ML122750409

Draft Operating Exam (Sections a, B, and C)

ML122750409
Person / Time
Site:	FitzPatrick
Issue date:	07/20/2012
From:	Laing D Entergy Nuclear Northeast
To:	Garchow S, Diane Jackson Operations Branch I
Jackson D
Shared Package
ML120270122	List: IR 05000333/2012302 ML120310565 ML12250A011 ML122710023 ML122710026 ML122710033 ML122750357 ML122750389 ML122750393 ML122750396 ML122750409 ML122750422 ML12356A250
References
TAC U01843
Download: ML122750409 (188)

Text

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.1.7 4.4/4.7 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

CANDIDATE NAME: LOGIN ID:

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

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update By:

Date Int Previous Revision Date:

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. 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 Attachment 1 with the following values filled in for steps 1-15:

Step # Value Step # Value Step # Value 1 502 6 0.85 11 625 2 420 7 47 12 3.95 3 159 8 1026 13 4.00 4 155 9 59 14 392 / 392 5 0.85 10 15 391.9 / 391.9 V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. A plant startup is in progress.

B. Verification of Core Thermal Power is required.

C. Data has been recorded by another operator for RAP-7.3.03, Core Thermal Power Evaluation, Attachment 1 Items 1-15.

D. EPIC computer points are not available.

E. Items 14 and 15 were obtained from 02TT-168A/C and B/D on Attachment 3.

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SRO/RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power

• - CRITICAL STEP VII. INITIATING CUE Inform the candidate, Calculate Core Thermal Power manually per section 9.2 of RAP-7.3.03, Core Thermal Power Evaluation.

STEP STANDARD EVALUATION / COMMENT

1. Calculates Feedwater correction Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT factors. Item 16: 392 Item 17: 391.9 Item 18: -28 Item 19: -28.1 Item 20: 1.01031 (1 - 1.02)

Item 21: 1.01034 (1 - 1.02)

2. Calculates Feedwater compensated Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT flows. Item 22: 3.99 (3.95 - 4.05)

Item 23: 4.04 (3.99 - 4.09)

3. Determines enthalpy values. Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT Item 24: 1191.56 (1190.6 - 1192.6)

Item 25: 645.06 (640.45 - 650.04)

Item 26: 366.47 (364.31 - 369.7)

Item 27: 366.47 (364.31 - 369.7)

Item 28: 490.27 (487.89 - 493.84)

Item 29: 396.89 (394.15 - 399.64)

Item 30: 63.046 (60.55 - 65.54)

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SRO/RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power STEP STANDARD EVALUATION / COMMENT

4. Calculates Feedwater flow, Feedwater Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT enthalpy, and Steam enthalpy. Item 31: 8.032 (7.94 - 8.14)

Item 32: 366.4 (364.3 - 369.7)

Item 33: 1191.56 (1190.6 - 1192.6)

• 5. Calculates Q to Feedwater. Records the following on RAP-7.3.03 Attachment 1: CRITICAL STEP Item 34: 1941.9 (1909.7 - 1975.5) SAT / UNSAT

6. Calculates CRD flow. Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT Item 35: 0.0369 (0.03-0.04)

• 7. Calculates Q to CRD. Records the following on RAP-7.3.03 Attachment 1: CRITICAL STEP Item 36: 12.19 (9.8 - 13.3) SAT / UNSAT

8. Calculates RWCU flow and enthalpy Records the following on RAP-7.3.03 Attachment 1: SAT / UNSAT change. Item 37: 0.156 (0.15 - 0.16)

Item 38: 93.38 (88.2 - 99.7)

• 9. Calculates Q to RWCU. Records the following on RAP-7.3.03 Attachment 1: CRITICAL STEP Item 39: 4.28 (3.8 - 4.7) SAT / UNSAT

• 10. Calculates QPUMP. Records the following on RAP-7.3.03 Attachment 1: CRITICAL STEP Item 41: 1.58 (1.57 - 1.59) SAT / UNSAT

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SRO/RO NRC A1 LOI-12-2 TASK TITLE: Manually Calculate Core Thermal Power STEP STANDARD EVALUATION / COMMENT

• 11. Calculates Core Thermal Power. Records the following on RAP-7.3.03 Attachment 1: CRITICAL STEP Item 42: 1957.9 (1922 - 1993.1) SAT / UNSAT Item 43: 77.2 (75.7 - 78.6)

EVALUATOR: Terminate the task at this point.

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HANDOUT

• A plant startup is in progress.

• Verification of Core Thermal Power is required.

• Data has been recorded by another operator for RAP-7.3.03, Core Thermal Power Evaluation, Attachment 1 Items 1-15.

• EPIC computer points are not available.

• Items 14 and 15 were obtained from 02TT-168A/C and B/D on Attachment 3.

Calculate Core Thermal Power manually per section 9.2 of RAP-7.3.03, Core Thermal Power Evaluation.

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 2.1.31 4.6/4.3 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

CANDIDATE NAME: LOGIN ID:

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

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update By:

Date Int Previous Revision Date:

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-4B, HPCI Monthly Operability Test III. TOOLS AND EQUIPMENT C. None IV. SET UP REQUIREMENTS B. Provide a copy of ST-4B completed up to step 8.2.

C. Reset the simulator to an IC (IC-152) with HPCI in a normal standby lineup, except for the following:

a. Set HPCI FLOW CNTRL setpoint between 3800-3900 gpm on panel 09-3.

b. Close INBD STM SUPP VLV 23MOV-15 on panel 09-3.

c. Close COND PMP DISCH TO RADW 23AOV-39 on panel 09-4.

d. Close STM LINE DRN TO RADW 23AOV-42 on panel 09-4.

V. EVALUATOR NOTES D. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

E. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

F. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

G. Should Candidate inform CRS that ST cannot be continued due to the out of position valve or out of spec readings, etc, inform Candidate the deviation has been noted and for them to continue with the ST.

VI. TASK CONDITIONS F. ST-4B, HPCI Monthly Operability Test, is in progress.

G. Other operators have completed ST-4B thru Section 8.1.

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SRO/RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B

• - CRITICAL STEP VII. INITIATING CUE Inform the candidate, Complete ST-4B Section 8.2, HPCI Valve Lineup.

STEP STANDARD EVALUATION / COMMENT

1. Record HPCI FLOW CNTRL output at Records HPCI FLOW CNTRL output as greater than or SAT / UNSAT panel 09-3. equal to 100%.

2. Verify the following lineup at panel 09-3: Verifies the following lineup at panel 09-3 and SAT / UNSAT D. HPCI FLOW CNTRL setpoint - 4300 documents in ST-4B:

gpm M. HPCI FLOW CNTRL setpoint - 3800 - 3900 gpm E. HPCI FLOW CNTRL - AUTO N. HPCI FLOW CNTRL - AUTO F. TEST SPEED ADJUST - Full O. TEST SPEED ADJUST - Full counterclockwise counterclockwise P. TURB GOV VLV 23HOV Closed G. TURB GOV VLV 23HOV Closed Q. TURB STOP VLV 23HOV Closed H. TURB STOP VLV 23HOV R. TURB TEST 23A-S23 - NORMAL Closed S. TEST PWR 23A-S24 - OFF I. TURB TEST 23A-S23 - NORMAL T. OUTBD STM SUPP VLV 23MOV Closed J. TEST PWR 23A-S24 - OFF U. TURB STM SUPP VLV 23MOV Closed K. OUTBD STM SUPP VLV 23MOV-16 - Closed EVALUATOR NOTE: The bolded item above is out-of-spec. Should Candidate inform CRS that ST cannot be L. TURB STM SUPP VLV 23MOV- continued due to the out of spec value, inform Candidate 14 - Closed the deviation has been noted, continue with the ST and the deviation will be corrected by another Operator.

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SRO/RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B STEP STANDARD EVALUATION / COMMENT

2. Verify the following lineup at panel 09-3 Verifies the following lineup at panel 09-3 and SAT / UNSAT (cont.) (cont.): documents in ST-4B (cont.): (cont.)

V. HPCI & RCIC TEST VLV TO CST HH. HPCI & RCIC TEST VLV TO CST 23MOV 23MOV Closed Closed W.MIN FLOW VLV 23MOV II. MIN FLOW VLV 23MOV Closed Closed JJ. INBD TORUS SUCT VLV 23MOV Closed X. INBD TORUS SUCT VLV 23MOV- KK.TEST VLV TO CST 23MOV Closed 58 - Closed LL. STM LINE DRN TRAP BYP VLV 23AOV Y. TEST VLV TO CST 23MOV AUTO Closed MM. TURB EXH COND DRN VLV 23AOV Z. STM LINE DRN TRAP BYP VLV AUTO 23AOV AUTO NN. INBD STM SUPP VLV 23MOV Closed AA. TURB EXH COND DRN VLV 23AOV AUTO OO. OUTBD TORUS SUCT VLV 23MOV Closed BB. INBD STM SUPP VLV 23MOV Open PP.PMP DISCH VLV 23MOV Open CC. OUTBD TORUS SUCT VLV QQ. STM LINE WARMING ISOL VLV 23MOV 23MOV Closed Open DD. PMP DISCH VLV 23MOV-20 RR. CST SUCT VLV 23MOV Open

- Open SS.INJ VLV 23MOV Closed EE. STM LINE WARMING ISOL VLV 23MOV Open EVALUATOR NOTE: The bolded item above is out-of-FF. CST SUCT VLV 23MOV spec. Should Candidate inform CRS that ST cannot be Open continued due to the out of spec value, inform Candidate GG. INJ VLV 23MOV Closed the deviation has been noted, continue with the ST and the deviation will be corrected by another Operator.

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SRO/RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B STEP STANDARD EVALUATION / COMMENT

2. Verify the following lineup at panel 09-3 Verifies the following lineup at panel 09-3 and SAT / UNSAT (cont.) (cont.): documents in ST-4B (cont.): (cont.)

TT. COND PMP DISCH TO WW. COND PMP DISCH TO RADW 23AOV RADW 23AOV AUTO AUTO UU. STM LINE DRN TO RADW XX. STM LINE DRN TO RADW 23AOV Open 23AOV Open YY. HPCI EXH VAC BKR 23MOV Open VV. HPCI EXH VAC BKR 23MOV-59 - Open

3. Verify the following lineup at panel 09-4: Verifies the following lineup at panel 09-4 and SAT / UNSAT

• COND PMP DISCH TO RADW documents in ST-4B (cont.):

23AOV Open

• COND PMP DISCH TO RADW 23AOV Closed

• STM LINE DRN TO RADW 23AOV-

• STM LINE DRN TO RADW 23AOV Closed 42 - 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.

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SRO/RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B STEP STANDARD EVALUATION / COMMENT

• 4. Determines HPCI FLOW CNTRL Determines HPCI FLOW CNTRL setpoint is low. CRITICAL STEP setpoint is low. SAT / UNSAT EVALUATOR NOTE: This determination should be evidenced by a verbal report to the CRS or SM.

• 5. Determines INBD STM SUPP VLV Determines INBD STM SUPP VLV 23MOV-15 is out of CRITICAL STEP 23MOV-15 is out of position. position. SAT / UNSAT EVALUATOR NOTE: This determination should be evidenced by a verbal report to the CRS or SM.

• 6. Determines COND PMP DISCH TO Determines COND PMP DISCH TO RADW 23AOV-39 CRITICAL STEP RADW 23AOV-39 is out of position. is out of position. SAT / UNSAT EVALUATOR NOTE: This determination should be evidenced by a verbal report to the CRS or SM.

• 7. Determines STM LINE DRN TO RADW Determines STM LINE DRN TO RADW 23AOV-42 is out CRITICAL STEP 23AOV-42 is out of position. of position. SAT / UNSAT EVALUATOR NOTE: This determination should be evidenced by a verbal report to the CRS or SM.

EVALUATOR: Terminate the task at this point.

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SRO/RO NRC A2 LOI-12-2 TASK TITLE: Perform HPCI Lineup Verification Per ST-4B HANDOUT

• ST-4B, HPCI Monthly Operability Test, is in progress.

• Other operators have completed ST-4B thru Section 8.1.

Complete ST-4B

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A3 LOI-12-2 TASK TITLE: Determine Tagout Boundary For RBCLC Pump APPL. TO JPM NUMBER Work REV: DATE: NRC K/A SYSTEM NUMBER: 2.2.13 4.1/4.3 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

CANDIDATE NAME: LOGIN ID:

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

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A3 LOI-12-2 TASK TITLE: Determine Tagout Boundary For RBCLC Pump APPL. TO JPM NUMBER Work Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update By:

Date Int Previous Revision Date:

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A3 LOI-12-2 TASK TITLE: Determine Tagout Boundary For RBCLC Pump APPL. TO JPM NUMBER Work I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EN-OP-102, Protective and Caution Tagging B. ESK-6AC C. FM-15A D. OP-40 III. TOOLS AND EQUIPMENT ZZ. None IV. SET UP REQUIREMENTS D. Ensure copies of the following references are available:

a. EN-OP-102

b. ESK-6AC

c. FM-15A

d. OP-40 V. EVALUATOR NOTES H. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

I. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

J. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS H. Troubleshooting is required for Reactor Building Closed Loop Cooling Pump A.

I. The troubleshooting activity will be intrusive to the pump motor and impeller casing.

J. eSOMS is unavailable.

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SRO/RO NRC A3 LOI-12-2 TASK TITLE: Determine Tagout Boundary For RBCLC Pump Work

• - CRITICAL STEP VII. INITIATING CUE Inform the candidate, Generate a tagout isolation boundary for RBCLC Pump A troubleshooting. Record the devices to be tagged and their required positions on the worksheet provided.

STEP STANDARD EVALUATION / COMMENT

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

e. EN-OP-102

f. FM-15A

g. ESK-6AC

h. OP-40 EVALUATOR NOTE: Component names and Required Position terminology may vary slightly from what is written below due to unavailability of eSOMS.

2. Determine RBCLC Pump A control Identifies RBCLC Pump A control switch should be SAT / UNSAT switch tagged position. tagged in the pull-to-lock position.

• 3. Determine RBCLC Pump A breaker Identifies RBCLC Pump A breaker should be tagged in CRITICAL STEP tagged position. the racked out or removed position. SAT / UNSAT

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SRO/RO NRC A3 LOI-12-2 TASK TITLE: Determine Tagout Boundary For RBCLC Pump Work STEP STANDARD EVALUATION / COMMENT

• 4. Determines RBCLC Pump A discharge Identifies RBCLC Pump A discharge isolation valve CRITICAL STEP isolation valve tagged position. (15RBC-2A) should be tagged in the closed position. SAT / UNSAT

• 5. Determines RBCLC Pump A discharge Identifies RBCLC Pump A suction isolation valve CRITICAL STEP isolation valve tagged position. (15RBC-40A) should be tagged in the closed position. SAT / UNSAT

6. Determines RBCLC Pump A venting Identifies one or more of the following paths for venting SAT / UNSAT path tagged position. RBCLC Pump A casing:

• RBCLC Pump A Discharge Pressure Indicator Root Valve (15RBC-645) open with either the Test/Drain valve open or the Pressure Indicator removed/uninstalled.

• RBCLC Pump A Suction Pressure Indicator Root Valve (15RBC-607) open with the Pressure Indicator removed/uninstalled.

• RBCLC Pump A Casing Vent Valve open.

EVALUATOR: Terminate the task at this point.

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HANDOUT

• Troubleshooting is required for Reactor Building Closed Loop Cooling Pump A.

• The troubleshooting activity will be intrusive to the pump motor and impeller casing.

• eSOMS is unavailable.

Generate a tagout isolation boundary for RBCLC Pump A troubleshooting. Record the components to be tagged and their required positions on the worksheet provided.

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WORKSHEET Component Required Position

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And APPL. TO JPM NUMBER Protected Area Evacuation REV: DATE: NRC K/A SYSTEM NUMBER: 2.4.43 3.2/3.8 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

CANDIDATE NAME: LOGIN ID:

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

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And APPL. TO JPM NUMBER Protected Area Evacuation Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update By:

Date Int Previous Revision Date:

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And APPL. TO JPM NUMBER Protected Area Evacuation I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. IAP-1, Emergency Plan Implementation Checklist B. EAP-10, Protected Area Evacuation C. OP-63, Intra-Plant Communications System III. TOOLS AND EQUIPMENT A. Simulator communications equipment (optional)

IV. SET UP REQUIREMENTS E. None V. EVALUATOR NOTES K. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

L. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

M. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS K. A Site Area Emergency has been declared due to high Drywell radiation.

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SRO/RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And Protected Area Evacuation

• - CRITICAL STEP VII. INITIATING CUE Inform the candidate, The Shift Manager directs you to sound the Station Alarm and make the announcement for a Site Area Emergency with accountability per the OP-63 posted attachment twice.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of OP-63 Obtains a controlled copy of OP-63 posted attachment. SAT / UNSAT posted attachment.

EVALUATOR NOTE: The OP-63 posted attachment is kept at the SNO, SM, CRS desks and OP Binders. The candidate should locate and use one of these copies.

• 2. Depress appropriate alarm pushbutton: Depresses STA alarm pushbutton. CRITICAL STEP

• STA for station alarm SAT / UNSAT

• 3. WHEN alarm is to be terminated, Depresses OFF pushbutton. CRITICAL STEP perform one of the following: OR SAT / UNSAT

a. Depress OFF pushbutton. Actuates and holds INSTR toggle switch.

OR

b. Actuate and hold INSTR toggle switch. (Alarm will re-actuate when INSTR toggle switch is released.)

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SRO/RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And Protected Area Evacuation STEP STANDARD EVALUATION / COMMENT

• 4. Make announcement for Site Area Announces the following over site paging system: CRITICAL STEP Emergency with accountability. Attention, Attention. A Site Area Emergency has been SAT / UNSAT declared at JAF due to high Drywell radiation (or similar). Activate all facilities. All personnel in the Protected Area commence accountability using badge readers and sign-in sheets.

5. Repeat announcement for Site Area Announces the following over site paging system: SAT / UNSAT Emergency with accountability. Attention, Attention. A Site Area Emergency has been declared at JAF due to high Drywell radiation (or similar). Activate all facilities. All personnel in the Protected Area commence accountability using badge readers and sign-in sheets.

6. Ensure Station Alarm is secured. If STA alarm was previously interrupted only by INSTR SAT / UNSAT / NA toggle switch, depresses OFF pushbutton.

EVALUATOR CUE: Provide JPM Handout #2 and inform the candidate, The Shift Manager directs you to make the announcement for a Protected Area evacuation with normal egress per the OP-63 posted attachment.

• 7. Depress appropriate alarm pushbutton: Depresses EVAC alarm pushbutton. CRITICAL STEP SAT / UNSAT

• EVAC for evacuation alarm

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SRO/RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And Protected Area Evacuation STEP STANDARD EVALUATION / COMMENT

• 8. WHEN alarm is to be terminated, Depresses OFF pushbutton. CRITICAL STEP perform one of the following: OR SAT / UNSAT

a. Depress OFF pushbutton. Actuates and holds INSTR toggle switch.

OR

b. Actuate and hold INSTR toggle switch. (Alarm will re-actuate when INSTR toggle switch is released.)

• 9. Make announcement for Protected Area Announces the following over site paging system: CRITICAL STEP evacuation with normal egress. Attention, Attention: all personnel. A high radiation SAT / UNSAT level exists in the Drywell (or similar). All non-essential personnel evacuate the Protected Area and proceed to the Training building auditorium. All essential personnel inside the Protected Area fence proceed to your designated primary assembly area. Personnel outside the Protected Area fence proceed to the Training building auditorium.

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SRO/RO NRC A4 LOI-12-2 TASK TITLE: Conduct Emergency Announcement And Protected Area Evacuation STEP STANDARD EVALUATION / COMMENT

10. Repeat announcement for Protected Announces the following over site paging system: SAT / UNSAT Area evacuation with normal egress. Attention, Attention: all personnel. A high radiation level exists in the Drywell (or similar). All non-essential personnel evacuate the Protected Area and proceed to the Training building auditorium. All essential personnel inside the Protected Area fence proceed to your designated primary assembly area. Personnel outside the Protected Area fence proceed to the Training building auditorium.

11. Ensure Evacuation Alarm is secured. If EVAC alarm was previously interrupted only by INSTR SAT / UNSAT / NA toggle switch, depresses OFF pushbutton.

EVALUATOR: Terminate the task at this point.

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HANDOUT A Site Area Emergency has been declared due to high Drywell radiation.

The Shift Manager directs you to sound the Station Alarm and make the announcement for a Site Area Emergency with accountability per the OP-63 posted attachment twice.

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HANDOUT #2 The Shift Manager directs you to make the announcement for a Protected Area evacuation with normal egress per the OP-63 posted attachment.

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P1 LOI-12-2 TASK TITLE: Restore H2O2 Monitors Following Isolation APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 223002 A2.09 3.6/3.7 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER X:\EXAMS\FITZPATRICK\DRAFT EXAM\DRAFT OPERATING\JF-2012-09-DRAFT OPERATING TEST.docx

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC P1 LOI-12-2 TASK TITLE: Restore H2O2 Monitors Following Isolation APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

1.

Current Update: By:

Date Int.

Previous Revision Date:

-33 of 188-

b. SAFETY CONSIDERATIONS A. None

c. REFERENCES A. OP-37, Containment Atmosphere Dilution System.

B. EP-2, Isolation/Interlock Overrides.

d. TOOLS AND EQUIPMENT A. None

e. 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.

f. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

g. 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. EOP-4 directs restoration of H2/O2 monitors.

-34 of 188-

h. INITIATING CUE Inform the candidate, "The CRS directs you to restore H2O2 monitors per Section 5.25 of EP-2 and then reinitialize 27PCX-101A per section D.2 of OP-37.

• - CRITICAL STEP STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-2. SAT / UNSAT EP-2, ISOLATION/INTERLOCK OVERRIDES. EVALUATOR: Provide working copy of EP-2.

NOTE: Steps 2 & 3 may be performed in any order or concurrently per EP-2

• 2. Place EMERG MANUAL At Panel 27MAP, places EMERG MANUAL OVERRIDE OVERRIDE SYSTEM A SYSTEM A switch in OVER/RI. CRITICAL STEP keylock switch in OVER/RI at SAT / UNSAT panel 27MAP. EVALUATOR CUE: Inform candidate keylock switch is in override.

• 3. Place EMER MANUAL At Panel 27MAP, places EMERG MANUAL OVERRIDE CRITICAL STEP OVERRIDE SYSTEM B SYSTEM b switch in OVER/RI.

SAT / UNSAT keylock switch in OVER/RI at panel 27MAP. EVALUATOR CUE: Inform candidate keylock switch is in override.

-35 of 188-

STEP STANDARD EVALUATION / COMMENT

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

EVALUATOR: Provide working copy of OP-37.

5. Ensure LOCAL POWER Observes LOCAL power switch in OFF. SAT / UNSAT 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.

• 6. Ensure open one set of the EVALUATOR NOTE \ CUE: If Candidate asks which Sample CRITICAL STEP following valve pairs: Path to use: inform Candidate to use normal path.

SAT / UNSAT

• SAMPLE GAS SUPP (The normal path is the Supp Pool 27SOV-119E1/E2)

POOL SAMP VALVE 27SOV-119E1

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

27SOV-119E2 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.

Attempts to open one of the following pairs of valve by placing control switches to OPEN:

• SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E1

• SAMPLE GAS SUPP POOL SAMP VALVE 27SOV-119E2

-36 of 188-

STEP STANDARD EVALUATION / COMMENT

• 7. Ensure open one set of the EVALUATOR CUE: If Candidate asks which Sample Path to CRITICAL STEP following valve pairs: use: inform Candidate to use DW mid path.

SAT / UNSAT

• SAMPLE GAS DRYW EVALUATOR CUE: For each valve in the second pair, when MID SAMP VALVE the candidate indicates the control switch is moved to open, 27SOV-120E1/E2 then inform the candidate that the red light came on the green light is off.

Attempts to open a different pair of the following valves by placing control switches to OPEN:

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

• 27SOV-120E2

• 8. Ensure open the following Places the control switch to the OPEN position for: CRITICAL STEP valves at MAP:

• SAMPLE GAS RETURN SAMP VALVE 27SOV-124E1 SAT / UNSAT

• SAMPLE GAS

• SAMPLE GAS RETURN SAMP VALVE 27SOV-124E2 RETURN SAMP VALVE 27SOV-124E1

• SAMPLE GAS EVALUATOR CUE: For each valve, when the candidate RETURN SAMP indicates the control switch is moved to open inform the VALVE 27SOV-124E2 candidate that the red light is on, the green light is off.

9. Ensure PUMP switch is in Observes PUMP switch in RUN. SAT / UNSAT RUN.

EVALUATOR CUE: If asked, inform the candidate it is in RUN.

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STEP STANDARD EVALUATION / COMMENT

10. Ensure POWER keylock Observes POWER keylock switch in ON. SAT / UNSAT switch is in ON.

EVALUATOR CUE: If asked, inform the candidate the keylock switch is in ON.

• 11. Depress 6. Depresses 6 on 27PCX-101A keypad. CRITICAL STEP 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.

• 12. When ENTER ACCESS Depresses 8, then 2, and then Enter key on 27PCX-101A CRITICAL STEP CODE appears on CRT keypad. SAT / UNSAT screen, perform the following:

a) Depress 8. EVALUATOR CUE: When the candidate indicates 8, 2 and b) Depress 2. Enter keys would be depressed, then state the monitor c) Depress ENTER. display appears on CRT screen.

• 13. WHEN monitor display Depresses 1 and then ESC key on 27PCX-101A keypad. CRITICAL STEP appears on CRT screen, SAT / UNSAT perform the following:

EVALUATOR CUE: When the candidate states he/she would a) Depress 1. depress 1 then ESC, inform the candidate that the 27PCX-b) Depress ESC. 101 graphic display is now visible.

14. Verify the following on Observes the following: SAT / UNSAT 27PCX-101A display:

• SV-1 open

• SV-1 is open

• SV-6 open

• SV-6 is open

• P1 running

-38 of 188-

STEP STANDARD EVALUATION / COMMENT

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

EVALUATOR: Terminate the task at this point.

-39 of 188-

HANDOUT

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

• The cause of the isolation has been determined.

• EOP-4 directs restoration of H2/O2 monitors.

The CRS directs you to 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.

-40 of 188-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P2 LOI-12-2 TASK TITLE: Cross-tie Fire Protection System To Inject To RHR Service Water APPL. TO JPM NUMBER NRC K/A SYSTEM NUMBER: 295031 EA1.08 3.8/3.9 ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

APPLICANT NAME: LOGIN ID:

JPM Completion X Simulated Performed Location: Plant Simulator X

DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED Page 41 of 188

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P2 LOI-12-2 TASK TITLE: Cross-tie Fire Protection System To Inject To RHR Service Water APPL. TO JPM NUMBER

i. SAFETY CONSIDERATIONS A. Comply with JAF Safety Standards and Requirements.

j. REFERENCES A. EP-8, Alternate Injection Systems

k. TOOLS AND EQUIPMENT A. Emergency cross connect hose located in the North Safety Pump Room.

B. N1 key.

l. SET UP REQUIREMENTS A. Make copy of EP-8 as handout for applicant.

m. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

Page 42 of 188

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P2 LOI-12-2 TASK TITLE: Cross-tie Fire Protection System To Inject To RHR Service Water APPL. TO JPM NUMBER

n. TASK CONDITIONS A. To maintain RPV water level above 0, water level control must be augmented by using the lake as a source.

B. The RHRSW pumps are unavailable.

Page 43 of 188

o. INITIATING CUE Inform the candidate, The CRS directs you to align the Fire Protection System to RHR Service Water A per EP-8 Section 5.3.

• - CRITICAL STEP STEP STANDARD EVALUATION / COMMENT

1. Verify the following RHR Contacts control room to verify RHR pumps A and C are SAT / UNSAT pumps are stopped: stopped.

• RHR PMP 10P-3A

• RHR PMP 10P-3C EVALUATOR CUE: RHR pumps A and C are stopped.

• 2. Remove caps from the Rotates caps counterclockwise and removes from: CRITICAL STEP following valves:

• 10RHR-432 (RHRSW to fire protection cross-tie isol SAT / UNSAT

• 10RHR-432 (RHRSW to valve) fire protection cross-tie

• 76FPS-720 (RHRSW/fire protection cross-tie isol valve) isol valve)

• 76FPS-720 (RHRSW/fire protection cross-tie isol EVALUATOR CUE: Both pipe caps are removed.

valve)

• 3. Connect hose (stored in Connects hose between valves: CRITICAL STEP cabinet 76CAB-1 on west wall

• 10RHR-432 SAT / UNSAT of north emergency service water room, N1 Key) between

• 76FPS-720 the following valves:

• 10RHR-432 EVALUATOR CUE: The hose is connected between the

• 76FPS-720 indicated valves.

NOTE: The candidate should locate the hose but not move it.

Page 44 of 188

STEP STANDARD EVALUATION / COMMENT

4. Ensure closed RHRSW Contacts control room to ensure closed RHRSW DISCH SAT / UNSAT DISCH VLV FROM HX A VLV FROM HX A 10MOV-89A.

10MOV-89A.

EVALUATOR CUE: 10MOV-89A is closed.

5. Start one or more of the Contacts the control room to start a Fire Pump. SAT / UNSAT following pumps:

EVALUATOR CUE: Report that the Electric Fire Pump has

• ELEC FIRE PMP 76P-2 been started.

• DIESEL FIRE PMP 76P-1

• DIESEL FIRE PMP 76P-4

• 6. Unlock and open the following Unlocks, removes locking mechanism and rotates CRITICAL STEP valves: handwheels counterclockwise to open the following valves: SAT / UNSAT

• 10RHR-432

• 10RHR-432

• 76FPS-720

• 76FPS-720 EVALUATOR CUE: The indicated valves are unlocked and open. Water is flowing thru hose.

Terminate the task at this point.

Page 45 of 188

HANDOUT

• To maintain RPV water level above 0, water level control must be augmented by using the lake as a source.

• The RHRSW pumps are unavailable.

The CRS directs you to align the Fire Protection System to RHR Service Water A per EP-8 Page 46 of 188

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P3 LOI-12-2 TASK TITLE: RCIC Turbine Trip/Throttle Valve Reset With Tappet Failure APPL. TO JPM NUMBER NRC K/A SYSTEM NUMBER: 217000 A2.02 3.8/3.7 ESTIMATED COMPLETION TIME: 15 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

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

APPLICANT NAME: LOGIN ID:

JPM Completion X Simulated Performed Location: Plant Simulator X

DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: Satisfactory Unsatisfactory

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED Page 47 of 188

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P3 LOI-12-2 TASK TITLE: RCIC Turbine Trip/Throttle Valve Reset With Tappet Failure APPL. TO JPM NUMBER

p. SAFETY CONSIDERATIONS A. Comply with JAF Safety Standards and Requirements.

q. REFERENCES A. OP-19, Reactor Core Isolation Cooling System

r. TOOLS AND EQUIPMENT A. None

s. SET UP REQUIREMENTS A. Make copy of OP-19 as handout for applicant.

t. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

Page 48 of 188

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC P3 LOI-12-2 TASK TITLE: RCIC Turbine Trip/Throttle Valve Reset With Tappet Failure APPL. TO JPM NUMBER

u. TASK CONDITIONS A. A Reactor scram has occurred.

B. The MSIVs are closed.

C. An inadvertent local manual trip of the RCIC turbine has occurred.

Page 49 of 188

v. INITIATING CUE Inform the candidate, The CRS directs you to reset 13HOV-1 per OP-19 Section G.6.

• - CRITICAL STEP STEP STANDARD EVALUATION / COMMENT

• 1. Manually operate 13HOV-1 Rotates 13HOV-1 handwheel clockwise to closed position. CRITICAL STEP handwheel to closed position. SAT / UNSAT EVALUATOR CUE: 13HOV-1 handwheel is in closed position.

2. IF turbine trip was from Determines from task conditions that turbine trip was a local SAT / UNSAT overspeed or local manual, manual trip.

THEN perform the following:

• 3. Pull spring loaded emergency Pulls emergency connecting rod to move emergency head CRITICAL STEP connecting rod against spring lever away from emergency tappet and tappet nut. SAT / UNSAT force, moving emergency head lever away from emergency tappet and tappet EVALUATOR CUE: The emergency connecting rod has nut. moved.

4. Verify emergency tappet and Observes emergency tappet and tappet nut position. SAT / UNSAT tappet nut moves downward into reset position, engaging EVALUATOR CUE: Emergency tappet and tappet nut did head lever and holding NOT move into the reset position.

emergency connecting rod in position under spring tension.

Page 50 of 188

STEP STANDARD EVALUATION / COMMENT

5. IF emergency tappet and Recognizes that emergency tappet and tappet nut did not SAT / UNSAT tappet nut did not move into move into reset position and alternate steps are required.

the reset position per Step G.6.2b, THEN perform the following:

• 6. Lift up on RCIC manual trip Lifts up on RCIC manual trip level while pulling spring CRITICAL STEP lever while pulling spring loaded emergency connecting rod to move emergency head SAT / UNSAT loaded emergency connecting lever away from emergency tappet and tappet nut.

rod against spring force, moving emergency head lever away from emergency tappet and tappet nut.

7. Verify emergency tappet and Observes emergency tappet and tappet nut position. SAT / UNSAT tappet nut moves downward into "reset" position, engaging EVALUATOR CUE: Emergency tappet and tappet nut DID head lever and holding move into the reset position.

emergency connecting rod in position under spring tension.

8. Ensure trip hook engages Observes trip hook and latchup lever. SAT / UNSAT latchup lever.

EVALUATOR CUE: Trip hook has engages latchup lever.

• 9. Manually open 13HOV-1 to full Rotates 13HOV-1 handwheel counterclockwise to full open CRITICAL STEP open. position. SAT / UNSAT EVALUATOR CUE: 13HOV-1 handwheel is in full open position.

10. Manually close one-quarter Rotates 13HOV-1 handwheel clockwise one-quarter turn. SAT / UNSAT Page 51 of 188

STEP STANDARD EVALUATION / COMMENT turn 13HOV-1 handwheel to allow for thermal expansion. EVALUATOR CUE: 13HOV-1 handwheel is one-quarter turn closed.

11. Verify annunciator 09-4-1-14 Contacts control room to verify annunciator 09-4-1-14 is SAT / UNSAT RCIC TRIP is clear. clear.

EVALUATOR CUE: Annunciator 09-4-1-14, RCIC TRIP, is clear.

12. Verify TURB TRIP & Contacts control room to verify TURB TRIP & THROTTLE SAT / UNSAT THROTTLE VLV 13HOV-1 VLV 13HOV-1 indicates open at panel 09-4.

indicates open at panel 09-4.

EVALUATOR CUE: TURB TRIP & THROTTLE VLV 13HOV-1 indicates open at panel 09-4.

Terminate the task at this point.

Page 52 of 188

HANDOUT

• A Reactor scram has occurred.

• The MSIVs are closed.

• An inadvertent local manual trip of the RCIC turbine has occurred.

The CRS directs you to reset 13HOV-1 per OP-19 Section G.6.

ENTERGY - FITZPATRICK JOB PERFORMANCE MEASURE S/RO NRC S1 LOI-12-2 TASK TITLE: EDG Load Run with Governor Failure (Alt Path)

APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 2640000 A4.04 3.7/3.7 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: _______

ESTIMATED COMPLETION TIME: 18 Minutes SUBMITTED: OPERATION REVIEW:

APPROVED: __________________________

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

CANDIDATE NAME:

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

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-54 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S1 LOI-12-2 TASK TITLE: EDG Load Run with Governor Failure (Alt Path)

APPL. TO JPM NUMBER Current Update: By:

Date Int.

Outstanding Items:

Technical Review Additional Information Questions and Answers ___ Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Dates:

-55 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S1 LOI-12-2 TASK TITLE: EDG Load Run with Governor Failure (Alt Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST B. OP-22, DIESEL GENERATOR EMERGENCY POWER III. TOOLS AND EQUIPMENT A. Synchronizing Switch IV. SET UP REQUIREMENTS A. Initialize the simulator to IC 151.

B. Obtain a controlled copy of ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST. Initial as complete Section 4.0, 5.0 and Step 8.1 through and including Step 8.7.

C. Copies of EDG Demand Log for EDG B & D forms from OP-22, DIESEL GENERATOR EMERGENCY POWER.

D. Trigger 1 = EDG B Governor Switch to Raise.

E. Event trigger 1 = dgpdgen(2)>900000.

F. Trigger 2 = EDG B KW meter = 3000.

G. Event Trigger 2 = dgpdgen(2) >3,000,000. Command = dor zdi1c1edgb11 V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, placekeeping and self checking.

VI. TASK CONDITIONS A. EDG B and D load testing is in progress with ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST complete through Step 8.7.

-56 of 188-

• - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to perform ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST, starting at Step 8.8 for EDGs B & D."

NOTE: All controls and indications located on panel 09-8 unless otherwise stated.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of procedure Obtains a controlled copy of ST-9BB SAT / UNSAT ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST

2. Reviews the precautions Reviews the precautions, making note of any that are SAT / UNSAT applicable

3. Select the correct section to perform the Selects Section 8.8 of ST-9BB SAT / UNSAT task.

4. Verify the following Annunciators are Verifies 09-8-4-11 and 09-8-4-14 alarms are clear SAT / UNSAT clear:

• 09-8-4-11 EDG B ENG TROUBLE OR SHUTDOWN

• 09-8-4-14 EDG D ENG TROUBLE OR SHUTDOWN

5. IF both of the following conditions exist: Request reading of outside air temperature on 17WR- SAT / UNSAT

-57 of 188-

STEP STANDARD EVALUATION / COMMENT 101K, CHAN A, digital indication at panel 17EMRP.

• Outside ambient temperature is GREATER THAN 88 deg F on 17WR-101K, CHAN A, digital EVALUATOR: When asked for outside air temperature, indication at panel 17EMRP. inform the candidate that it is 60 deg F.

AND

• Screenwell intake temperature is GREATER THAN 78 deg F on EPIC-A-1503 or EPIC-A-1504 THEN ..

6. Station 3 operators with stopwatches to Request Operators with stopwatches to monitor/record: SAT / UNSAT monitor/record times for:

• Frequency

• Frequency

• Voltage

• Voltage

• Steady State Voltage and Frequency

• Steady State Voltage and Frequency EVALUATOR: When requested, inform candidate that the 3 operators are briefed on responsibilities and are stationed with stop watches.

Candidate may inform CRS to declare EDG B system inoperable. Inform Candidate, CRS acknowledges report.

• 7. Simultaneously place the EDG B & D Simultaneously places the EDG B & D control switches CRITICAL STEP control switches to START and start all in START.

SAT / UNSAT 3 stopwatches.

-58 of 188-

STEP STANDARD EVALUATION / COMMENT

8. Record stopwatch times for: Requests for and records stopwatch times. SAT / UNSAT

• Frequency EVALUATOR: When requested, inform candidate that the stopwatch times are:

• Voltage

• Frequency - 6 secs

• Steady State Voltage and Frequency

• Voltage - 6 secs

• Steady State Voltage and Frequency - 7 secs

9. Record EDG B/D frequency and For both B & D EDGs, records frequency and voltage. SAT / UNSAT voltage.

10. Verify the following: Verifies the following by observing the control switch red SAT / UNSAT indicating light is on and the green light is off:

• EDG B & D TIE BKR 10604 is closed

• EDG B & D TIE BKR 10604 is closed

• ESW pump 46P-2B is running

• ESW pump 46P-2B is running

• 11. Trip tie Breaker 10604 and allow switch Places the control switch for Breaker 10604, EDG B & D CRITICAL STEP to spring return to AUTO position and TIE BKR, to TRIP, allow switch to spring return to AUTO SAT / UNSAT record the time.

-59 of 188-

STEP STANDARD EVALUATION / COMMENT Records time the control switch for Breaker 10604, EDG SAT / UNSAT B & D TIE BKR, is placed to TRIP

12. Record EDG B/D frequency For both B & D EDGs, records frequency. SAT / UNSAT

13. Verify EPIC-D-732 closed and open on Verifies EPIC-D-732 closed and open on alarm typer. SAT / UNSAT alarm typer.

• 14. Place EDG B and D governor mode Places the EDG GOV MODE toggle switches for EDGs CRITICAL STEP switches in the droop position B&D to DROOP SAT / UNSAT

15. IF an EDG functions improperly while Reads the actions for an improperly functioning EDG. SAT / UNSAT paralleled with 10600 bus, THEN perform the following:

EVALUATOR NOTE: This step is to be used by the

• Trip associated EDG load operator to trip the associated load breaker towards the breaker. end of this JPM.

• Shut down malfunctioning EDG per Section G of OP-22 (Single EDG Shutdown from Control Room).

16. Steps 8.27 and 8.28 may be performed Request direction from SM. SAT / UNSAT in any order per SM direction.

EVALUATOR CUE: Inform the candidate that EDG B is to be paralleled first.

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STEP STANDARD EVALUATION / COMMENT

• 17. Place EDG B LOAD BKR SYNCH SW Places the EDG B LOAD BKR SYNCH SW to ON CRITICAL STEP in ON SAT / UNSAT

• 18. Adjust EDG B VOLT REG to match Matches INCOMING (EDG) and RUNNING (bus 10600) CRITICAL STEP INCOMING and RUNNING voltages voltages with EDG B VOLT REG adjustments SAT / UNSAT

• 19. Adjust EDG B GOV to rotate Adjusts EDG B GOV to rotate synchroscope slowly in CRITICAL STEP synchroscope slowly in the FAST fast direction SAT / UNSAT direction (clockwise)

• 20. When EDG B and the 10600 BUS are Places the control switch 10602, EDG B LOAD BKR, to CRITICAL STEP in phase (synchroscope at 12 oclock) CLOSE when synchroscope is at 12:00 SAT / UNSAT close EDG B LOAD BKR 10602

• 21. Adjust EDG B GOV to raise EDG B Places the EDG B GOV switch to RAISE and loads EDG CRITICAL STEP load to between 100 and 300 Kw B to between 100 and 300 kW SAT / UNSAT

22. Place EDG B LOAD BKR SYNCH SW Places the EDG B LOAD BKR SYNCH SW to OFF and SAT / UNSAT in OFF and remove synch switch removes synch switch handle.

handle.

NOTE: When EDG B load reaches approximately 900 KW, the governor will malfunction and run to approximately 3050 KW. Further adjustments of the EDG B GOV switch will have no effect.

-61 of 188-

STEP STANDARD EVALUATION / COMMENT

23. Adjust EDG B GOV to raise EDG B Adjusts EDG B GOV to raise EDG B load to >2340 KW SAT / UNSAT load to 2340 KW and 2600 kW over and >2600 kW over 3 to 5 minutes in 800 kW 3 to 5 minutes in approximately 800 kW increments.

increments

• 24. Recognize EDG B Governor Trips EDG B load breaker by either: CRITICAL STEP malfunction.

SAT / UNSAT

• Placing the control switch for 10602, EDG B LOAD BKR, to TRIP

• Placing the EDG B control switch in STOP EVALUATOR: Terminate the task at this point

-62 of 188-

HANDOUT EDG B and D load testing is in progress with ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST complete through Step 8.7.

The CRS directs you to perform ST-9BB, EDG B & D FULL LOAD TEST AND ESW PUMP OPERABILITY TEST, starting at Steps 8.8 for EDG B & D.

-63 of 188-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S2 LOI-12-2 TASK TITLE: Switching Relay Room Supply and Exhaust Fans APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 290003 A4.02 2.8/2.8 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: OP-56 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-64 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S2 LOI-12-2 TASK TITLE: Switching Relay Room Supply and Exhaust Fans APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-65 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S2 LOI-12-2 TASK TITLE: Switching Relay Room Supply and Exhaust Fans APPL. TO JPM NUMBER

w. SAFETY CONSIDERATIONS A. None

x. REFERENCES A. OP-56, Relay Room Ventilation and Cooling

y. TOOLS AND EQUIPMENT A. None

z. SET UP REQUIREMENTS A. Initialize the simulator to IC-153.

B. Control Room Ventilation Train A in service.

C. Relay Room Ventilation Train B in service.

aa. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

bb. TASK CONDITIONS A. Relay Room Ventilation train B was placed in service last Shift to support maintenance on train A.

B. Relay Room Ventilation train A is now ready to be placed back in service.

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• - CRITICAL STEP cc. INITIATING CUE Inform the candidate, "The CRS directs you to switch Relay Room supply and exhaust fans to the A train per OP-56 Relay Room Ventilation and Cooling.

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

1. Obtain a controlled copy of Obtains a controlled copy of OP-56. SAT / UNSAT OP-56 Relay Room Ventilation Reviews Notes.

and Cooling.

2. Select the correct section to Selects Section G.5 of OP-56, Switching Relay Room SAT / UNSAT perform the task. Supply and Exhaust Fans.

3. Place Relay Room ventilation SAT / UNSAT Selects Subsection G.3.

in purge per Subsection G.3.

4. Place the following Relay Places Isol & Purge Cntrl A and Isol & Purge Cntrl B SAT / UNSAT Room Vent control switches in switches in Purge position.

PURGE:

• Isol & Purge Cntrl A

• Isol & Purge Cntrl B

5. Verify closed the following Verifies closed Recirc A 70MOD-104A and Recirc B SAT / UNSAT dampers: 70MOD-104B.

• Recirc A 70MOD-104A Green light on, Red light off

• Recirc B 70MOD-104B

6. Verify open the following Verifies open Exh 70MOD-103 and Inlet 70MOD-100. SAT / UNSAT dampers:

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STEP STANDARD EVALUATION / COMMENT Red light on, Green light off

• Exh 70MOD-103

• Inlet 70MOD-100

7. Place control switch for the Note: Candidate returns to G.5.2.

following in Pull-to-Lock and verify associated damper is closed:

a. Standby Control Room air Places control switch for Fan 70AHU-3B in Pull-to-Lock SAT / UNSAT handling unit 70AHU-3B (PTL).

Green and Red light Off Verifies closed Discharge Damper AHU-3B Disch 70MOD- SAT / UNSAT 106B.

Green light on, Red light off

b. Standby Control Room Places control switch for Fan 70FN-4B in Pull-to-Lock SAT / UNSAT exhaust fan 70FN-4B (PTL).

Green and Red light Off Verifies closed Discharge Damper FN-4B Disch 70MOD- SAT / UNSAT 108B.

Green light on, Red light off

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STEP STANDARD EVALUATION / COMMENT

c. Standby Relay Room exhaust Places control switch for Fan 70FN-13A in Pull-to-Lock SAT / UNSAT fan 70FN-13A (PTL).

Green and Red light Off Verifies closed Discharge Damper FN-13A Disch 70MOD- SAT / UNSAT 102A.

Green light on, Red light off

• d. Running Relay Room air Places control switch for Fan 70AHU-12B in Pull-to-Lock CRITICAL STEP handling unit 70AHU-12B (PTL). SAT / UNSAT Green and Red light Off Verifies closed Discharge Damper AHU-12B Disch SAT / UNSAT 70MOD-101B.

Green light on, Red light off

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STEP STANDARD EVALUATION / COMMENT

• 12. Place control switch for the Places the control switch for Fan 70AHU-12A to ON. CRITICAL STEP other Relay Room air SAT / UNSAT handling unit to ON, spring Red light On, Green light Off return to normal, and verify the associated discharge damper opens.

Verifies open Discharge Damper AHU-12A Disch 70MOD- SAT / UNSAT 101A.

Red light On, Green light Off

• 13. Place control switch for the Places the control switch for Fan 70FN-13B to Pull-to Lock CRITICAL STEP running Relay Room exhaust (PTL). SAT / UNSAT fan in Pull-to Lock and verify the associated discharge Green and Red light Off damper closes:

Verifies closed Discharge Damper FN-13B Disch 70MOD- SAT / UNSAT 102B.

Green light On, Red light Off

• 14. Place control switch for the Places the control switch for Fan 70FN-13A to ON. CRITICAL STEP other Relay room exhaust fan SAT / UNSAT to ON, spring return to normal, Red light On, Green light Off and verify the associated discharge damper opens:

-70 of 188-

STEP STANDARD EVALUATION / COMMENT Verifies open Discharge Damper FN-13A Disch 70MOD- SAT / UNSAT 102A.

Red light On, Green light Off

• 15. Ensure the following control Ensures the following control switches are restored from CRITICAL STEP switches are restored from Pull-to-Lock to green flagged: SAT / UNSAT Pull-to-Lock to green flagged:

• 70AHU-12B

• 70FN-13B

• 70AHU-3B

• 70FN-4B Switch in center position, Flag green

16. Restore Relay Room Selects Subsection G.4 and begins at Step 1. SAT / UNSAT ventilation from purge per Subsection G.4

• 17. Place the following Relay Places/verifies Isol & Purge Cntrl A and Isol & Purge CRITICAL STEP Room Ventilation control Cntrl B switches in Auto position. SAT / UNSAT switches in AUTO:

• Isol & Purge Cntrl A

• Isol & Purge Cntrl B

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STEP STANDARD EVALUATION / COMMENT EVALUATOR: Terminate the task at this point.

-72 of 188-

HANDOUT A. Relay Room Ventilation train B was placed in service last Shift to support maintenance on train A.

B. Relay Room Ventilation train A is now ready to be placed back in service.

The CRS directs you to switch Relay Room supply and exhaust fans to the A train per OP-56 Relay Room Ventilation and Cooling.

-73 of 188-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S3 LOI-12-2 TASK TITLE: Start Reactor Recirc Pump - High Vib trip (Alt Path)

APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 202001 A4.01 3.7/3.7 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: OP-27 ESTIMATED COMPLETION TIME: 15 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER Page 74 of 188

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S3 LOI-12-2 TASK TITLE: Start Reactor Recirc Pump - High Vib trip (Alt Path)

APPL. TO JPM NUMBER dd. SAFETY CONSIDERATIONS A. None ee. REFERENCES A. OP-27, Recirculation System ff. TOOLS AND EQUIPMENT A. None gg. SET UP REQUIREMENTS A. Initialize simulator to power operating IC (IC-152).

B. RWR Pump B at minimum flow.

C. RWR Pump A ready to start, up through OP-27 Step G.10.38.

D. Trigger 10 = Malfunction for high vibrations on RWR pump A.

E. Event trigger 10 = 02MOV-53A near full open.

F. Ensure ST-26K requirements will be met.

hh. EVALUATOR NOTES A. The Candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the Candidate that the conditions of each step need only be properly identified and not actually performed.

C. The Candidate should demonstrate proper use of HU tools such as procedure use, self checking and three-point communication.

ii. TASK CONDITIONS A. The Plant is operating in Mode 1.

B. RWR Pump B is running.

C. RWR Pump A is ready to start.

-75 of 188-

jj. INITIATING CUE The CRS directs you to start RWR Pump A per OP-27, beginning at Step G.10.39.

• - CRITICAL STEP STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of OP- The Candidate obtains a controlled copy of OP-27. SAT / UNSAT 27, Recirculation System.

2. Reviews the precautions. Reviews the precautions associated with the procedure. SAT / UNSAT

3. Select the correct section to Selects Section G of OP-27. SAT / UNSAT perform the task.

• 4. Start RWR PMP 02-2P-1A. Rotates RWR Pump A control switch clockwise to CRITICAL STEP START. SAT / UNSAT

5. Perform the following: Observes normal start parameters. SAT / UNSAT

a. Verify speed rises to approximately 80% on RWR MG A SPEED CNTRL.

b. Verify RWR MG A GEN FIELD BKR closes.

c. Ensure speed returns to approximately 26% on RWR MG A.

-76 of 188-

STEP STANDARD EVALUATION / COMMENT

• 6. Slowly open RWR PMP A Slowly opens 02MOV-53A by rotating control switch CRITICAL STEP DISCH 02MOV-53A as follows: clockwise. SAT / UNSAT Evaluator Note: The procedure provides a bump and wait methodology with suggested operating and wait times. The valve should take approximately 1-2 minutes to open.

Evaluator Note: When 02MOV-53A nears the full open position, high pump vibrations will be automatically inserted, leading to the JPM alternate path.

7. Observes annunciator for high Candidate acknowledges alarm and reports condition to SAT / UNSAT motor vibs (09-4-2-18). supervisor (examiner).

8. Refers to ARP 09-4-2-18. Refers to ARP. SAT / UNSAT

9. Attempt to clear alarm by Depresses RWR PMP A VIB ALARM pushbutton. SAT / UNSAT depressing RWR PMP A VIB ALARM pushbutton.

10. If annunciator 09-4-2-18 does Note: RWR vibs are read in Relay Room. Candidate SAT / UNSAT not clear may state they are going to the Relay Room.

Evaluator Cue: Report that all X-Y RWR Pump A vibrations readings are 10 mils.

Recognizes RWR Pump A vibrations are above RESTRICTED level.

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STEP STANDARD EVALUATION / COMMENT

11. If any A RWR 1A X or Y value Recognizes RWR Pump A speed is already at minimum. SAT / UNSAT reaches (RESTRICTED), then perform the following:

Evaluator Cue: Report that all RWR Pump A vibrations readings are still 10 mils.

Reduce A RWR pump speed to reduce seal area vibration to below ALERT trigger.

12. IF RWR Pump B is running, Continues at Step G.2.2c. SAT / UNSAT THEN perform the following:

If RWR Pump A must be shutdown to protect plant equipment whose failure could adversely impact plant safety (example: RWR pump high temp alarm), THEN continue at Step G.2.2c.

13. WHEN RWR Pump A trips, Evaluator Cue: Another operator will perform AOP-8. SAT / UNSAT execute AOP-8 concurrently with this procedure.

Acknowledges cue.

• 14. Close RWR PMP A DISCH Rotates 02MOV-53A control switch counterclockwise. CRITICAL STEP 02MOV-53A. SAT / UNSAT

-78 of 188-

STEP STANDARD EVALUATION / COMMENT

15. Verify RWR PMP 02-2P-1A is Verifies RWR PMP 02-2P-1A tripped. SAT / UNSAT tripped.

Booth Operator: Remove hi Vib alarm when Recirc pump trips.

16. Place RWR PMP 02-2P-1A Places RWR PMP 02-2P-1A control switch in PTL. SAT / UNSAT control switch in PTL.

17. Verify open RWR MG A GEN Verifies field breaker opens 17 seconds after drive motor SAT / UNSAT FIELD BKR. breaker trips.

EVALUATOR Terminate the task at this point.

-79 of 188-

Handout A. The Plant is operating in Mode 1.

B. RWR Pump B is running.

C. RWR Pump A is ready to start.

The CRS directs you to start RWR Pump A per OP-27, beginning at Step G.10.39.

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S4 LOI-12-2 TASK TITLE: Initiate RCIC in Pressure Control with Speed APPL. TO JPM NUMBER Failure (Alt Path)

REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 217000 A4.07 3.9 / 3.8 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: OP-19 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S4 LOI-12-2 TASK TITLE: Initiate RCIC in Pressure Control with Speed APPL. TO JPM NUMBER Failure (Alt Path)

Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-82 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S4 LOI-12-2 TASK TITLE: Initiate RCIC in Pressure Control with Speed APPL. TO JPM NUMBER Failure (Alt Path) kk. SAFETY CONSIDERATIONS A. None ll. REFERENCES A. OP-19, Reactor Core Isolation Cooling System mm. TOOLS AND EQUIPMENT A. None nn. SET UP REQUIREMENTS A. Plant in a post scram condition with RPV level between 177 and 222.5 (IC-153).

B. RPV pressure between 700 psig and 1000 psig and rising slowly.

C. Main Steam Isolation Valves closed.

D. Insert malfunction RC07A (RCIC Governor Fails High).

E. HPCI is not available.

oo. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

pp. TASK CONDITIONS

1. Plant is in a post-scram condition with RPV level between 177 and 222.5.

2. RPV pressure is between 700 psig and 1000 psig and rising slowly.

3. Main Steam Isolation valves are closed.

4. HPCI is not available.

-83 of 188-

• - CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to start the RCIC System for RPV pressure control. Maximize heat removal with RCIC to minimize SRV operations per OP-19.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-19. SAT / UNSAT Posted Attachment, RCIC MANUAL START UP FOR RPV PRESSURE CONTROL or OP-19, D.2.

2. Caution: Operating RCIC in Reviews Caution. SAT / UNSAT pressure control mode with suction from the CST and CST level below 79.5 inches could Verifies that CST level is greater than 79.5 inches.

cause vortexing.

3. Verify HPCI auto-initiation Verifies that there is no HPCI automatic initiating condition SAT / UNSAT condition is clear. present of high drywell pressure or low RPV water level.

4. Verify Annunciator 09-4-0-32 Verifies Annunciator 09-4-0-32 RCIC LOGIC RX LVL HI is SAT / UNSAT RCIC LOGIC RX LVL HI is clear.

clear.

5. Align RCIC to CSTs as follows. Ensures: SAT / UNSAT

a. Ensure open CST SUCT VLV 13MOV-18.

• CST SUCT VLV 13MOV open

b. Ensure closed the following

• INBD TORUS SUCT 13MOV closed valves:

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STEP STANDARD EVALUATION / COMMENT

• INBD TORUS SUCT

• OUTBD TORUS SUCT 13MOV closed 13MOV-41

• OUTBD TORUS SUCT 13MOV-39

• 6. Open HPCI & RCIC TEST VLV At Panel 09-3, opens 23MOV-24 by placing its control CRITICAL STEP TO CST 23MOV-24. switch to the OPEN position. SAT / UNSAT

• 7. Start VAC PMP 13P-3. At Panel 09-4, starts pump 13P-3 by placing its control CRITICAL STEP switch to the START position. SAT / UNSAT

• 8. Open OIL CLR WTR SUPP At Panel 09-4, opens 13MOV-132 by placing its control CRITICAL STEP 13MOV-132. switch to the OPEN position. SAT / UNSAT

• 9. Throttle open TEST VLV TO At Panel 09-4, throttles open 13MOV-30, by placing its CRITICAL STEP CST 13MOV-30 approximately control switch to the OPEN position and releasing after 10 SAT / UNSAT 10 seconds. seconds.

• 10. Open TURB STM SUPP VLV At Panel 09-4, opens 13MOV-131, by placing its control CRITICAL STEP 13MOV-131. switch to the OPEN position. SAT / UNSAT

11. Verify RCIC Flow rate is Observes RCIC flow rate is high. May attempt to adjust SAT / UNSAT approximately 400 gpm. auto setpoint.

EVALUATOR NOTE: Informs the CRS of the failure of automatic speed control Applicant should recognize of the RCIC turbine; follow guidance of EN-OP-115 to place the RCIC turbine speed controller in manual.

RCIC speed has failed high.

-85 of 188-

STEP STANDARD EVALUATION / COMMENT Examiner: Role Play as CRS to direct the Candidate to take manual control and establish pressure control with RCIC.

• 12. Place RCIC flow controller in Places RCIC flow controller in manual to control speed. CRITICAL STEP manual to control speed SAT / UNSAT

13. Ensure closed the following Observes that the green - closed indicating light is on for: SAT / UNSAT valves:

• MIN FLOW VLV 13MOV-27

• 13MOV-27

• STM LINE DRN TO RADW

• 13AOV-34 13AOV-34

• 13AOV-35

• STM LINE DRN TO RADW 13AOV-35

14. NOTE: As RPV pressure Reviews Note. SAT / UNSAT lowers, indicated level on 02-3LI-283A may rise and result in an undesired trip at the red line high level trip value.

Posted Attachment 3 will give an equivalent trip level for 06LI-94/A/B/C indicators on panel 09-5.

-86 of 188-

STEP STANDARD EVALUATION / COMMENT

15. CAUTION: Operating RCIC at Reviews Caution. SAT / UNSAT less than 2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

Failure to closely monitor RCIC pump discharge pressure could result in exceeding RCIC piping design pressure of 1320 psig.

• 16. WHILE controlling RPV At 09-4 Panel, monitors RCIC turbine speed on 13SPI-1 CRITICAL STEP pressure, maintain RCIC speed and throttles closed 13MOV-30 to ensure RCIC only runs SAT / UNSAT GREATER THAN 2200 rpm by below 2200 rpm during transient operation.

throttling closed TEST VLV TO CST 13MOV-30.

NOTE: RCIC flow control manual adjustment knob will need to be adjusted in tandem with 13MOV-30 to maintain RCIC flow near 400 gpm.

• 17. Throttle TEST VLV TO CST At Panel 09-4, throttles closed 13MOV-30 to begin the CRITICAL STEP 13MOV-30, to obtain the desired RPV depressurization to minimize SRV operation.

RPV pressure control. SAT / UNSAT Note to Evaluator: RPV pressure may be approaching 1000 psig and Candidate may suggest opening an SRV.

Inform Candidate that another Operator is assigned to SRVs.

18.

Startup RHR Torus cooling per Section D of OP-13B, as soon EVALUATOR: Inform the applicant that another operator as practicable. has been tasked with initiating Torus cooling and

-87 of 188-

STEP STANDARD EVALUATION / COMMENT monitoring Torus parameters.

19.

WHEN time permits, verify the Dispatches an Operator to verify the following RCIC SAT / UNSAT following RCIC parameters: parameters:

• Oil pump discharge

• Oil pump discharge pressure: 12 to 15 psig.

pressure: 12 to 15 psig.

• Oil temperature from cooler: GREATER THAN

• Oil temperature from 60°F.

cooler: GREATER

• Oil temperature from the turbine bearings: LESS THAN 60°F.

THAN 160°F

• Oil temperature from the turbine bearings: LESS THAN 160°F EVALUATOR: Terminate the task at this point.

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HANDOUT Formatted: Bullets and Numbering

1. Plant is in a post-scram condition with RPV level between 177 and 222.5.

2. RPV pressure is between 700 psig and 1000 psig and Formatted: Bullets and Numbering rising slowly.

3. Main Steam Isolation Valves are closed.

4. HPCI is not available.

The CRS directs you to start the RCIC System for RPV pressure control. Maximize heat removal with RCIC to minimize SRV operations per OP-19.

-89 of 188-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S5 LOI-12-2 TASK TITLE: Restore ESW after injection into RBCLC APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 400000 A4.01 3.1 / 3.0 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: OP-21 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-90 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S5 LOI-12-2 TASK TITLE: Restore ESW after injection into RBCLC APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-91 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S5 LOI-12-2 TASK TITLE: Restore ESW after injection into RBCLC APPL. TO JPM NUMBER qq. SAFETY CONSIDERATIONS A. None rr. REFERENCES B. OP-21, Emergency Service Water C. OP-40, Reactor Building Closed Loop Cooling ss. TOOLS AND EQUIPMENT A. None tt. SET UP REQUIREMENTS B. Reset to IC-154.

C. Place RBCLC pump control switches in PTL.

uu. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

vv. TASK CONDITIONS

5. The Plant is shutdown

6. All RBCLC pumps were placed in Pull to Lock.

7. ESW auto aligned to RBCLC.

8. RBCLC pumps are ready to be returned to service.

9. Attachment 3, STATUS CONTROL FORM FOR ESW RESET FOLLOWING INJECTION TO RBCLC, of OP-21 has been performed.

-92 of 188-

• - CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to restore the ESW system to normal per OP-21 Section F.3.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-21. SAT / UNSAT OP-21, ESW. Reviews Precautions.

• 2. Reset ESW Logic A by Depresses ESW SYS A INJ SIG RESET pushbutton. CRITICAL STEP depressing ESW SYS A INJ SIG SAT / UNSAT RESET pushbutton.

3. Verify white ESW SYS A INJ Verifies white ESW SYS A INJ SIG light is off. SAT / UNSAT SIG light is off.

• 4. Reset ESW Logic B by Depresses ESW SYS B INJ SIG RESET pushbutton. CRITICAL STEP depressing ESW SYS B INJ SIG RESET pushbutton. SAT / UNSAT

5. Verify white ESW SYS B INJ Verifies white ESW SYS B INJ SIG light is off. SAT / UNSAT SIG light is off.

• 6. Close ESW RETURN TO SERV Closes ESW RETURN TO SERV WTR 15MOV-175B by CRITICAL STEP WTR 15MOV-175B. taking control switch CCW to Close. SAT / UNSAT

• 7. Open ESW SYS B TEST VLV Opens ESW SYS B TEST VLV 46MOV-102B by taking CRITICAL STEP 46MOV-102B. control switch CW to Open. SAT / UNSAT

• 8. Close ESW SYS B INJ VLV Closes ESW SYS B INJ VLV 46MOV-101B by taking CRITICAL STEP 46MOV-101B. control switch CCW to Close. SAT / UNSAT

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STEP STANDARD EVALUATION / COMMENT

• 9. Close ESW RETURN TO SERV Closes ESW RETURN TO SERV WTR 15MOV-175A by CRITICAL STEP WTR 15MOV-175A. taking control switch CCW to Close. SAT / UNSAT

• 10. Open ESW SYS A TEST VLV Opens ESW SYS A TEST VLV 46MOV-102A by taking CRITICAL STEP 46MOV-102A. control switch CW to Open. SAT / UNSAT

• 11. Close ESW SYS A INJ VLV Closes ESW SYS A INJ VLV 46MOV-101A by taking CRITICAL STEP 46MOV-101A. control switch CCW to Close. SAT / UNSAT

12. Ensure open 15RBC-41 RBCLC EVALUATOR CUE:

Makeup Tank TK-4 Outlet Time compression will be invoked and another Operator Start up RBCLC System per will restore RBCLC.

Section D of OP-40.

STANDBY INSTRUCTOR ACTION:

Start RBCLC pumps A & B.

Inform Candidate RBCLC discharge pressure is stable and > 80 psig.

13. Candidate reads Steps F.3.14, EVALUATOR CUE:

15 & 16.

Inform Candidate no ESW valves were manually re-positioned during AOP-11.

14. WHEN RBCLC discharge EVALUATOR CUE:

header pressure is stable at OP-21 Attachment 3, Restoration section, is complete.

GREATER THAN OR EQUAL TO 80 psig, perform Restoration section of Attachment 3.

-94 of 188-

STEP STANDARD EVALUATION / COMMENT

15. Shut down ESW per Obtains Subsections F.1 and F.2. SAT / UNSAT Subsections F.1 and F.2.

16. Verify RBCLC System is in Verifies RBCLC system is in normal operation. SAT / UNSAT normal operation.

EVALUATOR CUE:

RBCLC system is in normal operation.

17. Verify EDG A and C are Verifies EDG A and C are shutdown. SAT / UNSAT shutdown.

18. Verify ventilation loads EVALUATOR CUE: SAT / UNSAT downstream of 46MOV-101A do Ventilation loads downstream of 46MOV-101A do not not require ESW. require ESW.

19. Ensure open ESW SYS A TEST Ensures open ESW SYS A TEST VLV 46MOV-102A. SAT / UNSAT VLV 46MOV-102A.

• Red light on, Green light off

20. Ensure closed ESW SYS A INJ Ensures closed ESW SYS A INJ VLV 46MOV-101A. SAT / UNSAT VLV 46MOV-101A

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STEP STANDARD EVALUATION / COMMENT

• Red light off, Green light on

• 21. Stop ESW PMP A 46P-2A. Stops ESW PMP A 46P-2A by taking control switch CCW CRITICAL STEP to Stop. SAT / UNSAT EVALUATOR: Terminate the task at this point.

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HANDOUT

1. The Plant is shutdown.

2. All RBCLC pumps were placed in Pull to Lock.

3. ESW auto aligned to RBCLC.

4. RBCLC pumps are ready to be returned to service.

5. Attachment 3, STATUS CONTROL FORM FOR ESW RESET FOLLOWING INJECTION TO RBCLC, of OP-21 has been performed.

The CRS directs you to restore the ESW system to normal per OP-21 Section F.3.

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S6 LOI-12-2 TASK TITLE: Core Spray Loop A Shutdown APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 209001 A4.01 3.8 / 3.6 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: OP-14 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-98 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S6 LOI-12-2 TASK TITLE: Core Spray Loop A Shutdown APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-99 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S6 LOI-12-2 TASK TITLE: Core Spray Loop A Shutdown APPL. TO JPM NUMBER ww. SAFETY CONSIDERATIONS A. None xx. REFERENCES D. OP-14, Core Spray System yy. TOOLS AND EQUIPMENT A. None zz. SET UP REQUIREMENTS D. Reset to IC-154.

E. Core Spray Loop A injecting into RPV.

F. Core Spray Loop B in a standby lineup.

G. DW pressure > 2.7 psig.

aaa. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

bbb. TASK CONDITIONS

10. The Plant has experienced a loss of coolant accident.

11. Core Spray is the only injection source available to the RPV.

12. Core Spray Loop A is currently injecting and maintaining RPV level > TAF.

13. Core Spray Loop B is in standby and available.

14. A report from the field states that failure of Core Spray Pump A is imminent.

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• - CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to start Core Spray Loop B then shutdown Core Spray Loop A per OP-14 while maintaining RPV level >0 inches <222.5 inches.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-14. SAT / UNSAT OP-14, Core Spray System Reviews Precautions.

2. Select Section D.2 of OP-14 Selects Section D.2 of OP-14 SAT / UNSAT Role Play: If asked if Core Spray was shutdown under EP-5 Terminate and Prevent, inform Candidate that Core Spray was NOT shutdown per EP-5 Terminate and Prevent.

• 3. Ensure PMP 14P-1B is running. Starts Core Spray Pump B by rotating control switch CW. CRITICAL STEP SAT / UNSAT

4. Ensure open OUTBD INJ VLV Ensures open Core Spray Loop B outboard injection valve SAT / UNSAT 14MOV-11B. 14MOV-11B by observing red light on, green light off.

• 5. When annunciator 09-3-1-27 Throttles Core Spray Loop B inboard injection valve to CRITICAL STEP RHR & CORE SPRAY INJ VLV maintain RPV level > 0 inches and < 222.5 inches. SAT / UNSAT PERM is in alarm, throttle INBD INJ VLV 14MOV-12B to control RPV water level as directed by EVALUATOR NOTE: This step may be performed after subsequent steps are taken for shutdown of Core Spray

-101 of 188-

STEP STANDARD EVALUATION / COMMENT Shift Manager. Loop A, as required for Reactor water level control.

6. When Core Spray Loop B flow Ensures closed MIN FLOW VLV 14MOV-5B when flow SAT / UNSAT rate is greater than 980 gpm, rate > 980 gpm by observing green light on, red light off.

ensure closed MIN FLOW VLV 14MOV-5B.

EVALUATOR NOTE: This step may be performed after subsequent steps are taken for shutdown of Core Spray Loop A, as required for Reactor water level control.

7. Select Section F.1 of OP-14 Selects Section F.1 of OP-14 SAT / UNSAT

• 8. Ensure closed INBD INJ VLV Closes INBD INJ VLV 14MOV-12A by rotating control CRITICAL STEP 14MOV-12A switch CCW. SAT / UNSAT

9. Ensure open MIN FLOW VLV Ensures open MIN FLOW VLV 14MOV-5A by observing SAT / UNSAT 14MOV-5A red light on, green light off.

• 10. Stop PMP 14P-1A Stops PMP 14P-1A by rotating control switch CCW. CRITICAL STEP SAT / UNSAT

11. If Core Spray auto-initiated and N/A. Core Spray initiation conditions are still present SAT / UNSAT Core Spray initiation conditions (Drywell pressure >2.7 psig).

are no longer present then

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STEP STANDARD EVALUATION / COMMENT

12. Ensure Core Spray Loop A is in EVALUATOR CUE:

the standby lineup per Section Another Operator will place Core Spray Loop A in a E, as soon as practicable. standby lineup.

Evaluator: Terminate JPM at this point.

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HANDOUT

1. The Plant has experienced a loss of coolant accident.

2. Core Spray is the only injection source available to the RPV.

3. Core Spray Loop A is currently injecting and maintaining RPV level >

TAF.

4. Core Spray Loop B is in standby and available.

5. A report from the field states that failure of Core Spray Pump A is imminent.

The CRS directs you to start Core Spray Loop B then shutdown Core Spray Loop A per OP-14 while maintaining RPV level >0 inches <222.5 inches.

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ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S7 LOI-12-2 TASK TITLE: Perform APRM Gain Adjust APPL. TO JPM NUMBER REV: 0 DATE: 3/2012 NRC K/A SYSTEM NUMBER: 215005 A1.07 3.0 / 3.4 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER: ST-5D ESTIMATED COMPLETION TIME: 20 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-105 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S7 LOI-12-2 TASK TITLE: Perform APRM Gain Adjust APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-106 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S7 LOI-12-2 TASK TITLE: Perform APRM Gain Adjust APPL. TO JPM NUMBER ccc. SAFETY CONSIDERATIONS A. None ddd. REFERENCES E. ST-5D, APRM Calibration F. OP-16, NEUTRON MONITORING eee. TOOLS AND EQUIPMENT A. Jewelers screwdriver fff. SET UP REQUIREMENTS H. Approximately 100% power (IC-151)

I. EPIC/3D available and plant conditions stable.

J. Adjust all APRMs to an acceptable value per ST-5D.

K. Adjust D APRM to 3-4% below desired value of ST-5D.

L. Prepare a working copy of ST-5D complete up to section 8.0.

ggg. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

hhh. TASK CONDITIONS A. The Plant is operating at approximately 100% power.

B. ST-5D, APRM Calibration, is required.

C. The plant has been stable for several hours.

D. 3D Monicore is available.

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• - CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to perform ST-5D.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of ST-5D. SAT / UNSAT ST-5D Reviews Precautions.

2. Determine the applicable Selects Section 8.3. SAT / UNSAT procedure subsection to perform as follows:

• IF reactor power is LESS THAN 25%, THEN perform Subsection 8.2.

• IF reactor power is GREATER THAN OR EQUAL TO 25%, AND the 3D MONICORE Core Power and Flow Log program is operable, THEN perform Subsection 8.3.

• IF reactor power is GREATER THAN OR EQUAL TO 25%, AND the 3D MONICORE Core Power and Flow Log program is not operable, THEN perform Subsection 8.4 with Reactor Engineering assistance as required.

• 3. Demand Core Power and Flow Determines APRM DR (desired reading) is approximately CRITICAL STEP Log to determine APRM DR. 100% power SAT / UNSAT DR = CORE POWER = %

-108 of 188-

STEP STANDARD EVALUATION / COMMENT

4. Adjust APRMs per Subsection Goes to Subsection 8.5. SAT / UNSAT 8.5.

5. Record initial APRM readings in Initial APRM readings are recorded in Table 1. SAT / UNSAT Table 1.

6. Record DR in Table 1. DR is recorded in Table 1. SAT / UNSAT

7. Identify any APRM(s) requiring APRM D is identified as requiring adjustment. SAT / UNSAT adjustment in Table 1.

APRM shall be adjusted to indicate within + 2% of the DR.

8. IF APRM adjustment is required, EVALUATOR CUE: The Shift Manager directs APRM D SAT / UNSAT THEN perform the following for to be bypassed per OP-16.

each APRM requiring adjustment: Candidate acknowledges SM direction.

NOTE: Bypassing APRM may be omitted per SM.

9. Bypass the APRM channel OP-16 Section E.16 (Bypassing an APRM) obtained. SAT / UNSAT requiring calibration per Section E of OP-16.

• 10 Place APRM BYP switch in (*). Places APRM BYP switch in D position. CRITICAL STEP SAT / UNSAT

11. Verify APRM (*) is bypassed APRM D verified bypassed by: SAT / UNSAT using one or both of the following:

• APRM D BYPASS indicating light is on

• APRM (*) BYPASS and \ or indicating light is on

• APRM D EPIC alarm indicates bypassed

• APRM (*) EPIC alarm indicates bypassed

-109 of 188-

STEP STANDARD EVALUATION / COMMENT

12. Verify the other two APRM APRMs B and F verified to be in service by: SAT / UNSAT channels associated with the same APRM BYP switch are in

• APRM BYPASS indicating lights are off for the service using one or both of the other two APRMs following:

and \ or

• APRM BYPASS

• No EPIC bypassed alarms for the other two indicating lights are off APRMs for the other two APRMs

• No EPIC bypassed alarms for the other two APRMs

13. ST-5D, 8.5.4 continued: Observes APRM D METER FUNCTION switch set to SAT / UNSAT Ensure METER FUNCTION AVERAGE.

switch is set to AVERAGE.

14. Ensure APRM MODE switch is Observes APRM D MODE switch in OPERATE position. SAT / UNSAT in the OPERATE position.

15. NOTE: Clockwise turn raises Candidate reviews Note concerning manipulation of gain SAT / UNSAT meter reading; counterclockwise adjust control.

turn lowers meter reading.

• 16. Turn gain adjustment control Gain adjustment control (R16), on LPRM card Z-31, CRITICAL STEP (R16) on LPRM card Z-31 to adjusted to obtain a meter reading within +/-2% of DR. SAT / UNSAT obtain a meter reading within

+/-2% of DR.

17. Unbypass APRM per Section E Section E.17 of OP-16, Returning an APRM to Service, SAT / UNSAT of OP-16. obtained.

18. Verify the following lights for Observes the following lights for APRM D are off at panel SAT / UNSAT APRM (*) are off at panel 09-14: 09-14:

• INOP

• INOP

-110 of 188-

STEP STANDARD EVALUATION / COMMENT

• UPSCL NEUT TRIP

• UPSCL NEUT TRIP

• UPSCL THERM TRIP

• UPSCL THERM TRIP

• 19. Place APRM BYP switch for Places APRM BYP switch (joystick) for APRM D in center CRITICAL STEP APRM (*) in center position. position. SAT / UNSAT

20. Verify APRM (*) is returned to APRM D verified to be returned to service using one or SAT / UNSAT service using one or both of the both of the following:

following:

• APRM D BYPASS indicating light is off

• APRM (*) BYPASS and \ or indicating light is off

• No EPIC bypassed alarm for APRM D

• No EPIC bypassed alarm for APRM (*)

21. Verify all three APRM channels All three APRM channels associated with the same APRM SAT / UNSAT associated with the same APRM BYP switch are verified in service using one or both of the BYP switch are in service using following:

one or both of the following:

• APRM BYPASS indicating lights are off for the

• APRM BYPASS three APRMs indicating lights are off and \ or for the three APRMs

• No EPIC bypassed alarms for the three APRMs

• No EPIC bypassed alarms for the three APRMs

22. Record final APRM readings for Records final APRM readings for adjusted APRMs in SAT / UNSAT adjusted APRMs in Table 1. Table 1.

Evaluator: Terminate JPM at this point

-111 of 188-

HANDOUT A. The Plant is operating at approximately 100% power.

B. ST-5D, APRM Calibration, is required.

C. The plant has been stable for several hours.

D. 3D Monicore is available.

"The CRS directs you to The CRS directs you to perform ST-5D.

-112 of 188-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC S8 LOI-12-2 TASK TITLE: Initiate Torus Cooling With LPCI Signal Present APPL. TO JPM NUMBER REV: DATE: NRC K/A SYSTEM NUMBER: 219000 A4.02 3.7/3.5 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 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 CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-113 of 188-

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC S8 LOI-12-2 TASK TITLE: Initiate Torus Cooling With LPCI Signal Present APPL. TO JPM NUMBER Current Update: By:

Date Int Outstanding Items Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-114 of 188-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC S8 LOI-12-2 TASK TITLE: Initiate Torus Cooling With LPCI Signal Present APPL. TO JPM NUMBER iii. SAFETY CONSIDERATIONS A. None jjj. REFERENCES A. OP-13B, RHR - Containment Control B. OP-13C, RHR Service Water kkk. TOOLS AND EQUIPMENT A. None lll. SET UP REQUIREMENTS A. Initialize the simulator to an IC (IC-155) with the following:

• Elevated Torus water temperature

• LPCI auto-initiation signal sealed in due to high Drywell pressure

• RPV water level controlled above 10 on fuel zone indications by a system other than RHR A mmm. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

nnn. TASK CONDITIONS A. Torus cooling is required due to elevated torus water temperature.

B. Drywell pressure is above 2.7 psig.

-115 of 188-

• - CRITICAL STEP ooo. INITIATING CUE Inform the candidate, "The CRS directs you to place RHR A in the torus cooling lineup per OP-13B and OP-13C. Maximize torus cooling from this loop of RHR.

STEP STANDARD EVALUATION / COMMENT

1. Obtain a controlled copy of Determines where to obtain a controlled copy of OP-13B SAT / UNSAT procedures OP-13B, RHR - and OP-13C.

Containment Control, and OP-13C, RHR Service Water.

2. Select the correct section to Selects Posted Attachment 1 or Section D.1 OP-13B. SAT / UNSAT perform the task.

3. IF a LPCI auto-initiation signal Determines a LPCI auto-initiation signal is sealed in. SAT / UNSAT is sealed in, THEN perform the following:

4. IF RPV water level is LESS Determines RPV water level is above 10 inches on fuel SAT / UNSAT THAN 10 inches on fuel zone zone water level indication.

water level indication, AND the EOPs permit diverting LPCI flow, THEN place DW &

TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 10A-S18A keylock switch in MANUAL OVERRD.

• 5. Place SPRAY CNTRL 10A- Places SPRAY CNTRL 10A-S17A switch to MANUAL, then CRITICAL STEP

-116 of 188-

STEP STANDARD EVALUATION / COMMENT S17A switch to MANUAL, releases to normal. SAT / UNSAT spring return to normal.

6. Verify white SPRAY PERM Observes white SPRAY PERM 10A-DS67A light is on. SAT / UNSAT 10A-DS67A light is on.

7. Ensure at least one of the Observes red light on, green light off for: SAT / UNSAT following RHR pumps is

• RHR PMP 10P-3A running:

• RHR PMP 10P-3C

• RHR PMP 10P-3A

• RHR PMP 10P-3C

• 8. Open RHR TEST TORUS Places RHR TEST TORUS CLG & SPRAY 10MOV-39A CRITICAL STEP CLG & SPRAY 10MOV-39A. control switch to OPEN. SAT / UNSAT

• 9. Throttle RHR TEST & TORUS Places RHR TEST & TORUS CLG 10MOV-34A control CRITICAL STEP CLG 10MOV-34A to establish switch to OPEN. SAT / UNSAT desired flow.

Subsequently places RHR TEST & TORUS CLG 10MOV-34A control switch to OPEN and/or CLOSE as necessary to establish desired flow.

-117 of 188-

STEP STANDARD EVALUATION / COMMENT

10. WHEN RHR Loop A flow is Observes MIN FLOW VLV 10MOV-16A green light on, red SAT / UNSAT GREATER THAN 1500 gpm, light off.

ensure closed MIN FLOW VLV 10MOV-16A.

11. IF RHR Loop A condensate Contacts plant operator to determine if RHR Loop A SAT / UNSAT transfer keep-full is in service, condensate transfer keep-full is in service.

AND RHR Loop A pressure is LESS THAN condensate transfer pressure, THEN close EVALUATOR CUE: Report that RHR Loop A condensate 10RHR-274 (RHR loop A transfer keep-full is NOT in service.

containment spray keep-full cond xfer connection valve).

-118 of 188-

STEP STANDARD EVALUATION / COMMENT

12. Establish RHRSW flow per Selects Posted Attachment 1 or Section D.1 of OP-13C. SAT / UNSAT OP-13C, if desired.

13. Verify one of the following Observes either of the following: SAT / UNSAT alarms is clear:

• Annunciator 09-4-3-4 RHRSW A OR B DISCH LINE

• Annunciator 09-4-3-4 NOT FULL is clear RHRSW A OR B

• EPIC-D-134 10LS-105A is clear DISCH LINE NOT FULL

• EPIC-D-134 10LS-105A

• 14. Start one of the following Rotates RHRSW PMP 10P-1A or 10P-1C control switch to CRITICAL STEP RHRSW pumps: START. SAT / UNSAT

• RHRSW PMP 10P-1A

• RHRSW PMP 10P-1C

• 15. Throttle RHRSW DISCH VLV Rotates RHRSW DISCH VLV FROM HX A 10MOV-89A CRITICAL STEP FROM HX A 10MOV-89A to control switch to OPEN. SAT / UNSAT establish 2500 to 4000 gpm.

Subsequently rotates RHRSW DISCH VLV FROM HX A 10MOV-89A control switch to OPEN and/or CLOSE as necessary to establish 2500 to 4000 gpm flow.

• 16. Start the second RHRSW Rotates RHRSW PMP 10P-1A or 10P-1C control switch to CRITICAL STEP pump if desired. START.

-119 of 188-

STEP STANDARD EVALUATION / COMMENT SAT / UNSAT EVALUATOR CUE: If candidate asks if second RHRSW pump start is desired, direct them to maximize torus cooling from this loop of RHR.

• 17. Throttle RHRSW DISCH VLV Rotates RHRSW DISCH VLV FROM HX A 10MOV-89A CRITICAL STEP FROM HX A 10MOV-89A to control switch to OPEN and/or CLOSE as necessary to SAT / UNSAT establish 2500 to 4000 gpm establish 2500 to 4000 gpm flow per RHRSW pump.

per RHRSW pump.

• 18. Close HX A BYP VLV 10MOV- Rotates HX A BYP VLV 10MOV-66A control switch to CRITICAL STEP 66A. CLOSE. SAT / UNSAT EVALUATOR: Terminate the task at this point.

-120 of 188-

HANDOUT

• Torus cooling is required due to elevated torus water temperature.

• Drywell pressure is above 2.7 psig.

The CRS directs you to place RHR A in the torus cooling lineup per OP-13B and OP-13C. Maximize torus cooling from this loop of RHR.

-121 of 188-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI-12-2 NRC EXAMINATION SCENARIO 1 TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 1 SCENARIO NUMBER: NRC 1 PATH: STAND ALONE Validation: ______________________ Training: ______________________ Operations: ______________________

CANDIDATES CRS ATC BOP LOI-12-2 NRC Examination Scenario 1 Page 122 of 188

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/2/12 New New Scenario T. Hooper LOI-12-2 NRC Examination Scenario 1 Page 123 of 188

A. TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 1 B. SCENARIO SETUP:

1. IC-156

2. Special Instructions:

a. The Plant is operating at approximately 100% power.

b. APRM A is bypassed due to erratic indication.

c. CRD pump A is out of service for maintenance.

d. Feedwater level control is selected to level column A, and is to be swapped to level column B.

e. Reactor power is to be lowered to 95% with recirculation flow in preparation for Turbine Valve testing.

f. Ensure LOI Pull Sheets Binder is staged at the 09-5 Panel (CRAM Rods at 08)

3. Preset Conditions:

a. Preset, M:RD06:A CRD Hydraulic Pump Trip A

b. Preset, OL:RD ZLO3BS3A(1) CRD Feed Pump Green Light, off

c. Preset, R:EP04 Lake Ontario Water Temperature, 48

d. TRIGGER 1, M:RR10:A RWR MG Set A Flow Controller Failure, 52%, Rmp=60s

e. Preset, M:SW15 Service Water Pump A Auto Start Failure

f. TRIGGER 2, M:SW05:B Service Water Pump B Trip

g. TRIGGER 3, M:FW19:A Condensate PMP 33P-8A Trip

h. TRIGGER 4, M:FW19:B Condensate PMP 33P-8B Trip

i. TRIGGER 4, M:FW19:C Condensate PMP 33P-8C Trip

j. Preset, M:RP01:A Reactor Protection System Automatic Scram Failure

k. Preset, M:RP09 ARI Fails to Actuate

l. TRIGGER 5, M:RR15:A Coolant (A) Leakage Inside Primary Containment, 25%,

Ramp=12:00

m. TRIGGER 20, R:MS22, Mn Steam To Rblr

n. Preset, M:HP07 HPCI Valve MOV-19 Fails to Auto Open

o. Preset, OS:HP ZDI23AS5 HPCI Injection Valve Control Switch, close

p. Event Trigger 1, RWR Pump A Flow, rrfpa(1)<4635

4. Consumable Forms and Procedures:

OP-2A Sections G.29 and G.40 Reactivity Maneuvering sheets AOP-1 AOP-8 AOP-10 AOP-32 AOP-39 AOP-41 LOI-12-2 NRC Examination Scenario 1 Page 124 of 188

C. SCENARIO

SUMMARY

The scenario will begin with the plant operating at 100% Power. The Crew will begin by swapping Feedwater level control from level column A to B per OP-2A. Once this is complete, the Crew will begin lowering Reactor power to 95% in preparation for Turbine valve testing.

When RWR pump A flow lowers to approximately 4250 gpm, the RWR A speed controller will fail such that loop flow abruptly rises, and then lowers. Pump A flow will stabilize significantly below Pump B flow. The Crew will lockup the RWR pump A scoop tube and take action to restore RWR flow mismatch to an acceptable level.

Service Water pump B will trip and Service Water pump A will fail to auto-start. The Crew will execute AOP-10 and manually start Service Water pump A.

Condensate pump A will trip. The Crew will execute AOP-41. The Crew will enter RAP-7.3.16 and OP-65 to lower Reactor power within the capacity of the remaining Condensate pumps. As power is lowered, the Crew will transfer Reboiler steam supply, secure a Condensate Booster pump and may secure a Circulating Water pump.

Once plant conditions are stable, the remaining Condensate pumps will trip. Reactor water level will lower due to the complete loss of Condensate and Feedwater, however automatic scrams and ARI will fail to insert control rods. The Crew will manually scram the Reactor to insert control rods. AOP-1 will be executed to stabilize the plant after the scram.

A coolant leak will develop inside Primary Containment. The Crew will execute AOP-39, EOP-2, and EOP-

4. Containment Sprays will be required to mitigate degrading containment parameters. The HPCI injection valve, MOV-19, will fail to automatically open and will not be able to be manually opened. Combined with the loss of all Feedwater, this will limit high pressure injection capacity to less than the flow rate of the coolant leak. Reactor water level will continue to lower. An RPV Blowdown will be required based on low Reactor water level. As Reactor pressure lowers, the Crew will restore and maintain Reactor water level with low pressure systems.

The Scenario will be terminated when all control rods are inserted, the RPV Blowdown has been performed, and Reactor water level is being controlled above TAF with low pressure injection systems.

LOI-12-2 NRC Examination Scenario 1 Page 125 of 188

Shift Turnover The Plant is operating at approximately 100% power.

APRM A is bypassed due to erratic indication.

CRD pump A is out of service for maintenance.

Feedwater level control is selected to level column A following calibrations affecting level column B.

When you take the shift, complete the following:

1. Swap Feedwater level control from level column A to level column B per OP-2A. Due to previous Feedwater level control issues, place Feedwater level control in MANUAL during the swap and restore Feedwater level control to AUTOMATIC after the swap.

2. Then, lower Reactor power to 95% with recirculation flow in preparation for Turbine Valve testing, per OP-65 and RAP-7.3.16.

LOI-12-2 NRC Examination Scenario 1 Page 126 of 188

Critical Tasks/Standards Critical Task #1: Given the need for a Reactor scram and failure of automatic actions to insert control rods, the crew will manually scram the Reactor, in accordance with AOP-1.

Critical Task #2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain RPV water level above the Top of Active Fuel (TAF), the crew will initiate an RPV Blowdown before RPV water level lowers below -19, in accordance with EOP-2.

LOI-12-2 NRC Examination Scenario 1 Page 127 of 188

EVENT NO. EVENT SEQUENCE Swap Feedwater Level Control from (Normal: BOP) 1.

Level Column A to B Lower Reactor Power to 95% with (Reactivity: BOP) 2.

Recirculation Flow

3. RWR MG A Speed Controller Failure Low (Instrument: BOP)

Service Water Pump Trip with Failure to Auto-Start (Component: BOP) 4.

5. Trip of Condensate Pump A (Component: All)

6. Trip of Condensate Pumps B and C (Component: All)

Automatic Scram and ARI Fail to Insert (Instrument: ATC) 7.

Control Rods

8. Coolant Leak Inside Containment (Major: All)

9. HPCI Injection Valve Fails to Open (Component: All)

D. TERMINATION CUES:

• All control rods are inserted

• RPV Blowdown has been performed

• Reactor water level is being controlled above TAF with low pressure injection systems LOI-12-2 NRC Examination Scenario 1 Page 128 of 188

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, allow All SAT / UNSAT / NA no more than five minutes for panel walkdown

• Walkdown the control panels and assume the watch SRO

• Perform Crew Brief

• Direct BOP to swap Feedwater level columns per OP-2A

• Provide oversight BOP SAT / UNSAT / NA

• Obtain OP-2A Section G.29

• 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 BOP cont.

• 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 LOI-12-2 NRC Examination Scenario 1 Page 129 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Place RX WTR LVL CNTRL 06LC-83 controller in BAL SRO

• Direct ATC to lower power to 95% with Recirc flow

• Provide oversight for reactivity manipulation Note: BOP SAT / UNSAT / NA Trigger 1 automatically inserts the RWR A speed controller

• Lower Recirc flow alternately with RWR MG A(B) SPEED failure low when RWR loop A CNTRL flow is approximately 45.2

• Monitor APRMs, CTP, Recirc flow, Reactor water level Kgpm.

• Recognize / report RWR A speed controller is malfunctioning SRO

• Acknowledge report Note:

• Direct lock-up of RWR A scoop tube per OP-27 Section G.6 The decision to restore loop

• Enter AOP-8 (Loss or Reduction in Reactor Coolant Flow) flow mismatch may be made

• Enter AOP-32 (Unexplained/Unanticipated Reactivity Change) from OP-27 precaution C.2.14

• Direct lowering RWR B flow to restore loop flow mismatch or Tech Specs.

LOI-12-2 NRC Examination Scenario 1 Page 130 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Role Play:

If asked as Reactor Engineering how to respond, recommend restoring loop flow mismatch by rapidly lowering RWR loop B flow.

BOP SAT / UNSAT / NA

• Place RWR A SCOOP TUBE control switch to TRIP

• Place SCOOP TUBE A AUTO UNLOCK control switch in ON

• Lower RWR B flow to restore loop flow mismatch less than or equal to either 5% of rated core flow (if >70% flow) or 10% of rated core flow (if <70% flow)

ATC SAT / UNSAT / NA

• Monitor for Thermal Hydraulic Instabilities

• Monitor Feedwater response On Lead Examiner Cue: BOP SAT / UNSAT / NA ACTIVATE TRIGGER 2 Service Water pump B trips

• Recognize / report annunciators:

o 09-6-2-13, SERV WTR PMP 46P-1B OVERLOAD OR Service Water pump A fails to TRIP auto-start o 09-6-2-34, SERV WTR HDR PRESS LO

• Recognize / report trip of Service Water pump B

• Recognize / report failure of Service Water pump A to auto-start LOI-12-2 NRC Examination Scenario 1 Page 131 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

• Acknowledge reports

• Enter AOP-10 (Loss of Service Water Cooling)

• Direct start of Service Water pump A Booth Operator: BOP SAT / UNSAT / NA If requested as NPO, maintenance, etc., wait 3

• Start Service Water pump A minutes and then report that

• Review AOP-10 actions for degraded Service Water Service Water pump B breaker has tripped on overcurrent, but there are no other abnormal indications at the Service Water pumps or breakers.

On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 3 Condensate pump A trips

• Recognize / report annunciator 09-6-3-1, COND PMP 33P-8A OVERLOAD OR TRIP

• Recognize / report trip of Condensate pump A

• Monitor Condensate and Feedwater pressures and flows

• Monitor Reactor water level, Feedwater flow, and Reactor power Booth Operator: SRO If requested as NPO, maintenance, etc., wait 3

• Acknowledge report minutes and then report that

• Enter AOP-41 (Feedwater Malfunction)

Condensate pump A breaker

• Direct power reduction to approximately 65% power per OP-65 has tripped on overcurrent and and RAP-7.3.16 LOI-12-2 NRC Examination Scenario 1 Page 132 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION the motor is hot to the touch.

• Provide oversight for reactivity manipulation

• Direct Reboiler steam supply swapped to Main Steam per OP-Crew may direct RWR A flow 72 Section G locally reduced. If directed to

• Direct securing one Condensate Booster pump per OP-3 lower RWR A flow, use Section F REMOTE RR07 RECIRC

• May direct securing one Circulating Water pump per OP-4 PUMP A M\G SCOOP TUBE Section G MANUAL ADJUSTMENT.

Note: ATC SAT / UNSAT / NA Due to RWR A speed control malfunction, use of

• Lower Reactor power with recirculation flow, as available recirculation flow for power

• Insert CRAM rods reduction is limited.

• Monitor Reactor power Role Plays: BOP SAT / UNSAT / NA When dispatched to swap Reboiler steam supply, wait 1

• Swap Reboiler steam supply to Main Steam per OP-72 Section minute, insert Trigger 20, then G.4.1:

report task completion. o Direct operator to place Reboiler Source Selector Switch in MAIN STEAM TO REBOILER o Verify open 31MOV-153 When dispatched to check o Direct operator to verify open 31PCV-100 31PCV-100 position, report o Verify closed 31MOV-145A 31PCV-100 is open. o Verify closed 31MOV-145B

• Secure one Condensate Booster pump per OP-3 Section F.1

• May secure one Circulating Water pump per OP-4 Section G.5 LOI-12-2 NRC Examination Scenario 1 Page 133 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 4

• Recognize / report trip of Condensate pumps B and C Trip of Condensate pumps B and C

• May recognize / report failure of automatic Reactor scram to insert control rods Note: SRO Preset malfunctions prevent automatic Reactor scram and

• Acknowledge report ARI from inserting control

• Direct Reactor scram rods.

• Enter AOP-1 (Reactor Scram)

• Enter EOP-2 (RPV Control) on low RPV water level

• Direct RPV water level restored and maintained 177-222.5 Note:

using CRD and RCIC RPV water level will likely go

• Direct RPV pressure controlled 900-1000 psig using Turbine below 126.5 due to loss of Bypass Valves Feedwater and scram. This

• Enter AOP-15 (Isolation Verification and Recovery) will cause both HPCI and RCIC initiation signals. Preset malfunctions will cause the HPCI injection valve, MOV-19, to fail closed.

LOI-12-2 NRC Examination Scenario 1 Page 134 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Critical Task #1 Given the need for a Reactor scram and failure of automatic Pass / Fail actions to insert control rods, the crew will manually scram the Reactor, in accordance with AOP-1.

Critical Task #1 Standard: All control rods inserted by:

Depressing manual Scram pushbuttons Or Placing Mode Switch to Shutdown ATC SAT / UNSAT / NA Critical Task #1

• Depress manual Scram pushbuttons

• Place Mode Switch to Shutdown

• Report all control rods have inserted

• Enter AOP-1 o Fully insert IRMs and SRMs o Observe Reactor power downscale on APRMs o Observe SDIV vent and drain valves closed o Ensure Main Turbine is tripped o Verify 4 KV loads transfer to reserve power o Transfer APRM/IRM recorders to IRMs o Down-range IRMs o Monitor Reactor pressure control on the Turbine Bypass Valves Booth Operator: BOP SAT / UNSAT / NA If requested as NPO, maintenance, etc. to

• Enter AOP-1 investigate HPCI injection o Operate RCIC per OP-19 Section D valve, wait 3 minutes and then o Recognize / report failure of HPCI injection valve to open report that there is an acrid o May attempt to manually open HPCI injection valve odor near the motor and the (23MOV-19) breaker is tripped. o Trips HPCI o May initiate SLC injection, as directed If requested to manually open LOI-12-2 NRC Examination Scenario 1 Page 135 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION HPCI injection valve, wait 2

• Verify Group 2 isolation per AOP-15 minutes and report the valve is stuck closed.

On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 5

• Recognize / report degrading Primary Containment conditions Coolant leak inside Primary (leakage, temperature, pressure).

Containment SRO

• Acknowledge report

• Enter AOP-39 (Loss of Coolant)

• 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 LOI-12-2 NRC Examination Scenario 1 Page 136 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION within 60 minutes

• Re-enter EOP-2 (RPV Control) on high Drywell pressure

• Enter EOP-4 (Primary Containment Control) on high Drywell pressure

• May direct Core Spray and RHR injection Terminated and Prevented per EP-2.

• 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:

o Verify Recirculation pumps tripped o Direct trip of Drywell cooling fans o Direct initiation of Drywell Spray BOP / ATC SAT / UNSAT / NA

• Isolate Control Room and Relay Room Ventilation per OP-55B Section G.1 o Place Control Room Ventilation ISOL & PURGE CNTRL switch in ISOL o Verify closed:

o 70MOD-109 o 70MOD-105 o 70MOD-107 o 70MOD-108 o Verify open:

o 70MOD-110A o 70MOD-110B o Verify one Control Room Emergency Air Supply fan running with discharge damper open o Close 70DMPR-105 o Ensure closed all access doors to Control Room LOI-12-2 NRC Examination Scenario 1 Page 137 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP / ATC SAT / UNSAT / NA cont.

• Isolate Relay Room Ventilation per OP-56 Section G o Place Relay Room Ventilation control switches in ISOL:

o ISOL & PURGE CNTRL A o ISOL & PURGE CNTRL B o Verify closed:

o 70MOV-105 o 70MOV-106 o 70MOD-115 o Verify open:

o 70MOD-104A o 70MOD-104B o Ensure closed all access doors to Relay Room LOI-12-2 NRC Examination Scenario 1 Page 138 of 188

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

• Terminate and Prevent injection from Core Spray and RHR as SAT / UNSAT / NA follows:

Core Spray o Core Spray Loop A o Place 14MOV-11A AUTO ACTUATION BYPASS SW 14A-S16A switch in bypass o Verify white 14MOV-11A AUTO ACTUATION BYPASS LT 14A-DS35A light is on o Ensure closed OUTBD INJ VLV 14MOV-11A o Ensure PMP 14P-1A is stopped o Core Spray Loop B o Place 14MOV-11B AUTO ACTUATION BYPASS SW 14A-S16B switch in bypass o Verify white 14MOV-11B AUTO ACTUATION BYPASS LT 14A-DS35B light is on o Ensure closed OUTBD INJ VLV 14MOV-11B o Ensure PMP 14P-1B is stopped BOP / ATC SAT / UNSAT / NA cont. RHR LOI-12-2 NRC Examination Scenario 1 Page 139 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o RHR Loop A o Place 10MOV-27A AUTO CONTROL BYPASS 10A-S23A o Verify white light above 10MOV-27A AUTO CONTROL BYPASS 10A-S23A is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27A o Ensure RHR Loop A pumps which are not required to be running are stopped o Direct NPO to rotate Timers fully counterclockwise o RHR Loop B o Place 10MOV-27B AUTO CONTROL BYPASS 10A-S23B o Verify white light above 10MOV-27B AUTO CONTROL BYPASS 10A-S23B is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27B o Ensure RHR Loop B pumps which are not required to be running are stopped o Direct NPO to rotate Timers fully counterclockwise BOP / ATC

• Initiate Torus Spray per OP-13B Posted Attachment 2 SAT / UNSAT / NA o Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL 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 LOI-12-2 NRC Examination Scenario 1 Page 140 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION establish desired torus spray flow rate o When RHR Loop A(B) flow is greater than 1500 gpm, ensure closed MIN FLOW VLV 10-MOV-16A(B) o Throttle RHR TEST & TORUS CLG 10MOV-34A(B) to divert excess flow to the torus to maintain at least 6500 gpm RHR Loop A(B) flow with one RHR pump operating or at least 13000 gpm RHR Loop A(B) flow with two RHR pumps operating o Establish RHRSW flow and temperature control

• Establish RHRSW flow per OP-13C Posted Attachment 1 o Start one RHRSW pump o Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm o Start second RHRSW pump in selected loop o RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm Note: BOP / ATC o If drywell or torus sprays are in service, then establish SAT / UNSAT / NA When RPV water level lowers cont. 4000 gpm per RHRSW pump below 59.5, Torus and o Close HX A(B) BYP VLV 10MOV-66A(B)

Drywell Spray are automatically secured as LPCI receives an initiation signal.

The SRO will direct Torus and

• Initiate Drywell Spray per OP-13B Posted Attachment 3 Drywell Spray re-established o Ensure RWR pumps are tripped at a later time. o Ensure Drywell cooling fans are tripped o Verify Drywell temperature and pressure are within the Drywell Spray Initiation Limit o Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL o Verify white SPRAY PERM 10A-DS67A(B) light is on o Ensure available RHR pumps in RHR Loop A(B) are LOI-12-2 NRC Examination Scenario 1 Page 141 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION 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 o When RHR Loop A(B) flow is greater than 1500 gpm, ensure closed MIN FLOW VLV 10MOV-16A(B) o Establish RHRSW flow and temperature control per OP-13C Posted Attachment 1 (see above)

SRO

• Determine available Group 1 high pressure injection systems (CRD, RCIC) are not capable of maintaining RPV water level

• Direct injection of SLC

• Determine RPV water level cannot be maintained above 0 (TAF)

• Transition to the Alternate RPV Level Control leg of EOP-2

• Direct ADS overridden

• Wait until RPV water level drops to 0 TAF

• Determine RPV injection source lined up and running

• Determine RPV water level cannot be restored and maintained above -19

• Direct open 7 ADS valves

• Direct RPV water level restored and maintained 177 to 222.5 using available injection systems

• Transition back to EOP-2 normal RPV level leg Critical Task #2 Given a coolant leak, a loss of high pressure injection Pass / Fail systems, and the inability to restore and maintain RPV water LOI-12-2 NRC Examination Scenario 1 Page 142 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION level above the Top of Active Fuel (TAF), the crew will initiate an RPV Blowdown before RPV water level lowers below -19, in accordance with EOP-2.

Critical Task #2 Standard: Open 7 ADS valves BOP / ATC SAT / UNSAT / NA

• 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

• Verify Group I Isolation per AOP-15

• Open 7 ADS valves

• Restore and maintain RPV water level 177 to 222.5 using available injection systems Critical Task #2

• Control Core Spray injection o Throttle 14MOV-12A(B)

• Control LPCI injection Note: o Throttle 10MOV-27A(B) 10MOV-27A (B) cannot be o Secure RHR pumps if running throttled until LPCI has had an injection signal for 5 minutes unless Timers were ordered to be rotated to zero. Before this time has elapsed, RHR pumps may need to be secured to control RPV injection.

LOI-12-2 NRC Examination Scenario 1 Page 143 of 188

Termination Criteria:

• All control rods are inserted

• RPV Blowdown has been performed

• Reactor water level is being controlled above TAF with low pressure injection systems LOI-12-2 NRC Examination Scenario 1 Page 144 of 188

ATTACHMENT 1 A. Shift Turnover The Plant is operating at approximately 100% power.

APRM A is bypassed due to erratic indication.

CRD pump A is out of service for maintenance.

Feedwater level control is selected to level column A following calibrations affecting level column B.

When you take the shift, complete the following:

1. Swap Feedwater level control from level column A to level column B per OP-2A. Due to previous Feedwater level control issues, place Feedwater level control in MANUAL during the swap and restore Feedwater level control to AUTOMATIC after the swap.

2. Then, lower Reactor power to 95% with recirculation flow in preparation for Turbine Valve testing, per OP-65 and RAP-7.3.16.

LOI-12-2 NRC Examination Scenario 1 Page 145 of 188

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI-12-2 NRC EXAMINATION SCENARIO 2 TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: NRC 2 PATH: STAND ALONE Validation: ______________________ Training: ______________________ Operations: ______________________

CANDIDATES CRS ATC BOP LOI-12-2 NRC Examination Scenario 2 Page 146 of 188

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/3/12 New New Scenario T. Hooper LOI-12-2 NRC Examination Scenario 2 Page 147 of 188

B. TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

2. IC-157

4. Special Instructions:

a. The Plant is operating at approximately 85% power.

b. RCIC is out of service for maintenance.

c. Reactor power is to be raised to 100% with Recirculation flow.

5. Preset Conditions:

a. Preset, M:RC03 RCIC System Turbine Trip

b. Preset, R:EP04 Lake Ontario Water Temperature, 48

c. TRIGGER 1, M:RD06:B CRD Hydraulic Pump Trip (B)

d. TRIGGER 2, M:TU04E Main Turbine High Bearing #5 Vibration, Initial=21%,

Final=27%, Ramp=5:00

e. TRIGGER 2, M:TU04F Main Turbine High Bearing #6 Vibration, Initial=21%,

Final=28%, Ramp=5:00

f. TRIGGER 3, M:MC01 Main Condenser Air In Leakage, 30%

g. Preset, M:RP01:AA RPS Automatic Scram Failure A Side Only

h. Preset, M:RP01:BA RPS Manual Scram Failure A Side Only

i. Preset, M:RP09 ARI Fails to Actuate

j. TRIGGER 4, M:SL03:A SBLC pump A Relief 11-RV-39A Lifts

k. TRIGGER 5, M:SL03:B SBLC pump B Relief 11-RV-39B Lifts

l. TRIGGER 6, M:EG01 Main Generator Trip

m. TRIGGER 7, M:TC04:A Turbine Bypass Valve Failure (A), 0%

n. TRIGGER 7, M:TC04:B Turbine Bypass Valve Failure (B), 0%, Delay=15 sec

o. TRIGGER 7, M:TC04:C Turbine Bypass Valve Failure (C), 0%, Delay=30 sec

p. TRIGGER 25, M:IA01 Vent Scram Air Header, 100%, Ramp=30 sec

q. Event Trigger 4, SLC Pump A Running, sl:pumpona==1

r. Event Trigger 5, SLC Pump B Running, sl:pumponb==1

s. Event Trigger 6, APRM Less than 42%, nmaprmfx(1)<0.42

t. Event Trigger 7, APRM Less than 24%, nmaprmfx(1)<0.24

5. Consumable Forms and Procedures:

Reactivity Maneuvering sheets AOP-1, AOP-31, AOP-66A, OP-69 LOI-12-2 NRC Examination Scenario 2 Page 148 of 188

C. SCENARIO

SUMMARY

The scenario will begin with the plant operating at 85% Power. The Crew will begin by raising Reactor power to 100% with Recirculation flow. During the power ascension, CRD pump B will trip. The Crew will enter AOP-69 and start CRD pump A.

As Reactor power is being raised, Turbine vibrations will develop. The Crew will enter AOP-66 to address the vibrations. The vibrations will subside as Reactor power is lowered, however the vibrations will have caused damage resulting in Main Condenser air in-leakage. Main Condenser vacuum will degrade. The Crew will enter AOP-31 and eventually insert a manual Reactor scram.

RPS B will fail to process the scram and ARI will also fail to insert control rods. The Crew will enter EOP-2 and EOP-3. The Crew will lower Recirculation flow to minimum and then trip the RWR pumps. The Crew will terminate and prevent injection except CRD, SLC and RCIC. The SLC pump discharge relief valves will both lift, diverting boron injection from the RPV. The Main Turbine will be available until power lowers to approximately 40%, when a spurious turbine trip occurs. As power lowers, Turbine Bypass Valves will begin failing closed, challenging RPV pressure control and Primary Containment control. The Crew will be able to manually insert control rods. Eventually, either pulling RPS fuses or venting the scram air header will result in all rods inserting.

The Scenario will be terminated when all control rods are inserted and RPV water level is being restored \

maintained 177-222.5.

LOI-12-2 NRC Examination Scenario 2 Page 149 of 188

Shift Turnover The Plant is operating at approximately 85% power.

RCIC is out of service for maintenance (LCO 3.5.3, day 1 of planned 3 day maintenance window).

When you take the shift, raise Reactor power to 100% with Recirculation flow per OP-65 and RAP-7.3.16.

LOI-12-2 NRC Examination Scenario 2 Page 150 of 188

Critical Tasks/Standards Critical Task #1: Given a failure to scram with Reactor power above 2.5%, the crew will terminate and prevent all RPV injection except SLC, RCIC and CRD, in accordance with EOP-3.

Critical Task #2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

LOI-12-2 NRC Examination Scenario 2 Page 151 of 188

EVENT NO. EVENT SEQUENCE Raise Reactor Power to 100% with (Reactivity: BOP) 1.

Recirculation Flow

2. Trip of CRD Pump B (Component: ATC)

3. Turbine Vibrations (Component: BOP)

4. Loss of Main Condenser Vacuum (Component: ATC)

5. Failure of RPS and ARI to Actuate (Major: All)

6. SLC Discharge Relief Valves Lift (Component: All)

Main Generator Trip and Turbine Bypass (Component: All) 7.

Valves Sequentially Fail Closed D. TERMINATION CUES:

• All control rods are inserted

• RPV water level is being restored \ maintained 177-222.5 LOI-12-2 NRC Examination Scenario 2 Page 152 of 188

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, allow All SAT / UNSAT / NA no more than five minutes for panel walkdown

• Walkdown the control panels and assume the watch SRO

• Perform Crew Brief

• Direct BOP to raise power to 100% with Recirc flow

• Provide oversight of reactivity manipulation BOP

• Raise Recirc flow alternately with RWR MG A(B) SPEED SAT / UNSAT / NA CNTRL

• Monitor APRMs, CTP, Recirc flow, Reactor water level On Lead Examiner Cue: ATC SAT / UNSAT / NA ACTIVATE TRIGGER 1 CRD pump B trips

• Recognize / report annunciators:

o 09-5-1-9, CRD CHARGING WTR PRESS LO LOI-12-2 NRC Examination Scenario 2 Page 153 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o 09-5-1-40, CRD PMP 3P-16B OVERLOAD o 09-5-1-50, CRD PMP 39-16B TRIP

• Recognize / report trip of CRD pump B SRO

• Acknowledge report

• Enter AOP-69 (Control Rod Drive Pump Trouble)

• Direct start of CRD pump A

• Direct continuation of Control Rod Pattern Adjustment ATC SAT / UNSAT / NA Role Play;

• Execute AOP-69 If dispatched to investigate pump trip, wait 2 minutes, then

• Note override conditions for RPV pressure above 900 psig and report CRD pump B breaker is required scram tripped and there are no

• Monitor ACCUM alarm lights on full core display abnormal indications at the

• Ensure CRD FLOW CNTRL 03FIC-301 is in MAN pump.

• Rotate manual control knob on CRD FLOW CNTRL 03FIC-301 fully counterclockwise ATC cont.

• Verify in-service CRD flow control valve (03FCV-19A or B) is closed

• Start CRD PMP 03P-16A

• Slowly adjust manual control knob on CRD FLOW CNTRL 03FIC-301 to establish 59 to 61 gpm on 03-FI-310 or 03FIC-301

• Place CRD FLOW CNTRL 03FIC-301 in automatic as follows:

o Balance controller by adjusting setpoint tape o Place controller in AUTO o Adjust setpoint to BETWEEN 59 and 61 gpm LOI-12-2 NRC Examination Scenario 2 Page 154 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

• Continue Control Rod Pattern Adjustment On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 2 Turbine Vibrations

• Recognize / report high Turbine vibrations

• Monitor Turbine vibrations

• Report vibrations on bearing 5 & 6 are greater than 9 mils but less than 12 mils SRO

• Acknowledge report

• Enter AOP-66 (Main Turbine High Vibration)

• Direct power reduction per RAP-7.3.16 to lower vibrations to less than 9 mils LOI-12-2 NRC Examination Scenario 2 Page 155 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Booth Operator: BOP SAT / UNSAT / NA Once Reactor power is lowered to approximately

• Lower Recirc flow with RWR MG A(B) SPEED CNTRL 85%, ramp malfunctions

• Monitor APRMs, CTP, Recirc flow, Reactor water level TU04:E and TU04:F from

• Monitor Turbine vibrations current value to 15% over 2

• Report Turbine vibrations are less than 9 mils minutes.

On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 3 Loss of Main Condenser

• 09-3-1-28 Offgas Recombiner Trouble vacuum

• Recognize / report lowering Main Condenser vacuum SRO

• Acknowledge reports

• Enter AOP-31 (Loss of Condenser Vacuum)

• Direct power reduction per RAP-7.3.16 to maintain Main Condenser vacuum within Normal Operating Region

• Direct Reactor scram BOP SAT / UNSAT / NA

• Monitor Main Condenser vacuum

• Trip Recombiner

• Attempt to determine cause of vacuum degradation

• Lower Recirc flow with RWR MG A(B) SPEED CNTRL if Core LOI-12-2 NRC Examination Scenario 2 Page 156 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Flow is >55%.

ATC SAT / UNSAT / NA

• May insert CRAM rods

• Depress manual Scram pushbuttons

• Place Mode Switch to Shutdown ATC cont.

• Recognize / report failure to scram

• Manually initiate ARI 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 EP-3 Failure to Scram Actions Note:

• Direct bypassing MSIV low RPV water level isolation interlocks As condenser vacuum per EP-2 degrades, the Turbine may

• Direct terminate and prevent all injection except SLC, RCIC trip, Turbine Bypass Valves and CRD per EP-5 may close, and MSIVs may go

• Direct RPV water level controlled between -19 and 110 with shut. Additionally, only Group 1 Water Level Control Systems malfunctions will:

(Condensate/Feedwater, CRD, HPCI, RCIC, LPCI) o Trip the Main Generator

• Direct RPV pressure controlled 900-1000 psig with Turbine when Reactor power Bypass Valves lowers to approximately

• May direct RPV pressure controlled 800-1000 psig with 42%

LOI-12-2 NRC Examination Scenario 2 Page 157 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Sequentially fail closed 3 Turbine Bypass Valves and SRVs, as required of the 4 Turbine Bypass Valves when Reactor power lowers to approximately 24%

ATC SAT / UNSAT / NA

• Perform EP-3 Failure to Scram Actions o Ensure Rx Mode Switch in SHUTDOWN o Ensure ARI initiated o Run Recirc flow to minimum o Determine Rx power greater than 2.5%

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 ATC cont.

LOI-12-2 NRC Examination Scenario 2 Page 158 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Obtain CRS concurrence to inject SLC o Inject SLC o Verify white SQUIB VLVS READY lights are on o Note level on TK LVL 11LI-66 o Place SLC pup keylock switch in START SYS-A or START SYS-B o Verify red SLC pump running light is on o Verify SLC pump discharge pressure on DISCH PRESS 11PI-65 is greater than or equal to RPV pressure 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 failure of SLC pump to inject o Inject with other SLC pump o Recognize / report failure of second SLC pump to inject

• Insert IRMs and SRMs

• Range IRMs as necessary Critical Task #1 Given a failure to scram with Reactor power above 2.5%, the Pass / Fail crew will terminate and prevent all RPV injection except SLC, RCIC and CRD, in accordance with EOP-3.

LOI-12-2 NRC Examination Scenario 2 Page 159 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Terminate and prevent all injection except SLC, RCIC and Critical Task #1 Standard:

CRD per EP-5 Booth Operator: BOP SAT / UNSAT / NA When directed to install MSIV low water level jumpers, wait 2

• Direct NPO to bypass MSIV low RPV water level isolation minutes and run interlocks per EP-2 Section 5.1 MSIVLEVEL.cae.

• 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 BOP cont.

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 LOI-12-2 NRC Examination Scenario 2 Page 160 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL o Ensure closed FDWTR STARTUP VLV 34FCV-137 o HPCI o Trip HPCI by depressing TURB TRIP 23A-S19 Note: pushbutton RCIC is out of service as part o RCIC of the scenario setup, so RCIC o Place 13MOV-16 AUTO CONTROL BYPASS 13A-S2A actions may not be taken. keylock switch in BYPASS at panel 09-4 o Verify white light above 13MOV-16 AUTO CONTROL BYPASS 13A-S2A keylock switch is on o Ensure closed OUTBD STM SUPP VLV 13MOV-16 o Core Spray Loop A o Place 14MOV-11A AUTO ACTUATION BYPASS SW BOP cont. 14A-S16A switch in bypass o Verify white 14MOV-11A AUTO ACTUATION BYPASS LT 14A-DS35A light is on o Ensure closed OUTBD INJ VLV 14MOV-11A o Ensure PMP 14P-1A is stopped o Core Spray Loop B o Place 14MOV-11B AUTO ACTUATION BYPASS SW 14A-S16B switch in bypass o Verify white 14MOV-11B AUTO ACTUATION BYPASS LT 14A-DS35B light is on o Ensure closed OUTBD INJ VLV 14MOV-11B o Ensure PMP 14P-1B is stopped o RHR Loop A o Place 10MOV-27A AUTO CONTROL BYPASS 10A-S23A LOI-12-2 NRC Examination Scenario 2 Page 161 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Verify white light above 10MOV-27A AUTO CONTROL BYPASS 10A-S23A is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27A o Ensure RHR Loop A pumps which are not required to be running are stopped o RHR Loop B o Place 10MOV-27B AUTO CONTROL BYPASS 10A-S23B o Verify white light above 10MOV-27B AUTO CONTROL BYPASS 10A-S23B is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27B o Ensure RHR Loop B pumps which are not required to be running are stopped BOP cont.

• Report RPV water level is less than 110 to CRS Critical Task #2 Given a failure to scram, the crew will initiate Control Rod Pass / Fail insertion, in accordance with EOP-3.

LOI-12-2 NRC Examination Scenario 2 Page 162 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Perform EP-3 Backup Control Rod Insertion Actions to insert Critical Task #2 Standard:

control rods.

ATC SAT / UNSAT / NA Role Play: When Candidate Critical Task #2 attempts to pull Scram Fuses,

• Perform EP-3 Backup Control Rod Insertion Actions inform Candidate that the o De-energize scram solenoids per Subsection 5.2 panel door cannot be opened. o Determine fuses to be pulled based on lit RPS Scram Another operator has relieved Group lights you of this task. o Direct NPO to pull fuses 5A-F18B, 5A-F18F, 5A-F18D, and 5A-F18H When Candidate orders the Scram Air Header depressurized, wait 3 min and report that the valves cannot be opened to vent.

o Direct NPO to vent scram air header per Subsection 5.3 Booth Operator: when directed to reset ARI, insert Remote RP20. o Direct NPO to reset ARI per Subsection 5.4 ATC cont.

LOI-12-2 NRC Examination Scenario 2 Page 163 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Booth Operator: (with Lead Examiner concurrence)

When RPV water level is controlled below 110 and o Insert Rods using RMCS per Subsection 5.7 control rod insertion is in o Ensure ARI is reset progress: o Place RWM keylock switch in BYPASS if directed, pull RPS fuses by o Select control rod on ROD SEL matrix running o Insert control rod using ROD MOVEMENT CNTRL or SCRAMFUSEOUT.cae. ROD EMERG IN NOTCH OVERRIDE o Raise dP using CRD cooling water per Subsection 5.8

• Inform ATC when pulling o Direct NPO to close 03CRD-91 fuses. o Ensure open CRD DRV WTR PRESS VLV 03MOV-20 o Ensure closed CRD CLG WTR PRESS CNTRL VLV 03MOV-22 if directed to vent Scram Air o Raise CRD system flow rate to maximum by adjusting Header, Activate Trigger 25, CRD FLOW CNTRL 03FIC-301 in automatic or manual Scram Air Header pressure to

• Report progress of control rod insertion to CRS 0 psig LOI-12-2 NRC Examination Scenario 2 Page 164 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION BOP SAT / UNSAT / NA

• Control RPV water level between -19 and 110 with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, RCIC, LPCI) o Feedwater o If any Reactor feed pump is running:

o Ensure feedwater pump discharge pressure is less than RPV pressure by adjusting reactor feed pump speed o Lineup injection flow path by performing on or both of the following:

o Adjusting FDWTR STARTUP VLV 34FCV-137 o Ensure open or throttled open Reactor feed pump discharge valve for running pump (34MOV-100A or B) o Control feed flow to RPV by performing any of the following:

o Adjust RFP speed o Adjust FDWTR STARTUP VLV 34FCV-137 o Close feed pump discharge valves o If both Reactor feed pumps are shutdown, and BOP cont. feedwater discharge header pressure is greater than RPV pressure, then control feed flow to RPV by performing one or both of the following:

o Throttling FDWTR STARTUP VLV 34FCV-137 o Throttling one or both of the following valves, only if APRMs are on scale:

LOI-12-2 NRC Examination Scenario 2 Page 165 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o RFP A DISCH 34MOV-100A o RFP B DISCH 34MOV-100B o HPCI o Preparation for injection:

o Ensure SGT is running per OP-20 o Ensure open one of the following valves:

o HPCI GLAND SEAL SUCT 01-125MOV-13A o HPCI GLAND SEAL SUCT 01-125MOV-13B o Ensure HPCI FLOW CNTRL 23FIC-108-1 setpoint is adjusted to minimum o Ensure HPCI FLOW CNTRL 23FIC-108-1 is in AUTO o Injection with initiation signal:

o Depress INITIATION SIG/MAN TURB TRIP RESET 23A-S17 pushbutton o Verify annunciator 09-3-3-28 HPCI TURB TRIP BOP cont. SOLENOID ENERGIZED is clear o Verify HPCI auto-initiation o Control HPCI turbine speed in manual or automatic o Periodically verify HPCI turbine speed is greater than 2100 rpm ATC SAT / UNSAT / NA

• Report all control rods are inserted LOI-12-2 NRC Examination Scenario 2 Page 166 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

• Acknowledge report

• Exit EOP-3

• Enter EOP-2

• Direct RPV water level restored and maintained 177-222.5 BOP SAT / UNSAT / NA

• Begins restoring and \ or maintaining RPV water level 177-222.5 LOI-12-2 NRC Examination Scenario 2 Page 167 of 188

Termination Criteria:

• All control rods are inserted

• Reactor water level is being restored \ maintained 177-222.5 LOI-12-2 NRC Examination Scenario 2 Page 168 of 188

ATTACHMENT 1 B. Shift Turnover The Plant is operating at approximately 85% power.

RCIC is out of service for maintenance (LCO 3.5.3, day 1 of planned 3 day maintenance window).

When you take the shift, raise Reactor power to 100% with Recirculation flow per OP-65 and RAP-7.3.16.

LOI-12-2 NRC Examination Scenario 2 Page 169 of 188

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI-12-2 NRC EXAMINATION SCENARIO 3 TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: NRC 3 PATH: STAND ALONE Validation: ______________________ Training: ______________________ Operations: ______________________

CANDIDATES CRS ATC BOP LOI-12-2 NRC Examination Scenario 3 Page 170 of 188

RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 5/7/12 LOI-12-1 Backup Scenario Updated for LOI-12-2 exam T. Hooper LOI-12-2 NRC Examination Scenario 3 Page 171 of 188

C. TITLE: LOI-12-2 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

3. IC-158

6. Special Instructions:

a. The Plant is operating at approximately 5% power.

b. A Plant start-up is in progress.

c. RFP A is out of service for maintenance (Red tags on the following: 101A, 100A, Trip P\B, Turning Gear, Hyd Coupler, AC and DC Oil Pumps).

d. APRM A & B recorder selector switch in APRM position

7. Preset Conditions:

a. Preset, HP11, 23MOV-15 Auto Isolation failure

b. Preset, AD07A-K, All SRVs fail to open

c. Preset, RD10, Control Rod 50-27 Stuck

d. TRIGGER 2, OR EDZDI11HOEB01 Bus 10400-10600 Breaker 10614 Trip

e. TRIGGER 4, ED21:D, 600VAC Emerg Bus 12600 Failure

f. TRIGGER 4, R: EP09, Seismic Event

g. TRIGGER 6, HP06, HPCI Steam Leak Initial 0.4% Ramp 10 min. to 2%

h. TRIGGER 7, R: HP03, 23MOV-15 Ckt Bkr

i. TRIGGER 10, R: DG23:B, EDG-B Local Maintenance Switch, Maint

j. TRIGGER 11, R: DG23:D, EDG-D Local Maintenance Switch, Maint

k. TRIGGER 12, R: DG23:A, EDG-A Local Maintenance Switch, Maint

l. TRIGGER 12, R: DG23:C, EDG-C Local Maintenance Switch, Maint

m. TRIGGER 13, R: SW21, EDG Manual Isolation VVS ESW-2A/2B, 100%

n. Assure Trigger 7 is tied to EVENT TRIGGER MOV CLOSED

o. Event Trigger 30, rdpdrvdp>290, dmf RD10:50:27

6. Consumable Forms and Procedures:

Reactivity Maneuvering sheets AOP-1 AOP-14 AOP-19 AOP-19B LOI-12-2 NRC Examination Scenario 3 Page 172 of 188

C. SCENARIO

SUMMARY

The scenario will begin at approximately 5% power with a Plant start-up in progress. The crew will begin the shift by pulling two control rods from position 00 to 12. The second control rod will not move at normal drive water pressure. The crew will raise drive water pressure and successfully withdraw the control rod.

The crew will then place the Mode Switch in RUN and withdraw IRMs per OP-65. Following transition to mode 1, a degraded voltage condition on the 10600 Bus occurs. This results in both EDGs B and D starting and paralleling onto the 10600 Bus. AOP-19 (Loss of 10600 Bus) will be entered. Following the auto start of the EDGs, a report from the field states that EDG B has a Low Lube Oil Pressure which is an automatic trip of EDG B with a LOCA signal not present. However, EDG B is still running and the Operator should recognize this and shutdown EDG B.

Next, a Seismic Event occurs and L26 de-energizes. AOP-14 (Earthquake) is entered and AOP-19B (Loss of Switchgear L26) will be entered which requires EDG D to be shutdown. This results in a complete loss of the 10600 Bus and AOP-19 will be re-addressed. Additionally, AOP-60 (Loss of RPS Bus B Power) will be entered.

While the Electric Plant transient is being addressed, an unisolable steam leak from the HPCI steam line becomes evident. This results in rising Reactor Building area temperatures. EOP-5 will be entered. EOP-5 actions will require EOP-2 entry and a manual Scram ordered before any area exceeds its Maximum Safe temperature.

The HPCI steam leak degrades resulting in two area temperatures exceeding their Max Safe values. When this occurs, an Emergency Depressurization is required to be performed. When SRVs are attempted to be opened, none will operate. This requires Group 2 Pressure Control Systems to be used for Emergency Depressurization.

The Scenario will be terminated when the RPV is being rapidly depressurized with Group 2 Pressure Control Systems and RPV level is in the assigned band.

LOI-12-2 NRC Examination Scenario 3 Page 173 of 188

Shift Turnover The Plant is operating at approximately 5% power with a start-up in progress.

RFP A is out of service for maintenance.

When you take the shift, complete the following:

3. Withdraw the next two control rods in the start-up sequence (26-51 and 50-27, from position 00 to 12).

4. Then, perform OP-65 steps D.20.2 through D.20.4 to place the Mode Switch to RUN and withdraw IRMs.

5. Then, continue control rod withdrawals per the start-up sequence.

LOI-12-2 NRC Examination Scenario 3 Page 174 of 188

Critical Tasks/Standards Critical Task #1: Given the plant operating at power with an unisolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

Critical Task #2: Given an unisolable primary system discharging into Secondary Containment, two areas exceeding Maximum Safe Temperatures, and failure of multiple SRVs to open, the crew will rapidly depressurize the RPV, in accordance with EOP-2.

LOI-12-2 NRC Examination Scenario 3 Page 175 of 188

EVENT NO. EVENT SEQUENCE

1. Continue Raising Reactor Power with Control Rods (Reactivity: ATC)

2. Stuck Control Rod (Component: ATC)

3. Transition to Mode 1 (Normal: ATC)

4. Degraded 10600 Voltage (Component: BOP)

5. EDG B Low Lube Oil Pressure (Component: BOP)

6. Seismic Event with Loss of L26 (Component: BOP)

7. HPCI Steam Leak (Major: All)

8. HPCI Fails to Isolate (Component: All)

9. SRVs Fail to Open (Component: All)

D. TERMINATION CUES:

• All control rods are inserted

• RPV is being rapidly depressurized with Group 2 Pressure Control Systems

• Reactor water level is controlled 177-222.5 LOI-12-2 NRC Examination Scenario 3 Page 176 of 188

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, allow All SAT / UNSAT / NA no more than five minutes for panel walkdown

• Walkdown the control panels and assume the watch SRO

• Perform Crew Brief

• Direct ATC to continue Rx Startup

• Provide oversight of reactivity manipulation

• Direct Mode Switch placed in RUN ATC SAT / UNSAT / NA

• Withdraw Control Rod 26-51 to position 12 per OP-26

• Attempt to withdrawal Control Rod 50-27

• Report Control Rod 50-27 failed to move at position 00

• Raise CRD drive water differential pressure in 50 psid increments per OP-25, Section E.6

• Attempt to withdraw Control Rod with differential pressure at

~300 psid ATC cont.

LOI-12-2 NRC Examination Scenario 3 Page 177 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

• Report Control Rod moved out

• Restore Drive Water dP to original value (~260)

• Continue withdrawal of Rod 50-27 to 12.

ATC SAT / UNSAT / NA

• Rotate Mode Switch clockwise to RUN

• Place Channel Selector switches in APRM/RBM

• Withdraw IRMs to full out as follows:

o Ensure POWER ON light is on o Ensure IRM(s) that will be withdrawn is(are) selected o Ensure IRM SELECT light(s) is (are) off for IRM(s) that will not be withdrawn o Verify IRM RETRCT PERMIT light(s) is (are) on for IRM(s) that will be withdrawn o Depress DRIVE OUT/DRIVING OUT pushbutton o Verify DRIVE OUT light is on o Verify DRIVING OUT light comes on o WHEN IRM(s) is (are) at desired position OR detector OUT light comes on, depress DRIVE OUT/DRIVING OUT pushbutton o Verify the following lights are off:

o DRIVE OUT o DRIVING OUT o WHEN operation of IRMs is no longer desired, ensure IRMs are de-selected On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 2

• Recognize / report trip of Bus 10600 normal supply breaker Degraded Bus 10600 Voltage

• Recognize / report start of EDGs B and D LOI-12-2 NRC Examination Scenario 3 Page 178 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

• Acknowledge reports

• Place start-up on hold

• Enter AOP-19 (Loss of 10600 Bus)

• Enter AOP-60 (Loss RPS B)

BOP SAT / UNSAT / NA

• Execute AOP-19

• Execute AOP-60

• Dispatches NPO to verify proper EDG operation and to restore RBC temp

• Stop DW Cooling Fans 68FN-2D and 4A

• Exit AOP-19 and enter AOP-60 (Loss of RPS Bus B Power)

• Verify SBGT B start per OP-20 Section G.6 o Verify the following:

o White light for AIR HTR 01-125E-5B is on o Red light for AIR HTR 01-125E-5B is on o BELOW EL 369 SUCT 01-125MOV-12 is open o TRAIN B CLG VLV 01-125MOV-100B is closed o TRAIN B INLET 01-125MOV-14B is open BOP cont.

o FN DISCH 01-125MOV-15B is open o TRAIN B FN 01-125FN-1B is running o If SGT Train A is shutdown, then verify flow rate on SGT FLOW 01-125FI-106A:

o RB un-isolated - Approximately 6000 scfm o RB isolated - Approximately 5600 to 5800 scfm

• Verify RWCU isolation per OP-28 Section G.2 o Ensure the following pumps are stopped at panel 09-4:

LOI-12-2 NRC Examination Scenario 3 Page 179 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o CLN UP PMP 12P-1A o CLN UP PMP 12P-1B o Dispatch NPO to perform field actions for RWCU isolation o Ensure closed the following valves:

o CLN UP SUCT 12MOV-15 o CLN UP SUCT 12MOV-18 o CLN UP RETURN ISOL VLV 12MOV-69 o FILTER DEMIN BYP 12MOV-74 o CLN UP BLOWDOWN FLOW CNTRL 12FCV-55 o BLOWDOWN ORIFICE BYP 12MOV-53 o BLOWDOWN TO MAIN CNDSR 12MOV-56 o BLOWDOWN TO RDW 12MOV-57

• Isolate RB Ventilation per OP-51A Section G.1:

o Ensure SBGT is running per OP-20 BOP cont. o Depress the following pushbuttons at panel 09-75:

o RB VENT ISOL A o RB VENT ISOL B o Verify isolation per Subsection G.2:

o INBD SUPP ISOL 66AOV-100A - Closed o OUTBD EXH ISOL 66AOV-101A - Closed o BELOW EL 369' RECIRC 66AOD-105 -Open o EL 369' RECIRC 66AOD-108 - Open o OUTBD SUPP ISOL 66AOV-100B - Closed o INBD EXH ISOL 66AOV-101B - Closed o SUPP FN 66FN-5A, 5B, 5C (two of three) - On o BELOW EL 369' EXH FN 66FN-12A OR 66FN-12B -

On o EL 369' EXH FN 66FN-13A AND 66FN-13B - Off LOI-12-2 NRC Examination Scenario 3 Page 180 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o TK EXH FN 66FN Off o CRESC SUPP FN 66FN-26A OR 66FN-26B - On o STANDBY GAS TREATMENT - Running per OP-20 o Reactor building to atmosphere differential pressure o -0.25 to -2.50 in. water gauge

• Notify Chemistry of RWCU, Drywell CAMS and RB Vent Rad Monitor isolations On Lead Examiner Cue: BOP SAT / UNSAT / NA Role Play:

• Receive report of low lube oil pressure (<20 psig)

As NPO at EDG B panel, report that EDG B has a Lube

• Recognize this a trip since EDG did NOT start on ECCS signal Oil pressure of 12 psig

• Inform SRO of EDG condition indicated on 93PS-3B (Low Lube Oil Pressure Alarm is in.).

SRO

• Acknowledge report

• Direct Emergency Shutdown of EDG B Booth Operator: BOP SAT / UNSAT / NA When NPO directed to take EDG B Control Sw to MAINT,

• Coordinate with NPO to perform an Emergency Shutdown of insert Remote DG23:B to EDG B per OP-22 Section G.17:

Maint. (Trigger 10) o Ensure EDG (B) load breaker (71-10602) is tripped and placed in PULL TO LOCK position LOI-12-2 NRC Examination Scenario 3 Page 181 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Ensure EDG tie breaker (10604) is tripped o Place EDG (B) CONTROL SWITCH in MAINT at panel 93ECP-(B) o Place EDG (B) CNTRL switch to STOP at panel 09-8

• Report EDG (B) is shutdown On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 4

• Recognize / report seismic alarm Seismic event and L26 fault

• Recognize / report L26 is de-energized SRO

• Enter AOP-19B (Loss of Switchgear L26)

• Re-enter AOP-60 (Loss of RPS Bus B Power)

• Re-enter AOP-19 (Loss of 10600 Bus)

• Enter AOP-14 (Earthquake)

BOP SAT / UNSAT / NA

• Execute AOP-19B:

o Shutdown EDG D o Ensure EDG (D) load breaker (71-10612) is tripped and placed in PULL TO LOCK position o Ensure EDG tie breaker (10604) is tripped o Place EDG (D) CONTROL SWITCH in MAINT at panel Booth Operator: 93ECP-(D)

When NPO directed to take o Place EDG (D) CNTRL switch to STOP at panel 09-8 EDG D Control Sw to MAINT, o Supply cooling water to B & D EDGs from ESW Pump 46P-insert Remote DG23:D to 2A per OP-22 Section G.24:

Maint. (Trigger 11) o Verify EDGs A and C are shutdown o Verify ESW Pump 46P-2B is not available LOI-12-2 NRC Examination Scenario 3 Page 182 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION o Verify ESW Pump 46P-2A is available Booth Operator: BOP cont. o Place the following switches in MAINT to prevent EDG When NPO directed to take operation:

EDG A and C Control Sw to o EDG A CONTROL SWITCH at panel 93ECP-A MAINT, insert Remote o EDG C CONTROL SWITCH at panel 93ECP-C DG23:A and DG:23C to Maint.

o Dispatch NPO to:

(Trigger 12) o Unlock and close 46ESW-3A o Open the following valves:

When NPO directed to realign ESW valves, wait 3 minutes, o 46ESW-2A insert Remote SW21 to 100% o 46ESW-2B (Trigger 13). o Ensure ESW Pump 46P-2A is running o Ensure closed the following valves:

o ESW SYS B INJ VLV 46MOV-101B o ESW SYS B TEST VLV 46MOV-102B

• Re-execute AOP-60, as necessary

• Re-execute AOP-19, as necessary Role Play:

• Execute AOP-14 If dispatched as NPO, wait 2 o Dispatch plant operators for inspections minutes and report 27SOV-o Dispatch plant operator to ensure open 27SOV-129A or 129A is open.

27SOV-129B o Call NMP2 and/or National Earthquake Information Center Role Play: for confirmation of seismic activity If called as NMP2 or National o Direct I&C to analyze seismic tapes Earthquake Information Center, report that you have detected a seismic event of greater than 0.01g but less than 0.08g.

LOI-12-2 NRC Examination Scenario 3 Page 183 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION On Lead Examiner Cue: BOP / ATC SAT / UNSAT / NA ACTIVATE TRIGGER 6

• Recognize / report rising RB pressure Unisolable HPCI steam leak

• Recognize / report rising HPCI area temperatures

• Recognize / report HPCI alarms o 09-3-3-2 DIV I AMBIENT TEMP HI o 09-3-3-33 HPCI ISOL TRIP INITIATED

• Dispatches NPO to inspect drywell entrance

• Recognize / report 23MOV-15 (INBD STM SUPP VLV) does not isolate automatically

• Manually attempt to close 23MOV-15

• Report 23MOV-15 can not be closed due to MOV being de-energized Critical Task #1 Given the plant operating at power with an unisolable primary Pass / Fail system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

Manual Scram pushbuttons (preferred) depressed Critical Task #1 Standard:

OR Mode Switch placed in Shutdown SRO

• Acknowledge reports

• Enter EOP-5 (Secondary Containment Control)

• Direct maximizing Reactor Building area cooling LOI-12-2 NRC Examination Scenario 3 Page 184 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

• Direct local area evacuation of Reactor Building

• Set benchmark for HPCI area temperatures

• Enter EOP-2

• Direct manual Reactor scram

• Direct Reactor pressure control 900 to 1000 psig

• Direct RPV level control 177-222.5 inches

• Direct a Reactor cooldown <100oF/hr

• Monitor for 2 Max Safe values

• May anticipate Emergency Depressurization and rapidly depressurize RPV with Turbine Bypass Valves ATC SAT / UNSAT / NA Critical Task #1

• Depress manual Scram pushbuttons

• Place Mode Switch to Shutdown

• Report all control rods have inserted

• Enter AOP-1 o Fully insert IRMs and SRMs o Observe Reactor power downscale on APRMs ATC cont.

o Observe SDIV vent and drain valves closed o Ensure Main Turbine is tripped o Verify 4 KV loads transfer to reserve power o Transfer APRM/IRM recorders to IRMs o Down-range IRMs o Monitor Reactor pressure control on the Turbine Bypass LOI-12-2 NRC Examination Scenario 3 Page 185 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Valves o May open Turbine Bypass Valves to initiate cooldown or rapidly depressurize RPV in anticipation of Emergency Depressurization BOP SAT / UNSAT / NA

• Announce Reactor Building Evacuation

• Enter AOP-1 o Control RPV water level between 177 and 222.5 using any of the following methods:

o Adjust feedwater level control auto-setpoint o Take manual control of reactor feed pump and adjust FDWTR STARTUP VLV (34FCV-137) o Operate RCIC per OP-19 Section D o Operate HPCI per OP-15 Section D

• Verify Group 2 isolation per AOP-15 BOP / ATC SAT / UNSAT / NA

• Update crew on RB area temperatures

• Report two area temperatures above Max Safe Value Critical Task #2 Given an unisolable primary system discharging into Pass / Fail Secondary Containment, two areas exceeding Maximum Safe Temperatures, and failure of multiple SRVs to open, the crew will rapidly depressurize the RPV, in accordance with EOP-2.

Rapidly depressurize the RPV using one or more Group 2 Critical Task #2 Standard:

Pressure Control Systems.

LOI-12-2 NRC Examination Scenario 3 Page 186 of 188

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SRO

• Recognize / acknowledge two area temperatures above Max Safe Value

• Enter Emergency Depressurization leg of EOP-2

• Direct 7 ADS valves opened

• Acknowledge SRVs fail to open

• Direct rapid depressurization of RPV with one or more Group 2 Pressure Control Systems BOP / ATC

• Attempts to opens 7 ADS valves SAT / UNSAT / NA

• Reports no ADS valves open

• Reports no SRVs will open

• Rapidly depressurize RPV using one or more Group 2 Critical Task #2 Pressure Control System Termination Criteria:

• All control rods are inserted

• RPV is being rapidly depressurized with Group 2 Pressure Control Systems

• Reactor water level is controlled 177-222.5 LOI-12-2 NRC Examination Scenario 3 Page 187 of 188

ATTACHMENT 1 C. Shift Turnover The Plant is operating at approximately 5% power with a start-up in progress.

RFP A is out of service for maintenance.

When you take the shift, complete the following:

1. Withdraw the next two control rods in the start-up sequence (26-51 and 50-27, from position 00 to 12).

2. Then, perform OP-65 steps D.20.2 through D.20.4 to place the Mode Switch to RUN and withdraw IRMs.

3. Then, continue control rod withdrawals per the start-up sequence.

LOI-12-2 NRC Examination Scenario 3 Page 188 of 188