / UNSAT Core Spray Loop A is in the standby lineup per Section E, as soon as practicable. Evaluator cue: Another Operator will perform OP-14 section E while you continue with the remainder of your procedure execution.

9. (EP-5 step 5.1.3.B) Ensure Rotates 14MOV-11A AUTO ACTUATION BYPASS SW CRITICAL STEP 14MOV-11A AUTO 14A-S16A switch to NORMAL. SAT / UNSAT ACTUATION BYPASS SW 14A-S16A switch in NORMAL.

10. (EP-5 step 5.1.3.C) Verify Observes 14MOV-11A AUTO ACTUATION BYPASS LT SAT / UNSAT 14MOV-11A AUTO 14A-DS35A white light is off.

ACTUATION BYPASS LT 14A-DS35A white light is off.

EVALUATOR: Terminate the task at this point.

Task Standard: Core Spray Loop A secured per EP-5 section 5.1.3 and OP-14 section F.1.

-4 of 5-

HANDOUT

The plant is shutdown following a significant transient.

Core Spray A was previously terminated/prevented.

Core Spray A is now running and aligned for injection.

Secure Core Spray Loop A per EP-5 section 5.1.3.

-5 of 5-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC D TASK TITLE: Restore L34 to Normal Power Source, Loss of 10400 Bus APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 262001 A4.01 (3.4/3.7)

ESTIMATED COMPLETION TIME: 12 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-46A, 4160 V and 600 V Normal AC Power Distribution B. AOP-17, Loss of 10400 Bus III. TOOLS AND EQUIPMENT A. Sync key IV. SET UP REQUIREMENTS A. Reset to a power-operating IC (IC-228).

B. Ensure L34 has been transferred to the alternate supply per OP-46A section G.8.6.

C. Place malfunction ED19:D on Trigger 1 with a 4 second time delay.

D. Setup event trigger 1 to actuate when the control switch for breaker 13404 is taken to OFF.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. The plant is operating at power.

B. L34 is currently being supplied by the 10300 bus.

-2 of 7-

VII. INITIATING CUE Inform the candidate, Restore L34 to the normal power source per OP-46A section G.12. The procedure is in progress up to step G.12.3.d.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-46A. SAT / UNSAT OP-46A.

Proceeds to step G.12.3.d.

2. (OP-46A step G.12.3.d) Observes L14 L24 L34 L44 4KV FDR BKR 10440 green SAT / UNSAT Ensure closed L14 L24 L34 light off, red light on.

L44 4KV FDR BKR 10440.

3. (OP-46A step G.12.3.e) Place Inserts sync key for L33 L34 TIE SYNCH SW. CRITICAL STEP L33 L34 TIE SYNCH SW SAT / UNSAT switch in ON.

Rotates sync key clockwise to ON.

4. (OP-46A step G.12.3.f) WHEN Rotates L34 600V FDR BKR 13402 control switch clockwise CRITICAL STEP incoming and running voltages to CLOSE. SAT / UNSAT are matched, AND synchroscope is at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:

Close L34 600V FDR BKR 13402.

-3 of 7-

STEP STANDARD EVALUATION / COMMENT

5. (OP-46A step G.12.3.f.2) Rotates L33-L34 TIE BKR 13404 control switch CRITICAL STEP Open L33-L34 TIE BKR counterclockwise to OPEN. SAT / UNSAT 13404.

Alternate Path begins here which is a loss of the 10400 bus.

6. Recognize / report loss of Recognize / report loss of 10400 bus. SAT / UNSAT 10400 bus.

Evaluator note: If candidate asks for direction on how to proceed, direct them to make a recommendation and then carry out that recommendation.

7. Determines need to perform Determines need to perform AOP-17 immediate actions. SAT / UNSAT AOP-17 immediate actions.

Evaluator note: Since the following actions are immediate actions, the candidate may perform them prior to referencing the procedure.

8. (AOP-17 step D.1) IF 10300 Proceeds to complete AOP-17 attachment 1 (posted SAT / UNSAT Bus is energized, THEN cross attachment).

tie 10400 Bus L Gear with 10300 Bus L Gear per Attachment 1 (sync switch required).

-4 of 7-

STEP STANDARD EVALUATION / COMMENT

9. (AOP-17 att.1 step 1) Verify Observes L13 L23 L33 L43 4KV FDR BKR 10340 green SAT / UNSAT closed L13 L23 L33 L43 4KV light off, red light on.

FDR BKR 10340.

10. (AOP-17 att.1 step 2) Cross Places L44 600V FDR BKR 14402 control switch in PULL CRITICAL STEP tie L44 with L43 as follows: TO LOCK. SAT / UNSAT Place L44 600V FDR BKR 14402 in PULL TO LOCK.

11. (AOP-17 att.1 step 2.b) Close Rotates L43 L44 TIE BKR 14304 control switch clockwise to CRITICAL STEP L43 L44 TIE BKR 14304. CLOSE. SAT / UNSAT Note: The sync key must be used to accomplish this step.

12. (AOP-17 att.1 step 3) Cross Places L34 600V FDR BKR 13402 control switch in PULL CRITICAL STEP tie L34 with L33 as follows: TO LOCK. SAT / UNSAT Place L34 600V FDR BKR 13402 in PULL TO LOCK.

13. (AOP-17 att.1 step 3.b) Close Rotates L33 L34 TIE BKR 13404 control switch clockwise to CRITICAL STEP L33 L34 TIE BKR 13404. CLOSE. SAT / UNSAT Note: The sync key must be used to accomplish this step.

14. (AOP-17 att.1 step 4) Cross Places L24 600V FDR BKR 12402 control switch in PULL CRITICAL STEP tie L24 with L23 as follows: TO LOCK SAT / UNSAT Place L24 600V FDR BKR 12402 in PULL TO LOCK.

-5 of 7-

STEP STANDARD EVALUATION / COMMENT

15. (AOP-17 att.1 step 4.b) Close Rotates L23 L24 TIE BKR 12404 control switch clockwise to CRITICAL STEP L23 L24 TIE BKR 12404. CLOSE. SAT / UNSAT Note: The sync key must be used to accomplish this step.

16. (AOP-17 att.1 step 5) Cross Places RBC PMP B 15P-2B control switch in PULL TO CRITICAL STEP tie L14 with L13 as follows: LOCK. SAT / UNSAT Place RBC PMP B 15P-2B control switch in PULL TO LOCK.

17. (AOP-17 att.1 step 5.b) Place Places L14 600V FDR BKR 11402 control switch in PULL CRITICAL STEP L14 600V FDR BKR 11402 in TO LOCK. SAT / UNSAT PULL TO LOCK.

18. (AOP-17 att.1 step 5.d) Close Rotates L13 L14 TIE BKR 11304 control switch clockwise to CRITICAL STEP L13 L14 TIE BKR 11304. CLOSE. SAT / UNSAT Note: The sync key must be used to accomplish this step.

19. (AOP-17 att.1 step 6) Ensure Observes green light on, red light off for CIRC WTR PMP SAT / UNSAT closed CIRC WTR PMP DISCH VLV 36MOV-100B.

DISCH VLV 36MOV-100B.

EVALUATOR: Terminate the task at this point.

Task Standard: L34 restored to service on Bus 10400 per OP-46A. Then, after loss of Bus 10400, 10400 Bus L Gear cross-tied with 10300 Bus L Gear per AOP-17.

-6 of 7-

HANDOUT

The plant is operating at power.

L34 is currently being supplied by the 10300 bus.

Restore L34 to the normal power source per OP-46A section G.12.

The procedure is in progress up to step G.12.3.d.

-7 of 7-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC E TASK TITLE: Reset Group 2 Isolation, Restore RWCU, RWCU Steam Leak APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 223002 A4.03 (3.6/3.5)

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-15, Isolation Verification and Recovery B. OP-28, Reactor Water Clean-Up System III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a power operating IC (IC-229).

B. Insert a Reactor scram.

C. Restore Reactor water level above 177.

D. Trip both Recirculation pumps.

E. Ensure simulator has the following programming:

Malfunction CU07 on trigger 1 to 50 over 15 seconds

Malfunctions CU10 and CU12 preset

Event 1 = zlo12as3(2)==1 V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. Both Recirculation pumps have tripped.

B. A Reactor scram has been inserted.

C. Reactor water level lowered to 140 inches.

D. Reactor water level has been recovered above 177 inches and is high.

E. Other operators have completed isolation verifications per AOP-15 Attachments 1 & 2.

-2 of 15-

VII. INITIATING CUE Inform the candidate, "Reset the Group 2 isolation per AOP-15 section F.1. Then, restore RWCU per OP-28 section G.4.

Establish gravity blowdown flow to the Main Condenser.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of AOP-15. Refers to section F.1. SAT / UNSAT AOP-15.

2. (AOP-15 step F.1.1) WHEN it Continues with procedure. SAT / UNSAT has been determined that an undesired release will not occur when isolation is reset, EVALUATOR CUE: If the candidate requests assistance continue with procedure. determining an undesired release will not occur, then inform the candidate An undesired release will not occur when isolation is reset.

3. (AOP-15 step F.1.2) Place Rotates control switch for DW FLOOR DRN 20AOV-83 to SAT / UNSAT control switch for DW FLOOR CLOSE.

DRN 20AOV-83 in CLOSE.

4. (AOP-15 step F.1.3) Place Rotates control switch for DW EQUIP DRN 20AOV-95 to SAT / UNSAT control switch for DW EQUIP CLOSE, then releases.

DRN 20AOV-95 to CLOSE, spring return to AUTO.

-3 of 15-

STEP STANDARD EVALUATION / COMMENT

5. (AOP-15 step F.1.4) Simultaneously rotates PCIS VLV RESET switches 16A- CRITICAL STEP Simultaneously rotate the S32 and 16A-S33 to clockwise positions.

following PCIS VLV RESET SAT / UNSAT switches to both RESET positions, spring return to NORM: Simultaneously rotates PCIS VLV RESET switches 16A- CRITICAL STEP

16A-S32 S32 and 16A-S33 to counterclockwise positions. SAT / UNSAT

16A-S33 EVALUATOR NOTE: These switches may be rotated in either direction first.

6. (AOP-15 step F.1.5) Restore Obtains a controlled copy of OP-28. Refers to section G.4 SAT / UNSAT RWCU System, if necessary, per initiating cue.

per Section G of OP-28.

7. (OP-28 step G.4.1) IF boron Determines no boron has been injected. SAT / UNSAT was injected per the EOPs, THEN Subsection G.4 cannot be performed. EVALUATOR CUE: If asked about boron injection, report that no boron has been injected.

8. (OP-28 step G.4.2) Ensure Indicates need to ensure Subsection G.2 is complete. SAT / UNSAT Subsection G.2 is complete.

EVALUATOR CUE: OP-28 section G.2 have been completed by another operator.

-4 of 15-

STEP STANDARD EVALUATION / COMMENT

9. (OP-28 step G.4.3) Ensure Determines RWCU pump A is the preferred pump to isolate. SAT / UNSAT one of the following RWCU pumps is isolated by performing one of the EVALUATOR NOTE: A note in OP-28 identifies RWCU following: pump A as the preferred pump to isolate.

EVALUATOR CUE: If asked about which pump to isolate, direct the candidate to isolate RWCU pump A.

10. (OP-28 step G.4.3.a) IF Directs operator to close valves to isolate RWCU pump A SAT / UNSAT RWCU Pump A will be the (may reference OP-28 step G.4.3.a).

isolated pump, THEN ensure closed the following valves:

12RWC-19A (RWCU pump EVALUATOR CUE: OP-28 step G.4.3.a has been A suct inner isol valve) completed to isolate RWCU pump A.

12RWC-73A (RWCU pump A suct outer isol valve)

12RWC-29A (RWCU pump A disch isol valve)

12RWC-87A (outlet block valve 12FE-20A)

12RWC-38A (RWCU pump A disch check valve RWC-28A bypass valve)

11. (OP-28 step G.4.4) Reset Determines isolation has been reset per AOP-15. SAT / UNSAT isolation per AOP-15, if necessary.

-5 of 15-

STEP STANDARD EVALUATION / COMMENT

12. (OP-28 step G.4.5) Ensure Directs operator to ensure closed 12RWC-63 (may SAT / UNSAT closed 12RWC-63 (RWCU reference OP-28 step G.4.5).

return line manual isol valve).

EVALUATOR CUE: 12RWC-63 is closed.

13. (OP-28 step G.4.6) IF 12MOV- Determines the Reactor is NOT in Mode 5 and skips step. SAT / UNSAT 15 is closed, AND the reactor is in Mode 5, THEN perform the following:

14. (OP-28 step G.4.7) IF 12MOV- Transitions to section G.35. SAT / UNSAT 15 is closed, AND the reactor is not in Mode 5, THEN perform Subsection G.35 for opening 12MOV-15 and 12MOV-18.

-6 of 15-

STEP STANDARD EVALUATION / COMMENT

15. (OP-28 step G.35.1) Open the Directs operator to open valves (may reference OP-28 step SAT / UNSAT following valves: G.35.1).

12RWC-16 (RWCU pumps suct header 12MOV-18 inner LLRT connection isol EVALUATOR CUE: OP-28 step G.35.1 has been valve) completed.

12RWC-17 (RWCU pumps suct header 12MOV-18 outer LLRT connection isol valve)

12RWC-718 (12MOV-18 manual bypass isolation valve)

12RWC-706 (RWCU MOV-18 LLRT conn valve)

12RWC-707 (RWCU MOV-18 LLRT conn valve)

12RWC-719 (12MOV-18 manual bypass isolation valve)

16. (OP-28 step G.35.2) Slowly Directs operator to slowly open 12RWC-120 (may reference SAT / UNSAT open 12RWC-120 (12MOV-18 OP-28 step G.35.2).

bypass valve).

EVALUATOR CUE: 12RWC-120 is open.

-7 of 15-

STEP STANDARD EVALUATION / COMMENT

17. (OP-28 step G.35.3) WHEN Directs operator to close 12RWC-120 when pressure on SAT / UNSAT pressure on 12PI-116 12PI-116 is equal to pressure on 12PI-115 (may reference (12MOV-18 manual bypass OP-28 step G.35.3).

pressure indicator) is equal to pressure on 12PI-115 (12MOV-18 manual bypass EVALUATOR CUE: If asked, pressure on 12PI-116 is pressure indicator), close equal to pressure on 12PI-115.

12RWC-120.

EVALUATOR CUE: When directed, 12RWC-120 is closed.

18. (OP-28 step G.35.4) Throttle Throttles open CLN UP SUCT 12MOV-18 for 1 second by SAT / UNSAT open CLN UP SUCT 12MOV- rotating control switch clockwise to OPEN.

18 for 1 second each minute UNTIL pressure is stable on 12PI-115 AND 12PI-116. EVALUATOR CUE: Time compression is in effect, pressure is stable on 12PI-115 AND 12PI-116.

19. (OP-28 step G.35.5) Open Opens 12MOV-18 by rotating control switch clockwise to CRITICAL STEP CLN UP SUCT 12MOV-18. OPEN. SAT / UNSAT

20. (OP-28 step G.35.6) WHEN EVALUATOR CUE: If asked, pressure on 12PI-115 is 10 SAT / UNSAT pressure on 12PI-115 is 10 psig GREATER THAN RPV pressure.

psig GREATER THAN RPV pressure, throttle open 12MOV-15 for 1 second each Throttles open 12MOV-15 for 1 second by rotating control minute UNTIL pressure is switch clockwise to OPEN.

stable on 12PI-115.

EVALUATOR CUE: Time compression is in effect, pressure is stable on 12PI-115.

-8 of 15-

STEP STANDARD EVALUATION / COMMENT

21. (OP-28 step G.35.7) Open Opens 12MOV-15 by rotating control switch clockwise to CRITICAL STEP 12MOV-15. OPEN. SAT / UNSAT

22. (OP-28 step G.35.8) Close the Directs operator to close 12RWC-718 and 12RWC-719 SAT / UNSAT following valves: (may reference OP-28 step G.35.8).

12RWC-718

12RWC-719 EVALUATOR CUE: 12RWC-718 and 12RWC-719 are closed.

23. (OP-28 step G.35.9) Close Directs operator to close and lock 12RWC-16 (may SAT / UNSAT and lock 12RWC-16. reference OP-28 step G.35.9).

EVALUATOR CUE: 12RWC-16 is closed and locked.

24. (OP-28 step G.35.10) Close Directs operator to close and lock 12RWC-17 (may SAT / UNSAT and lock 12RWC-17. reference OP-28 step G.35.10).

EVALUATOR CUE: 12RWC-17 is closed and locked.

25. (OP-28 step G.35.11) Close Directs operator to close 12RWC-706 (may reference OP- SAT / UNSAT 12RWC-706. 28 step G.35.11).

EVALUATOR CUE: 12RWC-706 is closed.

-9 of 15-

STEP STANDARD EVALUATION / COMMENT

26. (OP-28 step G.35.12) Close Directs operator to close 12RWC-707 (may reference OP- SAT / UNSAT 12RWC-707. 28 step G.35.12).

EVALUATOR CUE: 12RWC-707 is closed.

27. (OP-28 step G.35.13) Directs operator to independently verify valve positions SAT / UNSAT Independently verify the (may reference OP-28 step G.35.13).

following AND record independent verification in the narrative logs: EVALUATOR CUE: OP-28 step G.35.13 is complete.

12RWC-16 closed and locked

12RWC-17 closed and EVALUATOR CUE: This is the end of OP-28 section G.35.

locked The candidate will now transition back to OP-28 step G.4.8.

12RWC-706 closed

12RWC-707 closed

28. (OP-28 step G.4.8) IF plant Directs operator to establish seal purge flow for RWCU SAT / UNSAT conditions permit as pump A (may reference OP-28 step G.4.8).

determined by the SM, THEN ensure seal purge flow rate to the unisolated RWCU pump as EVALUATOR CUE: If asked, SM has determined plant follows: conditions permit establishing seal purge flow.

IF seal purge flow is for 12P-1B only, THEN throttle EVALUATOR CUE: RWCU pump seal purge is 2 gpm.

12RWC-88B as necessary (bypass regulating valve 12P-1B) to establish a flow rate BETWEEN 1.8 and 2.2 gpm as indicated on 12FI-20 (RWCU pumps mini purge flow indic).

-10 of 15-

STEP STANDARD EVALUATION / COMMENT

29. (OP-28 step G.4.9) Ensure Acknowledges cue. SAT / UNSAT ST-26J, Heatup and Cooldown Temperature Checks, is in progress prior to establishing EVALUATOR CUE: Another operator is performing ST-blowdown flow. 26J.

30. (OP-28 step G.4.10) Slowly Proceeds to OP-28 section G.5. SAT / UNSAT establish a gravity blowdown flow rate of LESS THAN OR EQUAL TO 30 gpm per Subsection G.5.

31. (OP-28 step G.5.1) Direct RP Directs RP to ensure posting requirements are met to SAT / UNSAT to ensure posting support the blowdown operation.

requirements are met to support the blowdown operation. EVALUATOR CUE: RP reports that posting requirements are met.

32. (OP-28 step G.5.2) IF reactor Determines Reactor coolant temperature is greater than SAT / UNSAT coolant temperature is LESS 212oF.

THAN 212oF, THEN ensure RPV is vented to prevent drawing a vacuum inside RPV.

33. (OP-28 step G.5.3) At the Acknowledges cue. SAT / UNSAT discretion of the Shift Manager, contact the Reactor Analyst prior to commencing EVALUATOR CUE: The Shift Manager directs continuing blowdown to turn off core with the procedure prior to contacting the Reactor Analyst.

thermal monitoring.

-11 of 15-

STEP STANDARD EVALUATION / COMMENT

34. (OP-28 step G.5.4) IF RPV Observes 12MOV-53 green light on, red light off. SAT / UNSAT pressure is GREATER THAN 50 psig, THEN ensure closed BLOWDOWN ORIFICE BYP 12MOV-53.

35. (OP-28 step G.5.5) IF RPV Determines RPV pressure is greater than 50 psig. SAT / UNSAT pressure is LESS THAN 50 psig, THEN open BLOWDOWN ORIFICE BYP 12MOV-53.

36. (OP-28 step G.5.6) IF Determines blowdown will not be routed to Waste Collector SAT / UNSAT blowdown will be routed to Tank per initiating cue.

Waste Collector Tank, THEN perform the following:

37 (OP-28 step G.5.7) IF Observes 12MOV-57 green light on, red light off. SAT / UNSAT blowdown will be routed to Main Condenser, THEN perform the following:

Ensure closed BLOWDOWN TO RADW 12MOV-57.

38. (OP-28 step G.5.7.b) Open Opens 12MOV-56 by rotating control switch clockwise to CRITICAL STEP BLOWDOWN TO MAIN OPEN. SAT / UNSAT CNDSR 12MOV-56.

Note: The alternate path begins when 12MOV-56 is opened. This inserts a steam leak into the Reactor Building. JPM steps 39-41 are provided below for completeness, but may not be performed once the candidate recognizes the steam leak.

-12 of 15-

STEP STANDARD EVALUATION / COMMENT

39. (OP-28 step G.5.8) Establish Directs operator to ensure closed 12RWC-63 or determines SAT / UNSAT / NA blowdown flow as follows: it is closed from earlier cue (may reference OP-28 step G.5.8.a.1).

IF gravity blowdown will be used, THEN perform the following: EVALUATOR CUE: If asked, report that 12RWC-63 is closed.

Ensure closed 12RWC-63 (RWCU return line manual isol valve).

40. (OP-28 step G.5.8.a.2) Throttles open 12MOV-74 by rotating control switch SAT / UNSAT / NA Throttle open FILTER DEMIN clockwise to OPEN.

BYP 12MOV-74 until red open light comes on (dual position indication).

41. (OP-28 step G.5.8.b) Adjust Throttles open 12FCV-55 by rotating potentiometer SAT / UNSAT / NA CLN UP BLOWDOWN FLOW clockwise.

CNTRL 12FCV-55 until desired blowdown flow rate is established.

-13 of 15-

STEP STANDARD EVALUATION / COMMENT

42. Recognize / report steam leak Recognizes / reports steam leak in Reactor Building. SAT / UNSAT in Reactor Building.

EVALUATOR CUE: If asked how to proceed, tell the candidate to make a recommendation and then carry out that recommendation.

43. Isolate RWCU steam leak. Closes 12MOV-15 by rotating control switch CRITICAL STEP counterclockwise to CLOSE. SAT / UNSAT Note: 12MOV-18 will likely also be closed, but it is not critical due to location of the steam leak.

EVALUATOR: Terminate the task at this point.

Task Standard: PCIS Group 2 isolation is reset. RWCU gravity blowdown flow to the Main Condenser is established at least up to the point of opening 12MOV-56. RWCU steam leak into Reactor Building isolated.

-14 of 15-

HANDOUT

Both Recirculation pumps have tripped.

A Reactor scram has been inserted.

Reactor water level lowered to 140 inches.

Reactor water level has been recovered above 177 inches and is high.

Other operators have completed isolation verifications per AOP-15 Attachments 1 & 2.

Reset the Group 2 isolation per AOP-15 section F.1.

Then, restore RWCU per OP-28 section G.4.

Establish gravity blowdown flow to the Main Condenser.

-15 of 15-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC F TASK TITLE: Restore CRD to Normal Alignment Following ATWS (Alt Path)

APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 201001 A2.07 (3.2/3.1)

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-3, Backup Control Rod Insertion B. OP-25, Control Rod Drive Hydraulic System III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to an appropriate IC (IC-230).

B. Ensure the Reactor is scrammed, but RPS is reset.

C. Ensure both CRD pumps are running.

D. Ensure full open CRD Drive Water Pressure Control Valve 03MOV-20.

E. Ensure full closed CRD Cooling Water Pressure Control Valve 03MOV-22.

F. Ensure CRD Flow Control tapeset is run to maximum.

G. Ensure override RD ZAI3FC301(2), CRD FLOW CONTROLLER - AUTO, is preset at a high value

(>95).

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. An ATWS has occurred.

B. Control rods were inserted by raising CRD drive water and cooling water differential pressure.

C. Another operator is assigned Reactor water level control.

-2 of 6-

VII. INITIATING CUE Inform the candidate, "Perform EP-3 Section 5.15, CRD Hydraulic System Restoration. The procedure has been completed up to step 5.15.4. Secure CRD pump B and leave CRD pump A running.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-3. SAT / UNSAT EP-3.

2. (EP-3 step 5.15.4) IF both Stops CRD pump B by rotating control switch CRITICAL STEP CRD pumps are running, counterclockwise. SAT / UNSAT THEN shut down one of the CRD pumps.

3. (EP-3 step 5.15.5)Establish Obtains a controlled copy of OP-25 Section E. SAT / UNSAT normal CRD Hydraulic System operating values per Section E of OP-25.

EVALUATOR NOTE: JPM steps 4-9 may be performed in any order, but each has the potential to affect CRD parameters established in other steps. JPM steps 7 and 8 should only be graded SAT if the associated parameter is ensured in band at the completion of the JPM. This may require the candidate to re-adjust the associated controls.

-3 of 6-

STEP STANDARD EVALUATION / COMMENT Alternate Path begins here:

4. (OP-25 step E.1) Establish Attempts to adjust tapeset on CRD FLOW CNTRL 03FIC- CRITICAL STEP normal CRD system flow. 301 to lower CRD system flow. SAT / UNSAT EVALUATOR NOTE: The tapeset on 03FIC-301 is failed, such that the controller will not respond to the operators adjustments while in AUTO. OP-AA-101-111 provides guidance for the operator to take manual control of a controller that has failed in automatic.

5. Recognize / report CRD Flow Reports CRD Flow Control Valve failure. SAT / UNSAT Control Valve failure.

EVALUATOR NOTE: If candidate asks how to proceed, direct them to make a recommendation and then carry out that recommendation.

6. Places CRD FLOW CNTRL Rotates CRD FLOW CNTRL 03FIC-301 selector clockwise CRITICAL STEP 03FIC-301 in MAN. to MAN. SAT / UNSAT

7. Establish normal CRD system Adjusts knob on CRD FLOW CNTRL 03FIC-301 to establish CRITICAL STEP flow. between 59 and 61 gpm (on 03FI-310). SAT / UNSAT

-4 of 6-

STEP STANDARD EVALUATION / COMMENT

8. (OP-25 step E.6) Establish Throttles closed CRD Drive Water Motor Operated Pressure CRITICAL STEP normal CRD drive water Control Valve 03MOV-20 by rotating control switch SAT / UNSAT differential pressure. counterclockwise.

Adjusts 03MOV-20 as required to establish 260 to 270 psid drive water differential pressure (on 03DPI-303).

9. (OP-25 step E.7) Establish Fully opens CRD Cooling Water Motor Operated Pressure SAT / UNSAT normal CRD cooling water Control Valve 03MOV-22 by rotating control switch valve alignment. clockwise.

EVALUATOR CUE: If necessary, report CRD stabilizing valve flow is 6 gpm.

EVALUATOR: Terminate the task at this point.

Task Standard: The CRD system is restored to normal parameter values. The CRD flow controller is operated in manual due to failure of the automatic setpoint tape to respond to changes in operator demand.

-5 of 6-

HANDOUT

An ATWS has occurred.

Control rods were inserted by raising CRD drive water and cooling water differential pressure.

Another operator is assigned Reactor water level control.

Perform EP-3 Section 5.15, CRD Hydraulic System Restoration.

The procedure has been completed up to step 5.15.4.

Secure CRD pump B and leave CRD pump A running.

-6 of 6-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC G TASK TITLE: Perform Main Steam Shutdown Lineup APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 239001 A4.01 (4.2/4.0)

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-1, Main Steam System III. TOOLS AND EQUIPMENT A. None.

IV. SET UP REQUIREMENTS A. Reset the simulator to IC-230 (shutdown in progress, Reactor pressure <5 psig).

B. If there are cycle-specific tags on 29MOV-74 and 29MOV-77, remove them.

C. Have all MSIVs closed except for 29AOV-80A.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. A shutdown is in progress.

B. The plant is expected to remain offline for 3 days.

C. LLRT is NOT being performed during the shutdown.

D. It is desired to slow-close inboard MSIVs.

E. All MSIVs have been closed with the exception of 29AOV-80A.

-2 of 6-

VII. INITIATING CUE Inform the candidate, "Complete the Main Steam Shutdown Lineup per OP-1 Section F. The procedure is complete up to steps F.1.3 and G.13.2.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-1. SAT / UNSAT OP-1.

2. (OP-1 step G.13.2) IF Slow Determines 29AOV-80A needs to be closed. SAT / UNSAT Closing inboard isolation valve 29AOV-80A(B)(C)(D), THEN Determines plant conditions support closing 29AOV-80A.

perform the following:

Verify proper plant conditions for valve(s) to be closed.

3. (OP-1 step G.13.2.b) Depress Depresses and holds MSIV SLOW CLOSE 29AOV-80A CRITICAL STEP and hold MSIV SLOW CLOSE pushbutton. SAT / UNSAT 29AOV-80A(B)(C)(D) pushbutton.

4. (OP-1 step G.13.2.c) WHEN Observes 29AOV-80A green light on, red light off. CRITICAL STEP 29AOV-80A(B)(C)(D) SAT / UNSAT indicates closed, place MSIV 29AOV-80A(B)(C)(D) in Places MSIV 29AOV-80A control switch in CLOSE.

CLOSE.

5. (OP-1 step G.13.2.d) Release Releases MSIV SLOW CLOSE 29AOV-80A pushbutton. SAT / UNSAT MSIV SLOW CLOSE 29AOV-80A(B)(C)(D) pushbutton.

-3 of 6-

STEP STANDARD EVALUATION / COMMENT

6. (OP-1 step F.2) Open the Opens MAIN STM DRN VLV 29MOV-101A by depressing CRITICAL STEP following valves: OPEN pushbutton until green light off, red light on. SAT / UNSAT

MAIN STM DRN VLV 29MOV-101A

7.

MAIN STM DRN VLV Opens MAIN STM DRN VLV 29MOV-101B by depressing CRITICAL STEP 29MOV-101B OPEN pushbutton until green light off, red light on. SAT / UNSAT

8.

MAIN STM DRN VLV Opens MAIN STM DRN VLV 29MOV-101C by depressing CRITICAL STEP 29MOV-101C OPEN pushbutton until green light off, red light on. SAT / UNSAT

9.

MAIN STM DRN VLV Opens MAIN STM DRN VLV 29MOV-101D by depressing CRITICAL STEP 29MOV-101D OPEN pushbutton until green light off, red light on. SAT / UNSAT

10.

RX VENT 02AOV-17 Opens RX VENT 02AOV-17 by rotating control switch CRITICAL STEP clockwise to OPEN. SAT / UNSAT

11.

RX VENT 02AOV-18 Opens RX VENT 02AOV-18 by rotating control switch CRITICAL STEP clockwise to OPEN. SAT / UNSAT

-4 of 6-

STEP STANDARD EVALUATION / COMMENT

12. (OP-1 step F.3) IF the plant Determines plant will not be shutdown for greater than 1 SAT / UNSAT will be shutdown for week.

GREATER THAN 1 week, THEN drain main steam line low points per Subsection G.10.

EVALUATOR: Terminate the task at this point.

Task Standard: Main Steam shutdown lineup complete per OP-1 section F.

-5 of 6-

HANDOUT

A shutdown is in progress.

The plant is expected to remain offline for 3 days.

LLRT is NOT being performed during the shutdown.

It is desired to slow-close inboard MSIVs.

All MSIVs have been closed with the exception of 29AOV-80A.

Complete the Main Steam Shutdown Lineup per OP-1 Section F.

The procedure is complete up to steps F.1.3 and G.13.2.

-6 of 6-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC H TASK TITLE: Bypass LPRM APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 215005 A4.06 (3.6/3.8)

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-16, Neutron Monitoring III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to a power operating IC (IC-228).

B. Ensure no APRMs or LPRMs are bypassed.

C. Ensure alarm typer is up and running.

D. Ensure all applicable sections of OP-16 are provided/available - E.11, E.16, and E.17.

E. Ensure the following simulator programming:

Malfunction NM11:4C0421, LPRM (4C-04-21) Failure, 0% (Preset)

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. LPRM 4C-04-21 has failed downscale.

B. LPRM 4C-04-21 is assigned to APRM A.

-2 of 11-

VII. INITIATING CUE Inform the candidate, "Bypass LPRM 4C-04-21 per OP-16.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-16. SAT / UNSAT OP-16.

2. (OP-16 step E.11.1) Bypass Moves to OP-16 Section E.16. SAT / UNSAT associated APRM per Subsection E.16.

Evaluator note: If asked about desire to also bypass APRM B, state that it is not desired to also bypass APRM B.

3. (OP-16 step E.16.1) Place Places APRM BYP switch in A position. CRITICAL STEP APRM BYP switch in (*). SAT / UNSAT

4. (OP-16 step E.16.2) Verify Observes APRM A BYPASS light is on. SAT / UNSAT APRM (*) is bypassed using one or both of the following:

and/or

APRM (*) BYPASS indicating light is on

APRM (*) EPIC alarm Observes APRM A EPIC alarm indicates bypassed.

indicates bypassed

-3 of 11-

STEP STANDARD EVALUATION / COMMENT

5. (OP-16 step E.16.3) Verify the Observes APRM BYPASS indicating lights are off for SAT / UNSAT other two APRM channels APRMs C and E.

associated with the same APRM BYP switch are in service using one or both of and/or the following:

APRM BYPASS indicating Observes no EPIC bypassed alarms for APRMS C and E.

lights are off for the other two APRMs

No EPIC bypassed alarms EVALUATOR NOTE: The candidate will now move back to for the other two APRMs OP-16 Section E.11.

6. (OP-16 step E.11.2) Verify Observe BYP light for APRM A is on at top of panel 09-14. SAT / UNSAT BYP light for APRM (*) is on at top of panel 09-14.

7. (OP-16 step E.11.3) Select Places APRM A S3 switch in position 4. CRITICAL STEP LPRM for display on APRM (*) SAT / UNSAT meter as follows:

Place left hand METER FUNCTION switch (S3) in numerical position for LPRM.

8.

Place right hand METER Places APRM A S2 switch in position C. CRITICAL STEP FUNCTION switch (S2) in SAT / UNSAT alphabetical position for LPRM.

-4 of 11-

STEP STANDARD EVALUATION / COMMENT

9. (OP-16 step E.11.4) Place Places LPRM 4C-04-21 amplifier card switch in BY. CRITICAL STEP LPRM amplifier card switch in SAT / UNSAT BY.

10. (OP-16 step E.11.5) Verify the Observes LPRM 4C-04-21 middle white light is lit. SAT / UNSAT following:

Downscale light is on for LPRM (middle white light at top of panel)

11.

Bypass light is on for Observes LPRM 4C-04-21 left hand white light is lit. SAT / UNSAT LPRM (left hand white light at top of panel)

12.

LPRM BYPASSED light is Observes LPRM BYPASSED light is lit for APRM A. SAT / UNSAT on (white light on left hand side of meter)

13.

APRM (*) meter indicates Observes APRM A meter indicates 0. SAT / UNSAT zero

14. (OP-16 step E.11.6) Place Places APRM A S2 switch in AVERAGE. CRITICAL STEP right hand METER SAT / UNSAT FUNCTION switch (S2) in AVERAGE.

-5 of 11-

STEP STANDARD EVALUATION / COMMENT

15. (OP-16 step E.11.7) Perform Observes ROD SEL PWR switch is in ON. SAT / UNSAT the following at the 09-5 panel:

Ensure ROD SEL PWR switch is in ON.

16. (OP-16 step E.11.7.b) Select a Selects a control rod near LPRM 4C-04-21. CRITICAL STEP control rod near the bypassed SAT / UNSAT LPRM by depressing rod select pushbutton on ROD Evaluator note: Attachment 4 identifies the following rods SEL matrix. as being near LPRM 4C-04 02-19, 02-23, 06-19, 06-23.

17. (OP-16 step E.11.7.c) Verify Observes selected control rod pushbutton is brightly backlit. SAT / UNSAT the following:

Select pushbutton is Observes selected control rod indicating light is lit.

brightly backlit

Control rod indicating light is on (light with coordinates Observes C level LPRM meter indicates downscale.

on FULL CORE DISPLAY)

Meter at the level of the bypassed LPRM indicates downscale.

18. (OP-16 step E.11.7.d) Place Rotates ROD SEL PWR switch counterclockwise to OFF. CRITICAL STEP ROD SEL PWR switch in SAT / UNSAT OFF.

-6 of 11-

STEP STANDARD EVALUATION / COMMENT

19. (OP-16 step E.11.7.e) Place Rotates ROD SEL PWR switch clockwise to ON. CRITICAL STEP ROD SEL PWR switch in ON. SAT / UNSAT

20. (OP-16 step E.11.8) Identify Determines no other LPRMs are bypassed. SAT / UNSAT core location of the "bypassed LPRM", and all its adjacent LPRMs at the same level.

IF these LPRMs are bypassed

21. (OP-16 step E.11.9) Perform Determines all LPRMs assigned to APRM A except 4C SAT / UNSAT the following at LPRM 21 are operable.

amplifier card section of APRM (*):

Evaluator note: 16 of 17 are operable.

Count and note total number of operable LPRMs.

22. (OP-16 step E.11.9.b) Count Determines all LPRMs assigned to APRM A except 4C SAT / UNSAT and note the number of 21 are operable.

operable LPRMs which are at the same detector level as the LPRM that was bypassed. Evaluator note: 16 of 17 are operable.

-7 of 11-

STEP STANDARD EVALUATION / COMMENT

23. (OP-16 step E.11.9.c) IF either Determines adequate LPRMs remain operable. SAT / UNSAT of the following conditions exist:

Evaluator note: >12 are operable.

the total number of operable LPRMs EQUALS 12 OR Evaluator note: All other LPRMs are operable.

the number of operable LPRMs which are at the same detector level as the bypassed LPRM EQUALS 2

THEN perform the following

24. (OP-16 step E.11.9.d) IF Determines adequate LPRMs remain operable. SAT / UNSAT either of the following conditions exist:

Evaluator note: >12 are operable.

the total number of operable LPRMs is LESS THAN 11 OR Evaluator note: All other LPRMs are operable.

the number of operable LPRMs which are at the same detector level as the bypassed LPRM is LESS THAN 2, THEN perform the following

-8 of 11-

STEP STANDARD EVALUATION / COMMENT

25. (OP-16 step E.11.9.e) IF the Determines adequate LPRMs remain operable. SAT / UNSAT number of operable LPRMs is EQUAL TO 11, THEN perform the following

26. (OP-16 step E.11.10) IF plant Indicates need to calibrate APRMs. SAT / UNSAT conditions will permit calibrating APRMs per ST-5D, THEN calibrate APRMs per EVALUATOR CUE: Another operator has calibrated all ST-5D. APRMs.

27. (OP-16 step E.11.11) Return Moves to OP-16 Section E.17. SAT / UNSAT APRM (*) to service per Subsection E.17.

28. (OP-16 step E.17.1) Verify the Observes APRM A INOP, UPSCL NEUT TRIP, and UPSCL SAT / UNSAT following lights for APRM (*) THERM TRIP lights are off.

are off at panel 09-14:

INOP

UPSCL NEUT TRIP

UPSCL THERM TRIP

29. (OP-16 step E.17.2) Place Places APRM A BYP switch in center position. CRITICAL STEP APRM BYP switch for APRM SAT / UNSAT

(*) in center position.

-9 of 11-

STEP STANDARD EVALUATION / COMMENT

30. (OP-16 step E.17.3) Verify Observes APRM A BYPASS light is off. SAT / UNSAT APRM (*) is returned to service using one or both of the following: and/or

APRM (*) BYPASS indicating light is off Observes no EPIC bypassed alarm for APRM A.

No EPIC bypassed alarm for APRM (*)

31. (OP-16 step E.17.4) Verify all Observes APRM A, C, and E BYPASS lights are off. SAT / UNSAT three APRM channels associated with the same APRM BYP switch are in and/or service using one or both of the following: Observes no EPIC bypassed alarm for APRMs A, C, and E.

APRM BYPASS indicating lights are off for the three APRMs

No EPIC bypassed alarms for the three APRMs EVALUATOR: Terminate the task at this point.

Task Standard: APRM A is bypassed, then LPRM 4C-04-21 is bypassed per OP-16, then APRM A is returned to service.

-10 of 11-

HANDOUT

LPRM 4C-04-21 has failed downscale.

LPRM 4C-04-21 is assigned to APRM A.

Bypass LPRM 4C-04-21 per OP-16.

-11 of 11-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC I TASK TITLE: Restore H2O2 Monitors Following Isolation (Alt Path)

APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 223002 A2.09 3.6/3.7 ESTIMATED COMPLETION TIME: 10 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME: LOGIN ID:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED Page 1 of 9

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-37, Containment Atmosphere Dilution System.

B. EP-2, Isolation/Interlock Overrides.

III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Obtain SM permission prior to performing this task.

B. Obtain a controlled copy of EP-2 Isolation/Interlock Overrides.

C. Obtain a controlled copy of OP-37, Reinitializing Hydrogen/Oxygen Monitor Panel.

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. A Primary Containment isolation has occurred due to High Drywell Pressure (2.7 psig).

B. The cause of the isolation has been determined.

C. The Shift Manager directs restoration of H2/O2 monitors.

Page 2 of 9

VII. INITIATING CUE Inform the candidate, "Override the High Drywell Pressure Isolation per Section 5.25 of EP-2 and then reinitialize 27PCX-101A per section D.2 of OP-37.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of EP-2, Obtains a controlled copy of EP-2. SAT \ UNSAT ISOLATION/INTERLOCK OVERRIDES.

EVALUATOR: Provide working copy of EP-2.

2. (EP-2 Step 5.25.1) At Panel 27MAP, places EMERG MANUAL OVERRIDE SYSTEM CRITICAL STEP Place EMERG MANUAL OVERRIDE A switch in OVER/RI.

SAT \ UNSAT SYSTEM A keylock switch in OVER/RI at panel 27MAP.

EVALUATOR CUE: Inform candidate keylock switch is in override.

(PA2-35 key)

3. (EP-2 Step 5.25.1) At Panel 27MAP, places EMERG MANUAL OVERRIDE SYSTEM CRITICAL STEP Place EMER MANUAL OVERRIDE B switch in OVER/RI.

SAT \ UNSAT SYSTEM B keylock switch in OVER/RI at panel 27MAP.

EVALUATOR CUE: Inform candidate keylock switch is in override.

(PA2-35 key)

Page 3 of 9

STEP STANDARD EVALUATION / COMMENT

4. (EP-2 Step 5.25.2) Exits EP-2 and enters OP-37. SAT \ UNSAT Reinitialize hydrogen/oxygen monitor panel per Section D of OP-37.

EVALUATOR: Provide working copy of OP-37.

5. (OP-37 Step D.2.1) Observes LOCAL power switch in OFF. SAT \ UNSAT Ensure LOCAL POWER switch is in OFF.

EVALUATOR: Inform the Candidate all valves referenced in Section D.2.2 are found with their green light on, red light off.

Page 4 of 9

STEP STANDARD EVALUATION / COMMENT

6. (OP-37 Step D.2.2) EVALUATOR NOTE \ CUE: If Candidate asks which Sample Path CRITICAL STEP Ensure open one set of the following to use: inform Candidate to use normal path.

SAT \ UNSAT valve pairs: (The normal path is the Supp Pool 27SOV-119E1/E2)

SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E1 Attempts to open one of the following pairs of valve by placing control switches to OPEN:

SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E2

SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E1

SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E2 EVALUATOR CUE: When the candidate moves the first control switch to open, state the red light is on, green light off.

Alternate Path begins here:

EVALUATOR CUE: When the second valve (of the pair) control switch is placed to open, state the red light is off and the green light remains on.

EVALUATOR CUE: If Candidate asks how to proceed, tell them to reinitialize 27PCX-101A per section D.2 of OP-37. If asked specifically which Sample Path to use, tell them to use DW mid sample path.

6a. Note: Candidate may re-close first EVALUATOR CUE: If the first valve previously opened is taken to SAT \ UNSAT valve previously opened. close, state the green light is on, the red light is off.

Page 5 of 9

STEP STANDARD EVALUATION / COMMENT

7. (OP-37 Step D.2.2) EVALUATOR CUE: If Candidate asks which Sample Path to use: CRITICAL STEP Ensure open one set of the following inform Candidate to use DW mid sample path.

SAT \ UNSAT valve pairs:

SAMPLE GAS DRYW LOW Opens any one set of the following valves by placing control SAMP VALVE 27SOV-123E1 switches to OPEN:

SAMPLE GAS DRYW LOW SAMP VALVE 27SOV-123E2

SAMPLE GAS DRYW LOW SAMP VALVE 27SOV-123E1

-OR-

SAMPLE GAS DRYW LOW SAMP VALVE 27SOV-123E2

SAMPLE GAS DRYW MID -OR-SAMP VALVE 27SOV-120E1

SAMPLE GAS DRYW MID SAMP VALVE 27SOV-120E1

SAMPLE GAS DRYW MID

SAMPLE GAS DRYW MID SAMP VALVE 27SOV-120E2 SAMP VALVE 27SOV-120E2

-OR-

SAMPLE GAS DRYW UP SAMP VALVE 27SOV-122E1

SAMPLE GAS DRYW UP SAMP VALVE 27SOV-122E1

SAMPLE GAS DRYW UP SAMP VALVE 27SOV-122E2

SAMPLE GAS DRYW UP SAMP VALVE 27SOV-122E2 EVALUATOR CUE: For each valve in the second pair, when the candidate indicates the control switch is moved to open, then inform the candidate that the red light came on the green light is off.

Page 6 of 9

STEP STANDARD EVALUATION / COMMENT

8. (OP-37 Step D.2.3) Places the control switch to the OPEN position for: CRITICAL STEP Ensure open the following valves at

SAMPLE GAS RETURN SAMP VALVE 27SOV-124E1 SAT \ UNSAT MAP:

SAMPLE GAS RETURN SAMP VALVE 27SOV-124E2

SAMPLE GAS RETURN SAMP VALVE 27SOV-124E1 EVALUATOR CUE: For each valve, when the candidate indicates

SAMPLE GAS RETURN the control switch is moved to open inform the candidate that the SAMP VALVE 27SOV-124E2 red light is on, the green light is off.

9. (OP-37 Step D.2.4) Places PUMP switch in RUN. CRITICAL STEP Ensure PUMP switch is in RUN. SAT \ UNSAT EVALUATOR CUE: Inform the candidate it is in RUN.

10. (OP-37 Step D.2.5) Places POWER keylock switch in ON. CRITICAL STEP Ensure POWER keylock switch is in SAT \ UNSAT ON. EVALUATOR CUE: Inform the candidate the keylock switch is in ON.

(PA2-35 key)

11. (OP-37 Step D.2.6.a) Depresses 6 on 27PCX-101A keypad. CRITICAL STEP Depress 6. SAT \ UNSAT EVALUATOR CUE: When indicates 6 would be depressed, then inform the candidate 6 has been depressed and ENTER ACCESS CODE appears on CRT screen.

Page 7 of 9

STEP STANDARD EVALUATION / COMMENT

12. (OP-37 Step D.2.6.b) Depresses 8, then 2, and then Enter key on 27PCX-101A keypad. CRITICAL STEP When ENTER ACCESS CODE SAT \ UNSAT appears on CRT screen, perform the EVALUATOR CUE: When the candidate indicates 8, 2 and Enter following: keys would be depressed, then state the monitor display appears

1) Depress 8. on CRT screen.

2) Depress 2.

3) Depress ENTER.

13. (OP-37 Step D.2.6.c) Depresses 1 and then ESC key on 27PCX-101A keypad. CRITICAL STEP WHEN monitor display appears on SAT \ UNSAT CRT screen, perform the following: EVALUATOR CUE: When the candidate states they would

1) Depress 1. depress 1 then ESC, inform the candidate that the 27PCX-101

2) Depress ESC. graphic display is now visible.

14. (OP-37 Step D.2.7) Observes the following: SAT \ UNSAT Verify the following on 27PCX-101A

SV-1 open display:

SV-6 open

SV-1 is open

P1 running

SV-6 is open

Flow indication for P1 (red light EVALUATOR CUE: If asked, inform the candidate SV-1 and SV-6 on) indicate open and P1 red light is on.

EVALUATOR: Terminate the task at this point.

Task standard: High Drywell Pressure Isolation is overridden per Section 5.25 of EP-2. 27PCX-101A re-initialized and aligned to Drywell per section D.2 of OP-37.

Page 8 of 9

HANDOUT

A Primary Containment isolation has occurred due to High Drywell Pressure (2.7 psig).

The cause of the isolation has been determined.

The Shift Manager directs restoration of H2/O2 monitors.

Override the High Drywell Pressure Isolation per Section 5.25 of EP-2 and then reinitialize 27PCX-101A per section D.2 of OP-37.

Page 9 of 9

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC J TASK TITLE: Perform In-Plant Actions for Station Blackout (AOP-49 Attachment 3) (Time Critical)

APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 295003 AA1.04 (3.6/3.7)

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

S/RO 14-1 NRC J TASK TITLE: Perform In-Plant Actions for Station Blackout (AOP-49 Attachment 3) (Time Critical)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. Part of this task involves simulating the operation of circuit breakers. The proper electrical PPE should be made available to the Candidate.

II. REFERENCES A. AOP-49, Station Blackout III. TOOLS AND EQUIPMENT A. Gloves IV. SET UP REQUIREMENTS A. Provide a working copy of AOP-49 Attachment 3 pages 4 of 8 (Battery Room Actions) and 8 of 8 (Turbine Building Actions).

V. EVALUATOR NOTES A. None VI. TASK CONDITIONS A. A station blackout is in progress.

B. AOP-49, Station Blackout, Attachment 3 is in progress.

-2 of 8-

VII. INITIATING CUE Inform the candidate, "Perform the in-plant actions of AOP-49 Attachment 3 for the Battery Rooms and the Turbine Building.

This is a time critical task. Your time starts now.

Note: This JPM is time critical. All steps must be completed within 30 minutes.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains AOP-49 Attachment 3 from the evaluator. SAT / UNSAT AOP-49, Station Blackout, Attachment 3.

EVALUATOR: Provide candidate a current copy of AOP-49 Attachment 3 pages 4 of 8 (Battery Room Actions) and 8 of 8 (Turbine Building Actions).

EVALUATOR NOTE: AOP-49 Attachment 3 allows steps to be performed in any order or concurrently.

EVALUATOR NOTE: The following steps are performed at 71BCB-2A in the A Battery Charger Room on Admin Building elevation 272.

2. (AOP-49 Att. 3 Page 4 Step 1) Simulates re-positioning FEED TO 71LPERDC2 REACTOR CRITICAL STEP Place the following circuit BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT breakers in OFF at 71BCB-2A PANEL to OFF.

BATTERY CONTROL BOARD A in A Battery Charger Room: EVALUTOR CUE: The indicated circuit breaker is in OFF.

FEED TO 71LPERDC2 REACTOR BUILDING EMERGENCY LIGHTING DISTRIBUTION PANEL

-3 of 8-

STEP STANDARD EVALUATION / COMMENT

3. (AOP-49 Att. 3 Page 4 Step 1) Simulates re-positioning FEED TO 71LPEADC1 ADMIN CRITICAL STEP

FEED TO 71LPEADC1 BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT ADMIN BUILDING PANEL to OFF.

EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

4. (AOP-49 Att. 3 Page 4 Step 1) Simulates re-positioning FEED TO 71LPESWDC1 CRITICAL STEP

FEED TO 71LPESWDC1 SCREENWELL EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT SCREENWELL PANEL to OFF.

EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

5. (AOP-49 Att. 3 Page 4 Step 1) Simulates re-positioning FEED TO 71LPE1 ADMIN CRITICAL STEP

FEED TO 71LPE1 ADMIN BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT BUILDING EMERGENCY PANEL to OFF.

LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

-4 of 8-

STEP STANDARD EVALUATION / COMMENT EVALUATOR NOTE: The following steps are performed at 71BCB-2B in the B Battery Charger Room on Admin Building elevation 272.

6. (AOP-49 Att. 3 Page 4 Step 2) Simulates re-positioning 71LPEHB1 FEEDWATER CRITICAL STEP Place the following circuit HEATER BAY EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT breakers in OFF at 71BCB-2B PANEL to OFF.

BATTERY CONTROL BOARD B in B Battery Charger Room: EVALUTOR CUE: The indicated circuit breaker is in OFF.

71LPEHB1 FEEDWATER HEATER BAY EMERGENCY LIGHTING DISTRIBUTION PANEL

7. (AOP-49 Att. 3 Page 4 Step 2) Simulates re-positioning 71LPERDC3 REACTOR CRITICAL STEP

71LPERDC3 REACTOR BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT / UNSAT BUILDING EMERGENCY PANEL to OFF.

LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

8. (AOP-49 Att. 3 Page 4 Step 2) Simulates re-positioning 71LPERW1 & 25 ASP-4 CRITICAL STEP

71LPERW1 & 25 ASP-4 RADWASTE BUILDING EMERGENCY LIGHTING AUX SAT / UNSAT RADWASTE BUILDING SHUTDOWN PANEL to OFF.

EMERGENCY LIGHTING AUX SHUTDOWN PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

-5 of 8-

STEP STANDARD EVALUATION / COMMENT EVALUATOR NOTE: The following steps are performed at panel 94HSC on Turbine Building elevation 252.

9. (AOP-49 Att. 3 Page 8 Step 1) Simulates closing 89H2S-G-05 by rotating valve operator CRITICAL STEP Depressurize main generator clockwise. SAT / UNSAT casing and secure Emergency Seal Oil Pump 94P-13 as follows: EVALUTOR CUE: 89H2S-G-05 has been rotated and has reached a stop.

(AOP-49 Att. 3 Page 8 Step 1.a)

Close the following valves:

89H2S-G-05 (main generator hydrogen 89RO-112 bypass valve)

10. (AOP-49 Att. 3 Page 8 Step Simulates closing 89H2S-G-07 by rotating valve operator CRITICAL STEP 1.a) clockwise. SAT / UNSAT

89H2S-G-07 (main generator hydrogen 89RO-112 outlet isolation valve) EVALUTOR CUE: 89H2S-G-07 has been rotated and has reached a stop.

-6 of 8-

STEP STANDARD EVALUATION / COMMENT

11. (AOP-49 Att. 3 Page 8 Step Simulates opening 89H2S-G-02 by rotating valve operator CRITICAL STEP 1.b) counterclockwise. SAT / UNSAT Open the following valves:

89H2S-G-02 (main EVALUTOR CUE: 89H2S-G-02 has been rotated and has generator casing gas vent reached a stop.

isol valve)

12. (AOP-49 Att. 3 Page 8 Step Simulates opening 89H2S-G-03 by rotating valve operator CRITICAL STEP 1.b) counterclockwise. SAT / UNSAT

89H2S-G-03 (main generator casing gas vent valve) EVALUTOR CUE: 89H2S-G-03 has been rotated and has reached a stop.

EVALUTOR CUE: Main generator casing pressure indicates 0 psig.

13. (AOP-49 Att. 3 Page 8 Step Contacts Control Room to place EMERG SEAL OIL PMP CRITICAL STEP 1.c) 94P-13 control switch in PULL TO LOCK. SAT / UNSAT WHEN main generator casing is depressurized, Request the Control Room place EMERG EVALUTOR CUE: Inform Candidate that the Control Room SEAL OIL PMP 94P-13 has placed 94P-13 control switch in PULL TO LOCK.

control switch in PULL TO LOCK.

EVALUATOR: Terminate the task at this point.

Task Standard: Station Blackout load shedding actions for Main Generator depressurization, Emergency Seal Oil pump, and Battery Control Boards A and B are completed.

-7 of 8-

HANDOUT

A station blackout is in progress.

AOP-49, Station Blackout, Attachment 3 is in progress.

Perform the in-plant actions of AOP-49 Attachment 3 for the Battery Rooms and the Turbine Building.

This is a time critical task.

Your time starts now.

-8 of 8-

James A. Fitzpatrick JOB PERFORMANCE MEASURE S/RO 18-1 NRC K TASK TITLE: Swap CRD Flow Control Valves APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 201001 2.1.20 4.6/4.6 ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

CANDIDATE NAME:

JPM Completion Simulated Performed Location: Plant Simulator DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED

I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-25, Control Rod Drive Hydraulic System III. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. JPM is written with flow control valve 03FCV-19A in-service.

V. EVALUATOR NOTES A. None VI. INITIAL CONDITIONS

The Control Rod Drive Hydraulic System is in operation.

The A CRD Flow Control Valve (03FCV-19A) is currently in service.

The standby CRD Flow Control Valve must be placed in-service in order to verify its ability to operate correctly in automatic.

-2 of 7-

VII. INITIATING CUE Inform the candidate, Swap CRD Flow Control Valves per OP-25 (Control Rod Drive Hydraulic System), Section G.14 (Changing Inservice CRD Flow Control Valves).

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Applicant obtains a controlled copy of OP-25. SAT / UNSAT OP-25.

EVALUATOR: Provide a working copy of OP-25.

2. Select the correct section to Selects Section G.14 of OP-25. SAT / UNSAT perform the task.

EVALUATOR NOTE: All actions are simulated performed on Rx Bldg 272 area west of the West HCUs.

3. (G.14.1) The candidate goes to the Rx Building 272 level to the SAT / UNSAT Establish communication between area West of the West HCUs.

Flow Control Hand Select Station When the candidate states that he/she would establish and the Control Room. communications between the Control Room and the master control station using either the West HCU area Gaitronics or nearby sound powered phone jack or cell phone.

Evaluator Cue: Communications with the Control Room are ESTABLISHED.

-3 of 7-

STEP STANDARD EVALUATION / COMMENT

4. (G.14.2) a. Contacts the Control Room to ensure the controller is SAT / UNSAT Line up CRD FLOW CNTRL in AUTO.

03FIC-301 per the following steps:

Evaluator Cue: Controller is in AUTO.

a. Ensure controller is in AUTO.

b. Adjust controller setpoint to zero b. Requests the Control Room place the CRD flow gpm. controller setpoint to zero gpm Evaluator Cue: The CRD Flow Controller setpoint is at zero gpm.

5. (G.14.3.a) Verifies 03CRD-68B is open by rotating handwheel in SAT / UNSAT Perform the following for the flow the clockwise (closed) direction then rotating control valve to be placed in handwheel in the counterclockwise (open) direction.

service:

a. Verify open inlet isolation valve: Evaluator Cue: Valve 03CRD-68B is open.

03CRD-68B (CRD water 03FCV-19B inlet isol valve)

6. (G.14.3.b) Opens 03CRD-69B by rotating handwheel full CRITICAL STEP Slowly open outlet isolation valve: counterclockwise. SAT / UNSAT 03CRD-69B (CRD water 03FCV-19B outlet isol valve) Evaluator Cue: 03CRD-69B is open.

-4 of 7-

STEP STANDARD EVALUATION / COMMENT

7. (G.14.4) Closes 03CRD-69A by rotating handwheel full CRITICAL STEP Close outlet isolation valve for flow clockwise. SAT / UNSAT control valve to be removed from service.

03CRD-69A Evaluator Cue: 03CRD-69A is closed.

(CRD water 03CRD-69A outlet isolation valve).

8. (G.14.5) Places AUTO-MAN knob to AUTO at 03HSS-245B. CRITICAL STEP Place AUTO-MAN select knob in SAT / UNSAT AUTO for inservice flow control Evaluator Cue: AUTO-MAN knob is in AUTO.

valve:

AUTO-MAN select knob at 03HSS-245B

9. G.14.6 Places AUTO-MAN knob to MAN at 03HSS-245A. CRITICAL STEP Ensure AUTO-MAN select knob is SAT / UNSAT in MAN for standby flow control valve.

Evaluator Cue: AUTO-MAN knob is in MAN.

AUTO-MAN select knob at 03HSS-245A

-5 of 7-

STEP STANDARD EVALUATION / COMMENT

10. (G.14.7) Requests Control Room slowly raises setpoint on SAT / UNSAT Slowly raise setpoint on CRD 03FIC-301 to 59-61 gpm.

FLOW CNTRL 03FIC-301 to establish 59 to 61 gpm on 03FI- Evaluator Cue: 03FIC-301 is set to 60 gpm; flow is 60 310. gpm and steady

11. (G.14.8) Requests Control Room verifies parameters. SAT / UNSAT Verify normal operating values on the following indicators at panel 09-5:

Evaluator Cue: All parameters on the 09-5 panel are

CHG WTR PRESS 03PI-302: satisfactory.

BETWEEN 1390 and 1580 psig, not to exceed 1670 psig

DRV WTR DIFF PRESS 03DPI-303: 260 to 270 psid

CLG WTR DIFF PRESS 03DPI-304: approximately 10 to 26 psid

DRV WTR FLOW 03FI-305:

zero when no CRD is being driven

FLOW 03FI-306: 59 to 61 gpm EVALUATOR: Terminate the task at this point.

Task Standard: The B CRD Flow Control valve is in service, in automatic at 60 gpm and the A CRD FCV is in manual and valved out of service.

-6 of 7-

HANDOUT Initial Conditions:

The Control Rod Drive Hydraulic System is in operation.

The A CRD Flow Control Valve (03FCV-19A) is currently in service.

The standby CRD Flow Control Valve must be placed in-service in order to verify its ability to operate correctly in automatic.

Initiating Cue:

Swap CRD Flow Control Valves per OP-25 (Control Rod Drive Hydraulic System), Section G.14 (Changing Inservice CRD Flow Control Valves).

-7 of 7-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 18-1 NRC EXAMINATION SCENARIO 1 TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 1 SCENARIO NUMBER: NRC 1 PATH: STAND ALONE Validation: ___________________ Training: ___________________ Operations: ___________________

CANDIDATES CRS ATC BOP LOI 18-1 NRC Examination Scenario 1 Page 1 of 30

A. TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 1 B. SCENARIO SETUP:

1. IC-221

2. Special Instructions:

a. The plant is operating at approximately 93% power.

b. RBCLC pump A is out of service for maintenance.

c. SRV A is inoperable.

d. Line 3 is out of service and ready to be restored.

3. Preset Conditions:

0

<ACTION>Insert malfunction ED44 on event 1</ACTION>

<DESCRIPTION>LOSS OF 115KV SYSTEM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AD06:C on event 2</ACTION>

<DESCRIPTION>RX PRESS RELIEF VALVE (2E-RV-71C) INADVERTENTLY OPENS</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote AD07:C to LOCAL on event 25</ACTION>

<DESCRIPTION>&aposC&apos SRV ISOLATION SWITCH AT REMOTE PANEL 25ASP-5</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote AD02:C to OUT on event 26</ACTION>

<DESCRIPTION>&aposC&apos SRV FUSE PULL OUT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction FW05:A on event 3</ACTION>

LOI 18-1 NRC Examination Scenario 1 Page 2 of 30

<DESCRIPTION>RX FEEDWTR PMP A HIGH VIBRATION</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction FW01:A on event 16</ACTION>

<DESCRIPTION>RX FEEDWTR PMP A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MS02:A to 2.50000 in 90 on event 4</ACTION>

<DESCRIPTION>(MSL A) STM LEAKAGE INSIDE PRIM CONTNMT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR15:A after 420 to 32.00000 in 600 on event 5</ACTION>

<DESCRIPTION>COOLANT (A) LEAKAGE INSIDE PRIMARY CONTAINMENT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction HP02 after 600 on event 5</ACTION>

<DESCRIPTION>HPCI TURBINE TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RH55 to OUT on event 17</ACTION>

<DESCRIPTION>10-MOV-38A BREAKER RACKOUT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RH56 to OUT on event 18</ACTION>

<DESCRIPTION>10-MOV-38B BREAKER RACKOUT</DESCRIPTION>

</ITEM>

0

<ACTION>Event Events/18-1 NRC/Scenario 1.evt</ACTION>

LOI 18-1 NRC Examination Scenario 1 Page 3 of 30

</ITEM>

0

<ACTION>Insert malfunction SW09:A</ACTION>

<DESCRIPTION>RBCLC PUMP A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AD04:A</ACTION>

<DESCRIPTION>RX PRESS RELIEF VALVE (2E-RV2-71A) SOLENOID FAILURE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert override AD-ZLO271A(1) to OFF</ACTION>

<DESCRIPTION>DEPRESSURIZATION 2-71A (GREEN)</DESCRIPTION>

</ITEM>

</SCHEDULE>

<EVENT>

<TRIGGER id="16" description="fwvrfpt(1)&gt8">fwvrfpt(1)&gt8</TRIGGER>

</EVENT>

LOI 18-1 NRC Examination Scenario 1 Page 4 of 30

C. SCENARIO

SUMMARY

The scenario will begin at approximately 93% power with RBCLC pump A out of service. SRV A is inoperable. Line 3 is out of service and ready to be restored. The crew will begin by restoring Line 3 to service per OP-44. Then, the crew will raise Reactor power using Recirculation flow.

During power ascension, all 115KV power will be lost. The crew will execute AOP-72. The SRO will determine the Technical Specification impact.

SRV C will inadvertently open. The crew will execute AOP-36. The crew will take action to close the SRV.

The SRO will determine the Technical Specification impact.

High vibrations will develop on Feedwater pump A. The crew will attempt to mitigate the vibrations by lowering Reactor power. Once vibrations exceed 6 mils, the crew will trip Feedwater pump A. If the crew does not trip Feedwater pump A by approximately 8 mils, it will spuriously trip.

After the plant is stabilized, a steam leak inside the Drywell develops. The crew will insert a manual Reactor scram due to rising Drywell pressure. The crew will control Reactor water level with HPCI and/or RCIC due to the loss of all Condensate and Feedwater, since 115KV power is unavailable from the earlier event.

Approximately 7 minutes after the scram, the steam leak will degrade further into a significant loss of coolant accident. Rising inventory losses will require additional injection to the Reactor. Degrading Containment parameters will require Torus and then Drywell sprays. The first Torus spray valve attempted will fail to open, requiring the crew to switch to the other RHR loop for Torus spray.

Approximately 10 minutes after the scram HPCI will trip. The crew will maximize other injection systems (RCIC, CRD, SLC), but will be unable to keep up with lowering Reactor water level. The crew will execute the Alternate Level Control leg of EOP-2 to attempt to maintain Reactor water level above the Top of Active Fuel (zero inches).

Due to lowering Reactor water level and insufficient high pressure injection sources, the crew will perform an Emergency Depressurization to allow low pressure injection sources to restore and\or maintain Reactor water level >0 inches.

The scenario will be terminated when all control rods are inserted, Emergency Depressurization is in progress, and Reactor water level is being controlled above 0 inches.

LOI 18-1 NRC Examination Scenario 1 Page 5 of 30

Shift Turnover The plant is operating at approximately 93% power.

RBCLC pump A is out of service for maintenance.

SRV A is inoperable.

Line 3 is out of service and ready to be restored.

When you take the shift:

1. Restore Line 3 to service per OP-44 section G.9. The procedure is in progress up to step G.9.12.

2. Raise Reactor power using Recirculation flow per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 1 Page 6 of 30

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Critical Task #2: Given a coolant leak, a loss of high pressure injection system and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF),

the crew will initiate actions for an Emergency RPV Depressurization, in accordance with EOP-2. Reactor water level must be restored and maintained above TAF within 30 minutes of lowering below TAF.

D. TERMINATION CUES:

All control rods are inserted

Emergency Depressurization is in progress

Reactor water level is being controlled above 0 LOI 18-1 NRC Examination Scenario 1 Page 7 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All allow no more than five

Walkdown the control panels and assume the watch minutes for panel walkdown Event 1 SRO

Perform Crew Brief Restore Line 3 to Service

Direct BOP to restore Line 3 to service per OP-44 G.9 starting at step G.9.12:

BOP

Restore Line 3 to service per OP-44 G.9, starting at step G.9.12:

Verify voltage is 117 to 121 KILOVOLTS on the following voltmeters:

o LHH-FITZ 115 KV LINE 3 o NMP-FITZ 115 KV LINE 4

Verify frequency is approximately 60 Hz on both incoming 115 KV lines by selecting input selector switch for 115 KV FREQ meter to the following positions:

o POS 1 LHH-FITZ LINE 3 o POS 2 NMP-FITZ LINE 4 LOI 18-1 NRC Examination Scenario 1 Page 8 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY

Verify RECLOSER CUTOFF BKR 10022 switch is in OFF

Obtain permission from Power Control to close FitzPatrick Lighthouse 3 115 KV Line Breaker 71BRK-10022.

Role Play:

Place 115 KV BKR 10022 SYNCH SW switch in ON.

If contacted as Power

Verify voltage is matched on NON-EMERG BKRS INCOMING Control, give permission to and RUNNING voltmeters.

close Breaker 10022 and to

Verify frequency is in phase on NON-EMERG BKRS activate auto-reclosure. SYNCHROSCOPE.

Close LHH-FITZ 115 KV LINE 3 BKR 10022.

Verify voltage is 117 to 121 KILOVOLTS on the following voltmeters:

o LHH-FITZ 115 KV LINE 3(EPIC-A-1570) o NMP-FITZ 115 KV LINE 4 (EPIC-A-1569)

Place 115 KV BKR 10022 SYNCH SW switch in OFF.

Obtain permission from Power Control to activate auto-reclosure for FitzPatrick Lighthouse Line 3 115 KV Breaker 71BRK-10022.

Place RECLOSER CUTOFF BKR 10022 switch in ON.

Report 115 KV System status to the following parties:

o Power Control o Nine Mile Point Unit One Control Room LOI 18-1 NRC Examination Scenario 1 Page 9 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Event 2 SRO

Direct ATC to raise power to 98% with Recirc flow Raise Reactor Power with

Provide oversight of reactivity manipulation Recirculation Flow ATC

Raise Recirc flow alternately with RWR MG A(B) SPEED CNTRL

Monitor APRMs, CTP, Recirc flow, Reactor water level, Core Map LOI 18-1 NRC Examination Scenario 1 Page 10 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Event 3 BOP / ATC

Recognize / report loss of Lines 3 and 4 On Lead Examiner Cue:

ACTIVATE TRIGGER 1 Loss of Offsite Power SRO

Acknowledge report

Enter AOP-72 (115KV)

Determine Technical Specification 3.8.1 Condition C must be entered (restore one offsite circuit to operable within 7 days)

Brief crew on impact of plant shutdown without offsite power Role Play: BOP

Execute AOP-72 (115KV)

When contacted as National o Notify the following of electrical status and request Grid, acknowledge that rapid restoration of 115 KV line voltage:

Lines 3 and 4 have de-o National Grid Power Control energized and are investigating. o Nine Mile Point Unit One Control Room o Notify Security there has been an unplanned loss or When contacted as NMP, degradation of the 115 KV system acknowledge report.

o Monitor 115 KV System parameters o May dispatch Operator to investigate switchyard When contacted as Security, report that Security will LOI 18-1 NRC Examination Scenario 1 Page 11 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY investigate the switchyard.

Event 4 BOP \ ATC

Recognize / report annunciators:

On Lead Examiner Cue:

o 09-4-1-16, SRV Leaking ACTIVATE TRIGGER 2 o 09-4-2-6, SRV Sonic Mon Alarm Hi SRV C Inadvertently Opens

Recognize / report SRV C open

Recognize / report low DW/Torus D/P SRO

Acknowledge report

Enter AOP-36, Stuck Open Relief Valve Note: The lead examiner may delay the closing of

If Torus water temperature exceeds 95oF or Torus water SRV C to allow sufficient level exceeds 14.0 feet, enter EOP-4, Primary Containment heatup of the Torus to drive Control placing Torus Cooling in

May enter AOP-32 (Unplanned Power Change) service (Torus temp of 90-95oF).

Direct initiation of Torus Cooling

Determine SRV C is inoperable and is an ADS valve per Technical Specification 3.5.1

Enter TS LCO 3.5.1.E (14 day LCO for ADS)

Enter TS 3.6.2.4.A (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months LCO for DW/Torus D/P)

LOI 18-1 NRC Examination Scenario 1 Page 12 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Role Play: BOP

Execute AOP-36 When directed to place SRV o Identify open SRV C isolation switch in LOCAL, wait 2 minutes, insert o Determine annunciator 09-4-2-37 is NOT in alarm Trigger 25, wait o Determine annunciator 09-4-3-3 is NOT in alarm approximately 15 seconds, then report task completion. o Cycle SRV C control switch at panel 09-4 o Direct Operator to place SRV C isolation switch in Role Play: LOCAL at panel 25ASP-5 When directed to remove o Determine SRV C closed SRV C fuses, wait 1 minute, o Direct Operator to remove the four control power insert Trigger 26, then report fuses for SRV C at panel 09-45 task completion.

o Direct Operator to place SRV C isolation switch in REMOTE at panel 25ASP-5 Role Play:

When directed to place SRV o Monitor Torus water temperature C isolation switch in

May direct Torus vent REMOTE, wait 1 minute, re-insert remote AD07:C in

Initiate Torus Cooling per OP-13B posted attachment:

REMOTE, wait LOI 18-1 NRC Examination Scenario 1 Page 13 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY approximately 15 seconds, o Ensure at least one of the RHR pumps is running then report task completion.

o Open RHR TEST TORUS CLG & SPRAY 10MOV-39A(B) o Throttle RHR TEST & TORUS CLG 10MOV-34A(B) to Role Play:

establish desired/flow If Torus vent directed, wait 2 minutes, start a SBGT fan in o WHEN RHR Loop A(B) flow is GREATER THAN 1500 the simulator, then run gpm, ensure closed MIN FLOW VLV 10MOV-16A(B) applicable schedule. o Establish RHRSW flow and temperature control

Initiate RHRSW per OP-13C posted attachment:

BOP cont.

Establish RHRSW flow and temperature control:

o Start one of the RHRSW pumps o Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm o Start the second RHRSW pump if desired o Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 5000 to 8000 gpm o Close HX A(B) BYP VLV 10MOV-66A(B)

LOI 18-1 NRC Examination Scenario 1 Page 14 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Event 5 ATC / BOP

Recognize / report EPIC alarms SAT / UNSAT / NA On Lead Examiner Cue:

Recognize / report annunciator 09-6-4-11, RFPT A VIB HI ACTIVATE TRIGGER 3

Recognize / report rising Feedwater pump A vibrations Feedwater Pump Vibration and Delayed Pump Trip SRO

Acknowledge report SAT / UNSAT / NA Note:

Direct ARP response The ARP directs tripping Feedwater pump A if

May direct emergency power reduction with Recirculation vibration reaches 6 mils. flow (43-45 Mlbm/hr) and/or CRAM rods There is no automatic trip

Direct trip of Feedwater pump A on vibration, however the pump will spuriously trip in

Enter AOP-41 (Feedwater Malfunction)

LOI 18-1 NRC Examination Scenario 1 Page 15 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY this scenario if vibration

May enter AOP-8 (Unexpected Change in Core Flow) reaches ~8 mils.

Note: BOP

Execute ARP 09-6-4-11 SAT / UNSAT / NA Recirculation pumps will o Monitor vibration level and trend likely runback to the 44%

limiter due to only one o When vibration approaches/exceeds 6 mils, trip Feedwater Feedwater pump operating pump A and Reactor water level

Coordinate with ATC to lower Reactor power with Recirculation lowering to 196.5. flow, as required / directed Role Play:

If dispatched to investigate, wait 2 minutes, then report that Feedwater pump A is vibrating, but there is no obvious cause.

Note: ATC

Coordinate with BOP to lower Reactor power with CRAM SAT / UNSAT / NA Following the trip of rods, as required / directed Feedwater pump A, Reactor

Monitor for thermal-hydraulic instabilities (THI) power will likely stabilize between 65-70% power. o May select control rod(s) to monitor LPRMs The crew may decide to

Monitor Turbine vibrations lower Reactor power further by inserting CRAM rods, since during a startup the second Feedwater pump is started prior to exceeding 50% power.

LOI 18-1 NRC Examination Scenario 1 Page 16 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY Role Play:

If the crew is not taking action to lower Reactor power by inserting CRAM rods, when crew informs Ops Management or Reactor Engineering of event, direct crew to lower Reactor power to 50% using RAP-7.3.16.

Event 6 ALL

Recognize / report rising Drywell pressure and On Lead Examiner Cue: temperature ACTIVATE TRIGGER 4

Recognize / report EPIC alarm 358, DW Cam Hi Rad Steam Leak in Drywell SRO

Acknowledge reports Note:

Direct Reactor scram LOI 18-1 NRC Examination Scenario 1 Page 17 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY If Torus vent is in service

Enter AOP-1 (Reactor Scram) and it is desired to speed up this event, modify the

Enter AOP-39 (Loss of Coolant) severity of malfunction

Enter EOP-2 (RPV Control) on low Reactor water level and MS02:A to 3.5. high Drywell pressure (as they occur)

Enter EOP-4 (Primary Containment Control) on high Drywell pressure and high Drywell temperature (as they occur)

Direct Reactor water level controlled 180-220 using HPCI, RCIC, CRD, and/or SLC

Direct Reactor pressure controlled 800-1000# using SRVs

Direct Control Room and Relay Room Ventilation isolated per OP-55B Section G within 30 minutes

Direct TSC filtered ventilation started per Section D of OP-59B within 60 minutes

May direct Core Spray and RHR injection prevented per EP-5 ATC

Enter AOP-1

Depress MANUAL SCRAM A and MANUAL SCRAM B pushbuttons

Place RX MODE switch in SHUTDOWN LOI 18-1 NRC Examination Scenario 1 Page 18 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Ensure Main Turbine is tripped

May control Reactor pressure on SRVs

May begin Reactor depressurization BOP

Enter AOP-1

Control Reactor water level 180-220 using HPCI, RCIC, CRD, and/or SLC

Control Reactor pressure on SRVs

May begin Reactor depressurization BOP

If needed to manually start HPCI, then per OP-15:

o Ensure reset RPV high level light LOI 18-1 NRC Examination Scenario 1 Page 19 of 30

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION INSTRUCTOR ACTIVITY o Ensure desired suction path open o Ensure open 23MOV-16 o Ensure running 23P-140 o Perform the following steps without unnecessary delay:

o If 09-3-3-28 is in, then depress 23A-S17 o Ensure running 23P-150 o Ensure open 23MOV-19 o Adjust thumbwheel for desired flow

If needed to manually start RCIC, then per OP-19:

o Verify Annunciator 09-4-0-32 RCIC LOGIC RX LVL HI is clear o Verify CST SUCT VLV 13MOV-18 open o Start VAC PMP 13P-3 o Open OIL CLR WTR SUPP 13MOV-132 o Perform the following without unnecessary delay:

o Open TURB STM SUPP VLV 13MOV-131 o Open INJ VLV 13MOV-21 o Adjust RCIC FLOW CNTRL 13FIC-91 to desired flow rate LOI 18-1 NRC Examination Scenario 1 Page 20 of 30

Events 7, 8, & 9 All

Recognize / report rising Drywell pressure and lowering Loss of Coolant Accident; Reactor water level First Torus Spray Valve

Recognize / report trip of HPCI (~10 min after scram)

Used Fails to Open; HPCI Trips Note:

The loss of coolant accident automatically initiates ~7 minutes after the Reactor scram. The HPCI trip automatically initiates ~10 minutes after the Reactor scram.

Critical Task #1 Given a coolant leak inside the Containment, the crew will spray the Pass / Fail Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Spray the Drywell.

Critical Task #1 Standard:

Critical Task #2 Given a coolant leak, a loss of high pressure injection systems, and the Pass / Fail inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization in accordance with EOP-2. Reactor water level must be restored and maintained >TAF within 30 minutes of lowering below TAF.

LOI 18-1 NRC Examination Scenario 1 Page 21 of 30

Open at least 5 SRVs.

Critical Task #2 Standard:

SRO

Acknowledge reports

Re-enter EOP-2 (RPV Control) on low Reactor water level, as necessary

When Primary Containment pressure exceeds 2.7 psig and before Torus pressure exceeds 15 psig, direct initiation of Torus Spray

When Torus pressure exceeds 15 psig, direct Drywell Critical Task #1 spray

Determine Reactor water level cannot be maintained above 0

Enter Alternate RPV Level Control leg of EOP-2

Direct override of ADS

Direct SLC injection, if not done previously Critical Task #2

When Reactor water level reaches 0, enter Emergency RPV Depressurization leg of EOP-2

Direct opening all ADS valves

Direct opening two additional SRVs

Direct Reactor water level restored and maintained 180-220 using Core Spray and/or LPCI

As time allows, directs re-start of Drywell spray ATC / BOP

Recognize / report trip of HPCI

Attempt to control Reactor water level 180-220 using RCIC, CRD, and/or SLC LOI 18-1 NRC Examination Scenario 1 Page 22 of 30

Recognize / report inability to maintain Reactor water level with available injection systems ATC / BOP

Initiate Torus spray:

Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring return to normal Note:

Verify white SPRAY PERM 10A-DS67A(B) light is on The first Torus spray valve (10MOV-38A(B)) attempted Ensure available RHR pumps in RHR Loop A(B) are will fail to open. The crew running will then spray with the Open RHR TEST TORUS CLG & SPRAY 10MOV-39A(B) other RHR system.

Throttle TORUS SPRAY INBD VLV 10MOV-38A(B) to establish desired torus spray flow rate Booth Operator:

Recognize / report failure of 10MOV-38A(B) and switch Once the first Torus spray to spraying with other RHR loop valve (10MOV-38A(B)) has failed to open, delete the WHEN RHR Loop A(B) flow is GREATER THAN 1500 remote on the other Torus gpm, ensure closed MIN FLOW VLV 10MOV-16A(B) spray valve (RH55/56). Throttle RHR TEST & TORUS CLG 10MOV-34A(B) to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop A(B) flow with one RHR pump operating or > 13,000 gpm RHR Loop A(B) flow with two RHR pumps operating

Establish RHRSW flow and temperature control:

Establish RHRSW flow and temperature control:

Start one of the RHRSW pumps Note:

Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-Once the crew has sprayed 89A(B) to establish 2500 to 4000 gpm LOI 18-1 NRC Examination Scenario 1 Page 23 of 30

the Drywell, the lead Start the second RHRSW pump if desired examiner may direct tripping HPCI earlier than Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-previously programmed to 89A(B) to establish 2500 to 4000 gpm per RHRSW move the scenario along. pump Additionally, the lead

IF drywell or torus sprays are in service, THEN establish examiner may direct 4000 gpm per RHRSW pump ramping the coolant leak faster than previously

Close HX A(B) BYP VLV 10MOV-66A(B) programmed.

LOI 18-1 NRC Examination Scenario 1 Page 24 of 30

ATC / BOP

Ensure Recirc pumps tripped

Ensure Drywell Cooling fans tripped

Initiate Drywell spray: Critical Task #1

Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring return to normal Verify white SPRAY PERM 10A-DS67A(B) light is on Ensure available RHR pumps in RHR Loop A(B) are running Open DW SPRAY OUTBD VLV 10MOV-26A(B)

Throttle DW SPRAY INBD VLV 10MOV-31A(B) to establish desired drywell spray flow rate

Override ADS:

Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on

Initiate SLC injection, if not done previously

Verify isolations per AOP-15

As time permits, execute AOP-39 (Loss of Coolant)

LOI 18-1 NRC Examination Scenario 1 Page 25 of 30

Critical Task #2 ATC / BOP

Open all ADS valves and two additional SRVs

Restore and maintain Reactor water level 180-220 using available injection systems

Control LPCI injection by throttling 10MOV-27A(B)

Control CS injection by throttling 14MOV-12A(B)

Secure RHR pumps if needed Termination Criteria:

All control rods are inserted, Emergency Depressurization is in progress and Reactor water level is being controlled above 0 inches.

LOI 18-1 NRC Examination Scenario 1 Page 26 of 30

ATTACHMENT 1 Shift Turnover The plant is operating at approximately 93% power.

RBCLC pump A is out of service for maintenance.

SRV A is inoperable.

Line 3 is out of service and ready to be restored.

When you take the shift:

1. Restore Line 3 to service per OP-44 section G.9. The procedure is in progress up to step G.9.12.

2. Raise Reactor power using Recirculation flow per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 1 Page 27 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific RWR control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp Raise power to 98%

1 RTP

- - - RWR NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI 18-1 NRC Examination Scenario 1 Page 28 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific RWR control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp Raise power to 98%

1 RTP

- - - RWR NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI 18-1 NRC Examination Scenario 1 Page 29 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific RWR control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp Raise power to 98%

1 RTP

- - - RWR NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps UNIT SUPERVISOR LOI 18-1 NRC Examination Scenario 1 Page 30 of 30

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 18-1 NRC EXAMINATION SCENARIO 2 TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: NRC 2 PATH: STAND ALONE Validation: ___________________ Training: ___________________ Operations: ___________________

CANDIDATES CRS ATC BOP LOI 18-1 NRC Examination Scenario 2 Page 1 of 30

A. TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

1. IC-222

2. Special Instructions:

a. The plant is operating at approximately 70% power.

b. RBCLC pump A is out of service for maintenance.

c. Feedwater level column is selected to A.

3. Preset Conditions:

0

<ACTION>Insert malfunction RD03:A to 0 on event 1</ACTION>

<DESCRIPTION>CRD FLOW CONTROL VALVE FAILURE (A)</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RD09 to OPEN on event 21</ACTION>

<DESCRIPTION>3-68B, 3-69B FCV-19B ISOLATING VALVES</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RD12 to B on event 22</ACTION>

<DESCRIPTION>3-FCV-19A OR 3-FCV-19B SELECT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RD08 to CLOSE on event 23</ACTION>

<DESCRIPTION>3-68A, 3-69A FCV-19A ISOLATING VALVES</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR23:B to 0 on event 2</ACTION>

<DESCRIPTION>RECIRCULATION FLOW UNIT B FAILS</DESCRIPTION>

</ITEM>

LOI 18-1 NRC Examination Scenario 2 Page 2 of 30

0

<ACTION>Insert malfunction SW01:B on event 3</ACTION>

<DESCRIPTION>LOSS OF RBCLC FLOW TO RECIRCULATION PUMP B</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RX03 to 15.00000 in 120 on event 4</ACTION>

<DESCRIPTION>CORE THERMAL HYDRAULIC INSTABILITIES</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD22:A to 100.00000</ACTION>

<DESCRIPTION>WEST SDV HYDRAULIC LOCK</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD22:B to 100.00000</ACTION>

<DESCRIPTION>EAST SDV HYDRAULIC LOCK</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction SL01:A on event 16</ACTION>

<DESCRIPTION>STANDBY LIQUID CONTROL PUMP 11P-2A BREAKER TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction SL01:B on event 17</ACTION>

<DESCRIPTION>STANDBY LIQUID CONTROL PUMP 11P-2B BREAKER TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Event Events/18-1 NRC/Scenario 2.evt</ACTION>

</ITEM>

LOI 18-1 NRC Examination Scenario 2 Page 3 of 30

0

<ACTION>Insert malfunction SW09:A</ACTION>

<DESCRIPTION>RBCLC PUMP A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RP21:A1 to IN on event 26</ACTION>

<DESCRIPTION>RPS JUMPER - A1 LOGIC - 5A-K14A &amp 5A-K14E</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RP21:A2 to IN on event 26</ACTION>

<DESCRIPTION>RPS JUMPER - A2 LOGIC - 5A-K14C &amp 5A-K14G</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RP21:B1 to IN on event 26</ACTION>

<DESCRIPTION>RPS JUMPER - B1 LOGIC - 5A-K14B &amp 5A-K14F</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RP21:B2 to IN on event 26</ACTION>

<DESCRIPTION>RPS JUMPER - B2 LOGIC - 5A-K14D &amp 5A-K14H</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RP20 to TEST on event 25</ACTION>

<DESCRIPTION>ARI TEST SWITCH 43SSARI</DESCRIPTION>

</ITEM>

</SCHEDULE>

<EVENT>

<TRIGGER id="30" description="SCRAM full scram">(zlo5ads8a == 0) &amp&amp (zlo5ads8b ==

0)</TRIGGER>

LOI 18-1 NRC Examination Scenario 2 Page 4 of 30

</EVENT>

LOI 18-1 NRC Examination Scenario 2 Page 5 of 30

C. SCENARIO

SUMMARY

The scenario will begin at approximately 70% power with RBCLC pump A out of service for maintenance.

The crew will begin the shift by swapping Feedwater level columns from A to B per OP-2A.

Following completion of the test, the crew will perform a control rod pattern adjustment. During the control rod movements, the in-service CRD flow control valve will fail closed. This will lower CRD drive water pressure and prevent moving control rods. The crew will swap CRD flow control valves, re-establish normal CRD parameters, and then continue control rod moves.

Recirculation flow unit B will fail downscale. This will result in a rod block and half scram. The SRO will determine the Technical Specification impact. The crew will bypass Recirculation flow unit B and reset the half scram.

All RBCLC flow to Recirculation pump B will isolate. This will cause multiple high temperature alarms. If left unmitigated, this will cause degradation of both Recirculation pump B seals and loss of coolant into the Drywell. The crew will secure Recirculation pump B. If damage has occurred to both pump seals, the crew will also isolate Recirculation pump B to stop the loss of coolant. The crew will execute AOP-8 due to the reduction in core flow. The SRO will determine the Technical Specification impact.

A thermal hydraulic instability will develop. The crew will execute AOP-32 for unplanned power changes.

The Reactor power oscillations will exceed the scram criteria in AOP-32. The crew will attempt insert a manual scram.

Following the manual scram attempt, all control rods do not fully insert (hydraulic ATWS). Reactor power will initially be approximately 40-50%. The crew will execute EOP-3 (Failure to Scram). The ATWS is complicated due to the first SLC pump started trips shortly after start. Execution of EOP-3 will eventually result in Reactor power being reduced to <2.5%.

The scenario will be terminated when Reactor power is downscale on APRMs, all control rods are inserted, and Reactor water level is controlled above 0.

LOI 18-1 NRC Examination Scenario 2 Page 6 of 30

Shift Turnover The plant is operating at approximately 70% power.

RBCLC pump A is out of service for maintenance.

When you take the shift:

1. Swap Feedwater level columns from A to B per OP-2A section G.27. It is desired to place Feedwater level control in manual during the swap and then restore it to automatic.

2. Perform a control rod pattern adjustment per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 2 Page 7 of 30

Critical Tasks/Standards Critical Task #1: Given a failure to scram with Reactor power above 2.5%, the crew will lower reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC and CRD

Tripping Recirculation pumps

Injecting boron The Reactor power reduction must be initiated within five minutes of the start of the failure to scram.

Critical Task #2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3. All insertable control rods must be inserted within one hour of the start of the failure to scram.

D. TERMINATION CUES:

Reactor power is downscale on APRMs

All control rods are inserted LOI 18-1 NRC Examination Scenario 2 Page 8 of 30

Reactor water level is controlled above 0 LOI 18-1 NRC Examination Scenario 2 Page 9 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All

Walkdown the control panels and assume the watch allow no more than five minutes for panel walkdown Event 1 SRO

Direct BOP to swap Feedwater level columns per OP-2A Swap Feedwater Level Columns BOP

Obtain OP-2A Section G.27

Place Feedwater level control in MANUAL per Section G.40.2 o Balance RX WTR LVL CNTRL 06LC-83 controller o Place RX WTR LVL CNTRL 06LC-83 controller in MAN

Place RX WTR LVL COLUMN SEL 06-S1 switch in B-LEVEL

Observe RPV water level stable

Place Feedwater level control in AUTO per Section G.40.7 o Balance RX WTR LVL CNTRL 06LC-83 controller by adjusting SP ADJUST knob o Place RX WTR LVL CNTRL 06LC-83 controller in BAL LOI 18-1 NRC Examination Scenario 2 Page 10 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 2 SRO

Direct ATC to position control rods per provided Perform Control Rod Pattern instructions Adjustment

Provide oversight of reactivity manipulation Note: ATC

While withdrawing control rods, monitor the following:

The reactivity instructions o Nuclear instrumentation require moving control rods 18-35, 34-35, 34-19, and 18- o Control rod position indication 19 from 04 to 08.

Ensure ROD SEL PWR switch is in ON

Ensure control rod to be moved is selected by depressing rod select pushbutton on ROD SEL matrix, if necessary

Verify the following:

o Select pushbutton is brightly backlit o Control rod indicating light is on o ROD OUT PERM light is on

Place ROD MOVEMENT CNTRL switch to OUT NOTCH, spring return to OFF

Verify control rod latches in the expected even numbered position before ROD SETTLE light goes off

Verify ROD SETTLE light is off

Repeat as necessary LOI 18-1 NRC Examination Scenario 2 Page 11 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 3 ATC / BOP

Recognize / report CRD flow control valve failure CRD Flow Control Valve Fails Closed (on Lead Examiner Cue:

ACTIVATE TRIGGER 1)

Role Play: SRO

Acknowledge CRD flow control valve failure If dispatched to investigate

Direct swapping CRD flow control valves per OP-25 CRD flow control valves, report that it appears flow control valve A is lined up but failed closed.

Role Play: ATC

Swap CRD flow control valves per OP-25 section G.14 When directed to un-isolate

Establish communication between Flow Control Hand CRD flow control valve B, Select Station and the Control Room wait 1 minute, insert Trigger 21, then report task

Line up CRD FLOW CNTRL 03FIC-301 per the following completion. steps:

o Ensure controller is in AUTO When directed to select CRD o Adjust controller setpoint to zero gpm flow control valve B (AUTO-MAN select knob at 03HSS-

Direct operator to verify open inlet isolation valve 03CRD-245B in AUTO), wait 1 68B (CRD water 03FCV-19B inlet isol valve) minute, insert Trigger 22,

Direct operator to slowly open outlet isolation valve then report task completion. 03CRD-69B (CRD water 03FCV-19B outlet isol valve)

Direct operator to close outlet isolation valve for 03FCV-LOI 18-1 NRC Examination Scenario 2 Page 12 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION When directed to isolate 19A CRD flow control valve A,

Direct operator to place AUTO-MAN select knob at 03HSS-wait 1 minute, insert Trigger 245B in AUTO 23, then report task completion.

Direct operator to ensure AUTO-MAN select knob is in If all of these orders are MAN for 03FCV-19A given at once, wait 2 minutes, insert all three ATC cont.

Triggers, then report task

Slowly raise setpoint on CRD FLOW CNTRL 03FIC-301 to completion. establish 59 to 61 gpm on 03FIC-301 or 03FI-310

Verify normal operating values on the following indicators at panel 09-5:

o CHG WTR PRESS 03PI-302: BETWEEN 1390 and 1580 psig, not to exceed 1670 psig o DRV WTR DIFF PRESS 03DPI-303: 260 to 270 psid o CLG WTR DIFF PRESS 03DPI-304: approximately 10 to 26 psid LOI 18-1 NRC Examination Scenario 2 Page 13 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 4 ATC

Recognize / report multiple annunciators, including 09-5 Recirc Flow Unit Failure 25, FLOW REF OFF NORM (on Lead Examiner Cue:

Recognize / report APRMs B, D, and F indicate normally ACTIVATE TRIGGER 2) but have an upscale trip

Recognize / report half scram SRO

Acknowledge report

Direct ARP response

Direct bypassing Recirc flow unit B per OP-16

Direct reset of half scram

Determine one of two required channels of Technical Specification Table 3.3.1.1-1 Function 2b is not operable with an inoperable Recirc flow unit

Determine Technical Specification 3.3.1.1 Condition A must be entered (place channel in trip or place associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

Determine one of four required channels of TRM Table T3.3.B-1 Function 1b is not operable with an inoperable Recirc flow unit (prior to bypassing only)

Determine TRM 3.3.B Condition A must be entered (restore inoperable channel within 7 days) (prior to bypassing only)

LOI 18-1 NRC Examination Scenario 2 Page 14 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC

Coordinate with BOP to bypass Recirc flow unit B per OP-16 Section E.21:

o Place RWR FLOW UNIT BYP switch in B o Verify the following FLOW UNIT indications:

Associated BYPASS indicating light is on Associated UPSC OR INOP light is off Associated COMPAR light is off o Verify BYPASS light is off for other flow unit channel on same side o Verify white BYP light in on at top of panel 09-14 for FLOW UNIT B o IF a flow unit is declared inoperable, THEN one of the two required APRM Neutron Flux-High (flow biased)

Channels in the associated trip system must be considered inoperable o Coordinate with BOP to place switch S-1 on FLOW UNIT B to INT TEST at panel 09-14

Reset half scram per ARP:

o Place RX SCRAM RESET switch to GROUP 2 & 3, then to GROUP 1 & 4, spring return to NORM o Verify RPS B SCRAM GROUPS 1, 2, 3, and 4 lights are on LOI 18-1 NRC Examination Scenario 2 Page 15 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP

Assist ATC with actions and/or plant monitoring, as required

Place switch S-1 on FLOW UNIT B to INT TEST at panel 09-14 Events 5 & 6 BOP / ATC

Recognize / report EPIC low flow alarm Loss of RBCLC Flow to

Recognize / report multiple annunciators, including:

Recirculation Pump B; Thermal Hydraulic o 09-4-3-16, RWR PMP B SEAL CLR FLOW LO Instability o 09-4-3-26, RWR PUMP B MTR WINDING CLR FLOW LO (on Lead Examiner Cue:

ACTIVATE TRIGGER 3) o 09-4-3-33, RWR PMP A OR B TEMP HI SRO

Acknowledge reports

Direct ARP execution

Direction shutdown of Recirculation pump B per OP-27

Enter AOP-8 (Unexpected Change in Core Flow)

Determine TRO 3.3.B Condition C entry is required (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to establish single loop limits for APRM flow biased scram and rod block) (as time permits)

May determine Technical Specification 3.4.1 Condition B is also applicable (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months action statement)

Note:

Acknowledge report of thermal-hydraulic instability Once the scram is inserted, LOI 18-1 NRC Examination Scenario 2 Page 16 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION the subsequent actions for

Enter AOP-32 (Unplanned Power Change) the failure to scram are

Direct inserting a manual scram continued in the next event.

BOP

Execute ARP 09-4-3-16, as time permits:

o Monitor seal cavity temps on 02TR-031 (points 20 & 21) o If seal cavity temp increases to 250oF, then shutdown B RWR pump per Section G of OP-27 o Ensure open 15AOV-132B and 15AOV-133B Note:

Some indication for 15FIS- o Verify RBC flow rate >300 gpm on 15FIS-102B 102B is available on EPIC o Monitor DW leakage for signs of seal leakage screen RWRB1.

Execute ARP 09-4-3-26, as time permits:

Role Play: o Monitor temps on 02-2TR-31 If dispatched to check RBC o Verify RBC flow rate >300 gpm on 15FIS-102B flow rate to RWR pump B, o If RBC flow cannot be restored and RWR pump and wait 2 minutes, then report motor temps are rising, then shut down RWR loop B that there is no RBC flow to per OP-27 Section G RWR pump B.

o Monitor DW sump levels

Execute ARP 09-4-3-33, as time permits:

o Check 02-2TR-31 o Check RBC temp o Check RBC lineup and verify at least 300 gpm on 15-FIS-102B LOI 18-1 NRC Examination Scenario 2 Page 17 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Monitor computer and annunciators for problem o Monitor DW leakage for possible leak in RBC system o If any RWR motor bearing exceeds 220oF, then shut down RWR pump per Section G of OP-27

Secure Recirculation pump B per OP-27:

Note: BOP cont. o Close RWR PMP B DISCH 02MOV-53B If Recirculation pump B is o Verify RWR PMP 02-2P-1B is tripped secured before damage to the seals results in coolant o Place RWR PMP 02-2P-1B control switch in PULL TO leakage into the Drywell, LOCK isolation of the pump is not o Verify open RWR MG B GEN FIELD BKR required to meet the critical task. o IF loop B isolation is required, THEN ensure closed the following valves:

Role Play: RWR PMP B DISCH 02MOV-53B If dispatched to close 02- RWR PMP B SUCT 02MOV-43B 2RWR-39B, wait 2 minutes, then report task completion. 02-2RWR-39B (RWR pump B seal purge upstr isol valve)

Coordinate with ATC to execute AOP-8, as time permits LOI 18-1 NRC Examination Scenario 2 Page 18 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Ensure RPV water level returns to normal and stabilizes

Determine operating point on Power-Flow Map (as time permits)

ATC

Monitor Reactor power

Monitor for thermal-hydraulic instability

Recognize / report thermal-hydraulic instability

Depress manual scram pushbuttons

Place Reactor Mode switch in SHUTDOWN

Manually initiates ARI BOP

Control reactor water level to prevent turbine trips Events 7 and 8 ATC

Recognize / report failure to scram Hydraulic Failure to Scram; First SLC Pump Delayed Trip Critical Task #1 Given a failure to scram with Reactor power above 2.5%, the Pass / Fail crew will lower reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC and CRD

Tripping Recirculation pumps

Injecting boron The Reactor power reduction must be initiated within five LOI 18-1 NRC Examination Scenario 2 Page 19 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION minutes of the start of the failure to scram.

Given a failure to scram, the crew will initiate Control Rod Critical Task #2 Pass / Fail insertion, in accordance with EOP-3. All insertable control rods must be inserted within one hour of the start of the failure to scram.

SRO

Acknowledge report

Enter EOP-2 (RPV Control) on Reactor power above 2.5%

or unknown when a scram is required

Determine the Reactor will NOT remain shutdown under all conditions without boron

Exit EOP-2

Enter EOP-3 (Failure to Scram)

Direct EOP-3 Failure to Scram Actions Critical Task #1

Direct bypassing MSIV low RPV water level isolation interlocks per EP-2

Direct terminate and prevent all injection except SLC, RCIC and CRD per EP-5 (may not direct low pressure Critical Task #1 systems T&P)

Role Play: If directed to

Direct Reactor water level controlled between -19 and insert MSIV low level 110 with only Group 1 Water Level Control Systems jumpers, run LOI 18-1 NRC Examination Scenario 2 Page 20 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION EP2_MSIVLEVEL schedule. (Feedwater, HPCI, RCIC, SLC)

Direct Reactor pressure controlled 800-1000 psig SRVs Critical Task #1

Concurs with BOP request to inject SLC

Ensure ADS overridden

Direct control rod insertion per EP-3 Critical Task #2 ATC

Perform EOP-3 Failure to Scram Actions:

o Ensure Rx Mode Switch in SHUTDOWN o Ensure ARI initiated o Determine Rx power greater than 2.5%

Critical Task #1 o Ensure Recirc pumps tripped o Override ADS o Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE o Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE o Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm o Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on o Obtain CRS concurrence to inject SLC Critical Task #1 o Inject SLC LOI 18-1 NRC Examination Scenario 2 Page 21 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Verify white SQUIB VLVS READY lights are on o Note level on TK LVL 11LI-66 o Place SLC pump keylock switch in START SYS-A or Booth Operator: START SYS-B When the first SLC pump is o Verify red SLC pump running light is on started, wait 5-10 seconds, then insert the appropriate o Verify SLC pump discharge pressure on DISCH PRESS trigger to trip that pump 11PI-65 is greater than or equal to RPV pressure (A=16, B=17).

o Verify the following:

o CLN UP SUCT 12MOV-18 is closed o CLN UP RETURN ISOL VALVE 12MOV-69 is closed o Recognize / report trip of first SLC pump started o Start 2nd SLC pump ATC cont.

Insert IRMs and SRMs

Range IRMs as necessary Role Play: If directed to

Perform EP-3 Backup Control Rod Insertion Actions reset ARI, insert Remote o Direct NPO to reset ARI per Subsection 5.4 RP20 to TEST.

o Reset Reactor scram per Subsection 5.5 Role Play: If directed to Direct installing RPS jumpers install RPS jumpers, run the Place SDIV HI LVL TRIP switch in BYPASS applicable schedule.

Place RX SCRAM RESET switch to GROUP 2&3, then to GROUP 1&4, spring return to NORM Verify the following lights are on:

RPS A SCRAM GROUPS 1, 2, 3, and 4

RPS B SCRAM GROUPS 1, 2, 3, and 4 Verify closed all scram inlet/outlet valves using one LOI 18-1 NRC Examination Scenario 2 Page 22 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION or a combination of the following:

Blue SCRAM lights are off at FULL CORE DISPLAY

Local valve position indication o May insert rods using RMCS per Subsection 5.7:

o Place RWM keylock switch in BYPASS o If reactor scram can be reset, then reset reactor scram as follows:

Place SDIV HI LVL TRIP switch in BYPASS Place RX SCRAM RESET switch to GROUP 2&3, Role Play: If directed to then to GROUP 1&4, spring return to NORM close 03CRD-56 and 91, o Verify the following lights are on:

insert Remote and report those valves closed. RPS A SCRAM GROUPS 1, 2, 3, and 4 RPS B SCRAM GROUPS 1, 2, 3, and 4 ATC cont.

o Raise CRD drive water differential pressure using one or more of the following methods:

Closing 03CRD-56, if the scram cannot be reset Starting second CRD pump Closing CRD DRV WTR PRESS VLV 03MOV-20 Raising CRD System flow rate using CRD FLOW CNTRL 03FIC-301 o Attempt to insert each control rod as follows, in the order specified on Attachment 1 and/or Attachment 2:

Select control rod on ROD SEL matrix.

Insert control rod using one of the following switches:

ROD MOVEMENT CNTRL LOI 18-1 NRC Examination Scenario 2 Page 23 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

ROD EMERG IN NOTCH OVERRIDE Repeat Steps A through B to insert control rods, as required.

o May insert rods by raising dP using CRD cooling water per Subsection 5.8:

May direct NPO to close 03CRD-56 Direct NPO to close 03CRD-91 Ensure open CRD DRV WTR PRESS VLV 03MOV-20 Ensure closed CRD CLG WTR PRESS CNTRL VLV 03MOV-22 Start 2nd CRD pump Place CRD FLOW CNTRL 03FIC 301 placed in MANUAL Raise CRD FLOW CNTRL 03FIC 301 output signal to maximum.

o May attempt repeated manual scrams o Recognize / report control rods inserting BOP

Terminate and prevent all injection except SLC, RCIC and Critical Task #1 CRD per EP-5 o Feedwater o If RFP A is running:

o Ensure RFP A FLOW CNTRL 06-84A is in MAN o Lower RFP A FLOW CNTRL 06-84A to minimum o Ensure open RFP A MIN FLOW 34FCV-135A LOI 18-1 NRC Examination Scenario 2 Page 24 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o If RFP B is running:

o Ensure RFP B FLOW CNTRL 06-84B is in MAN o Lower RFP BFLOW CNTRL 06-84B to minimum o Ensure open RFP B MIN FLOW 34FCV-135B o Ensure closed:

o RFP A DISCH 34MOV-100A o RFP B DISCH 34MOV-100B o Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL o Ensure closed FDWTR STARTUP VLV 34FCV-137 BOP cont.

o HPCI Critical Task #1 o Trip HPCI by depressing TURB TRIP 23A-S19 pushbutton o RHR Loop A(B) (may not T&P low pressure systems) o Place 10MOV-27A(B) AUTO CONTROL BYPASS 10A-S23A(B) o Verify white light above 10MOV-27A(B) AUTO CONTROL BYPASS 10A-S23A(B) is on LOI 18-1 NRC Examination Scenario 2 Page 25 of 30

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Ensure closed LPCI OUTBD INJ VLV 10MOV-27A(B) o Ensure RHR Loop A(B) pumps which are not required to be running are stopped o Core Spray Loop A(B) (may not T&P low pressure systems) o Place 14MOV-11A(B) AUTO ACTUATION BYPASS SW 14A-S16A(B) switch in BYPASS o Verify white 14MOV-11A(B) AUTO ACTUATION BYPASS LT 14A-DS35A(B) light is on o Ensure closed OUTBD INJ VLV 14MOV-11A(B) o Ensure PMP 14P-1A(B) is stopped

Report Reactor water level is less than 110 to CRS

Control Reactor water level between -19 and 110 with only Group 1 Water Level Control Systems (HPCI, RCIC, SLC)

Termination Criteria:

Reactor power is downscale on APRMs, all control rods are inserted, and Reactor water level is controlled above 0.

LOI 18-1 NRC Examination Scenario 2 Page 26 of 30

ATTACHMENT 1 Shift Turnover The plant is operating at approximately 70% power.

RBCLC pump A is out of service for maintenance.

When you take the shift:

1. Swap Feedwater level columns from A to B per OP-2A section G.27. It is desired to place Feedwater level control in manual during the swap and then restore it to automatic.

2. Perform a control rod pattern adjustment per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 2 Page 27 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Control Rod Pattern Adjustment Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 18-35 04 08 Notch NA -

2 Withdraw 34-35 04 08 Notch NA -

3 Withdraw 34-19 04 08 Notch NA -

4 Withdraw 18-19 04 08 Notch NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI 18-1 NRC Examination Scenario 2 Page 28 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Control Rod Pattern Adjustment Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 18-35 04 08 Notch NA -

2 Withdraw 34-35 04 08 Notch NA -

3 Withdraw 34-19 04 08 Notch NA -

4 Withdraw 18-19 04 08 Notch NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI 18-1 NRC Examination Scenario 2 Page 29 of 30

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Control Rod Pattern Adjustment Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 18-35 04 08 Notch NA -

2 Withdraw 34-35 04 08 Notch NA -

3 Withdraw 34-19 04 08 Notch NA -

4 Withdraw 18-19 04 08 Notch NA -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps UNIT SUPERVISOR LOI 18-1 NRC Examination Scenario 2 Page 30 of 30

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 18-1 NRC EXAMINATION SCENARIO 3 TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: NRC 3 PATH: STAND ALONE Validation: ___________________ Training: ___________________ Operations: ___________________

CANDIDATES CRS ATC BOP LOI 18-1 NRC Examination Scenario 3 Page 1 of 25

A. TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

1. IC-223

2. Special Instructions:

a. The plant is operating at approximately 100% power.

b. RBCLC pump A is out of service for maintenance.

c. TBCLC pumps A and B are in service and C is in standby.

3. Preset Conditions:

0

<ACTION>Insert malfunction FW25:C on event 1</ACTION>

<DESCRIPTION>CONDENSATE BOOSTER PUMP 33-P9C TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction NM14:A to 80.09080</ACTION>

<DESCRIPTION>APRM CHANNEL A FAILURE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction HP05 on event 2</ACTION>

<DESCRIPTION>HPCI INADVERTENT INITIATION</DESCRIPTION>

</ITEM>

0

<ACTION>Insert override HP-ZDI23AS19 to NORMAL</ACTION>

</ITEM>

0

<ACTION>Insert malfunction HP02 on event 3</ACTION>

<DESCRIPTION>HPCI TURBINE TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction YC01 on event 3</ACTION>

<DESCRIPTION>EMERGENCY AND PLANT INFORMATION COMPUTER FAILS</DESCRIPTION>

LOI 18-1 NRC Examination Scenario 3 Page 2 of 25

</ITEM>

0

<ACTION>Insert malfunction FW25:B on event 4</ACTION>

<DESCRIPTION>CONDENSATE BOOSTER PUMP 33-P9B TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction FW25:A after 20 on event 4</ACTION>

<DESCRIPTION>CONDENSATE BOOSTER PUMP 33-P9A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RC02</ACTION>

<DESCRIPTION>RCIC SYSTEM FAILURE TO AUTO START (ON LOW LEVEL)</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR33:B after 210 to 50.00000 on event 5</ACTION>

<DESCRIPTION>Reference Leg Leak N12B Inside Containment</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MS02:A after 210 to 35.00000 in 180 on event 5</ACTION>

<DESCRIPTION>(MSL A) STM LEAKAGE INSIDE PRIM CONTNMT</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR17:A after 60 on event 6</ACTION>

<DESCRIPTION>RX VESSEL FUEL ZONE LEVEL 02-3-LIS-73 FAILURE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR17:B after 90 on event 6</ACTION>

<DESCRIPTION>RX VESSEL FUEL ZONE LEVEL 02-3-LIS-79 FAILURE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR18 after 120 on event 6</ACTION>

<DESCRIPTION>REFUEL GEMAC VESSEL LEVEL INDICATOR 02-LI-86 FAILS</DESCRIPTION>

LOI 18-1 NRC Examination Scenario 3 Page 3 of 25

</ITEM>

0

<ACTION>Insert malfunction RR19:A after 120 to 0 on event 6</ACTION>

<DESCRIPTION>RX VESSEL LVL TRANSMITTER 06LT-52A FAILURE TO FDWTR CONTROL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR19:C after 120 to 0 on event 6</ACTION>

<DESCRIPTION>RX VESSEL LVL TRANSMITTER 06LT-52C FAILURE TO FDWTR CONTROL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR31:A2 after 120 on event 6</ACTION>

<DESCRIPTION>DNSCL FAILURE OF 02-3LT83A</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR31:C2 after 120 on event 6</ACTION>

<DESCRIPTION>DNSCL FAILURE OF 02-3LT83C</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR16:A on event 6</ACTION>

<DESCRIPTION>RX VESSEL WD RNG LVL TRANSMITTER 02-3-LI-85A FAILS DNSCL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR16:B on event 6</ACTION>

<DESCRIPTION>RX VESSEL WD RNG LVL TRANSMITTER 02-3-LI-85B FAILS DNSCL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RR16:C5 on event 6</ACTION>

<DESCRIPTION>RX VSL WD RNG LVL XMTR 02-3LT-72A FAILS DNSCL</DESCRIPTION>

</ITEM>

0

LOI 18-1 NRC Examination Scenario 3 Page 4 of 25

<ACTION>Insert malfunction RR16:C7 on event 6</ACTION>

<DESCRIPTION>RX VSL WD RNG LVL XMTR 02-3LT-72C FAILS DNSCL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AN951_06 after 120 to On on event 6</ACTION>

</ITEM>

0

<ACTION>Insert malfunction AN951_07 after 120 to On on event 6</ACTION>

</ITEM>

0

<ACTION>Insert malfunction AN951_28 after 120 to On on event 6</ACTION>

<DESCRIPTION>RX WTR LVL ALARM HI OR LO

(&lt196.5\&quot/&gt206.5\&quot)</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AN951_31 after 120 to On on event 6</ACTION>

<DESCRIPTION>RPS RX VESSEL LO LVL TRIP-RED</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AD01</ACTION>

<DESCRIPTION>ADS TIMER FAILS TO START</DESCRIPTION>

</ITEM>

0

<ACTION>Event Events/18-1 NRC/Scenario 3.evt</ACTION>

</ITEM>

0

<ACTION>Insert malfunction SW09:A</ACTION>

<DESCRIPTION>RBCLC PUMP A TRIP</DESCRIPTION>

</ITEM>

</SCHEDULE>

<EVENT>

LOI 18-1 NRC Examination Scenario 3 Page 5 of 25

<TRIGGER id="5" description="SCRAM full scram">(zlo5ads8a == 0) &amp&amp (zlo5ads8b ==

0)</TRIGGER>

<TRIGGER id="6" description="Containment spray flow">(rhfcntsprya&lt-10) l (rhfcntspryb&lt-10)</TRIGGER>

</EVENT>

LOI 18-1 NRC Examination Scenario 3 Page 6 of 25

C. SCENARIO

SUMMARY

The scenario will begin at approximately 100% power with RBCLC pump A out of service for maintenance.

The crew will begin the shift by swapping TBCLC pumps per OP-41.

Condensate Booster pump C trips. This will require the crew to lower Reactor power to approximately 65%.

APRM A fails as-is prior to the power reduction. During the power reduction, the crew will recognize that APRM A is not trending lower with the rest of the APRMs. The crew will bypass APRM A per OP-16.

HPCI will inadvertently initiate. The crew will take action to trip HPCI per AOP-77. The first method (pushbutton) will fail, so the crew will take alternate actions to trip HPCI. The SRO will determine the Technical Specification impact of the resulting HPCI inoperability.

Next, the Emergency Plant Information Computer (EPIC) system will fail. This will result in no Process Computer displays being available. The SRO will address Technical Specifications.

A second Condensate Booster pump trips, followed by the third pump 20 seconds later. The crew will scram the Reactor and enter AOP-1 due to the loss of Feedwater injection. EOP-2 (RPV Control) will be entered.

RCIC will fail to automatically start, but RCIC can be manually started for RPV injection. HPCI will fail to start if the crew attempts to manually start it.

The scram transient causes a steam leak and a Reactor water level instrument reference leg to break in the Drywell. EOP-4 (Primary Containment Control) will be entered.

Degrading Primary Containment parameters will require the Drywell to be sprayed. When Drywell spray is placed in service, all RPV water level instruments will sequentially fail. This requires EOP-7 (RPV Flooding) to be entered.

The crew will open 7 ADS valves, close steam isolation valves, and then flood the Reactor with Condensate, Core Spray, and/or LPCI.

The scenario will be terminated when the RPV is flooded to the Main Steam Lines.

LOI 18-1 NRC Examination Scenario 3 Page 7 of 25

Shift Turnover The plant is operating at approximately 100% power.

RBCLC pump A is out of service for maintenance.

When you take the shift, swap TBCLC pumps per OP-41 section G.1. Start TBCLC pump C and secure TBCLC pump A.

LOI 18-1 NRC Examination Scenario 3 Page 8 of 25

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Critical Task #2: Given an unknown Reactor water level, the crew will flood the RPV, in accordance with EOP-7. The RPV must be flooded to the Main Steam Lines within 30 minutes of when Reactor water level becomes unknown.

D. TERMINATION CUES:

Seven SRVs have been opened LOI 18-1 NRC Examination Scenario 3 Page 9 of 25

Indications of a flooded RPV are observed (eg. Reactor re-pressurizes after initial depressurization, SRVs re-open after closing)

LOI 18-1 NRC Examination Scenario 3 Page 10 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All

Walkdown the control panels and assume the watch allow no more than five minutes for panel walkdown Event 1 SRO

Perform Crew Brief Swap TBCLC Pumps

Direct BOP to start TBCLC pump B and secure TBCLC pump A per OP-41 section G.1.

BOP

Start TBCLC pump C

Verify pump motor current is LESS THAN maximum normal amps

Place and hold control switch for TBCLC pump A in STOP until TBCLC header pressure stabilizes GREATER THAN 95 psig, then release control switch

Verify pump motor current for the running TBCLC pumps is LESS THAN maximum normal amps

Ensure TBCLC header pressure is BETWEEN 95 and 135 psig per Section E of this procedure LOI 18-1 NRC Examination Scenario 3 Page 11 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 2 ATC \ BOP

Recognize / report annunciator 09-6-3-22, COND BSTR PMP Condensate Booster Pump 33P-9C OVERLOAD OR TRIP Trips

Recognize / report trip of Condensate Booster pump C (on Lead Examiner Cue:

insert TRIGGER 1)

Note: SRO

Acknowledge reports Reactor water level will be

Enter AOP-41, Feedwater Malfunction able to be maintained with just two Condensate Booster

Direct Reactor power reduction to within capacity of running pumps at 100% power, Condensate Booster pumps (RWR and Cram Rods) however both Condensate Booster pumps will be above their red-line current rating. Reactor power will need to be lowered to approximately 80% to restore pump currents within limits.

Role Play: ATC

Lower Reactor power using Recirculation flow If dispatched to investigate

May insert Cram Rods Condensate Booster pump C trip, wait 2 minutes, then report that the breaker is tripped on overcurrent, but there is no abnormal indication at the pump.

LOI 18-1 NRC Examination Scenario 3 Page 12 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP

Execute ARP 09-6-3-22 Event 3 ATC

Recognize / report APRM A is not lowering during the power APRM Fails As-Is reduction

Recognize / report annunciators 09-5-2-2, Rod Withdrawal Block, and 09-5-2-44, APRM Upscale, if power is lowered enough prior to bypassing APRM A SRO

Acknowledge report

Direct execution of ARPs (if annunciators received)

Determine Technical Specification Table 3.3.1.1-1 Functions 2b, c, and d are met with APRM A out of service

Determine TRM Table T3.3.B-1 Functions 1a, b, and c are met with APRM A out of service

Directs bypassing APRM A per OP-16 ATC

Bypass APRM A per OP-16 Section E.16:

o Place APRM BYP switch in A o Verify APRM A is bypassed using one or both of the following:

APRM A BYPASS indicating light is on LOI 18-1 NRC Examination Scenario 3 Page 13 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION APRM A EPIC alarm indicates bypassed o Verify the other two APRM channels associated with the same APRM BYP switch are in service using one or both of the following:

APRM BYPASS indicating lights are off for the other two APRMs No EPIC bypassed alarms for the other two APRMs Event 4 ALL

Recognize / report spurious HPCI initiation HPCI Inadvertently Initiates,

Recognize / report Reactor power rise, if applicable Trip Pushbutton Fails to Work, Trip Fails to Reset

Recognize / report Reactor water level rise, if applicable (on Lead Examiner Cue:

insert TRIGGER 2)

SRO

Acknowledge report

Enter AOP-77 (Inadvertent Initiation of ECCS or RCIC)

Verify HPCI injection not required

Direct trip of HPCI

May enter AOP-32 (Unexplained/Unanticipated Reactivity Change)

Declare HPCI inoperable

Determine Technical Specification 3.5.1 Condition C requires restoring HPCI to operable within 14 days

Declare the secured train of Standby Gas Treatment inoperable LOI 18-1 NRC Examination Scenario 3 Page 14 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Determine Technical Specification 3.6.4.3 Condition A requires restoring Standby Gas Treatment to operable within 7 days Role Play: BOP

Execute AOP-77 If dispatched to investigate

Observe Reactor water level and Drywell pressure indications HPCI, wait two minutes, to verify HPCI injection not required then report there is no obvious reason why HPCI

Attempt to trip HPCI using pushbutton started and there is no

Recognize / report failure of HPCI trip pushbutton to work observable damage to the system.

May lower HPCI flow rate to 0

Take keylock switch 23A-S2A, 23MOV-16 AUTO CONTROL BYPASS, to BYPASS

Close OUTBD STM SUPP VLV 23MOV-16

Close STM LINE WARMING ISOL VLV 23MOV-60

AFTER turbine comes to a complete stop, place AUX OIL PMP 23P-150 control switch in PULL-TO-LOCK

Secure one train of Standby Gas

For the running Standby Gas train, open 01-125MOV-11(12)

LOI 18-1 NRC Examination Scenario 3 Page 15 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

May execute AOP-32 (Unexplained/Unanticipated Reactivity Change) o Determine HPCI initiation was only cause of reactivity change Event 5 BOP \ ATC

Recognize / report annunciator 09-8-1-4, COMPUTER CNTRL EPIC Fails VOLT TROUBLE (On Lead Examiner cue,

Recognize / report loss of EPIC screens insert Trigger 3)

Role Play: SRO

Acknowledge reports When contacted to

Ensure ARP execution investigate / restore EPIC, acknowledge request.

Enter ST-40C (Computer Out of Service Surveillance) o Conduct crew briefing on effect of EPIC inoperability o Direct crew to review EP-1 o Notify computer specialist LOI 18-1 NRC Examination Scenario 3 Page 16 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Determine Technical Specification Surveillance Requirement 3.6.1.5.1 (Drywell average air temperature) must be met by manual calculation

May determine Technical Specification Table 3.3.2.1-1 Function 2 (RWM rod block) is inoperable but not applicable with Reactor power > 10%

Determine monitoring for SPDES permit must be met by manual calculation BOP

Execute ARP 09-8-1-4:

o Contact Instrument and Control o Notify SRO to perform ST-40C Events 6, 7, 8, & 9 BOP \ ATC

Recognize / report annunciators:

On Lead Examiner Cue:

o 09-6-3-12, COND BSTR PMP 33P-9B OVERLOAD OR TRIP (insert Trigger 4)

(first)

Remaining Condensate Booster Pumps Trip, RCIC o 09-6-3-02, COND BSTR PMP 33P-9A OVERLOAD OR TRIP Fails to Automatically Start, (20 seconds later)

Steam Leak in Drywell,

Recognize / report trip of Condensate Booster pumps Multiple Level Instrument Failures

Recognize / report degrading Primary Containment parameters (delayed)

Recognize / report loss of Reactor water level instruments (delayed)

LOI 18-1 NRC Examination Scenario 3 Page 17 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Critical Task #1 Given a coolant leak inside the Containment, the crew will spray Pass / Fail the Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Initiate Drywell spray.

Critical Task #1 Standard:

Critical Task #2 Given an unknown Reactor water level, the crew will flood the Pass / Fail RPV, in accordance with EOP-7. The RPV must be flooded to the Main Steam Lines within 30 minutes of when Reactor water level becomes unknown.

Open 7 SRVs.

Critical Task #2 Standard:

SRO

Direct a manual Reactor scram

Enter AOP-1, Reactor Scram

Enter EOP-2 (RPV Control) on low Reactor water level, high Drywell pressure, and high Drywell temperature (as occur)

Enter EOP-4 (Primary Containment Control) on high Drywell pressure and high Drywell temperature (as they occur)

Acknowledge RCIC failure to auto start

Direct Reactor water level control 180-220 using RCIC, SLC, and/or CRD LOI 18-1 NRC Examination Scenario 3 Page 18 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Direct Reactor pressure control 800-1000 psig using TBVs

Enter AOP-39 (Loss of Coolant)

Direct Control Room and Relay Room Ventilation isolated per Role Play: OP-55B Section G within 30 minutes When directed to place

Direct TSC filtered ventilation started per Section D of OP-59B Control Room, Relay Room, within 60 minutes and/or TSC filtered ventilation in service,

May direct Core Spray and RHR injection prevented per EP-5 acknowledge direction.

When Primary Containment pressure exceeds 2.7 psig and before Torus pressure exceeds 15 psig, direct Torus Spray

When Torus pressure exceeds 15 psig:

o Verify Recirculation pumps tripped o Verify trip of Drywell cooling fans o Direct initiation of Drywell Spray Critical Task #1 SRO cont.

Acknowledges failure of Reactor water level instruments

Acknowledge that Reactor water level cannot be determined

Exit EOP-2

Enter EOP-7 (RPV Flooding) Shutdown Flooding Leg

Direct open all 7 ADS valves Critical Task #2

Direct closed the following valves:

o MSIVs o Main steam line drain valves LOI 18-1 NRC Examination Scenario 3 Page 19 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o RCIC steam isolation valves per EP-2 o HPCI steam isolation valves per EP-2

Direct Reactor injection using Condensate, Core Spray, and/or LPCI to flood the Reactor to the main steam lines

Once Reactor is flooded to the main steam lines, direct controlling Reactor injection flow rate as low as possible ATC

Enter AOP-1

Depress MANUAL SCRAM A and MANUAL SCRAM B pushbuttons

Place RX MODE switch in SHUTDOWN

Fully insert IRMs and SRMs

Observe Reactor power lowering

Ensure closed SDIV vent and drain valves

Ensure Main Turbine is tripped

May control Reactor pressure on SRVs

May begin Reactor depressurization ATC / BOP

Attempt to maintain Reactor water level with RCIC, SLC and/or CRD

Initiate Torus spray:

o IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, AND the EOPs permit diverting LPCI flow, THEN place DW & TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A(B) keylock switch in MANUAL OVERRD o Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, LOI 18-1 NRC Examination Scenario 3 Page 20 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION spring return to normal o Verify white SPRAY PERM 10A-DS67A(B) light is on o Ensure available RHR pumps in RHR Loop A(B) are running o Open RHR TEST TORUS CLG & SPRAY 10MOV-39A(B) o Throttle TORUS SPRAY INBD VLV 10MOV-38A(B) to establish desired torus spray flow rate o WHEN RHR Loop A flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV 10MOV-16A(B) o Throttle RHR TEST & TORUS CLG 10MOV-34A(B) to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop A(B) flow with one RHR pump operating or > 13,000 gpm RHR Loop A(B) flow with two RHR pumps operating

Establish RHRSW flow and temperature control:

Start one of the RHRSW pumps Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm Start the second RHRSW pump if desired Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm per RHRSW pump

IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump

Close HX A(B) BYP VLV 10MOV-66A(B)

ATC / BOP cont.

Ensure Recirc pumps tripped

Ensure Drywell Cooling fans tripped

Initiate Drywell spray:

Critical Task #1 o IF RPV water level is LESS THAN 10 inches on fuel zone water level indication, AND the EOPs permit diverting LPCI LOI 18-1 NRC Examination Scenario 3 Page 21 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION flow, THEN place DW & TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A(B) keylock switch in MANUAL OVERRD o Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, spring return to normal o Verify white SPRAY PERM 10A-DS67A(B) light is on o Ensure available RHR pumps in RHR Loop A(B) are running o Open DW SPRAY OUTBD VLV 10MOV-26A(B) o Throttle DW SPRAY INBD VLV 10MOV-31A(B) to establish desired drywell spray flow rate ATC / BOP

Recognize / report failure of Reactor water level instruments.

Recognize / report that Reactor water level cannot be determined LOI 18-1 NRC Examination Scenario 3 Page 22 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Open 7 ADS valves Critical Task #2

Close the following valves:

o MSIVs o Main steam line drain valves o RCIC steam isolation valves per EP-2 section 5.12:

Place 13MOV-16 AUTO CONTROL BYPASS switch 13A-S2A in bypass Ensure closed the following valves:

13MOV-15 INBD STM SUPP VLV

13MOV-16 OUTBD STM SUPP VLV o HPCI steam isolation valves per EP-2 section 5.11:

Place the following HPCI steam supply isolation valve auto control bypass switches in BYPASS:

23MOV-15 AUTO CONTROL BYPASS 23A-S1A

23MOV-16 AUTO CONTROL BYPASS 23A-S2A Ensure closed the following valves:

STM LINE WARMING ISOL VLV 23MOV-60

INBD STM SUPP VLV 23MOV-15

OUTBD STM SUPP VLV 23MOV-16 ATC / BOP

Recognize / report indications of Reactor flooded to the cont. main steam lines LOI 18-1 NRC Examination Scenario 3 Page 23 of 25

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Lowers Reactor injection flow rate of Core Spray, LPCI, and Condensate while maintaining Reactor flooded Termination Criteria:

Seven SRVs have been opened

Indications of a flooded RPV are observed (eg. Reactor re-pressurizes after initial depressurization, SRVs re-open after closing)

LOI 18-1 NRC Examination Scenario 3 Page 24 of 25

ATTACHMENT 1 Shift Turnover The plant is operating at approximately 100% power.

RBCLC pump A is out of service for maintenance.

When you take the shift, swap TBCLC pumps per OP-41 section G.1. Start TBCLC pump C and secure TBCLC pump A.

LOI 18-1 NRC Examination Scenario 3 Page 25 of 25

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI 18-1 NRC EXAMINATION SCENARIO 4 TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 4 SCENARIO NUMBER: NRC 4 PATH: STAND ALONE Validation: ___________________ Training: ___________________ Operations: ___________________

CANDIDATES CRS ATC BOP LOI 18-1 NRC Examination Scenario 4 Page 1 of 29

A. TITLE: LOI 18-1 NRC EXAMINATION SCENARIO 4 B. SCENARIO SETUP:

1. IC-224

2. Special Instructions:

a. The plant is operating at approximately 90% power.

b. RBCLC pump A is out of service for maintenance.

c. Torus Cooling is in service on RHR A following completion of RCIC surveillance testing.

3. Preset Conditions:

0

<ACTION>Insert malfunction SW04:A after 15 on event 1</ACTION>

<DESCRIPTION>RHR SERVICE WATER PUMP A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD10:26:43</ACTION>

<DESCRIPTION>CONTROL ROD (26-43) BLADE STUCK</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RC09 to 2.00000 on event 2</ACTION>

<DESCRIPTION>RCIC STEAM LINE BREAK</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MC01 from 25.00000 to 40.00000 in 480 on event 3</ACTION>

<DESCRIPTION>MAIN CONDENSER AIR IN LEAKAGE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction CU09 after 150 to 30.00000 in 90 on event 4</ACTION>

LOI 18-1 NRC Examination Scenario 4 Page 2 of 29

<DESCRIPTION>RWCU INLET PIPE FAILURE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:30:39</ACTION>

<DESCRIPTION>CONTROL ROD (30-39) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:30:43</ACTION>

<DESCRIPTION>CONTROL ROD (30-43) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:30:47</ACTION>

<DESCRIPTION>CONTROL ROD (30-47) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:34:39</ACTION>

<DESCRIPTION>CONTROL ROD (34-39) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:34:43</ACTION>

<DESCRIPTION>CONTROL ROD (34-43) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:34:47</ACTION>

<DESCRIPTION>CONTROL ROD (34-47) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:38:39</ACTION>

<DESCRIPTION>CONTROL ROD (38-39) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

LOI 18-1 NRC Examination Scenario 4 Page 3 of 29

0

<ACTION>Insert malfunction RD13:38:43</ACTION>

<DESCRIPTION>CONTROL ROD (38-43) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:38:47</ACTION>

<DESCRIPTION>CONTROL ROD (38-47) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction RD13:30:51</ACTION>

<DESCRIPTION>CONTROL ROD (30-51) FAILURE TO SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction FW01:A after 300 on event 4</ACTION>

<DESCRIPTION>RX FEEDWTR PMP A TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction FW01:B after 300 on event 4</ACTION>

<DESCRIPTION>RX FEEDWTR PMP B TRIP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction HP01</ACTION>

<DESCRIPTION>HPCI FAILURE TO AUTO START</DESCRIPTION>

</ITEM>

0

<ACTION>Event Events/18-1 NRC/Scenario 4.evt</ACTION>

</ITEM>

0

<ACTION>Insert malfunction SW09:A</ACTION>

<DESCRIPTION>RBCLC PUMP A TRIP</DESCRIPTION>

</ITEM>

LOI 18-1 NRC Examination Scenario 4 Page 4 of 29

0

<ACTION>Insert malfunction AN933_31 to Off</ACTION>

<DESCRIPTION>STM LEAK DET LOGIC A IN TEST</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AN933_32 to Off</ACTION>

<DESCRIPTION>STM LEAK DET LOGIC B IN TEST</DESCRIPTION>

</ITEM>

0

<ACTION>Insert override LD-ZDI2FS5A to TEST</ACTION>

</ITEM>

0

<ACTION>Insert override LD-ZDI2FS5B to TEST</ACTION>

</ITEM>

0

<ACTION>Insert remote RC03 to OUT</ACTION>

<DESCRIPTION>RELAY 13A-K32 AA-69 OR AA-70 LEAD</DESCRIPTION>

</ITEM>

0

<ACTION>Insert remote RC04 to OUT</ACTION>

<DESCRIPTION>RELAY 13A-K12 AA-22 OR AA-23 LEAD</DESCRIPTION>

</ITEM>

0

<ACTION>Insert override RD-ZDI3BS1 to NORM on event 4</ACTION>

<DESCRIPTION>CRD DRIVE WTR PRESS 3-MOV-20</DESCRIPTION>

</ITEM>

</SCHEDULE>

LOI 18-1 NRC Examination Scenario 4 Page 5 of 29

<EVENT>

</EVENT>

LOI 18-1 NRC Examination Scenario 4 Page 6 of 29

C. SCENARIO

SUMMARY

The scenario will begin at approximately 90% power. RBCLC pump A is out of service for maintenance.

Torus Cooling is in service on RHR A following completion of RCIC surveillance testing. The crew will begin the shift by securing Torus Cooling. While securing Torus Cooling, RHRSW pump A will spuriously trip.

The SRO will determine the Technical Specification impact.

Following completion of this evolution, the crew will raise Reactor power using control rods and Recirculation flow. During the control rod withdrawals, the second rod will be stuck. The crew will raise drive water differential pressure to un-stick the control rod and complete the rod pattern adjustment.

A steam leak will develop from RCIC into the Reactor Building. RCIC will fail to automatically isolate on high temperature. The crew will enter EOP-5 (Secondary Containment Control) and isolate RCIC.

Elevated Main Condenser air in-leakage will occur. Main Condenser vacuum will degrade. The crew will enter AOP-31 and eventually insert a manual Reactor scram.

Following the manual scram attempt, all control rods do not fully insert (10 rods fail to scram but can be manually inserted). The crew will execute EOP-3 (Failure to Scram). Eventually, the 10 control rods will be inserted and the crew will transition from EOP-3 to EOP-2 (RPV Control). During this time, a coolant leak will develop in the Drywell. EOP-4 will also be executed due to the coolant leak. The crew will spray the Torus and Drywell.

Approximately 5 minutes after the scram, both Feedwater pumps will trip. Additionally, HPCI will fail to automatically start. The crew will control Reactor water level with HPCI, Condensate, CRD, and/or SLC.

The scenario will be terminated when all control rods are inserted, Containment pressure is being controlled per EOP-4, and Reactor water level is controlled above 0.

LOI 18-1 NRC Examination Scenario 4 Page 7 of 29

Shift Turnover The plant is operating at approximately 90% power.

RBCLC pump A is out of service for maintenance.

Torus Cooling is in service following completion of RCIC surveillance testing.

When you take the shift:

1. Secure Torus Cooling per OP-13B.

2. Raise Reactor power using control rods and Recirculation flow per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 4 Page 8 of 29

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Critical Task #2: Given a coolant leak inside the Containment and degraded high pressure injection sources, the crew will establish injection to the Reactor, in accordance with EOP-2 and/or EOP-3. Injection must be established such that Reactor water level does not lower below -19.

Critical Task #3: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3. All insertable control rods must be inserted within one hour of the start of the failure to scram.

D. TERMINATION CUES:

All control rods are inserted

Containment pressure controlled per EOP-4

Reactor water level is controlled above 0 LOI 18-1 NRC Examination Scenario 4 Page 9 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All

Walkdown the control panels and assume the watch allow no more than five minutes for panel walkdown Events 1 & 2 SRO

Perform Crew Brief Secure Torus Cooling;

Direct BOP to secure Torus Cooling per OP-13B sections RHRSW Pumps Trip F.1 and F.7

Acknowledge report of RHRSW pump A trip

Ensure ARP execution

Declare RHRSW pump A inoperable

Determine Technical Specification 3.7.1 Condition A must be entered (30 days)

LOI 18-1 NRC Examination Scenario 4 Page 10 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP

Close RHR TEST & TORUS CLG 10MOV-34A Note:

IF RHR Loop A flow is LESS THAN 1500 gpm, THEN ensure Trigger 1 automatically open MIN FLOW VLV 10MOV-16A initiates when 10MOV-34A

IF RHR Loop A operation is not required, THEN shut down red light turns off to initiate RHR Loop A per Subsection F.7 event 2.

Ensure one of the RHR Loop A keep-full systems is in service as follows:

o RHR KEEP-FULL PMP 10P-2A is running, OR o 10RHR-274 (RHR loop A reactor head spray keep-full cond xfer connection valve) is throttled open

Ensure closed the following valves:

o RHR TEST & TORUS CLG 10MOV-34A o TORUS SPRAY INBD VLV 10MOV-38A o DW SPRAY INBD VLV 10MOV-31A

Ensure the following RHR pumps are stopped:

o RHR PMP 10P-3A o RHR PMP 10P-3C

Ensure closed the following valves:

o RHR TEST TORUS CLG & SPRAY 10MOV-39A o DW SPRAY OUTBD VLV 10MOV-26A

Ensure open MIN FLOW VLV 10MOV-16A

Ensure open HX A BYP VLV 10MOV-66A

IF RHRSW Loop A operation is not required, THEN shut down RHRSW Loop A as follows:

o Close RHRSW DISCH VLV FROM HX A 10MOV-89A LOI 18-1 NRC Examination Scenario 4 Page 11 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Ensure the following RHRSW pumps are stopped:

RHRSW PMP 10P-1A RHRSW PMP 10P-1C

Recognize / report Annunciator 09-3-1-25 BOP cont.

Recognize / report trip of RHRSW pump A Role Play:

Dispatch operator to investigate If dispatched to investigate RHRSW pump A, wait 2 minutes, then report that their breaker is tripped, but there are no other abnormal indications at the breaker or pump.

LOI 18-1 NRC Examination Scenario 4 Page 12 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Events 3 & 4 SRO

Direct ATC to withdraw control rods per provided Raise Reactor Power with instructions Control Rods and

Provide oversight of reactivity manipulation Recirculation Flow; Stuck Control Rod

Acknowledge control rod 26-43 is stuck

Direct moving control rod 26-43 with raised drive water pressure per OP-25

Acknowledge control rod 26-43 has moved

Direct ATC to raise Reactor power to 98% with Recirculation flow ATC

While withdrawing control rods, monitor the following:

Note:

o Nuclear instrumentation Control rods 10-27, 26-43, 42-27, and 26-11 are to be o Control rod position indication moved from 08 to 10.

Ensure ROD SEL PWR switch is in ON Control rods 26-43 will initially be stuck and fail to

Ensure control rod to be moved is selected by depressing move at normal drive water rod select pushbutton on ROD SEL matrix, if necessary pressure.

Verify the following:

o Select pushbutton is brightly backlit Role Play:

o Control rod indicating light is on If dispatched to investigate, wait 2 minutes and then o ROD OUT PERM light is on report nothing is obviously

Repeat for other rods abnormal at HCU 26-43.

Recognize / report control rod 26-43 is stuck LOI 18-1 NRC Examination Scenario 4 Page 13 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Booth Operator:

Raises CRD drive water differential pressure in 50 psid Once drive water pressure increments per OP-25, Section E.6 has been raised 300 psig,

Attempt to withdraw rod 26-43 delete malfunction RD10:26:43.

Report rod 26-43 moved to position 10

Restore CRD drive water differential pressure to 260-270 psid

Continue rod pattern adjustments

Report completion of control rod withdrawals Note:

Raise Reactor power to 98% using Recirculation flow:

It is recommended to move on to the next event after a o Raise Recirc flow alternately with RWR MG A(B) few Recirc flow SPEED CNTRL manipulations have been o Monitor APRMs, CTP, Recirc flow, Reactor water observed. level LOI 18-1 NRC Examination Scenario 4 Page 14 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Event 5 BOP / ATC

Recognize / report EPIC alarms for high area temperatures RCIC Steam Leak, Fails to

Recognize / report annunciators 09-3-3-2(12), DIV I(II)

Automatically Isolate AMBIENT TEMP HI (on Lead Examiner Cue:

ACTIVATE TRIGGER 2)

Recognize / report annunciator 09-4-1-22, RCIC ISOL TRIP LOGIC INITIATED

Recognize / report RCIC has failed to automatically isolate Note: SRO

Acknowledge reports HPCI may automatically

Enter EOP-5 (Secondary Containment Control) on high isolate on high area area temperature temperature depending on the timing of the manual

Direct isolation of RCIC RCIC isolation. HPCI may

Declare RCIC inoperable also be manually isolated due to the given high

Determine Technical Specification 3.5.3 Condition A must temperature indications in be entered (verify HPCI operable immediately, restore an area common to HPCI RCIC to operable within 14 days) and RCIC. If HPCI is

If HPCI automatically isolates, determine Technical isolated, there will be Specification 3.5.1 Conditions C and G (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) must be additional Technical entered, along with Technical Specification 3.5.3 Condition Specification entries (3.5.1 B (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

Conditions C and G, 3.5.3 LOI 18-1 NRC Examination Scenario 4 Page 15 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Condition B). In this case, HPCI can be manually restored after area temperatures lower.

BOP

Isolate RCIC:

o Close 13MOV-15 o Close 13MOV-16

May perform RCIC isolation verification section of OP-19 section G, as time permits Events 6, 7, 8, and 9 BOP / ATC

Recognize / report annunciator 09-3-1-28 Offgas Loss of Main Condenser Recombiner Trouble Vacuum; Coolant Leak in

Recognize / report lowering Main Condenser vacuum Drywell; Ten Control Rods Fail to Scram; CRD Drive Water Pressure Control Valve Fails As-Is; Feedwater Pumps Trip; HPCI Fails to Automatically Start (on Lead Examiner Cue:

ACTIVATE TRIGGER 3)

Critical Task #1 Given a coolant leak inside the Containment, the crew will Pass / Fail spray the Drywell, in accordance with EOP-4. Drywell spray must be initiated within 15 minutes of Torus pressure exceeding 15 psig.

Critical Task #2 Given a coolant leak inside the Containment and degraded Pass / Fail high pressure injection sources, the crew will establish injection to the Reactor, in accordance with EOP-2 and/or EOP-3. Injection must be established such that Reactor LOI 18-1 NRC Examination Scenario 4 Page 16 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION water level does not lower below -19.

Critical Task #3 Given a failure to scram, the crew will initiate Control Rod Pass / Fail insertion, in accordance with EOP-3. All insertable control rods must be inserted within one hour of the start of the failure to scram.

SRO

Acknowledge report Note: The coolant leak

Enter AOP-31 (Loss of Condenser Vacuum) starts 2.5 minutes after the scram. Feedwater pumps

Direct power reduction per RAP-7.3.16 to maintain Main trip 5 minutes after the Condenser vacuum within Normal Operating Region, as scram. time permits

Direct Reactor scram

Enter EOP-2 (RPV Control) on low Reactor water level

Acknowledge failure of multiple control rods to insert

Determine the Reactor will NOT remain shutdown under all conditions without boron

Exit EOP-2

Enter EOP-3 (Failure to Scram)

Direct EOP-3 Failure to Scram Actions Role Play: If directed to insert MSIV low level

May direct bypassing MSIV low RPV water level isolation jumpers, run interlocks per EP-2 EP2_MSIVLEVEL schedule.

Direct Reactor water level controlled between -19 and LOI 18-1 NRC Examination Scenario 4 Page 17 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION 222.5 with only Group 1 Water Level Control Systems (Condensate/Feedwater, HPCI, CRD, SLC)

Direct Reactor pressure controlled 800-1000 psig on TBVs

Ensure ADS overridden

Direct control rod insertion per EP-3 Critical Task #3

Acknowledge control rod insertion using RMCS

Acknowledge all control rods are inserted

Exit EOP-3, enter EOP-2

Acknowledge degrading Primary Containment conditions SRO cont.

Enter EOP-4 (Primary Containment Control) due to high Drywell pressure and temperature

When Primary Containment pressure exceeds 2.7 psig and before Torus pressure exceeds 15 psig, direct initiation of Torus Spray

When Torus pressure exceed 15 psig, direct Drywell spray Critical Task #1

Acknowledge trip of Feedwater pumps

Direct injection with HPCI and/or Condensate Booster pumps Critical Task #2

May commence Reactor depressurization to get within shutoff head of Condensate Booster pumps LOI 18-1 NRC Examination Scenario 4 Page 18 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ATC

Lower Reactor power with recirculation flow and/or CRAM rods, as required / directed

Depress manual scram pushbuttons

Place Reactor Mode switch in SHUTDOWN

Manually initiates ARI

Recognize / report multiple control rods fail to insert

Perform EOP-3 Failure to Scram Actions:

o Ensure Rx Mode Switch in SHUTDOWN o Ensure ARI initiated o Ensure recirculation flow is runback to minimum o Determine Rx power less than 2.5%

ATC cont.

o Override ADS:

Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE Role Play: If directed to Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-reset ARI, insert Remote S2B in OVERRIDE RP20 to TEST. Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on

Insert IRMs and SRMs

Range IRMs as necessary LOI 18-1 NRC Examination Scenario 4 Page 19 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Perform EP-3 Backup Control Rod Insertion Actions o Direct NPO to reset ARI per Subsection 5.4 o Reset Reactor scram per Subsection 5.5 Direct installing RPS jumpers Place SDIV HI LVL TRIP switch in BYPASS Place RX SCRAM RESET switch to GROUP 2&3, then to GROUP 1&4, spring return to NORM Verify the following lights are on:

RPS A SCRAM GROUPS 1, 2, 3, and 4

RPS B SCRAM GROUPS 1, 2, 3, and 4 Verify closed all scram inlet/outlet valves using one or a combination of the following:

Blue SCRAM lights are off at FULL CORE DISPLAY

Local valve position indication Critical Task #3 o Insert rods using RMCS per Subsection 5.7:

o Place RWM keylock switch in BYPASS ATC cont.

o If reactor scram can be reset, then reset reactor scram as follows:

Role Play: If directed to Place SDIV HI LVL TRIP switch in BYPASS close 03CRD-56 and 91, insert Remote and report Place RX SCRAM RESET switch to GROUP 2&3, those valves closed. then to GROUP 1&4, spring return to NORM o Verify the following lights are on:

RPS A SCRAM GROUPS 1, 2, 3, and 4 RPS B SCRAM GROUPS 1, 2, 3, and 4 o Raise CRD drive water differential pressure using one or more of the following methods:

LOI 18-1 NRC Examination Scenario 4 Page 20 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Closing 03CRD-56, if the scram cannot be reset Starting second CRD pump Closing CRD DRV WTR PRESS VLV 03MOV-20 (wont work due to malfunction)

Raising CRD System flow rate using CRD FLOW CNTRL 03FIC-301 o Attempt to insert each control rod as follows, in the Note: CRD DRV WTR PRESS order specified on Attachment 1 and/or Attachment 2:

VLV 03MOV-20 is failed as-is, which will prevent Select control rod on ROD SEL matrix.

drifting in control rods by Insert control rod using one of the following raising cooling water D/P. switches:

ROD MOVEMENT CNTRL

ROD EMERG IN NOTCH OVERRIDE Repeat Steps A through B to insert control rods, as required.

o May attempt to insert rods by raising dP using CRD cooling water per Subsection 5.8:

May direct NPO to close 03CRD-56 Direct NPO to close 03CRD-91 Ensure open CRD DRV WTR PRESS VLV 03MOV-20 Ensure closed CRD CLG WTR PRESS CNTRL VLV 03MOV-22 Start 2nd CRD pump Place CRD FLOW CNTRL 03FIC 301 placed in MANUAL Raise CRD FLOW CNTRL 03FIC 301 output signal to maximum.

o May attempt repeated manual scrams (wont work for LOI 18-1 NRC Examination Scenario 4 Page 21 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION given rod malfunction)

BOP

Coordinate with ATC to lower Reactor power with Recirculation flow, as required / directed

Terminate and prevent Core Spray Loop A(B), as time permits o Place 14MOV-11A(B) AUTO ACTUATION BYPASS SW 14A-S16A(B) switch in BYPASS o Verify white 14MOV-11A(B) AUTO ACTUATION BYPASS LT 14A-DS35A(B) light is on o Ensure closed OUTBD INJ VLV 14MOV-11A(B) o Ensure PMP 14P-1A(B) is stopped

Control Reactor pressure 800-1000 psig using TBVs Critical Task #2

Control Reactor water level between -19 and 222.5 with only Group 1 Water Level Control Systems (Condensate/Feedwater, HPCI, CRD, SLC)

Recognize / report failure of HPCI to automatically start

Manually starts HPCI:

o Ensure open 23MOV-16 o Ensure running 23P-140 o Ensure open 23MOV-14 o Perform the following without unnecessary delay:

If 09-3-3-28 is in, then depress 23A-S17 Ensure running 23P-150 Ensure open 23MOV-19 LOI 18-1 NRC Examination Scenario 4 Page 22 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

Recognize / report trip of Feedwater pumps

May reduce Reactor pressure to get within shutoff head of Condensate Booster pumps ATC / BOP

Initiate Torus spray:

Place SPRAY CNTRL 10A-S17B switch to MANUAL, spring return to normal Verify white SPRAY PERM 10A-DS67B light is on Ensure available RHR pumps in RHR Loop B are running (recognize/report failure to automatically start)

Open RHR TEST TORUS CLG & SPRAY 10MOV-39B Throttle TORUS SPRAY INBD VLV 10MOV-38B to establish desired torus spray flow rate WHEN RHR Loop B flow is GREATER THAN 1500 gpm, ensure closed MIN FLOW VLV 10MOV-16B Throttle RHR TEST & TORUS CLG 10MOV-34B to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop B flow with one RHR pump operating or > 13,000 gpm RHR Loop B flow with two RHR pumps operating

Establish RHRSW flow and temperature control:

Establish RHRSW flow and temperature control:

Start one of the RHRSW pumps Throttle RHRSW DISCH VLV FROM HX B 10MOV-89B to establish 2500 to 4000 gpm Start the second RHRSW pump if desired LOI 18-1 NRC Examination Scenario 4 Page 23 of 29

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Throttle RHRSW DISCH VLV FROM HX B 10MOV-89B to establish 2500 to 4000 gpm per RHRSW pump

IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump

Close HX B BYP VLV 10MOV-66B

Ensure Recirc pumps tripped

Ensure Drywell Cooling fans tripped Critical Task #1

Initiate Drywell spray:

Place SPRAY CNTRL 10A-S17B switch to MANUAL, spring return to normal Verify white SPRAY PERM 10A-DS67B light is on Ensure available RHR pumps in RHR Loop B are running Open DW SPRAY OUTBD VLV 10MOV-26B Throttle DW SPRAY INBD VLV 10MOV-31B to establish desired drywell spray flow rate Termination Criteria:

All control rods are inserted, Containment pressure controlled per EOP-4, and Reactor water level is controlled above 0.

LOI 18-1 NRC Examination Scenario 4 Page 24 of 29

ATTACHMENT 1 Shift Turnover The plant is operating at approximately 90% power.

RBCLC pump A is out of service for maintenance.

Torus Cooling is in service following completion of RCIC surveillance testing.

When you take the shift:

1. Secure Torus Cooling per OP-13B.

2. Raise Reactor power using control rods and Recirculation flow per the provided reactivity instructions.

LOI 18-1 NRC Examination Scenario 4 Page 25 of 29

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 10-27 08 10 Notch NA -

2 Withdraw 26-43 08 10 Notch NA -

3 Withdraw 42-27 08 10 Notch NA -

4 Withdraw 26-11 08 10 Notch NA -

Raise power to 98%

5 RTP - - - RWR - -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI 18-1 NRC Examination Scenario 4 Page 26 of 29

LOI 18-1 NRC Examination Scenario 4 Page 27 of 29

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 10-27 08 10 Notch NA -

2 Withdraw 26-43 08 10 Notch NA -

3 Withdraw 42-27 08 10 Notch NA -

4 Withdraw 26-11 08 10 Notch NA -

Raise power to 98%

5 RTP - - - RWR - -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI 18-1 NRC Examination Scenario 4 Page 28 of 29

REACTIVITY M ANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps - (site specific control rod movement control sheet format is to be used)

Power Ascension Today Page 1 of 1 From Cplg RSCS Init Step Action Rod To Notch Method Notes Notch Chk Grp 1 Withdraw 10-27 08 10 Notch NA -

2 Withdraw 26-43 08 10 Notch NA -

3 Withdraw 42-27 08 10 Notch NA -

4 Withdraw 26-11 08 10 Notch NA -

Raise power to 98%

5 RTP

- - - RWR - -

Prepared By: __Joe Allen__ SM Approval: _Dave Roe__

(RxEng) (Shift Manager)

Reviewed By: __Bob Jones__

(RxEng or SRO)

Stamps UNIT SUPERVISOR LOI 18-1 NRC Examination Scenario 4 Page 29 of 29

v t e Letter Sequence Other
CAC:000500, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML18074A052, ML18074A053, ML18074A054, ML18074A055, ML18134A128, ML18134A137, ML18149A494, ML18323A272, ML18323A273, ML18323A274, ML19038A054, ML19038A101, ML19038A126, ML19045A271, ML19045A343, ML19045A424, ML19065A224, ML19065A230, ML19066A204, ML19066A214, ML19092A047, ML19217A267, ML19217A268, ML19217A269, ML19217A272, ML19217A273, ML19217A274, ML19298B558, ML19298B559, ML19302E287, ML19302F311, ML19302F437, ML19302F487, ML19330E279, ML19330E366, ML20020A001, ML20020A002, ML20022A259, ML20022A260, ML20022A261, ML20022A262, ML20055D883, ML20055E009, ML20057E559, ML20057E560, ML20087G852, ML20087H514, ML20184A247, ML20184A248, ML20240A318... further results
MONTHYEAR2019-02-07 [Table View]

ML20087G852

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