ML003741044
| ML003741044 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/25/2000 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR | |
| Download: ML003741044 (133) | |
Text
GRAND GULF Number: GG-1-JPM-SRO-A&E21 Revision: 00 NUCLEAR STATION Page: 1 of 8 Rtype:
-ENTERGY JOB PERFORMANCE MEASURE QA Record Number of pages Date _ Initials REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
REVIEW / APPROVAL:
R.ETURN RECEIPT FINAL ACCEPTANCE DATE INITIAL RETURNED FOR (DATE/INITIAL) BY RM TRANSMITTED RECEIPT BY RM CORRECTIONS (DATE/INITIALS)
TO RM (DATE/INITIAL) (DATE/INITIAL)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 1 JPM No. GG-l-JPM-SRO-A&E21 Rev. 00 Page 2 of 8 Task List No: SRO-A&E-015; SRO-A&E-041 K/A Reference and Importance Factors (RO/SRO):
K/A 2.4.41 - 4.1; 2.4.40 - 4.0; 2.4.30 - 3.6 10CFR55.45a(11)
Time Required for Completion: 15 Minutes (approximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Setting: Classroom X Plant X Simulator X SHOULD BE PERFORMED FOLLOWING SCENARIO 1 WITH SRO CANDIDATE EVALUATION Date Performed:
Performer: SSN: License: RO/SRO Score: PASS FAIL Time to complete:
Evaluator Signature: Date:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 1 GG-I-JPM-SRO-A&E21 Rev. 00 Page 3 of 8 JPM No.
DISCUSSION Performance of this JPM will demonstrate the ability of a Senior Reactor Operator to properly classify emergency events per Emergency Plan Procedure 10-S-01-1 and complete the required Initial Notification Form. Performance can be performed in the simulator, plant or in a classroom setting provided candidate has access to Emergency Plan Procedures.
Required Material(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 06-01, NOTIFICATION FORM General Reference(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Personnel Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 1 Rev. 00 Page 4 of 8 JPM No. GG-I-JPM-SRO-A&E21 READ TO TRAINEE I will explain the initial conditions, which step(s) to cues. Prior simulate or discuss, and provide the initiating JPM, I will to actually starting the performance of this answer any questions you have. For each step you perform, and what describe or state what indications you are observing in response to your action.
indications you expect to see When you have completed the task, inform me.
Task Standard(s):
an ALERT Emergency Plan is applied to classify the event as Notification form is completed per EAL 2.2.1 and the Initial (See Attached).
Condition(s): (The location for the initial conditions to Initial be given is
- are The plant was operating at 34% power. Thunder showers reported in Tensas Parish. The 115 KV line is out of service The CCW due to required maintenance on ESF 12 Transformer.
Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
if any, Determine the Emergency Action Level Classification, and if required complete the required Initial Notification Form. Communicators are available if required.
Start Time:
at pre-evaluation meeting by
- This location will be determined the evaluators involved.
G*AND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 1 Rev. 00 Page 5 of 8 JPM No. GG-I-JPM-SRO-A&E21 items denoted by (*). Sequence is assumed unless NOTE:Critical denoted in the Comments.
Item 1 (*) Consult EPP 10-S-01-1 "Activation of the Emergency Plan" and classifies an ALERT.
Standard: Candidate consults EPP 10-S-01-1 "Activation of the Emergency Plan" EAL 2.2.1 and classifies an ALERT based on leakage in the Drywell from the RPV being in excess of 50 gpm with the plant in modes 1, 2, or 3.
Comments: Since the leakage in the Drywell was in excess of that of CRD, this is greater than 50 gpm.
SAT UNSAT Item 2 (*) Complete the Initial Notification form EPP 06-01 for an ALERT.
Standard: Candidate completes Initial Notification form EPP 06-01 with data marked with an * (See Attached).
Comments:
SAT UNSAT
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 1 Page 6 of -8 JPM No. GG-I-JPM-SRO-A&E21 Rev. 00 TERMINATING CUE(s):
as an ALERT Emergency Plan is applied to classify the event Notification form is completed per EAL 2.2.1 and the Initial (See Attached).
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 1 JPM No. GG-I-JPM-SRO-A&E21 Rev. 00 Page 7 of 8 ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE OF THE JPM TO CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING OF TASK PERFORMED:
Question K/A Rating Expected Response Time Reference(s) Required: Yes / No Reference(s):
Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
The plant was operating at 34% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service due to required maintenance on ESF 12 Transformer. The CCW Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
Determine the Emergency Action Level Classification, if any, and if required complete the required Initial Notification Form. Communicators are available if required.
GRAND GULF Number: GG-1-JPM-SRO-A&E22 Revision: 00 NUCLEAR STATION Page: 1 of 8 Rtype:
ENTERGY JOB PERFORMANCE MEASURE QA Record Number of pages Date Initials __
REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
REVIEW / APPROVAL:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 2 Rev. 00 Page 2 of 8 JPM No. GG-l-JPM-SRO-A&E22 Task List No: SRO-A&E-015; SRO-A&E-041 K/A Reference and Importance Factors (RO/SRO):
K/A 2.4.41 - 4.1; 2.4.40 - 4.0; 2.4.30 - 3.6 10CFR55.45a(11)
Time Required for Completion: 15 Minutes (approximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Performance: Simulate _ Actual X Setting: Classroom X Plant X Simulator X SHOULD BE PERFORMED FOLLOWING SCENARIO 2 WITH SRO CANDIDATE EVALUATION Date Performed:
SSN: License: RO/SRO Performer:
FAIL Time to complete:
Score: PASS Date:
Evaluator Signature:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 2 JPM No. GG-I-JPM-SRO-A&E22 Rev. 00 Page 3 of 8 DISCUSSION Performance of this JPM will demonstrate the ability of a Senior Reactor Operator to properly classify emergency events per Emergency Plan Procedure 10-S-01-1 and complete the required Initial Notification Form. Performance can be performed in the simulator, plant or in a classroom setting provided candidate has access to Emergency Plan Procedures.
Required Material(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 06-01, NOTIFICATION FORM General Reference(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Personnel Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 2 JPM No. GG-l-JPM-SRO-A&E22 Rev. 00 Page 4 of 8 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, what describe or state what indications you are observing and indications you expect to see in response to your action.
When you have completed the task, inform me.
Task Standard(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 11.4 and the Initial Notification form is completed (See Attached).
Initial Condition(s): (The location for the initial conditions to be given is
- The plant was operating at 44% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service due to required maintenance on ESF 12 Transformer. The CCW Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
Determine the Emergency Action Level Classification, if any, and if required complete the required Initial Notification Form. Communicators are available if required.
Start Time:
- This location will be determined at pre-evaluation meeting by the evaluators involved.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 2 JPM No. GG-l-JPM-SRO-A&E22 Rev. 00 Page 5 of 8 NOTE:Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
Item 1 (*) Consult EPP 10-S-01-1 "Activation of the Emergency Plan" and classifies a SITE AREA EMERGENCY.
Standard: Candidate consults EPP 10-S-01-1 "Activation of the Emergency Plan" EAL 11.4 and classifies a SITE AREA EMERGENCY based on scram conditions confirmed, and multiple control rods beyond position 02, and reactor power > 4% on APRMs.
Comments: Since the leakage in the Drywell was in excess of 50 gpm the candidate may mention EAL 2.2.1. EAL 11.4 is the overriding EAL in this case due to severity.
SAT UNSAT Item 2 (*) Complete the Initial Notification form EPP 06-01 for a SITE AREA EMERGENCY.
Standard: Candidate completes Initial Notification form EPP 06-01 with data marked with an * (See Attached).
Comments:
SAT UNSAT
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 2 GG-l-JPM-SRO-A&E22 Rev. 00 Page 6 of 8 JPM No.
TERMINATING CUE(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 11.4 and the Initial Notification form is completed (See Attached).
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 2 Rev. 00 Page 7 of 8 JPM No. GG-l-JPM-SRO-A&E22 OF THE JPM TO ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE PERFORMED:
CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING OF TASK K/A Rating Question Expected Response Time Required: Yes / No Reference(s):
Reference(s)
Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
The plant was operating at 44% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service The CCW due to required maintenance on ESF 12 Transformer.
The event Pump C and RHR Pump C are red tagged for repairs.
just observed has occurred.
Initiating Cue(s):
if any, Determine the Emergency Action Level Classification, and if required complete the required Initial Notification Form. Communicators are available if required.
GRAND GULF Number: GG-1-JPM-SRO-A&E23 Revision: 00 NUCLEAR STATION Page: 1 of 8 Rtype:
JOB PERFORMANCE QA Record SENTERGY MEASURE Number of pages Date - Initials REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
REVIEW / APPROVAL:
DATE:
PREPARED BY:
DATE:
APPROVED BY:
Facility Representative RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE DATE INITIAL CORRECTIONS (DATE/INITIAL) BY RM TRANSMITTED RECEIPT BY RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
TO RM
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 3 Rev. 00 Page 2 of 8 JPM No. GG-I-JPM-SRO-A&E23 Task List No: SRO-A&E-015; SRO-A&E-041 K/A Reference and Importance Factors (RO/SRO):
2.4.41 - 4.1; 2.4.40 - 4.0; 2.4.30 - 3.6 K/A 10CFR55.45a(11)
Time Required for Completion: 15 Minutes (*3pproximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Simulate Actual X Performance:
Setting: Classroom X Plant x Simulator X SRO SHOULD BE PERFORMED FOLLOWING SCENARIO 3 WITH CANDI DATE EVALUATION Date Performed:
SSN: License: RO/SRO Performer:
Time to complete:
Score: PASS FAIL Date:
Evaluator Signature:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 3 00 Page 3 of -
JPM No. GG-l-JPM-SRO-A&E23 Rev.
DISCUSSION ability of a Performance of this JPM will demonstrate the events per Senior Reactor Operator to properly classify emergency the required Emergency Plan Procedure 10-S-01-1 and complete Performance can be performed in the Initial Notification Form.
provided candidate has simulator, plant or in a classroom setting access to Emergency Plan Procedures.
Required Material(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 06-01, NOTIFICATION FORM General Reference(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan Notification of Offsite Agencies and 02 EPP 10-S-01-6, Plant On-Call Personnel Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 3 JPM No. GG-l-JPM-SRO-A&E23 Rev. 00 Page 4 of 8 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, describe or state what indications you are observing and what indications you expect to see in response to your action.
When you have completed the task, inform me.
Task Standard(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 4.3.1 and the Initial Notification form is completed (See Attached).
Initial Condition(s): (The location for the initial conditions to be given is
- The plant was operating at 100% power. Scattered Thunder Showers are reported in Tensas Parish. The 115 KV line is out of service due to required maintenance on ESF 12 Transformer. The CCW Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
Determine the Emergency Action Level Classification, if any, and if required complete the required Initial Notification Form. Communicators are available if required.
Start Time:
- This location will be determined at pre-evaluation meeting by the evaluators involved.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 3 Rev. 00 Page 5 of -8 JPM No. GG-l-JPM-SRO-A&E23 Sequence is assumed unless NOTE:Critical items denoted by (*).
denoted in the Comments.
Item 1 (*) Consult EPP 10-S-01-1 "Activation of the Emergency Plan" and classifies a SITE AREA EMERGENCY.
Standard: Candidate consults EPP 10-S-01-1 "Activation of the Emergency Plan" EAL 4.3.1 and classifies a SITE AREA EMERGENCY based on steam leak outside primary containment which cannot be isolated or has evidence of MSIV leakage resulting in at least one Main Steam line not isolated.
Comments: EAL 4.3.1 is the overriding EAL in this case due to severity. Plant Shutdown Function is NOT a limiting emergency based on the small number of control rods not fully inserted.
SAT UNSAT Item 2 (*) Complete the Initial Notification form EPP 06-01 for a SITE AREA EMERGENCY.
Standard: Candidate completes Initial Notification form EPP 06-01 with data marked with an * (See Attached).
Comments: Cue Health Physics report there is NO RADIOACTIVE RELEASE in progress.
SAT UNSAT
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 3 GG-O-JPM-SRO-A&E23 Rev. 00 Page 6 of 8 JPM No.
TERMINATING CUE(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 4.3.1 and the Initial Notification form is completed (See Attached).
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 3 GG-I-JPM-SRO-A&E23 Rev. 00 Page 7 of 8 JPM No.
THE JPM TO ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE OF CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING OF TASK PERFORMED:
K/A Rating Question Expected Response Time Reference(s) Required: Yes / No Reference(s):
Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
Scattered Thunder The plant was operating at 100% power.
The 115 KV line is Showers are reported in Tensas Parish.
on ESF 12 out of service due to required maintenance C are red tagged for Transformer. The CCW Pump C and RHR Pump repairs. The event just observed has occurred.
Initiating Cue(s):
Classification, if any, Determine the Emergency Action Level Initial Notification and if required complete the required Form. Communicators are available if required.
GRAND GULF Number: GG-1-JPM-SRO-A&E24 NUCLEAR STATION Revision: 00 Page: 1 of 8 Rtype:
ENTERGY JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAININGC PROGRAM:
TRAINING PROGRAM:
OPERATOR TRAINING TITLE:
EAL CLASSIFICATION: SCENARIO 4 REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
REVIEW / APPROVAL:
PREPARED BY: DATE:
APPROVED BY: DATE:
Facility Representative DATE INITIAL RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED RECEIPT BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 4 JPM No. GG-l-JPM-SRO-A&E24 Rev. 00 Page 2 of 8 Task List No: SRO-A&E-015; SRO-A&E-041 K/A Reference and Importance Factors (RO/SRO):
K/A 2.4.41 - 4.1; 2.4.40 - 4.0; 2.4.30 - 3.6 10CFR55.45a(I)
Time Required for Completion: 15 Minutes (approximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Setting: Classroom X Plant X Simulator X SHOULD BE PERFORMED FOLLOWING SCENARIO 4 WITH SRO CANDIDATE EVALUATION Date Performed:
Performer: SSN: License: RO/SRO Score: PASS FAIL Time to complete:
Evaluator Signature: Date:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 4 JPM No. GG-I-JPM-SRO-A&E24 Rev. 00 Page 3 of 8 DISCUSSION Performance of this JPM will demonstrate the ability of a Senior Reactor Operator to properly classify emergency events per Emergency Plan Procedure 10-S-01-1 and complete the required Initial Notification Form. Performance can be performed in the simulator, plant or in a classroom setting provided candidate has access to Emergency Plan Procedures.
Required Material(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 06-01, NOTIFICATION FORM General Reference(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 10-S-01-6, Notification of Offsite Agencies and Plant On-Call Personnel Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 4 JPM No. GG-l-JPM-SRO-A&E24 Rev. 00 Page 4 of 8 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, describe or state what indications you are observing and what indications you expect to see in response to your action.
When you have completed the task, inform me.
Task Standard(s):
Emergency Plan is applied to classify the event as an ALERT per FAL 2.2.1 and the Initial Notification form is completed (See Attached).
Initial Condition(s): (The location for the initial conditions to be given is
- The plant was operating at = 90% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service due to required maintenance on ESF 12 Transformer. The CCW Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
Determine the Emergency Action Level Classification, if any, and if required complete the required Initial Notification Form. Communicators are available if required.
Start Time:
- This location will be determined at pre-evaluation meeting by the evaluators involved.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 4 JPM No. GG- -JPM-SRO-A&E24 Rev. 00 Page 5 of 8 NOTE:Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
Item 1 (*) Consult EPP 10-S-01-1 "Activation of the Emergency Plan" and classifies an ALERT.
Standard: Candidate consults EPP 10-S-01-1 "Activation of the Emergency Plan" EAL 2.2.1 and classifies an ALERT based on a feedwater leak inside the Drywell which has evidence of additional leakage.
Comments:
SAT UNSAT Item 2 (*) Complete the Initial Notification form EPP 06-01 for an ALERT.
Standard: Candidate completes Initial Notification form EPP 06-01 with data marked with an * (See Attached).
Comments:
SAT UNSAT
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 4 JPM No. GG-l-JPM-SRO-A&E24 Rev. 00 Page 6 of 8 TERMINATING CUE(s):
Emergency Plan is applied to classify the event as an ALERT per EAL 2.2.1 and the Initial Notification form is completed (See Attached).
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 4 Rev. 00 Page 7 of 8 JPM No. GG-I-JPM-SRO-A&E24 OF THE JPM TO ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING OF TASK PERFORMED:
K/A Rating Question Expected Response Time Required: Yes / No Reference(s):
Reference(s)
Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
The plant was operating at = 90% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service The CCW due to required maintenance on ESF 12 Transformer.
repairs. The event Pump C and RHR Pump C are red tagged for just observed has occurred.
Initiating Cue(s):
if any, Determine the Emergency Action Level Classification, required complete the required Initial Notification and if Form. Communicators are available if required.
GRAND GULF Number: GG-1-JPM-SRO-A&E25 Revision: 00 B SENTERGY NUCLEAR STATION JOB PERFORMANCE MEASURE Page: I of 8 Rtype:
QA Record Number of pages Date _ Initials REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
REVIEW / APPROVAL:
DATE:
PREPARED BY:
DATE:
APPROVED BY:
Facility Representative RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE DATE INITIAL CORRECTIONS (DATE/INITIAL) BY RM TRANSMITTED RECEIPT BY RM (DATE/INITIAL) (DATE/INITIALS)
TO RM (DATE/INITIAL)
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 5 Rev. 00 Page 2 of 8 JPM No. GG-I-JPM-SRO-A&E25 Task List No: SRO-A&E-015; SRO-A&E-041 K/A Reference and Importance Factors (RO/SRO):
K/A 2.4.41 - 4.1; 2.4.40 - 4.0; 2.4.30 - 3.6 10CFR55.45a(11)
Time Required for Completion: 15 Minutes (approximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Setting: Classroom X Plant X Simulator X SHOULD BE PERFORMED FOLLOWING SCENARIO 5 WITH SRO CANDIDATE EVALUATION Date Performed:
SSN: License: RO/SRO Performer:
Time to complete:
Score: PASS FAIL Date:
Evaluator Signature:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 5 Rev. 00 Page 3 of 8 JPM No. GG-l-JPM-SRO-A&E25 DISCUSSION of a Performance of this JPM will demonstrate the ability emergency events per Senior Reactor Operator to properly classify 10-S-01-1 and complete the required Emergency Plan Procedure Initial Notification Form. Performance can be performed in the provided candidate has simulator, plant or in a classroom setting access to Emergency Plan Procedures.
Required Material(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan 02 EPP 06-01, NOTIFICATION FORM General Reference(s):
01 EPP 10-S-01-1, Activation of the Emergency Plan Notification of Offsite Agencies and 02 EPP 10-S-01-6, Plant On-Call Personnel Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 5 JPM No. GG-l-JPM-SRO-A&E25 Rev. 00 Page 4 of 8 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, describe or state what indications you are observing and what indications you expect to see in response to your action.
When you have completed the task, inform me.
Task Standard(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 11.4 and the Initial Notification form is completed (See Attached).
Initial Condition(s): (The location for the initial conditions to be given is
- The plant was operating at 44% power. Thunder showers are reported in Tensas Parish. The 115 KV line is out of service due to required maintenance on ESF 12 Transformer. The CCW Pump C and RHR Pump C are red tagged for repairs. The event just observed has occurred.
Initiating Cue(s):
Determine the Emergency Action Level Classification, if any, and if required complete the required Initial Notification Form. Communicators are available if required.
Start Time:
- This location will be determined at pre-evaluation meeting by the evaluators involved.
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title EAL Classification: SCENARIO 5 JPM No. GG-l-JPM-SRO-A&E25 Rev. 00 Page 5 of 8 NOTE:Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
Item 1 (*) Consult EPP 10-S-01-1 "Activation of the Emergency Plan" and classifies a SITE AREA EMERGENCY.
Standard: Candidate consults EPP 10-S-01-1 "Activation of the Emergency Plan" EAL 11.4 and classifies a SITE AREA EMERGENCY based on scram conditions confirmed, and multiple control rods beyond position 02, and reactor power > 4% on APRMs.
Comments: EAL 11.4 is the overriding EAL in this case due to severity.
SAT UNSAT Item 2 (*) Complete the Initial Notification form EPP 06-01 for a SITE AREA EMERGENCY.
Standard: Candidate completes Initial Notification form EPP 06-01 with data marked with an * (See Attached).
Comments:
SAT UNSAT
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task Title : EAL Classification: SCENARIO 5 Rev. 00 Page 6 of 8 JPM No. GG-l-JPM-SRO-A&E25 TERMINATING CUE(s):
Emergency Plan is applied to classify the event as a SITE AREA EMERGENCY per EAL 11.4 and the Initial Notification form is completed (See Attached).
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET EAL Classification: SCENARIO 5 Task Title 2 5 Rev. 00 Page 7 of 8 JPM No. GG-l-JPM-SRO-A&E PERFORMANCE OF THE JPM TO ADDITIONAL QUESTION ASKED AFTER THE OF TASK PERFORMED:
CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING K/A Rating Question Expected Response Time Reference(s):
Reference(s) Required: Yes / No Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
The plant was operating at 44% power. Thunder Showers are reported in Tensas Parish. The 115 KV line is out of service The CCW due to required maintenance on ESF 12 Transformer.
repairs. The event Pump C and RHR Pump C are red tagged for just observed has occurred.
Initiating Cue(s):
if any, Determine the Emergency Action Level Classification, Notification and if required complete the required Initial Form. Communicators are available if required.
GRAND GULF Number: GG-1-JPM-SRO-ADM26 Revision: 00 NUCLEAR STATION Page: 1 of 9 Rtype:
- ENTERGY JOB PERFORMANCE MEASURE QA Record Number of pages Date Initials TITLE:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM REASON FOR REVISION: New JPM THIS DOCUMENT REPLACES N/A REVIEW / APPROVAL:
DATE:
PREPARED BY:
DATE:
APPROVED BY:
Facility Representative RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE DATE INITIAL CORRECTIONS (DATE/INITIAL) BY RN TRANSMITTED RECEIPT BY RM (DATE/INITIAL) (DATE/INITIALS)
TO RM (DATE/INITIAL)
JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM GG-l-JPM-SRO-ADM26 Rev. 00 Page 2 of 9 JPM No.
Task List No: SRO-ADMIN-038 K/A Reference and Importance Factors (RO/SRO):
K/A 2.1.12 4.0 Time Required for Completion: 15 Minutes (approximate).
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Performance: Simulat e X Actual X Plant X Simulator X Setting: Classroom EVALUATION Date Performed:
SSN: License: RO/SRO Performer:
Time to complete:
Score: PASS FAIL Date:
Evaluator Signature:
JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET AIR CONDITIONING Task
Title:
WRITE LCO FOR INOP CONTROL ROOM SYSTEM Rev. 00 Page 3 of 9 JPM No. GG-l-JPM-SRO-ADM26 DISCUSSION ability of a Senior Performance of this JPM will demonstrate the out an LCO form per Operations Reactor Operator to properly fill be simulated can Department Section Procedure 02-S-01-17. Performance setting provided candidate in the simulator, plant or in a classroom Specs.
has access to 02-S-01-17 and a set of Tech.
Required Material(s):
01 02-S-01-17, Control of Limiting Conditions for Operation 02 Technical Specifications General Reference(s):
01 02-S-01-17, Control of Limiting Conditions for Operation 02 Technical Specifications Safety Consideration(s):
01 None JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM JPM No. GG-l-JPM-SRO-ADM26 Rev. 00 Page 4 of 9 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, describe or state what indications you are observing and what indications you expect to see in response to your action. When you have completed the task, inform me.
Task Standard(s):
LCO form filled out properly for Tech. Spec. 3.7.4 action Condition A. required action 1.
Initial Condition(s): (The location for the initial conditions to be given is
- The plant was operating at 100 % power. The Unit I Control Room Air Conditioner has been declared inoperable due to a freon leak on the air conditioner evaporator. Unit II Control Room Air Conditioner is in operation. No other plant equipment is inoperable.
The CI number is xxxxxxl The WO number is xxxxxx2 Initiating Cue(s):
You are the Shift Supervisor. Complete the necessary LCO form for this condition.
Start Time:
- This location will be determined at pre-evaluation meeting by the evaluators involved.
JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM JPM No. GG-I-JPM-SRO-ADM26 Rev. 00 Page 5 of 9 NOTE:Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
Item 1 ( ) Obtain a controlled copy of 02-S-01-17, "Control of Limiting Conditions for Operation" Standard: Candidate obtains a controlled copy of 02-S-01-17.
Comments: This is an Information Use procedure and is NOT required to be obtained.
SAT UNSAT Item 2 (*) Fills in the blanks on the LCO form.
Standard: Candidate fills in all applicable blanks on the LCO form. See the attached LCO form for correct answer.
Blanks marked with ** are critical.
Comments: IF ASKED, CUE THE CANDIDATE PRESENT TIME IS WHEN IT WAS DECLARED INOP.
SAT UNSAT JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM Rev. 00 Page 6 of 9 JPM No. GG-l-JPM-SRO-ADM26 TERMINATING CUE(s):
out properly for Tech. Spec. 3.7.4 action LCO form filled Condition A. required action 1.
STOP TIME:
OVERALL COMMENTS:
JSADMIN26
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
WRITE LCO FOR INOP CONTROL ROOM AIR CONDITIONING SYSTEM GG-I-JPM-SRO-ADM26 Rev. 00 Page 7 of 9 JPM No.
TO CLARIFY ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE OF THE JPM THE TRAINEE' S ACTION OR UNDERSTANDING OF TASK PERFORMED:
K/A Rating Question Expected Response Time Reference(s) Required: Yes / No Reference(s):
Question:
Trainee's Response / Comments:
Correct Response:
JSADMIN26
THIS PAGE MAY BE GIVEN TO THE TRAINEE (The location for the initial conditions to be Initial Condition(s):
given is
- The plant was operating at 100 % power. The Unit I Control Room to a freon leak Air Conditioner has been declared inoperable due conditioner evaporator. Unit II Control Room Air on the air operation. No other plant equipment is Conditioner is in inoperable.
The CI number is xxxxxxl The WO number is xxxxxx2 Initiating Cue(s):
Complete the necessary LCO form You are the Shift Supervisor.
for this condition.
JSADMIN26
OPERATIONS SECTION PROCEDURE GRAND GULF NUCLEAR STATION 02-S-01-17 Revision: 102 Attachment I Page 1 of 3 LCO REPORT%W 10 LCO NO. XX-XXXX 4 MODE1 TIME PRESENT TIME %PWR 100 DATE 410312000 5 SYSTEM OR COMPONENT UNIT I CONTROL ROOM AIR CONDITIONING SYSTEM**
6 T.S. /TRM NO. 3.7.4** 7 CI/ WO NO. 98XXXXI/98XXXX2 OTHER DOCUMENT & NO. N/A 9 INITIATING CONDITION FREON LEAK ON THE AIR CONDITIONER EVAPORATOR**
10 CONDITION REQUIRED ACTION COMPLETION TIME A** A.1 RESTORE CONTROL ROOM AC SUBSYSTEM TO 30 DAYS" OPERABLE STATUS **
Al A1 4 13 3NAME OF DUTYMANAGER NOTIFI IF CO 7 DAYS NI1 IF OTHER DEPARTMENTREQUIREDTO COMPLETEACTION NAME/DEPARTMENTNOTIFIED.(COMPLETEATT II)
SLCO 3.0.6 ENTERED N/A 16LCO NO. EVALUATEDFOR LOSS OF SAFETY FUNCTION XXX 17 17 SHIFT SUPERVISOR CANDIDATE SIGNS HERE 18 SHIFT SUPERINTENDENT 19 SHIFT SUPERVISOR'S INITIAL INDICATES REQUIRED TESTING OR ACTIONS HAVE BEEN PERFORMED ON HIS SHIFT.
7 DAY 1 A 24 HR 72 HR DATE 00-08 08-16 14 15 1 2 3 4 5 6 7 8 9 10 11 12 13 16-24 30 DAY DATE 00-08 08-16 30 31 21 22 23 24 25 26 27 28 29 16-24 16 17 18 19 20 20 LCO RESTORED COMMENTS / CORRECTIVE ACTION DATE / TIME 22 SHIFT SUPERVISOR 23 SHIFT SUPERINTENDENT JSADMIN2 6
GRAND GULF Number: GG-1-JPM-SRO-ADM27 Revision: 00 NUCLEAR STATION Page: 1 of 8 Rtype:
ENTERGY JOB PERFORMANCE MEASURE QA Record Number of pages Date . Initials __
TRAINING PROGRAM:
TITLE:
REASON FOR REVISION: NEW JPM.
THIS DOCUMENT REPLACES N/A.
INITIAL RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE DATE RECEIPT BY RM CORRECTIONS (DATE/INITIAL) BY RM TRANSMITTED (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)
TO RM
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE Rev. 00 Page 2 of 8 JPM No. GG-i-JPM-SRO-ADM27 Task List No: SRO-M&S-014 K/A Reference and Importance Factors (RO/SRO):
K/A 2.2.12 - 3.4 30 Minutes *pproximate).
(F Time Required for Completion:
Time Critical: YES/NO Faulted JPM: YES/NO APPLICABLE METHOD OF TESTING Simulate Actual x Performance: _
Classroom Plant Simulator x _
Setting:
EVALUATION Date Performed:
SSN: License: RO/SRO Performer:
Time to complete:
Score: PASS FAIL Date:
Evaluator Signature:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE GG-1-JPM-SRO-ADM27 Rev. 00 Page 3 of 8 JPM No.
DISCUSSION demonstrate the review for Performance of this JPM will approval a completed surveillance.
Required Material(s):
01 06-OP-IE12-Q-0006, LPCI/RHR Subsystem B MOV Functional Test General Reference(s):
01 06-OP-IE12-Q-0006, LPCI/RHR Subsystem B MOV Functional Test 02 01-S-06-12, GGNS Surveillance Program Safety Consideration(s):
01 None
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE JPM No. GG-I-JPM-SRO-ADM27 Rev. 00 Page 4 of 8 READ TO TRAINEE I will explain the initial conditions, which step(s) to simulate or discuss, and provide the initiating cues. Prior to actually starting the performance of this JPM, I will answer any questions you have. For each step you perform, describe or state what indications you are observing and what indications you expect to see in response to your action.
When you have completed the task, inform me.
Task Standard(s):
Surveillance 06-OP-1E12-Q-0006 has been reviewed and the candidate denotes the discrepancies and identifies that surveillance cannot be satisfactory and that RHR B and one or more Primary Containment valves are INOP.
Initial Condition(s):
The plant is operating at 100 % power. An operator has just completed the performance of surveillance LPCI/RHR Subsystem B MOV Functional Test 06-OP-1E12-Q-0006 Attachment II.
Initiating Cue(s):
You are the Shift Supervisor. Perform the review and approval of the surveillance.
Start Time:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE Rev. 00 Page 5 of 8 JPM No. GG-1-JPM-SRO-ADM27 Sequence is assumed unless NOTE:Critical items denoted by (*).
denoted in the Comments.
Review the completed Attachment II of 06-OP-1E12 Item 1 (*)
Q-0006.
data Standard: Candidate reviews the completed Surveillance package noting the following information.
stroke time of 75.6 seconds is above Page 5 Item 5.2.3d(5) the Limiting Value, Maximum acceptable, and TRM Limit.
is above the Page 7 Item 5.2.4b stroke time of 11.6 seconds Limiting Value and Maximum acceptable.
5.2.8d stroke time of 121.5 seconds is above Page 12 Item the Limiting Value and Maximum acceptable.
stroke time of 63.1 seconds is above Page 22 Item 5.2.13e Value, Maximum acceptable, and TRM the Limiting Limit.
any of the The candidate should reviews the entire surveillance, and that various LCOs above will result in a failed surveillance These LCOs include applicable RHR System and must be entered.
Primary Containment Isolation Valves.
Candidate should indicate the failure of the Comments:
If surveillance with at least 3 of 4 items.
required, request the candidate to review all data on surveillance.
LCOs is NOT CRITICAL, recognition of RHR 'B' Identification of all being INOP IS CRITICAL. ,wm TThTCak'p OIWAo
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE Rev. 00 Page 6 of 8 JPM No. GG-I-JPM-SRO-ADM27 TERMINATING CUE(s):
and the Surveillance 06-OP-IE12-Q-0006 has been reviewed candidate denotes the discrepancies and identifies that B and one or surveillance cannot be satisfactory and that RHR more Primary Containment Valves are INOP.
STOP TIME:
OVERALL COMMENTS:
GRAND GULF NUCLEAR STATION JOB PERFORMANCE MEASURE WORKSHEET Task
Title:
REVIEW AND APPROVE COMPLETED SURVEILLANCE JPM No. GG-l-JPM-SRO-ADM27 Rev. 00 Page 7 of 8 THE JPM TO ADDITIONAL QUESTION ASKED AFTER THE PERFORMANCE OF CLARIFY THE TRAINEE'S ACTION OR UNDERSTANDING OF TASK PERFORMED:
Question K/A Rating Expected Response Time Reference(s) Required: Yes / No Reference(s):
Question:
Trainee's Response / Comments:
Correct Response:
THIS PAGE MAY BE GIVEN TO THE TRAINEE Initial Condition(s):
The plant is operating at 100 % power. An operator has just completed the performance of surveillance LPCI/RHR Subsystem B MOV Functional Test 06-OP-1E12-Q-0006 Attachment II.
Initiating Cue(s):
Perform the review and You are the Shift Supervisor.
approval of the surveillance.
Scenario Outline Form ES-D-1 Appendix D Facility: GRAND GULF NUCLEAR STATION Scenario No.: 1 Op-Test No.: Day 1 Examiners: Operators:
to the Obiectives: To evaluate the candidates' ability to operate the facility in response following evolutions:
- 1. Shift Recirculation Pumps to fast speed.
- 2. Raise Recirculation flow to 60 % core flow.
actions
- 3. Raise Reactor Power by withdrawing control rods, Perform operator for a stuck control rod per ONEP.
- 4. Analyze the impact of a failure of the reference leg of instruments connected to D004A and apply Technical Specifications.
- 5. Initiate a reactor scram based on rising Drywell Pressure.
- 6. Respond to a failure of Division 1 ECCS failure to initiate.
- 7. With a failure of Feedwater Line in the Turbine Building and reduced injection systems maintain reactor level per the EOPs.
an outage; Initial Conditions: Reactor Power is at 34 % bringing the plant up following in single element Reactor Recirculation pumps in Slow Speed; a single Reactor Feed Pump Master Level Control; INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
scattered thunder Turnover: Continue to bring the plant to full power per 101-2. There are showers reported in the Tensas Parish area.
Event Malf. No. Event Event No. Type* Description 1N (RO) Shift Reactor Recirculation Pumps to Fast Speed
-- (SOl 04-1-01-B33-1) 2 R (RO) Raise Total Core Flow to > 67.5 Mlbm/hr (101 03-1-01-2) 3 z022022_ C (RO, Withdraw control rods to increase power.
32_09 BOP) (Control Rod Pull Sheet)
Control Rod 32-09 is stuck, un-stick control rod per ONEP.
(ONEP 05-1-02-IV-1)
SCENARIO 1 PAGE 1 OF14
Appendix D Scenario Outline Form ES-D-1 Scenario 1 Day 1 (Continued)
Event Malf. No. Event Event No. Type* Description 4 rrl 88a I (RO, Respond to a failure of the reference leg of D004A level rrl88e BOP) instrument. (Tech Specs) rr063a @
0.5%
(ramp to 3% after scram) 5 initiate manual reactor scram in response to rising Drywell pressure. (05-1-02-1-1) 6 rr040a I (BOP) Failure of Division 1 ECCS to automatically initiate on High 0@0 Drywell Pressure 7 fw070a M Feedwater Line rupture in the Turbine Building with leakage
@100 (ALL) from the reactor 8 e22052 C HPCS pump trip on initiation (BOP) 9 e51044 C RCIC fails to achieve rated conditions for injection
@25 (BOP)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks Recognize failure of Division 1 to initiate and manually initiate Division 1 Lower reactor pressure to allow injection from low pressure systems SCENARIO 1 PAGE 2 OF14
Scenario 1 Day 1 (Continued)
Crew Turnover:
Rx at 34% CTP.
The plant is raising power following an outage. Reactor Recirculation Pumps are operating in Slow Speed. The 'A' Reactor Feed Pump is operating in Single Element Master Level Control.
Unit I Instrument Air Compressor is operating and Unit II Instrument Air Compressor is secured.
APRM 'F' is failed due to a failed power supply card and bypassed.
ESF 12 Transformer is tagged out of service for maintenance.
CCW Pump 'C' is tagged out of service for pump seal replacement.
RHR 'C' Pump is tagged out of service for motor oil replacement.
Appropriate clearances and LCOs are written.
Continue to bring the plant to full power per 101-2 step 5.11.
Startup Pull Sheet Step 117.
Fraction of Core Boiling Boundary is < 1.0.
There are scattered thunderstorms reported in the Tensas Parish area.
Simulator Setup:
Start the process from a new simulator load.
Reset to IC- 13.
Run BAT file setup 1 and verify or perform the following:
IC: 13 OOS: ESF Transformer 12 (Place tags on 152-1903. 1904, 1905, 1511, 1611, and 1704)
CCW C Pump (Place tag on start HS)
RHR C Pump (Place tag on start HS)
Active malfunctions: z022022_32_09 Control Rod 32-09 stuck rr04Oa @ 0 Drywell Pressure Transmitter B21-N094A e22052 HPCS Pump Trip on start e51044 @ 25 RCIC Turbine Speed Control Failure Active overrides p53038 on Unit I Inst Air Compressor operating p5303 9 _off Unit II Inst Air Compressor secured Pending overrides None SCENARIO 1 PAGE 3 OF14
Pending malfunctions: rr188a Upscale Failure D004A Narrow Range (TRG 1) rr188e Upscale Failure D004A Wide Range (TRG 1) rr063a @ 0.5% Recirc Loop A leak (TRG 1) ramp to 3%
after scram fw070a @ 100% Feedwater Rupture Turb Bldg (TRG 2) c11028a CRD A Pump Trip (TRG 3) c11028b CRD B Pump Trip (TRG 4)
Pending component malfunctions: None Trigger files: Trigger 1 D004A Instrument Failure Trigger 2 Feedwater Rupture in Turbine Building Trigger 3 CRD A pump trip after LSS sequence (will not restart after shed)
Trigger 4 CRD B will NOT be able to be started after LSS actuation.
(Triggers 3 and 4 are to simulate a common mode failure of LSS Sequencing.)
Place RHR C OOSVC handswitch to OOSVC.
Bypass Division 2 APRM Bypass Joystick to APRM F position.
Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place CCW pump B to STOP (to clear Standby light) then to START, stop CCW pump C.
Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.
Setup the presently used cyclops display and verify it is functional.
Ensure the correct startup sequence is available at the P680 for the present IC.
Install turnover guide, red tag, and LCO paperwork as applicable.
Advance all chart recorders and ensure all pens are inking properly.
(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)
SCENARIO 1 PAGE 4 OF14
SIMULATOR OPERATION of Freeze.
Once simulator is reinitialized and setup complete take the simulator out Once the Crew has taken control note the simulator time.
Crew will prepare to and shift Recirc Pumps to Fast Speed.
Cues:
flow is If asked, report as Auxiliary Building Operator - Recirc Pump Seal Purge 1.8 gpm on each pump.
34 %
If asked, report as Reactor Engineer - Core Thermal power is indicating
(- 1303 MWth).
control valves.
The Crew will raise Recirc Total Core Flow to - 67.5 Mlbm/hr using flow be placed After Recirc Pumps are in Fast Speed, the SS should request FCTR switches in NORMAL.
Remote Action page NEUTRON MONITOR C51309 to NORM C51310 to NORM Element The Crew should note Feedwater flow is not sufficient to transfer to Three Control.
rods If asked, as Reactor Engineer report sufficient margin to withdraw control in starting at step 117 to achieve 6.6 Mlbm/hr Feed flow. Withdrawal is allowed either gang or individual at SS and ACRO discretion.
note its The Crew when Control Rod 32-09 is attempted to be withdrawn will inability to move. After the second time to raise CRD Drive Water Pressure remove malfunction z022022 32 09.
Once CRD Drive Pressure is returned to normal activate TRIGGER 1.
On Scram, activate TRIGGER 2.
When Manual Scram inserted, Raise leak rr063a to 3%.
If required to cause Reactor level to begin to lower rr063a may be raised to 5%.
EP Attachments which may be requested:
Attachment 12 Defeat RHR Shutdown Cooling interlocks.
Attachment 26 Align Fire Water makeup to the Reactor (no simulator modeling)
Attachment 25 Align Condensate Transfer makeup to the Reactor (no simulator modeling)
SCENARIO I PAGE 5 OF14
If asked, report as Electrical Supervisor - HPCS Pump Breaker has Motor overcurrent lockout further investigation required.
If asked, report as I & C Supervisor - RCIC speed controller has failed.
Crew may request Circ Water Pump A cooling be transferred to pump discharge. Remote Function page Circulating Water N71195 to pump discharge.
TERMINATION Once Reactor Water Level is being restored using LPCS or LPCI and the Lead Evaluator concurs the scenario may be terminated.
Critical Tasks Recognize failure of Division 1 to initiate and manually initiate Division 1.
- Lower reactor pressure to allow injection from low pressure systems.
SCENARIO I PAGE 6 OF14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 1 -
Event
Description:
Shift Recirc Pumps A and B to Fast Speed. Then raise total Recirc flow to 67.5 Mlbm/hr. (04-1-01-B33-1)
Time [Position Applicant's Actions or Behavior SS Provides Reactivity brief to crew.
RO Verifies position on Power to Flow Map (Operating in Region Ill).
RO Closes Flow Control Valve in manual to - 6% valve position (Min valve position) for the first Recirc Pump.
BOP Raise Taps on 11 HD and 12HE Transformers to raise voltage on buses to 7.2 KV. (Candidate may elect to raise and lower taps for each pump start independently, this is acceptable.)
RO Start the first Recirc Pump in Fast Speed.
RO Closes Flow Control Valve in manual to - 6% valve position (Min valve position) for the second Recirc Pump.
RO Start the second Recirc Pump in Fast Speed.
BOP Lower Taps on 11 HD and 12HE Transformers to raise voltage on buses to 7.0 KV. (May be performed after each respective pump start.)
the BOP Monitor Power, Level, Pressure, and Turbine Loading during evolution.
I SCENARIO 1 PAGE 7 OF14
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 1 - Event No.: 2 Control.
Event
Description:
Raise Total Core Flow to 67.5 Mlbm/hr using Recirc Flow (This will raise Reactor Power from - 37% to -43% power and Total Core Flow from - 52 to - 67.5 Mlbm/hr.)
Time Position Applicant's Actions or Behavior RO Raise both Recirc Flow Control Valves positions to achieve 67.5 Mlbm/hr Total Recirc Flow. (The RO may elect to use both hands to adjust core flow by raising both Recirc Flow Control Valves at the same time to maintain the loops balanced. This is acceptable.)
BOP Monitors Pressure, Level, Power, and Turbine Loading.
RO & BOP Monitor operation on the Power to Flow Map.
SCENARIO 1 PAGE 8 OF14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 - Event No.: 3 Event
Description:
Withdraw control rods to increase power. (Control Rod Pull Sheet)
Control Rod 32-09 is stuck, un-stick control rod per ONEP. (ONEP 05-1-02-IV-1)
Time ] Position Applicant's Actions or Behavior SS Provides Reactivity brief to crew.
RO Verifies control rods and positions per Pull Sheet and selects control rods per next gang of control rods. ( May select Individual or Gang movement and may select any Control Rod in the Gang.)
BOP Act as Verifier for Control Rod movements.
RO Moves Control Rods from Position 04 to position 08. Once Control Rod 32-09 is attempted to be moved will recognize control rod is immovable.
SS Obtains CRD Malfunctions ONEP 05-1-02-IV-1 and verifies action per section 3.5, orders CRD Drive pressure raised -25 psid.
BOP Raises CRD Drive pressure - 25 psid using C11 -F003 Pressure Control Valve on H13-P601.
RO Attempts to move the Control Rod and reports no movement.
BOP Raises CRD Drive pressure -25 psid using C11 -F003 Pressure Control Valve on H13-P601.
and RO Attempts to move the Control Rod and reports movement positions Control Rod 32-09 at position 08.
SCENARIO 1 PAGE 90F14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 4 Event
Description:
Respond to a failure of the reference leg of D004A Reactor Level Instrument.
Time Position Applicant's Actions or Behavior RO Announces and acknowledges alarms on H13-P680.
- RPS scram (1/2 scram signal on RPS A)
- Main Turb/RFPT Level 8 trip (1 of 3; 2 of 3 required for trip)
- Level 8 Scram signal RO Observes Level Instruments and determines common indication of D004A failure on reference leg side.
BOP Observes Level Instruments on H13-P601 off the same condensing pot and determines upscale indication for confirmation.
RO Confirms with ARI actions correct and the Main Turbine and Reactor Feed Pumps should NOT have tripped and there should only be a /2 scram signal.
SS Verifies Technical Specifications.
See attached Attachment from 04-1 B21 -1 for LCOs associated with D004A.
(Based on Drywell Conditions the SS may require a followup question to cover this action.)
CREW Determines Drywell Pressure is rising and failure is most likely from an instrument line break. (May be a followup question.)
SCENARIO 1 PAGE 10 OF14
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 1 - Event No.: _5 Event
Description:
Manual scram the reactor based on rising Drywell Pressure.
Time I Position Position Applicant's Actions or Behavior Trim.--]
SS Based on rising Drywell Pressure due to the Instrument Line break, orders manual scram of the Reactor RO Places the Reactor Mode Switch to Shutdown or arms and depresses at least one Manual Scram Pushbutton per RPS Division (A & B).
RO Verifies All Control Rods have fully inserted to position 00 and reports to the SS "All Rods Inserted".
RO If the Manual Scram Pushbuttons utilized confirms stable reactor pressure and places the Reactor Mode Switch in Shutdown.
____ I _______
SCENARIO 1 PAGE II OF14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 - Event No.: _6 Event
Description:
Respond to a failure of Division 1 ECCS to automatically initiate on High Drywell Pressure.
Time (Position Applicant's Actions or Behavior BOP Observes Initiation of ECCS on High Drywell Pressure and
BOP Manually initiates Division 1 ECCS using the Division 1
- (LPCS/LPCI A Manual Initiation Pushbutton).
BOP Reports operation of Division 1 ECCS to the SS.
SS Enters Emergency Procedure 3 Containment Control.
SCENARIO 1 PAGE 12 OF14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 - Event No.: _7 Event
Description:
Feedwater Line Rupture in the Turbine Building with leakage from the Reactor.
Time Position Applicant's Actions or Behavior RO Announces loss of the ability to feed the Reactor and observes the following:
- Lowering Reactor Water Level
- Turbine Building Sump Level alarms
- Reactor Feed Pump Suction flow without Feed flow to Reactor SS Enters Emergency Procedure 2.
SS Determines systems for injection into the Reactor and prioritizes system use for injection into the reactor Reactor Core Isolation Cooling (RCIC)
High Pressure Core Spray (HPCS)
BOP Initiates RCIC either using the Manual Initiation Pushbutton or manual realignment.
Determines RCIC will NOT develop enough pressure to inject into the Reactor and reports failure to SS.
RO Secures the Condensate and Feedwater System after determination of unisolable rupture.
BOP Observes HPCS has tripped on initiation and reports failure to SS.
SS Orders injection from Control Rod Drive (CRD) system with maximized flow.
BOP Attempts to start CRD pumps A and B following LSS actuation and observes trip on both then reports failure to the SS.
SCENARIO 1 PAGE 13 OF14
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 1 Event No.: 8 Event
Description:
Respond to degraded high pressure injection systems and lowering Reactor level.
Time Position Applicant's Actions or Behavior SS Determine available high pressure injection systems and orders injection from Standby Liquid Control (SLC) from either the boron or test tank.
SS Determines Reactor level continuing to lower with CRD and SLC
- injection and orders reduction of Reactor pressure using either Main Steam Bypass Valves or Safety Relief Valves. Pressure reduction should be sufficient to allow injection with Low Pressure Core Spray (LPCS) or Low Pressure Coolant Injection (LPCI A or B). (LPCI may be through E12-F042 or E12-F053 with Attachment 12.)
RO Lowers Reactor pressure using the Main Steam Bypass Valves on
- the jack or lowering pressure set to the pressure band specified by the SS. (This action may be N/A if Safety Relief Valves are used.)
BOP Ifordered lowers RPV pressure using Safety Relief Valves to the
- band specified by the SS. (This action may be N/A if Main Steam Bypass Valves are used.)
SS Orders alignment of Systems for injection to the Reactor:
LPCS LPCI A or B (may order alignment of Fire Water (Att 26) and Condensate Transfer (Att 25))
BOP Aligns systems for injection to the vessel and when Reactor pressure allows injection informs the SS of injection and Reactor level recovery.
SCENARIO 1 PAGE 14 OF14
A *r.*rJtv r* *r,',n*ri* (3= =tlini= Form ES-D-1
/.lIA; n. Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 1 Op-Test No.: Day 1 Examiners: Operators:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Shift Recirculation Pumps to fast speed.
- 2. Raise Recirculationflow to 60 % core flow.
- 3. Raise Reactor Power by withdrawing control rods.
- 4. Perform operator actions for a stuck control rod per ONEP.
- 5. Analyze the impact of a failure of the reference leg of instruments connected to D004A and apply Technical Specifications.
- 6. Initiate a reactor scram based on rising Drywell Pressure.
- 7. Respond to a failure of Division 1 ECCS failure to initiate.
- 8. With a failure of Feedwater Line in the Turbine Building and reduced injection systems maintain reactor level per the EOPs.
Initial Conditions: Reactor Power is at 34 % bringing the plant up following an outage; Reactor Recirculation pumps in Slow Speed; a single Reactor Feed Pump in single element Master Level Control; INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Continue to bring the plant to full power per 101-2. There are scattered thunder showers reported in the Tensas Parish area.
C*r,*n*rin ('11 ItlinA Form ES-D-1
/Appendix U Q,-nnorin "flina Form ES-D-1 Scenario 1 Day 1 (Continued)
Event Event 10CFR55.45a K/A Event No. Type* __ ___
Description 202001 A4.01; A4.02; Shift Reactor Recirculation Pumps to Fast Speed (RO) 1,2,4, 202002 A4.0A4.04.08 (SOl 04-1-01 B33-1)
Raise Reactor Recirculation Flow with Flow Control Valves to 2 R (RO) 1, 2, 5, 6 202002 Al.08;A4.08 67.5 Mlbm/hr.
201005 A3.01; A3.02; Withdraw control rods to increase power.
C (RO, 1,2, 3, 5, 6 2010013; A4.014 (Control Rod Pull Sheet)
BOP) 2.2.2; 2.4.4; 2.4.11; Control Rod 32-09 is stuck, un-stick control rod per ONEP.
2.4.48 (ONEP 05-1-02-IV-1) 2.1.12; 2.4.45; 2.4.48 Respond to a failure of the reference leg of D004A level 4 I (RO, BOP) 3, AA2.02;1AA2.06 instrument. (Tech Specs) 2.4.4; 2.4.49 Initiate manual reactor scram in response to rising Drywell 5,6,12 295006 AA1.01; AA1.05; 5,,2AA1.07prsue(0--2-1 pressure. (05-1-02-I-i) 2.4.4 Failure of Division 1 ECCS to automatically initiate on High 6 I(BOP) 3,4,7,10 295024 EA1.0 Drywell Pressure 295031 EA1.0 Feedwater Line rupture in the Turbine Building with leakage M
7(ALL) 7, 13 203000 A3.08 241000 A4.06 from the reactor 295031 EA1.04 HPCS pump trip on initiation 8 C (BOP) 3 209002 A2.02 295031 EA1.05 9 C (BOP) 3 217000 A2.10; A3.02; RCIC fails to achieve rated conditions for injection A4.01
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, kv)ajor Critical Tasks
- Lower reactor pressure to allow injection from low pressure systems
- Recognize failure of Division 1 to initiate and manually initiate Division 1
I-' _*-.r,'*n*rin N= filing. Form ES-D-1 A-'pendix DM",""" ' . . ...
Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: Day 1 Examiners: Operators:
Obiectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Raise Reactor Power by withdrawing control rods.
- 2. Place 2 nd Reactor Feed Pump on Master Level Control.
- 3. Respond to a failure of APRM 'B' downscale and apply appropriate Technical Specifications.
- 4. Respond to the report of a leak on the Hydraulic Power Unit for Reactor Feed Pump 'B' to rise.
- 5. Respond to the above core plate pressure instrument line rupture which causes Drywell pressure
- 6. Respond to ATWS with a failure of the Main Steam Bypass valves to open per EOPs.
- 7. Respond to a failure of Standby Liquid Control to function.
pumps in Fast Speed; Initial Conditions: Reactor Power is at 42 % bringing the plant up following an outage; Reactor Recirculation a single Reactor Feed Pump in three element Master Level Control; INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
in the Tensas Parish Turnover: Continue to bring the plant to full power per 101-2. There are scattered thunder showers reported area.
h-nn*nrliY N .qnAn* tin *lJtlin* Form ES-D-1 A .inn fn. , , ... Fcrmri .
Scenario 2 Day 1 (Continued)
Event Event 10CFR55.45a K/A Event No. Type* Description 201005 A3.01; A3.02; 1 R (RO) 1, 2, 4, 5 A3.03; A4.01 Raise Reactor power using control rods to between 45 and 2.2.2 55%
(Control Rod Pull Sheet) 259001 A4.02 2 N (RO) 2, 4, 5, 6 259002 A3.09; A4.02; A4.03 Place Reactor Feed Pump 'B' in service on Master Level Control. (SOl 04-1-01-N21-1) 215005 A2.02 3 I (RO) 3,5 2.1.12; 2.1.33 Respond to a failure of APRM 'B' downscale and apply appropriate Technical Specifications.
295009 AA1.01 4 C (RO) 3, 4, 7 2.4.4; Respond to a leak on the Hydraulic Power Unit For RFPT 'B'.
2.4.46; 2.4.47; 2.4.48 5 I (RO, 3,4,5,6,13 295010 AA2.02; AA2.06 Respond to failure of the Above Core Plate Pressure Detector BOP) instrument line.
2.4.4; 2.4.49 6 2, 3, 4, 7 295006 AA1.01; AA1.05; Initiate manual reactor scram in response to rising Drywell AA1.07 pressure. (05-1-02-1-1) 295037 EA1.0; EA2.0 7 M (ALL) 6, 8, 12,13 203000 A3.08 ATWS 241000 A4.06 295007 AA1.04 8 C (RO) 3, 4 295025 EA1.03 Respond to failure of the Main Steam Bypass Valves to open.
239001 A2.06 241 000A2.03 295037 EA1.04; EAI.10 9 C (BOP) 3, 4 211000 A1.0; A2.04; A3.0 Respond to failure of Standby Liquid Control to inject into the I_ reactor.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Scenario 2 Day 1 (Continued)
Critical Tasks
- Inject Standby Liquid Control prior to Suppression Pool Temperature reaches 110 'F.
- Identify the need for Alternate Standby Liquid Control injection.
- Terminate and prevent injection from Feedwater and ECCS when conditions require entry into Level/Power Control.
- Commence injection into the reactor using Feedwater or RHR 'A' or 'B' through Shutdown Cooling when reactor level reaches
-192".
- Insert Control Rods in response to ATWS conditions.
Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: Day 1 Examiners: Operators:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Raise Reactor Power by withdrawing control rods.
- 2. Place 2 nd Reactor Feed Pump on Master Level Control.
- 3. Respond to a failure of APRM 'B' downscale and apply appropriate Technical Specifications.
- 4. Respond to the report of a leak on the Hydraulic Power Unit for Reactor Feed Pump 'B'
- 5. Respond to the above core plate pressure instrument line rupture which causes Drywell pressure to rise.
- 6. Respond to ATWS with a failure of the Main Steam Bypass valves to open per EOPs.
- 7. Respond to a failure of Standby Liquid Control to function.
Initial Conditions: Reactor Power is at 43 % bringing the plant up following an outage; Reactor Recirculation pumps in Fast Speed; a single Reactor Feed Pump in three element Master Level Control; INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Continue to bring the plant to full power per 101-2. There are scattered thunder showers reported in the Tensas Parish area.
Event Malf. No. Event Event No. Type* Description 1 R (RO) Raise Reactor power using control rods to between 45 and
_ 55% (Control Rod Pull Sheet) 2 N (RO) Place Reactor Feed Pump 'B' in service on Master Level Control. (S01 04-1-01-N21-1) 3 c5l01Ob I (RO) Respond to a failure of APRM 'B' downscale and apply I_ _ _ appropriate _Technical Specifications.
SCENARIO 2 PAGE 1 OF 13
Appendix D Scenario Outline Form ES-D-1 Scenario 2 Day 1 (Continued)
Event Malf. No. Event Event No. Type* Description 4 fw1 23b C (RO) Respond to a leak on the Hydraulic Power Unit For RFPT p680 113P.
2AC1 0 HPU Alarm light 5 rr062 I (RO, Respond to failure of the Above Core Plate Pressure BOP) Detector instrument line.
6 Initiate manual reactor) scram in response to rising Drywell pressure. (05-1-02-1-1 7 cl11164 @ M ATWS
- 25% (ALL) 8 tc082a C (RO) Respond to failure of the Main Steam Bypass Valves to tc082b open.
tc082c all @ 0 9 c41263 @ C Respond to failure of Standby Liquid Control to inject into IL_ 80% (BOP) the reactor.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks
- Inject Standby Liquid Control prior to Suppression Pool Temperature reaching 110 OF.
- Identify the need for Alternate Standby Liquid Control injection.
- Terminate and prevent injection from Feedwater and ECCS when conditions require entry into Level/Power Control.
- Commence injection into the reactor using Feedwater or RHR 'A' or 'B' through Shutdown Cooling when reactor level reaches -192".
- Insert Control Rods in response to ATWS conditions.
SCENARIO 2 PAGE 2 OF 13
Scenario 2 Day 1 (Continued)
Crew Turnover:
Rx at 43% CTP.
Pumps are operating in The plant is raising power following an outage. Reactor Recirculation Master Level Control.
Fast Speed. The 'A' Reactor Feed Pump is operating in Single Element APRM 'F' is failed due to a failed power supply card and bypassed.
ESF 12 Transformer is tagged out of service for maintenance.
CCW Pump 'C' is tagged out of service for pump seal replacement.
RHR 'C' Pump is tagged out of service for motor oil replacement.
Appropriate clearances and LCOs are written.
Continue to bring the plant to full power per 101-2 step 5.13.
Startup Pull Sheet Step 117.
area.
There are scattered thunderstorms reported in the Tensas Parish Simulator Setup:
Start the process from a new simulator load.
Reset to IC-13.
Run BAT file setup 1 and verify or perform the following:
IC: 13 OOS: ESF Transformer 12 (Place tags on 152-1903. 1904, 1905, 1511, 1611, and 1704)
CCW C Pump (Place tag on start HS)
RHR C Pump (Place tag on start HS)
Active malfunctions: tc082a @ 0 Main Steam Bypass A failure closed tc082b @ 0 Main Steam Bypass B failure closed tc082c @ 0 Main Steam Bypass C failure closed c41263 @ 80% SLC injection pipe rupture c1116 4 @ 25% SDV Hydraulic Block Active overrides FCTR Cards to NORM C51309 & C51310 Pending overrides RFPT Gov Trouble ann P680 2A-C10 (TRG 2)
Pending malfunctions: c51010b APRM B downscale (TRG 1) fw123b RFPT overspeed trip (TRG 3) rr062 Above Core Plate Pressure Inst Line fail (TRG 4)
None Pending component malfunctions:
SCENARIO 2 PAGE 3 OF 13
Trigger files: Trigger 1 APRM B failed downscale Trigger 2 Reactor Feed Pump HPU Failure Trigger 3 Reactor Feed Pump Trip Trigger 4 Above Core Plate Instrument Failure Place RHR C OOSVC handswitch to OOSVC.
Bypass Division 2 APRM Bypass Joystick to APRM F position.
Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 stop CCW pump C.
Place CCW pump B to STOP (to clear Standby light) then to START, raise Recirc total flow to Shift Recirc Pumps to Fast Speed return Transformer taps to normal, 67.5 Mlbm/hr.
Raise Turbine Load Demand to 25 MWe above actual load.
of SPDS.
Startup all PDS / SPDS screens. Clear any graphs and trends off Setup the presently used cyclops display and verify it is functional.
present IC.
Ensure the correct startup sequence is available at the P680 for the Install turnover guide, red tag, and LCO paperwork as applicable.
Advance all chart recorders and ensure all pens are inking properly.
SCENARIO 2 PAGE 4 OF 13
SIMULATOR OPERATION Scenario 2 the simulator out of Freeze.
Once simulator is reinitialized and setup complete take time.
Once the Crew has taken control note the simulator Master Level Control.
Crew will review procedures for placing Feedwater on Cues:
be raised by If asked, report as Reactor Engineer - Core Thermal may transfer Master Level withdrawing control rods to attain sufficient Feed flow to Control.
rods per the Control Rod If asked, report as Reactor Engineer - withdraw control be in gang or Pull Sheet beginning at step 117. Withdrawal of rods may individual mode.
Control and the second As the crew places the Reactor Feed Pump on Three Element Reactor Feed Pump is service.
crew informs outside As the crew asks for local operations and respond as the areas.
1.
One (1) Minute after the RFPT is in service, activate TRIGGER to the Control Room and When APRM 'B' fails downscale and I&C is notified respond further troubleshooting will verify to the SS that APRM 'B' is failed downscale and that be required.
Turbine Building Eight (8) Minutes after Trigger 1 is activated, Report as the barrier from RFPT 'B' Operator that hydraulic fluid is spraying on the plexiglass Hydraulic Power Unit.
One (1) Minute after report is made, activate TRIGGER 2.
the common If asked about isolability of the leak, report the leak is on discharge of the main pumps.
3.
Five (5) Minutes after report of leak, activate TRIGGER 4.
Two (2) Minutes after RFPT is tripped, activate TRIGGER SCENARIO 2 PAGE 5 OF 13
when requested.
After the ATWS is detected, perform the following attachments Attachment 18 3 minutes to DONE Attachment 19 4 minutes to DONE Attachment 20 5 minutes to DONE Attachment 12 6 minutes to DONE Attachment 8 9 minutes to DONE acknowledge the request. 8 can not be by any remote functions just Termination Evaluator concurs the scenario Once Control Rods are being inserted and the Lead may be terminated.
Critical Tasks reaching 110 OF.
- Inject Standby Liquid Control prior to Suppression Pool Temperature
- Identify the need for Alternate Standby Liquid Control injection.
require
- Terminate and prevent injection from Feedwater and ECCS when conditions entry into Level/Power Control.
through
- Commence injection into the reactor using Feedwater or RHR 'A' or 'B' Shutdown Cooling when reactor level reaches -192".
- Insert Control Rods in response to ATWS conditions.
SCENARIO 2 PAGE 6 OF 13
Appendix D Operator Actions Form ES-D-2 Op-Test No.: __ Scenario No.: 2 Event No.: 1 Event
Description:
Raise Reactor power using Control Rods from 43 % to 45 %
(Control Rod Pull Sheet)
Time Position Applicant's Actions or Behavior SS Conduct reactivity manipulation brief.
RO Withdraws control rods in individual or gang per control rod pull sheet to raise power to 45 %.
BOP Assists RO in Control Rod selection verification, monitors Pressure, Level, Power, and Turbine Loading.
SCENARIO 2 PAGE 7 OF 13
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 2 Event No.: 2 Event
Description:
Place Reactor Feed Pump 'B' (RFPT) in service on Master Level Control. (SOl 04-1-01-N21-1)
[Time 1 Position Applicant's Actions or Behavior RO Closes N21 -F047B RFPT B Discharge Valve.
RO Raise RFPT speed and transfer through Speed Auto, Feedwater Auto, raises RFPT Discharge pressure to within 50 psig above operating RFPT pressure.
BOP Monitors Pressure, Level, Power, and Turbine Loading.
RO Slowly opens N21 -F047B and monitors flow and brings RFPT B onto Master Level Control in Automatic.
SCENARIO 2 PAGE 8 OF 13
Appendix D Operator Actions Form ES-D-2 Op-Test No.: __ Scenario No.: 2 Event No.: 3 Event
Description:
Respond to a failure of APRM 'B' Downscale.
Time Position Applicant's Actions or Behavior RO Determines APRM 'B' is Downscale and reviews Alarm Response Instructions.
SS Reviews applicable Technical Specifications 3.3.1 Reactor Protection System 3.3.2 Control Rod Block Instrumentation BOP Observe and report indications on APRM 'B'.
SS Contact I&C to investigate.
SCENARIO 2 PAGE 9 OF 13
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 4 Event
Description:
Respond to leak on Hydraulic Power Unit (HPU) for RFPT 'B'.
Time Position Applicant's Actions or Behavior RO Reports alarms on RFPT 'B'.
SS Acts on the report of leak of hydraulic fluid on HPU to order the shutdown of RFPT 'B' by either tripping the RFPT or securing it rapidly. (Either method is acceptable.)
RO Shuts down RFPT 'B' by the method ordered by the SS. If the RFPT is tripped responds to the Recirc FCV Runback if received.
BOP Monitors Pressure, Level, Power, and Turbine Loading.
I I SCENARIO 2 PAGE 10 OF 13
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.:_ 5 Event
Description:
Respond to a failure of the Above Core Plate Pressure tap.
Time Position Applicant's Actions or Behavior RO Reports and acknowledges alarms caused by the Instrument failure and reports indications to the SS.
BOP Reports indications and actions caused by the Instrument failure and reports indications to the SS.
CREW Reports indication of rising Drywell pressure. (May require followup questions to identify what instrument has failed.)
SS Orders a manual Scram of the Reactor due to Drywell pressure rising.
RO Places the Reactor Mode Switch to Shutdown or arms and depresses at least one Manual Scram Pushbutton per RPS Division (A & B).
RO If the Manual Scram Pushbuttons utilized confirms stable reactor pressure and places the Reactor Mode Switch in Shutdown.
SCENARIO 2 PAGE 11 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 2 Event No.: 6 Event
Description:
ATWS Time Position I Applicant's Actions or Behavior RO Reports ALL Control Rods NOT fully inserted.
RO Reports downshift of Recirc Pumps to Slow Speed.
RO On orders initiates ARI/RPT.
BOP On orders initiates and overrides HPCS.
BOP Verifies initiation of Division 1 and 2 LSS and initiation of Load Shedding & Sequencing, Diesel starts, isolations, and Standby Gas operation.
BOP On orders overrides Low Pressure ECCS.
RO Realigns Condensate and Feedwater on Startup Level Control and maintains reactor level within level band specified by the SS.
RO When ordered by SS, attempts to set Pressure Control and identifies failure of Main Steam Bypass Valves to open, may attempt to open valves using the Jack.
SCENARIO 2 PAGE 12 OF 13
BOP When ordered by SS, maintains pressure band using SRVs.
SS Orders Standby Liquid Control initiated prior to Suppression Pool
- Temperature reaching 110 IF.
BOP When ordered by SS, initiates Standby Liquid Control and identifies
- the failure of SLC to inject.
SS Orders implementation of Attachment 28 for alternate Boron
- injection.
BOP When ordered by SS, restores Auxiliary Building, Containment, and Drywell isolation (Instrument Air, Plant Service Water, Drywell Chilled Water)
SS Orders installation of Attachments 18, 19, and 20 of EP-2.
SS Based on conditions, orders Terminate and Prevent step to lower
- RPV Level to reduce power.
BOP/RO Terminates and prevents systems ordered by SS.
RO On orders of SS, initiates flow to the RPV from Condensate /
BOP/RO Insert Control Rods by scramming rods and inserting rods using
A ..... ..J:.. Form ES-D-1 Appendix Q 0 %,V"CAI%J Uflinn Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 3 Op-Test No.: Day 2 Examiners: Operators:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Place Standby Service Water 'B' in operation for retest following repairs.
- 2. Lower Reactor Power using Reactor Recirculation Flow Control.
- 3. Respond to a trip of the Standby Service Water Pump 'B' and apply Technical Specifications.
- 4. Respond to a failure of the Main GeneratorHydrogen Temperature Controller.
- 5. Respond to a steam leak in the Auxiliary Building Steam Tunnel that will not completely isolate.
- 6. Respond to ATWS (no challenge to Containment).
- 7. Respond to plant parameters per EOP-4 Secondary Containment Control.
Initial Conditions: Reactor Power is at 100 %
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Start Standby Service Water 'B' for a retest of ESF Room Cooler T46-BOO2B-B following cleaning. There are scattered thunder showers reported in the Tensas Parish area.
A .,.,,*nHiv I'* .*r.*_n* rin (-}Htlinp. Form ES-D-1
/JZU,,AilIUIA Scenario Ou.tline; Form ES Scenario 3 Day 2 (Continued)
Event Event 10CFR55.45a K/A Event No. Type* Description 1 N (BOP) 4, 5, 6 2.1.30 Place Standby Service Water Pump 'B' in operation for retest following repairs. (SOl 04-1-01-P41-1) 202001 A4.04 2 R (RO) 2, 4, 5, 6 202002 A4.08 Lower Reactor power using Recirculation Flow Control by 150 MWe 2.2.2 3 C (BOP) 3, 4 2.4.48; 2.1.12 Respond to a trip of Standby Service Water Pump 'B' and apply Technical Specifications.
245000 A3.09; A4.11 4 I (RO) 3, 4, 5 2.1.30; 2.4.10 Respond to a failure of the Main GeneratorHydrogen Temperature Controller.
2.4.46; 2.4.47; 2.4.48; 5 M (ALL) 3,4,6,13 2.4.49 Respond to steam leak in the Auxiliary Building Steam tunnel 290001 A2.06; A4.04 (unisolable - failure of MSIVs to completely isolate).
295032 EA1.02; EA1.05 2.4.4; 2.4.49 2,3,4, 6295006 AA1.01; AA1.05; AA1.07 Initiate manual reactor scram due to Steam Leak in the Auxiliary Building. (05-1-02-1-1) 7 C (RO) 4, 6, 12,13 295037 EA1.0; EA2.0 ATWS (three control rods stuck full out) 8 C (BOP) 3, 4,7 259001 A2.04 Respond to loss of Feedwater with a failure HPCS 217000 A1.01;A2.10 (HPCS Pump will trip on start attempt).
I _Respond to RCIC Flow TransmitterFailure.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks Isolate the main steam lines Manually scram the reactor
Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 3 Op-Test No.: Day 2 Examiners: Operators:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 2. Place Standby Service Water 'B' in operation for retest following repairs.
- 1. Lower Reactor Power using Reactor Recirculation Flow Control.
- 4. Respond to a trip of the Standby Service Water Pump 'B' and apply Technical Specifications.
- 3. Respond to a failure of the Main GeneratorHydrogen Temperature Controller.
- 5. Respond to a steam leak in the Auxiliary Building Steam Tunnel which will not completely isolate.
- 6. Respond to ATWS (no challenge to Containment).
- 7. Respond to plant parameters per EOP-4 Secondary Containment Control.
Initial Conditions: Reactor Power is at 100 %
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Start Standby Service Water 'B' for a retest of ESF Room Cooler T46-BOO2B-B "followingcleaning. There are scattered thundershowers reported in the Tensas Parish area.
Event Malf. No. Event Event No. Type* Description 1 N Place Standby Service Water Pump 'B' in operation for (BOP) retest following repairs.(SOI 04-1 P41-1i) 2 R (RO) Lower Reactor power using Recirculation Flow Control by 150 MWe C Respond to a trip of Standby Service W ater Pum p Sp41148b
'B' and S(BOP) apply Technical Specifications.
4 N41107 I (RO) Respond to a failure of the Main GeneratorHydrogen
@0% Temperature Regulator.
SCENARIO 3 PAGE 1 OF 12
Appendix D Scenario Outline Form ES-D-1 Scenario 3 Day 2 (Continued)
Event Malf. No. Event Event No. Type* Description 5 epatt09 M Respond to steam leak in the Auxiliary Building Steam msl83b (ALL) tunnel (unisolable -failure of MSIVs to completely isolate).
ms184b ms066b
@0.2%
6 ms067b Initiate manual reactor scram due to Steam Leak in the
@20% Auxiliary Building. (05-1-02-1-1) 7 z022022 C (RO) ATWS (three control rods stuck full out) 08 29 12 09 20 61 8 e22052 C Respond to loss of Feedwater with a failure HPCS e51045 (BOP) (HPCS Pump will trip on start attempt).
I_Respond to RCIC Flow TransmitterFailure.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, ki)ajor Critical Tasks Manually scram the reactor Isolate the main steam lines SCENARIO 3 PAGE 2 OF 12
Scenario 3 Day 2 (Continued)
Crew Turnover:
Rx at 100% CTP.
ESF Room Cooler T46-BO02B-B has been cleaned and engineering requires operation of Standby Service Water 'B' to check flow balancing.
APRM 'F' is failed due to a failed power supply card and bypassed.
ESF 12 Transformer is tagged out of service for maintenance.
CCW Pump 'C' is tagged out of service for pump seal replacement.
RHR 'C' Pump is tagged out of service for motor oil replacement.
Appropriate clearances and LCOs are written.
There are scattered thunderstorms reported in the Tensas Parish area.
Simulator Setup:
Start the process from a new simulator load.
Reset to IC- 15.
Run BAT file setup 1 and verify or perform the following:
IC: 15 OOS: ESF Transformer 12 (Place tags on 152-1903. 1904, 1905, 1511, 1611, and 1704)
CCW C Pump (Place tag on start HS)
RHR C Pump (Place tag on start HS)
Active malfunctions: z022022_08_29 Control Rod 08-29 stuck z022022 12_09 Control Rod 12-09 stuck z022022_20_61 Control Rod 29-61 stuck ms183b as-is MSIV B21-F022B failed OPEN ms184b as-is MSIV B2 1-F028B failed OPEN e22052 HPCS Pump trip on start e51045 RCIC Flow Transmitter failure Active overrides epatt09 EP Attachment 9 Defeat MSIV and drains isolations Pending overrides RFPT Gov Trouble ann P680 2A-C 10 (TRG 2)
SCENARIO 3 PAGE 3 OF 12
Pending malfunctions: p41148b SSW Pump B trip (TRG 1) n41107@ 0% Main Generator Hydrogen Temperature Controller Failure (control valve closed) (TRG 2) ms066b@0.2% Main Steam Line B in Aux Bldg Tunnel (TRG 3) ramp to 20% over 2 minutes ms067b@20% Main Steam Line B rupture ramp to 40%
over 5 minutes (TRG 4)
Pending component malfunctions:
Trigger files: TRIGGER 1 SSW 'B' Pump Trip TRIGGER 2 Gen Hydrogen Temperature Controller Fail TRIGGER 3 Main Steam Line 'B' Leak TRIGGER 4 Main Steam Line 'B' Rupture in Stm Tunnel Place RHR C OOSVC handswitch to OOSVC.
Bypass Division 2 APRM Bypass Joystick to APRM F position.
Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place CCW pump B to STOP (to clear Standby light) then to START, stop CCW pump C.
Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.
Setup the presently used cyclops display and verify it is functional.
Ensure the correct shutdown sequence is available at the P680 for the present IC.
Install turnover guide, red tag, and LCO paperwork as applicable.
Advance all chart recorders and ensure all pens are inking properly.
SCENARIO 3 PAGE 4 OF 12
SIMULATOR OPERATION Scenario 3 Once simulator is reinitialized and setup complete take the simulator out of Freeze.
Once the Crew has taken control note the simulator time.
BOP operator will startup Standby Service Water 'B'.
After SSW 'B' is operating, Contact the SS as the System Dispatcher request the unit be reduced in power by 150 MWe to allow a fossil plant to be brought up in power for a test following repairs.
As soon as power is reduced, activate TRIGGER 1 and 2.
Trigger 1 is the SSW 'B' trip for the BOP operator.
Trigger 2 is the Hydrogen Temperature Controller failure for the RO.
SSW Failure If dispatched place Division 2 Diesel Generator in Maintenance, Remote Function Action P75 ESF PWR Dist. Div I & II, P75058_MAINT.
If dispatched to 16AB, report the SSW 'B' Pump Breaker on 16AB has an Overcurrent Trip.
If dispatched to the SSW pump, report a strange odor around the SSW Pump.
Generator Hydrogen Temperature Controller Failure If dispatched, report Temperature Control Valve is indicating closed locally.
If asked to open the Bypass Valve P43-F042, report the valve is open partially.
Two (2) Minutes after the Hydrogen Temperature Controller alarms are received, activate TRIGGER 3.
When Crew initiates Manual scram, activate TRIGGER 4.
Two (2) Minutes after Reactor Scram, report as Security white smoke or steam is coming out of the top of the Auxiliary Building.
If contacted, report as Health Physics there are NO abnormal radiation surveys of the Auxiliary Building.
If contacted, report as Chemistry there are NO verified leaking fuel bundles in the reactor.
TERMINATION Once reactor pressure has lowered to < 600 psig and a system is aligned for RPV level control and the Lead Evaluator concurs the scenario may be terminated.
SCENARIO 3 PAGE 5 OF 12
Critical Tasks Manually scram the reactor
- Isolate the main steam lines SCENARIO 3 PAGE 6 OF 12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Event
Description:
Place Standby Service Water 'B' in operation for retest following repairs. (SOl 04-1-01-P41-1)
Time Position Applicant's Actions or Behavior BOP Place SSW 'B' MOV Test Switch in TEST.
BOP Start SSW 'B' Cooling Tower Fans (Optional per SS.)
BOP Align SSW 'B' system per SOL.
BOP Place SSW 'B' MOV Test Switch in NORM.
SCENARIO 3 PAGE 7 OF 12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 3 Event No.: 2 Event
Description:
Lower Reactor Power using Recirculation Flow Control by 150 MWe.
Time Position Applicant's Actions or Behavior SS Conducts Reactivity Briefing.
RO Using Recirc Flow Control, slowly closes the Recirc Flow Control Valves monitoring Reactor Power, Recirc Flow, and Reactor Level.
BOP Monitors Pressure, Reactor Power, and Turbine Loading.
SCENARIO 3 PAGE 8 OF 12
Actions flnrntnr Actions Form L-U-2 my4tJ,[IUIA Lj NnAr*tnr Form ES-D-2 Op-Test No.: Scenario No.: 3- Event No.: 3 Event
Description:
Respond to a trip of Standby Service Water Pump 'B' and apply Technical Specifications.
Time Position Applicant's Actions or Behavior BOP Determines the SSW 'B' Pump has tripped and reviews Alarm Resonse Instruction (H1i3-P870-7A-A1).
BOP or SS Dispatches building operator to investigate SSW 'B' locally and the circuit breaker on 16AB.
BOP or SS Dispatches building operator to place Division 2 Diesel Generator in Maintenance.
BOP Coordinates with building operator to place Div 2 Diesel in Maintenance.
SS Reviews Technical Specifications and identifies LCO 3.7.1 and TR 3.7.1 SCENARIO 3 PAGE 9 OF 12
(3np.ratnr Actions 1-orm b&U-Form ES-D Appendix DAppedix (~erator Actions Op-Test No.: _ Scenario No.: 3 Event No.: 4 Event
Description:
Respond to a failure of the Main Generator Hydrogen Temperature Regulator (Valve fails closed - Hydrogen Temperature rises)
Time Position Applicant's Actions or Behavior RO Determines the Main Generator Hydrogen Temperature Regulator has failed and reviews Alarm Resonse Instruction (H13-P680-7A-A1).
RO Attempts to place Controller in manual and open valve.
Determines no response from the valve.
RO or SS Dispatches building operator to determine the status of the Temperature Control Valve.
SS Order Reactor Power reduction to reduce Generator Load.
RO Reduces Reactor Power using Recirc Flow Control. May adjust Generator Load Demand.
SS May order Reactive Load reduction on the Main Generator.
RO If ordered, reduce the Reactive Load on the Main Generator by adjusting field excitation with the Voltage Regulator.
SCENARIO 3 PAGE 10 OF 12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 3 Event No.: 5 Event
Description:
Respond to a Main Steam Line 'B' failure in the Auxiliary Building Steam Tunnel.
Time Position Applicant's Actions or Behavior BOP Responds to Main Steam Tunnel Differential Temperature High alarm and checks back panel indication on Riley Temperature indicators and reviews Alarm Response Instruction (H1 3-P601-19A-F3 and E3 when received).
RO Checks Steam Tunnel Temperature indications on PDS Computer.
SS Orders manual scram of the reactor on Steam Leak.
RO Places the Reactor Mode Switch to Shutdown or arms and
- depresses at least one Manual Scram Pushbutton per RPS RO Verifies All Control Rods have fully inserted to position 00 and reports to the SS "All Rods Inserted". Identifies three (3) Control Rods have NOT fully inserted.
RO If the Manual Scram Pushbuttons utilized confirms stable reactor pressure and places the Reactor Mode Switch in Shutdown.
BOP Upon receipt of MSL Pipe Tunnel Temperature High alarms,
SCENARIO 3 PAGE II OF 12
SS Dispatches BOP operator to check for other Secondary Containment Alarms on temperature, sump levels and radiation.
BOP Reports Main Steam Tunnel Temperature Alarms are the only EP-4 entry conditions. (may report temperature above 250 OF SS If BOP operator has NOT already performed action on his own, should order B21-F098A, B, C, D closed.
BOP Closes B21 -F098A, B, C, D motor operated Main Steam Isolation Valves.
SS May elect to lower reactor pressure by opening SRVs.
BOP If ordered, open SRVs to lower Reactor Pressure.
BOP If ordered, starts High Pressure Core Spray, recognizes failure of HPCS pump breaker.
BOP If ordered, starts Reactor Core Isolation Cooling, recognizes failure of Flow Transmitter.
BOP or RO If ordered, maximizes Control Rod Drive Flow.
RO Aligns Condensate System for feeding the Reactor on Startup Level Control.
SS May elect to inject Standby Liquid Control. (This is acceptable based on withdrawn control rods and reduced high pressure injection.)
SS Orders Attachments 18, 19, and 20 installed to insert remaining three control rods. (may elect to wait and send personnel to attempt local scrams of rods per Attachment 22.)
BOP & RO Monitor and control Reactor Pressure and Temperature as directed.
SCENARIO 3 PAGE 12 OF 12
Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 4 Op-Test No.: BACK UP 1 Examiners: Operators:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Raise power 5% with Recirc flow.
- 2. Startup one loop of Suppression Pool Cooling.
- 3. Implement Technical Specifications for LPCI inoperability of an RHR loop When it is running in suppression pool cooling.
- 5. Respond to a Seal Steam Controller failure.
- 6. Execute the EOPs for a Feedwater line break in the Drywell with check Valve leakage and degraded ECCS systems that requires emergency Depressurization on low reactor water level.
Initial Conditions: Rx at 9501o CTP, power ascension in progress, Suppression pool temperature is somewhat elevated due to weeping SRV's.
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Continue to bring the plant to full power per 101-2. Place RHR 'B' in Suppression Pool Cooling. There are scatteredthunder showers reported in the Tensas Parish area.
Event Malf. Event Event No. No. Type* Description 1 N Startup RHR 'B' in Suppression Pool Cooling (SRO must (BOP) declare LPCI 'B' Inop. (SOI 04-1-01-E12-1) (Tech Specs) 2 R (RO) Raise Reactor power at least 5% using Recirc Flow Control.
3 rr012b C (RO) Respond to Recirc Pump 'B' trip.
I I_(ONEP 05-1-02-111-3)
SCENARIO 4 PAGE 1 OF 12
Appendix D Scenario Outline Form ES-D-1 Scenario 4 BACK UP 1 (Continued)
Event Malf. No. Event Event No. Type* Description 4 MS094 I (RO) Respond to a failure of the Seal Steam Controller.
(Alarm Response Instructions) fw171b Feedwater line "B" break in Drywell with check valve M leakage 5 b2lf065bi (ALL) - RO performs scram actions, attempts to isolate affected Feedwater line (valve will fail to close).
rr063a% - BOP recognizes that RCIC is unavailable (injects to affected Feedwater line) rr04Oe @ 0 I Failure of Division 1 ECCS to initiate 6 rr041e @ (BOP) 83%
7 e22052 C HPCS pump trip on initiation (BOP) 8 e12050b C RHR B Pump trip (BOP) 9 e21186a C LPCS Injection Valve failure to open (BOP)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks Open at least five SRVs when RPV level drops to - 192 inches.
Manually initiate RHR A to restore RPV level above -167". Pump must be running before RPV pressure drops to 100 psig.
If RPV Flooding is required, injects with RHR A to attempt to restore RPV pressure 57 psig above containment pressure.
SCENARIO 4 PAGE 2 OF 12
Scenario 4 BACKUP (Continued)
Crew Turnover:
Rx at 95% CTP.
SRV have been weeping. Place Suppression Pool 'B' cooling in service.
APRM 'F' is failed due to a failed power supply card and bypassed.
ESF 12 Transformer is tagged out of service for maintenance.
CCW Pump 'C' is tagged out of service for pump seal replacement.
RHR 'C' Pump is tagged out of service for motor oil replacement.
Appropriate clearances and LCOs are written.
area.
There are scattered thunderstorms reported in the Tensas Parish Simulator Setup:
Start the process from a new simulator load.
Reset to IC-15.
Run BAT file setup 1 and verify or perform the following:
IC: 15 OOS: ESF Transformer 12 (Place tags on 152-1903. 1904, 1905, 1511, 1611, and 1704)
CCW C Pump (Place tag on start HS)
RHR C Pump (Place tag on start HS) e2205 2 HPCS Pump trip on start Active malfunctions:
e21186a LPCS Injection Valve failure to open rr04Oe @ 0 Failure of Division 1 Drywell Pressure B21-N094E b21f065b_I Failure of B21-F065B to close Active overrides None Pending overrides rr012b Recirc Pump B trip (TRG 1)
Pending malfunctions:
ms094 Seal Steam Controller Failure (TRG 2) fw171b@ 100% Feedwater B Line Rupture in Drywell (TRG 3) rr063a @ 20% Feedwater check valve leakage (Recirc Line Rupture) (TRG 3) rr041e @ 83% Reactor Level Transmitter B21-N091E (TRG 3) e12050b RHR B Pump trip (TRG 4)
SCENARIO 4 PAGE 3 OF 12
Pending component malfunctions: None Trigger files: TRIGGER 1 Recirculation Pump 'B' Trip TRIGGER 2 Seal Steam Controller Failure TRIGGER 3 Feedwater rupture in Drywell TRIGGER 4 RHR 'B' Pump Trip Place RHR C OOSVC handswitch to OOSVC.
Bypass Division 2 APRM Bypass Joystick to APRM F position.
Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place CCW pump B to STOP (to clear Standby light) then to START, stop CCW pump C.
Lower power to 95% power and reduce Turbine Load Demand accordingly.
Place Standby Service Water 'B' in service per section 4.3 of 04-1-01 -P41-1.
Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.
Setup the presently used cyclops display and verify it is functional.
Ensure the correct startup sequence is available at the P680 for the present IC.
Install turnover guide, red tag, and LCO paperwork as applicable.
Advance all chart recorders and ensure all pens are inking properly.
SCENARIO 4 PAGE 4 OF 12
SIMULATOR OPERATION Once simulator is reinitialized and setup complete take the simulator out of Freeze.
Once the Crew has taken control note the simulator time.
Pool BOP Operator will prepare to and place RHR 'B' in service for Suppression Cooling.
Cues:
If asked, report as Auxiliary Building Operator - RHR 'B' Pump is ready for operation.
If asked, report as Outside Operator - Standby Service Water 'B' is operating supporting a chemical addition.
to full As RHR 'B' pump is started, CUE the SS as System Dispatcher to return power power operation as soon as practical.
If asked, report as Reactor Engineer - the Core is preconditioned for 100 %
power operation. No ramp rate restrictions exist.
NOTE: 100 % power is essential prior to the Recirc Pump trip to prevent entering the Scram Required Region of the Power to Flow Map.
When reactor power reaches 100 %, activate TRIGGER 1.
If dispatched, report as Turbine Building Operator - Recirc Pump 'B' CB-5 (252 1205) has an overcurrent trip.
If dispatched, report as Electrical Supervisor - Recirc Pump 'B' has an overcurrent trip and you will require breaker 252-1205 be racked out such that further troubleshooting may take place.
Six (6) Minutes after the Recirc Pump trip, activate TRIGGER 2.
If requested respond as I&C Supervisor - the controller has a problem that will require more invasive troubleshooting, you will generate a Cl.
Four (4) Minutes after the Seal Steam Controller Failure, activate TRIGGER 3.
When Division 2 LSS actuates and sheds buses, activate TRIGGER 4 to simulate a failure of the LSS sequencing for the RHR 'B' pump.
SCENARIO 4 PAGE 5 OF 12
The SS may request Attachment 12 of EP-2 be installed. (Action Page EP Attachments DONE with a 3 minute time delay.)
Note: RCIC is unavailable because it injects into the 'B' Feedwater Line.
TERMINATION Once Reactor Water Level is being restored using RHR 'A' and the Lead Evaluator concurs the scenario may be terminated.
Critical Tasks Open at least five SRVs when RPV level drops to -192 inches.
Manually initiate RHR A to restore RPV level above -167". Pump must be running before RPV pressure drops to 100 psig.
- If RPV Flooding is required, injects with RHR A to attempt to restore RPV pressure 57 psig above containment pressure.
SCENARIO 4 PAGE 6 OF 12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: - Scenario No.: 4 Event No.: 1 Event
Description:
Start Residual Heat Removal Pump 'B' in Suppression Pool Cooling (SO 04-1-01-El 2-1)
Time Position Applicant's Actions or Behavior BOP Verifies operation of Standby Service Water 'B' through the RHR
'B' Heat Exchangers.
BOP Starts RHR 'B' and aligns system for Suppression Pool Cooling.
SS Reviews and applies Tech Specs for RHR 'B' being aligned for Suppression Pool Cooling.
____ I_______ ________________________________
SCENARIO 4 PAGE 7 OF 12
Form ES-D-2 Appendix D Operator Actions Form ES-D-2 Op-Test No.: - Scenario No.: 4 Event No.: 2 Event
Description:
Raise Reactor power by 5% using Reactor Recirculation Flow Control Time Position Applicant's Actions or Behavior SS Conducts shift Reactivity brief.
RO Using both Recirc Flow Control Valves raises total core flow while monitoring Reactor water level and Reactor power.
BOP Monitors Reactor power and pressure, and monitors and adjusts Main Turbine Load Demand as Reactor power rises.
SCENARIO 4 PAGE 8OF12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: - Scenario No.: 4 Event No.: 3 Event
Description:
Respond to Reactor Recirculation Pump 'B' trip.
Time [Position Applicant's Actions or Behavior RO Respond to annunciators concerning Recirc Pump 'B' trip, and performs immediate actions of "Decrease in Recirculation System Flow Rate" ONEP 05-1-02-111-3.
Closes B33-F067B Monitors for Thermal Hydraulic Instability Monitors position on Power to Flow Map and region of operation RO Verifies Recirc Loop 'A' flow is < 44,600 gpm.
BOP Monitors Thermal Hydraulic Instability and reaction of Reactor Power.
SS Verifies actions per ONEP are completed, dispatches personnel to investigate the trip.
RO Based on operating region on the Power to Flow Map and determine subsequent actions to be taken per the ONEP.
SS Consults with Reactor Engineer/STA on actions to be taken with regard to insertion of control rods or raising Recirc Loop 'A' flow.
RO Inserts Control Rods per Control Rod Pull Sheet, as directed by the SS.
SCENARIO 4 PAGE 9 OF 12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 4 Event No.: 4 Event
Description:
Respond to failure of Seal Steam Controller for the Main Turbine.
Time Position Applicant's Actions or Behavior RO Observes and communicates annunciators concerning Seal Steam Controller failure and refers to Alarm Response Instruction.
RO Takes manual control of the Seal Steam Controller and adjusts Seal Steam pressure per the Alarm Response Instructions.
BOP Monitors Reactor power, pressure, and level.
SS Contacts I & C for troubleshooting and repairs. May elect to dispatch an operator to the Seal Steam Generator Room to check the Seal Steam Regulating Valve operation.
____ ________ I _____________________________________
SCENARIO 4 PAGE 10OF12
Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 4 Event No.: 5 Event
Description:
Feedwater Rupture in the Drywell with leakage past check valves from the Reactor Time Position Applicant's Actions or Behavior RO Recognizes scram on High Drywell Pressure/Low Reactor Water level and performs the immediate actions for Reactor Scram.
Reports all rods fully inserted and places the Reactor Mode Switch to SHUTDOWN.
RO Recognizes loss of ability to feed the reactor with Condensate and Feedwater. Communicates the loss to the SS.
SS Enters EP-2 and EP-3, orders the BOP Operator to initiate HPCS, RCIC and inhibit ADS.
BOP Recognizes the failure of Division 1 to initiate and manually initiates Division 1 ECCS.
BOP Verifies/initiates HPCS (recognizes trip of HPCS pump)
BOP or RO Recognizes the trip of RHR 'B' pump BOP or RO Verifies/initiates RCIC (If RO/SS determine which Feedwater Line is ruptured prevents operation of RCIC - pumps into line with break.)
SS Orders CRD maximized and possible initiation of SLC.
SS Dispatches EP Attachments to be installed Attachment 12 RHR through Shutdown Cooling Attachment 25 Condensate Transfer injection Attachment 26 Fire Water injection SCENARIO 4 PAGE llOF12
SS Dispatches Operators, electricians to investigate problems with HPCS and RHR 'B' SS Orders alignment of RHR 'A' and LPCS for injection to the Reactor.
- (RHR "A" should be ordered to be aligned with the pump running and injection valve open if possible.)
BOP or RO Align RHR 'A' and LPCS for injection (based on Reactor pressure
- failure of the LPCS Injection valve may become apparent)
SS Orders depressurization of the Reactor with either SRVs or Main Steam Bypass Valves to a pressure which will allow injection from RHR and LPCS.
SS If Reactor Level drops below - 192 inches, orders Emergency
BOP or RO On orders, opens 8 SRVs using handswitches (initiation
SCENARIO 4 PAGE 12 OF 12
Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 4 Op-Test No.: BACK UP 1 Examiners: Operators:
Obiectives: To evaluate the candidates' ability to operate the facility in response to the following evolutions:
- 1. Raise power 5% with Recirc flow.
- 2. Startup one loop of Suppression Pool Cooling.
- 3. Implement Technical Specifications for LPCI inoperability of an RHR loop When it is running in suppression pool cooling.
- 5. Respond to a Seal Steam Controller failure.
- 6. Execute the EOPs for a Feedwater line break in the Drywell with check valve leakage and degraded ECCS systems that requires Emergency Depressurization on low reactor water level.
Initial Conditions: Rx at 95/o/ CTP, power ascension in progress, Suppression pool temperature is somewhat elevated due to weeping SRV's.
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement Appropriate clearances and LCOs are written.
Turnover: Continue to bring the plant to full power per 101-2. Place RHR 'B' in Suppression Pool Cooling. There are thunderstorms reported in the Tensas Parish area.
Scenario Outline Form ES-D-1 Appendix D Scenario 4 BACK UP 1 (Continued) r r T 1 11=
Event Event Malf. No. Event 10CFR55.45a K/A No. Description Type*
No... __
N A4.01; A4.02; A4.07 Startup RHR 'B' in Suppression Pool Cooling (SRO must 1 t(hPnp 4,8 declare LPCI 'B' Inop. (SOI 04-1-01-E12-1) (Tech Specs)
(130P) 202002 A4.08 Raise Reactor power at least 5% using Recirc Flow Control.
2 R 1,2,4,5,6 2.2.2
(_ )L-I 202001 A2.03 Respond to Recirc Pump 'B' trip ONEP.
3 RRO12B C 3,4,5,6 40NEP 05-1-02-111-3)
I ~ i~
3,4,5,6,4 L'(ROit MS094 I (RO) 2.1.30 Respond to a failure of the Seal Steam Controller.
4 3,4,8 (Alarm Response Instructions)
I FW171B L I __
295031 EA1.0 295031 EA1.0 Feedwater line "B" break in Drywell with check valve leakage 203000 A3.08 5 3,4,5,6,7, 241000 A4.06 - RO performs scram actions, attempts to isolate affected M 13 B21F065BI Feedwater line (valve will fail to close).
(ALL)
RR063A .02 - BOP recognizes that RCIC is unavailable 2.4.4 295024 EA1.0 6 3,4,5,7 Failure of Division 1 ECCS to initiate RR040E 0 RR041E 1 (BOP) 4- *l. 295031 EA1.04 i 209002 A2.02 HPCS pump trip on initiation 7 E22052 C 3,5 (RPop (BOP)/
C 203000 A2.02 8 E12050B 3,5 RHR B Pump trip (BOP) /
203000 A2.03 9 C 3,5 LPCS Injection Valve failure to open (BP ICopoet HM~O "k
(N)ormal, (R)eactivity, (I)nstrument, (Copoet (M.#ajor
Appendix D Scenario Outline Form ES-D-1 Scenario 4 BACK UP 1 (Continued)
Critical Tasks Open at least five SRVs when RPV level drops to -192 inches.
Manually initiate RHR A to restore RPV level above -167". Pump must be running before RPV pressure drops to 100 psig.
- If RPV Flooding is required, injects with RHR A to attempt to restore RPV pressure 57 psig above containment pressure.
Scenario Outline Form ES-D-1 Appendix D 5 Op-Test No.: BACK UP 2 Facility: GRAND GULF NUCLEAR STATION Scenario No.:
Examiners: Operators:
to the Obeetives: To evaluate the candidates' ability to operate the facility in response following evolutions:
- 1. Reduce power with Recirc flow
- 2. Respond to a Feedwater flow element failure that causes a feed pump trip.
- 3. Implement the AOP (ONEP) for a Feed Pump trip that places the plant in the increased operator awareness region (Region 4).
- 4. Reduce power by inserting control rods.
- 5. Respond to overcurrent trip of a load center that causes entry into several LCO's
- 6. Execute the EOPs to respond to a feedwater line break in the Turbine Building with failure to scram that requires emergency depressurization on low reactor water level.
Initial Conditions: Rx at 100% CTP, earthquake just occurred.
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement RCIC tagged due to steam leak on turbine casing Appropriate clearances and LCOs are written.
Turnover: Commence controlled plant shutdown (no apparent earthquake damage). There Cul 'J,-*t,'r,-rl thi inrhlr .howers reported in the Tensas Parish area.
Event Malf. Event Event No. No. Type* Description N (RO) Discernible power reduction with recirc flow.
2 FTN21N I (RO) Respond to RFPT trip due to flow instrument failure 088BB (minimum flow element for 'B' RFP) p6804 al_b_1 SCENARIO 5 PAGE 1 OF 13
Scenario Outline Form ES-D-1 Appendix D Scenario 5 BACK UP 2 (Continued)
Event Event Event Malf. No. Description No. Type*
3 Power reduction of >5% using control rods R (RO) 4 R21142S C ESF Load Center 15BA2 Trip (BOP) 5 M Feedwater line break in turbine building FW070A (ALL) 6 C11164 @ M ATWS qn"oI^ (ALL'*
I I ~(ALL)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks
- Insert control rods by scramming and/or driving.
- Inject SLC when suppression pool temperature cannot be maintained below 110F.
- Terminate and prevent injection from Condensate / Feedwater, RHR A, RHR B, RHR C, and LPCS when RPV level cannot be maintained above -192".
- Open at least five SRVs when when RPV level cannot be maintained above -192".
- When reactor pressure drops to MARFP, restore injection from RHR A through E12
-192".
F053A, or RHR B through E12-F053B, and restore RPV level above SCENARIO 5 PAGE 2 OF 13
Scenario 5 BACKUP (Continued)
Crew Turnover:
Rx at 100% CTP.
An earthquake occurred on the New Madrid Fault. No plant monitors indicated any problems.
The duty manager has decided to perform a normal plant shutdown for inspections.
APRM 'F' is failed due to a failed power supply card and bypassed.
ESF 12 Transformer is tagged out of service for maintenance.
CCW Pump 'C' is tagged out of service for pump seal replacement.
RHR 'C' Pump is tagged out of service for motor oil replacement.
Appropriate clearances and LCOs are written.
There are scattered thunderstorms reported in the Tensas Parish area.
Simulator Setup:
Start the process from a new simulator load.
Reset to IC- 15.
Run BAT file setup 1 and verify or perform the following:
IC: 15 OOS: ESF Transformer 12 (Place tags on 152-1903. 1904, 1905, 1511, 1611, and 1704)
CCW C Pump (Place tag on start HS)
RHR C Pump (Place tag on start HS)
Active malfunctions: c11164 @ 30% SDV Hydraulic Block Active overrides None Pending overrides p680_4alb_1 H22 P171 INFI 90 Trouble (TRG 1)
Pending malfunctions: ftn2lnO88b b Minimum Flow Element failure RFP B (TRG 1) r21142s ESF LCC 15BA2 trip (TRG 2) fw070a @ 100% Feedwater Line A rupture in Turbine Building (TRG 3)
Pending component malfunctions: None Trigger files: TRIGGER 1 Feedwater Minimum Flow Element failure TRIGGER 2 Loss of LCC 15BA2 TRIGGER 3 Feedwater Rupture in Turbine Building.
SCENARIO 5 PAGE 3 OF 13
Place RHR C OOSVC handswitch to OOSVC.
Bypass Division 2 APRM Bypass Joystick to APRM F position.
Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place CCW pump B to STOP (to clear Standby light) then to START, stop CCW pump C.
Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.
Setup the presently used cyclops display and verify it is functional.
Ensure the correct startup sequence is available at the P680 for the present IC.
Install turnover guide, red tag, and LCO paperwork as applicable.
Advance all chart recorders and ensure all pens are inking properly.
SCENARIO 5 PAGE 4 OF 13
SIMULATOR OPERATION Scenario 2 Once simulator is reinitialized and setup complete take the simulator out of Freeze.
Once the Crew has taken control note the simulator time.
Crew will review procedures for power reduction.
Shift Supervisor will notify the following of the plant shutdown:
Chemistry System Dispatcher Health Physics Radwaste Shift Technical Advisor/Reactor Engineering Respond that you understand the plant is shutting down.
If asked, respond as Reactor Engineer to begin at step 1 of the Shutdown Sequence Pull Sheet when core flow is 67.5 Mlbm/hr.
When dispatched to open N35-FO15A & B on the Turbine Deck, respond as Turbine Building Operator N35-F035A & B are open. (There are no console actions for this.)
Crew will begin power reduction. When Lead Evaluator or reactor power is < 97 %
power (whichever comes first), activate TRIGGER 1.
If dispatched to H22-P171, report Turbine Building Operator the Minimum Flow Controller for RFPT 'B' is in automatic and the N21-F503B is indicating full open.
The RFPT 'B' will trip resulting in a Recirc Flow Control Valve Runback, Power to Flow should still be in a region to allow continued operation. The Crew should reset the Runback and adjust core flow to allow continued plant shutdown.
If asked, respond as Reactor Engineer to insert control rods to move reactor power out of any undesired regions. Stress to the crew control rods need to be inserted prior to any Condensate or Feedwater evolutions.
After first two gangs of Control Rods are fully inserted and power has dropped by 5 % or Lead Evaluator cue, activate TRIGGER 2.
Loss of LCC 15BA2 - See attached Load List from 04-1-01-R21-15 for 15BA2, 15B21 and 15P21.
If dispatched, report as Auxiliary Building Operator the feeder breaker for LCC 15BA2 has an overcurrent trip and will NOT reset.
SCENARIO 5 PAGE 5 OF 13
If dispatched, report as Electrical Supervisor that a spare breaker should be racked out and tested and the trip setpoints adjusted to replace the LCC Feeder Breaker.
Ten (10) Minutes after loss of LCC 15BA2 or on Lead Evaluator cue, activate TRIGGER 3 Condensate and Feedwater are lost.
Standby Liquid Control Pump 'A' is lost.
After the ATWS is detected, perform the following attachments when requested.
Attachment 18 3 minutes to DONE Attachment 19 4 minutes to DONE Attachment 20 5 minutes to DONE Attachment 12 6 minutes to DONE Attachment 8 9 minutes to DONE 8 can not be by any remote functions just acknowledge the request.
Termination Once Control Rods are being inserted and the Lead Evaluator concurs the scenario may be terminated.
Critical Tasks
- Insert control rods by scramming and/or driving.
- Inject SLC when suppression pool temperature cannot be maintained below 110°F.
- Terminate and prevent injection from Condensate / Feedwater, RHR A, RHR B, RHR C, and LPCS when RPV level cannot be maintained above -192".
- Open at least five SRVs when when RPV level cannot be maintained above 192".
- When reactor pressure drops to MARFP, restore injection from RHR A through E12-F053A, or RHR B through E12-F053B, and restore RPV level above -192".
SCENARIO 5 PAGE 6 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 5 Event No.: 1 Control Event
Description:
Reduce Reactor power using Recirculation Flow Time Position Applicant's Actions or Behavior
.1.
Time Conduct reactivity manipulation brief.
SS RO Reduces Total Core Flow by throttling closed on the Recirc Flow Control Valves.
BOP Monitors Pressure, Level, Power, and Turbine Loading.
SCENARIO 5 PAGE 7 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: _5 Event No.: _2 Flow Valve Event
Description:
Respond to the Reactor Feed Pump Turbine 'B' Minimum Failure and trip.
Time Position Applicant's Actions or Behavior RO Recognizes opening of RFPT Min Flow Valve and subsequent trip of RFPT 'B'; observes the Recirc Flow Control Valve Runback due to the loss of RFPT and Low Reactor Water Level and Recirc Pumps in Fast Speed.
RO Plots Total Core Flow and Reactor Power on the Power to Flow Map to determine core stability.
BOP Monitors Pressure, Level, Power, and the core for Thermal Hydraulic Instability.
SS Verifies actions per "Decrease in Recirculation System Flow Rate ONEP 05-1-02-111-3.
SS Consults with Reactor Engineer on actions to be taken raise Core Flow or insert Control Rods to attain a more stable configuration.
RO Ifdirected, resets Recirc Flow Control Valve Runback.
SCENARIO 5 PAGE 8 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 5 Event No.: _3 Event
Description:
Reduce Reactor power using by inserting Control Rods (Control Rod Shutdown Sequence Pull Sheet)
Time Position Applicant's Actions or Behavior SS Conduct reactivity manipulation brief. (optional)
RO Inserts control rods in individual or gang per control rod pull sheet to lower reactor power.
BOP Assists RO in Control Rod selection verification, monitors Pressure, Level, Power, and Turbine Loading.
SCENARIO 5 PAGE 9 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: _ Scenario No.: 5 Event No.: 4 Event
Description:
Respond to loss of Load Control Center 15BA2 Time Position Applicant's Actions or Behavior BOP Determines and reports that LCC 15BA2 has tripped.
SS Dispatches an operator and electricians to investigate loss of 15BA2.
SS Obtains SO 04-1-01-R21-15 for load list for LCC 15BA2 and directs operators to review panels to determine equipment lost.
BOP Obtains Alarm Response Instruction for LCC 15BA2.
SS Reviews Technical Specifications for Equipment lost.
(multiple Tech Specs See attached load list)
SCENARIO 5 PAGE 10 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: Scenario No.: 5_ Event No.: 5_
Event
Description:
Feedwater Break in the Turbine Building Time Position Applicant's Actions or Behavior RO Responds to annunciators and Reactor Scram and loss of Reactor Level.
Reports rupture of Feedwater in the Turbine Building and is RO unisolable.
Trips running Condensate, Condensate Booster, Reactor Feed and RO Heater Drain Pumps.
SCENARIO 5 PAGE 11 OF 13
Operator Actions Form ES-D-2 Appendix D Op-Test No.: _ Scenario No.: 5__ Event No.: __
Event
Description:
ATWS Time Position Applicant's Actions or Behavior RO Reports ALL Control Rods NOT fully inserted.
Places Reactor Mode Switch in SHUDOWN.
RO Reports downshift of Recirc Pumps to Slow Speed.
RO On orders initiates ARI/RPT.
BOP On orders initiates and overrides HPCS.
BOP Initiates RCIC for level control if it has not initiated automatically.
BOP or RO Maximizes CRD Flow to the Reactor.
SCENARIO 5 PAGE 12 OF 13
When ordered by SS, attempts to set Pressure Control to close any RO cycling SRVs.
BOP When ordered by SS, maintains pressure band using SRVs.
SS Orders injection of Standby Liquid Control prior to 110 OF Suppression Pool Temperature.
BOP When ordered by SS, initiates Standby Liquid Control and identifies the failure of SLC to inject.
SS Orders implementation of Attachment 28 for alternate Boron injection.
BOP When ordered by SS, restores Auxiliary Building, Containment, and Drywell isolation (Instrument Air, Plant Service Water, Drywell Chilled Water)
SS Orders installation of Attachments 12, 18, 19, and 20 of EP-2.
SS Based on conditions, orders Terminate and Prevent step to lower RPV Level to reduce power/ preparation for Emergency Depressurization.
BOP/RO Terminates and prevents systems ordered by SS.
SS Orders Emergency Depressurization by opening 8 ADS Valves.
BOP or RO Opens 8 ADS SRVs using handswitches (may manually initiate ADS with pushbuttons and follow with handswitches, this is acceptable.)
RO On orders of SS, initiates flow to the RPV from RHR 'A' and /or 'B' through Shutdown Cooling if possible.
BOP/RO Insert Control Rods by scramming rods and inserting rods using CRD/RCIS. CRD Drive Pressure, Instrument Air to Containment and Auxiliary Building, RPS reset I___________j_________________
SCENARIO 5 PAGE 13 OF 13
A*n*nHiv I"1 Scenario outline Form ES-D-1 rA , ,,nrfivfl Se r OtnFm..
Facility: GRAND GULF NUCLEAR STATION Scenario No.: 5 Op-Test No.: BACK UP 2 Examiners: Operators:
evolutions:
Objectives: To evaluate the candidates' ability to operate the facility in response to the following
- 1. Reduce power with Recirc flow
- 2. Respond to a Feedwater flow element failure that causes a feed pump trip.
exit required region of the
- 3. Implement the AOP (ONEP) for a Feed Pump trip that places the plant in the immediate power-flow map.
- 4. Reduce power by inserting control rods.
- 5. Respond to overcurrent trip of a load center that causes entry into several LCO's to scram that requires
- 6. Execute the EOPs to respond to a feedwater line break in the Turbine Building with failure emergency depressurization on low reactor water level.
Initial Conditions: Rx at 100% CTP, earthquake just occurred.
INOPERABLE Equipment APRM 'F' is INOP due to a failed power supply card ESF 12 Transformer is tagged out of service for maintenance CCW Pump 'C' is tagged out of service for pump seal replacement RHR 'C' Pump is tagged out of service for motor oil replacement RCIC tagged due to steam leak on turbine casing Appropriate clearances and LCOs are written.
scattered thunder showers reported Turnover: Commence controlled plant shutdown (no apparent earthquake damage). There are in the Tensas Parish area.
A * *,,* *,,',((v £*.p.na rio Outline Form ES-D-1 MP ILII UA;A ni-~ Scenario OutlineForm....D Scenario 5 BACK UP 2 (Continued)
Event Event 10CFR55.45a K/A Event No. Type* Description 202001 A4.04 1 N (RO) 2, 4, 5, 6 202002 A4.08 2.2.2 Discernible power reduction with recirc flow.
259001 A3.10 Respond to RFPT trip due to flow instrument failure (minimum flow 2 I (RO) 3, 4, 5, 6, 7 295001 AA1.01; element for 'B' RFP)
AA1.05; AA2.01 201005 A3.01; A3.02; 3 R (RO) 2, 4, 5, 6 A3.03; A4.01 2.2.2 Power reduction of >5% using control rods 295003 AK2.04; 4 C (BOP) 3, 4, 8,13 AA1.01 2.1.31; 2.4.10; 2.4.48 ESF Load Center 15BA2 Trip 295031 EA1.0 5 M (ALL) 7, 13 203000 A3.08 241000 A4.06 Feedwater line break in turbine building 295037 EA1.0; EA2.0 6 M (ALL) 6,8, 12,13 203000 A3.08 241000 A4.06 ATWS
- (N)ormal, (R)eactivity, (I)nstrument, (u)omponeni, kvI)ajor Critical Tasks
- Insert control rods by scramming and/or driving. 0
- Inject SLC when suppression pool temperature cannot be maintained below 1 10 F.
- Terminate and prevent injection from Condensate / Feedwater, RHR A, RHR B, RHR C, and LPCS when RPV level cannot be maintained above -192".
- Open at least five SRVs when RPV level cannot be maintained above -192".
- When reactor pressure drops to MARFP, restore injection from RHR A through El 2-F053A, or RHR B through El 2-F053B, and restore RPV level above -192".