IR 05000324/2001301
| ML012300006 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/19/2001 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| -nr, -RFPFR | |
| Download: ML012300006 (166) | |
Text
FINAL SUBMITTAL BRUNSWICK EXAM 50-325 & 50-324 JULY 27-AUGUST 3,2001 FINAL AS-GIVEN JPMs FOR EACH WALK-THROUGH TEST I )yvns 'fd1
ES-301 Administrative Topics Outline Form ES-301-1 Facility: BRUNSWICK Date of Examination:7130-813101 Examination Level (circle one): RQ / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions GEN Evaluate Overtime Eligibility 2.1.3(3.0/3.4)
GEN 2.1.34 Evaluate Off-site Power Source Operability per the CO DSR (2.3/2.9) GEN 2.2.30 Evaluate SRM / IRM Overlap (3.5/3.3) /A4.05 Estimate Source Term for a Release from the Main Stack per (2.3 / 3.7)
PEP-03. GEN 2.4.30 NRC Reporting Requirements - Large Break LOCA (2.2/3.6)
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: A. Task Title: Evaluate Overtime Eligibilit Job Performance Measure No:
K/A Reference: GEN 2.1.3 (3.0/3.4) Knowledge of shift turnover practices Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator Control Room Plant Applicant Performance:
SAT/UNSAT Required Materials:
General References:
None 0AP-001, Rev 9 Modified LOT-QJT-JP-201-CO1 Time Critical Task: YES/NO Validation Time: 10 Mi Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outag INITIATING CUE:
Using the information in the schedule table, determine whether overtime guidelines have been violated; listing the violations (if any). Consider each case separately.
Operator # 1 Operator #2 Monday 0700-1900 0800- 2000 Came in late, stayed to make-up time Tuesday 0700-1900 0300-1900 (called in)
Wednesday 0700-2100 0700-1900 (held over; relief called in sick)
Thursday 1900-0700 0700-1900 (called in on off day)
Friday 1900-0100 OFF (went home sick)
Saturday 1900-0700 0700-1900 Sunday 1900-0700 0700-1900 A.1.a
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outag INITIATING CUE:
Using the information in the schedule table, determine whether overtime guidelines have been violated; listing the violations (if any). Consider each case separately.
Operator# 1 Operator #2 Monday 0700-1900 0800- 2000 Came in late, stayed to make-up time Tuesday 0700-1900 0300-1900 (called in)
Wednesday 0700-2100 0700-1900 (held over; relief called in sick)
Thursday 1900-0700 0700-1900 (called in on off day)
Friday 1900-0100 OFF (went home sick)
Saturday 1900-0700 0700-1900 Sunday 1900-0700 0700-1900
TASK STANDARD:
Step Description Standard I
SAT/UNSAT
Obtain a current Current Revision of OAP-001 revision of OAP-001 obtained
Evaluate Operator 1 Determine Operator #1 exceeded:
Critical *
1. >24 in 48 (wed - thur)
2. > 72 in 7 days
Evaluate Operator 2 Determine Operator #2 exceeded:
Critical *
1. < 8 hr break (mon - tue)
2. >16 in 24 hrs (mon - tue)
3. >24 in 48 hrs (mon - wed)
4. >72 in 7 day Five out of six violations must be identified to be satisfactor JPM A.1.b (SRO)
Form ES-C-1 Job Performance Measure Wn rk.*h*pt Facility: BRUNSWICK Task No: A.1.b Task Title:
EVALUATE OFF-SITE POWER SOURCE OPERABILITY PER THE CO DSR Job Performance Measure No:
K/A Reference:
262001/A2.10 (2.9/3.4)
Examinee:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom XX Simulator
_
Plant Required Materials:
Process Computer Calculator General References:
201-03.2 Rev. 67 Unit 2 Technical Specifications LOT-SIM-JP-201 -D07 Validation Time: RO - 10 Min, SRO - 15 Min Appendix C NRC Examiner:
Worksheet Time Critical Task: YES/N.OO
A. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: You are a Unit Two (2) Reactor Operato.
The load dispatcher has informed the Control Room that system reserve is lo.
The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-2.
Buses Common A and B are being supplied by their respective Unit powe.
Unit 2 is in Mode INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits established in the CO Daily Surveillance Report (DSR), and report the required actions for Unit READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: You are a Unit Two (2) Reactor Operato.
The load dispatcher has informed the Control Room that system reserve is lo.
The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-2.
Buses Common A and B are being supplied by their respective Unit powe.
Unit 2 is in Mode INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits established in the CO Daily Surveillance Report (DSR), and report the required actions for Unit Task Standard:
Supervisor informed SAT is inoperable. If Applicant is an SRO, determine that Tech Spec actions are applicable per LCO 3.8.1. Action C.
Applicant Performance:
SAT/UNSAT
Appendix C
Form ES-C-1 PERFORMANCE INFORMATION Task Description Standard Sat/U nsat
Obtain current revision of 201-Current revision of 201-03.2 obtained 0 and verified if applicabl Determine Attachment 1 notes Determine Attachment 1 notes S, T, S, T, and U appl and U appl PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E008 (Bus 2C Amps): 129 Determine amps on Bus 2 NOTE: Bus 2C amps determined using computer point EO0 PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E013 (Bus 2D Amps): 177 Determine amps on Bus 2 NOTE: Bus 2D amps determined using computer point EQ 1 PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E037 (Common B Amps): 33 Determine amps on Bus Common NOTE: Bus Common A amps determined using computer point E03 NOTE:
DO NOT PROVIDE THIS TO THE STUDENT:
The total of the above values is 3406.2 amp PROMPT:
If requested, inform examinee that the Motor Driven Fire Pump is being fed from E4 and is currently running for a PT on Unit 1 and that NSW 2B is running as indicated by the red lamp "on" on panel XU-PROMPT:
If requested, indicate to examinee that NSW Pump 2A, RHR 2A, RHR 2B, CS 2A and CS 2B are all in standby as indicated by green lights at the RTG Determine if the following PROMPT:
loads are running:
RHR 2A or 2 RHR 2A and 2B are NOT running.
NSW 2A or 2 NSW 2A is NOT running and NSW 2B IS runnin CS 2A or 2 CS 2A and 2B are NOT runnin Motor Driven Fire Pum Motor Driven Fire Pump is runnin Determine total amperage Total allowable load limit is 3389 limit, amps (3315 + 40+34).
Determine current load Determines total load of 340 Critical exceeds the allowable limit exceeds limit of 3389 and that SAT and that the SAT shall be is ino considered inoperabl Supervisor informed SAT is inoperabl NOTE:
IF THE EXAMINEE IS AN RO, THE JPM IS COMPLETE AT THIS TIM PROMPT:
If the examinee is an SRO, direct examinee to determine the required actions per Technical Specifications for the current condition (no other equipment inoperable at this time)
Determines that LCO 3.8.1 Action C applies requiring performance of SR 3.8.1.1., correct breaker alignments and indicated power availability (PT-12.8.1) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafte NOTE:
Required Action C.2 only applies if one 4 KV E Bus can not be supplied from offsite power. It does not apply in this cas Determines that LCO 3.8.1 Action C.3 applies, requiring restoration of the inoperable offsite circuit to OPERABLE status within the next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Refer to Tech Secs Determine that Tech Spec actions are Critical applicable per LCO 3.8.1. Action TERMINATING CUE: When the RO has determined that the SAT is inoperable, and the SRO has determined the required Tech Spec actions, this JPM is complete.
Sat/Unsat Task Description Standard
1051 300.00 160.0 0.00.0
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: Task Title: Evaluate SRM / IRM Overla Job Performance Measure No:
K/A Reference: 2.2.30 (3.5/3.3) Knowledge of RO duties in the control room during startup activitie Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room Plant Applicant Performance:
SAT/UNSAT Required Materials:
General References:
OGP-02, Rev 70 OGP-02, Rev 70 Time Critical Task: YES/NO Validation Time: 15 Mi Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserte. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings A
120 cps B
110 cps C
140 cps D
110 cps 3. Following control rod withdrawal observed:
SRM Indicated Readings A
5 x 102 cps B
5 x 104 cps C
5 x 105 cps D
5 x 104 cps IRM Indicated Readings A
1/40, Range 1 B
1/40, Range 1 C
2/40, Range 1 D
1/40, Range 1 E
2/40, Range 1 F
1/40, Range 1 G
1/40, Range 1 H
2/40, Range 1 to criticality the following SRM and IRM count rates are IRM Indicated Readings A
5/40, Range 1 B
4/40, Range 1 C
2/40, Range 1 D
6/40, Range 1 E
3/40, Range 1 F
6/40, Range 1 G
4/40, Range 1 H
5/40, Range 1 INITIATING CUE:
Assess the above SRM and IRM indications for proper overlap and determine applicable tech spec action(s) and whether the unit startup may continu READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
4. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserte. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings A
120 cps B
110 cps C
140 cps D
110 cps 6. Following control rod withdrawal observed:
SRM Indicated Readings A
5 x 102 cps B
5 x 103 cps C
5 x 104 cps D
5 x 103 cps IRM Indicated Readings A
1/40, Range B
1/40, Range C
2/40, Range D
1/40, Range E
2/40, Range F
1/40, Range G
1/40, Range H
2/40, Range to criticality the following SRM and IRM count rates are IRM Indicated Readings A
5/40, Range 1 B
4/40, Range 1 C
2/40, Range 1 D
6/40, Range 1 E
3/40, Range 1 F
6/40, Range 1 G
4/40, Range 1 H
5/40, Range 1 INITIATING CUE:
Assess the above SRM and IRM indications for proper overlap and determine applicable tech spec action(s) and whether the unit startup may continu TASK STANDARD:
1. Determines IRMs "C" and "E" are inoperable. (SRO ONLY)
2. Tech Spec table 3.3.1.1-1 item la. not met. Per LCO 3.3.1.1 Condition A, place inoperable IRM channels in the trip condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Determines tech spec surveillance requirement SR 3.3.1.1.6 can not be satisfied. (SRO ONLY)
3. Procedure OGP-02 Caution prior to step 5.2.18 requires a reactor shutdown and notification of reactor engineer. (RO and SRO)
SAT/UNSAT
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: Task Title: Estimate Source Term for a Release from the Main Stack per PEP-03. Job Performance Measure No:
K/A Reference:
272000/A4.05 (2.3 / 3.7) - Ability to manually convert process radiation monitor readings to offsite release rates Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room Plant Applicant Performance:
SAT/UNSAT Required Materials:
General References:
Calculator OPEP-03.6.1 Rev. 11, Release Estimation Based Upon Stack/Vent Reading LOT-OJT-JP-301 -A09 Time Critical Task: YES/NO Validation Time: 15 Mi Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. A Loss of Coolant Accident on Unit One (1) has required declaration of a General Emergenc Unit One (1) has initiated Drywell Venting actions due to high Containment Pressure per EOP-01-SEP-0. Off-Site Dose Projection is required. ERFIS is not available in the EOF, and the Radiological Control Manager has requested the Control Room to determine the Source Term for the Main Stack Releas. The Main Stack flow transmitter (2-VA-FT-3359) is not operational. Main Stack flow indication is not availabl. Unit Two (2) has been placed in Hot Shutdown. Unit Two (2) specific releases to the Main Stack are SJAE A and Seal Steam Exhauster. Unit One (1) releases to the Main Stack consist of two drywell purge fans in operation and one Standby Gas Train (A) in operatio. Plant common releases to the Main Stack consist of AOG Building Ventilation and one Radwaste Exhaust Fan (B) in operatio. Recorder 2-D12-RR-4599 indicates the following:
Low Range (green) Pen is pegged high Mid Range (blue) Pen indicates 3.3E-02 (scale is 1E-4 to 1E+2)
High Range (red) Pen is pegged lo INITIATING CUE:
You are directed by the Shift Superintendent to estimate the Source Term release from the Main Stack per PEP-03.6.1, and inform him of the Source Term estimatio READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. A Loss of Coolant Accident on Unit One (1) has required declaration of a General Emergenc Unit One (1) has initiated Drywell Venting actions due to high Containment Pressure per EOP-01-SEP-0. Off-Site Dose Projection is required. ERFIS is not available in the EOF, and the Radiological Control Manager has requested the Control Room to determine the Source Term for the Main Stack Releas. The Main Stack flow transmitter (2-VA-FT-3359) is not operational. Main Stack flow indication is not availabl. Unit Two (2) has been placed in Hot Shutdown. Unit Two (2) specific releases to the Main Stack are SJAE A and Seal Steam Exhauster. Unit One (1) releases to the Main Stack consist of two drywell purge fans in operation and one Standby Gas Train (A) in operatio. Plant common releases to the Main Stack consist of AOG Building Ventilation and one Radwaste Exhaust Fan (B) in operatio. Recorder 2-D12-RR-4599 indicates the following:
Low Range (green) Pen is pegged high Mid Range (blue) Pen indicates 3.3E-02 (scale is 1E-4 to 1E+2)
High Range (red) Pen is pegged lo INITIATING CUE:
You are directed by the Shift Superintendent to estimate the Source Term release from the Main Stack per PEP-03.6.1, and inform him of the Source Term estimatio Task Standard:
Step Description Standard I SAT/UNSAT
Obtain current revision of PEP-Current Revision of OPEP03.. obtained
Refer to Attachment 1 for source Determined that calculation of term calculation from the plant main stack source term is stack and determine calculation required by PEP-03. per Attachment 1 is required Attachment 1 Enter time on Attachment 1 Time is entered on Attachment
NOTE:
If requested, inform applicant that the digital readout indicates 3.31E-2 r Obtain monitor readings from 2-Record 2-D 12-RR-4599 reading D12-RR-4599 (on cue sheet)
as 3.3E-2 on Attachment 1
Estimate Stack Flow using Attachment 6 as follows:
Unit 1 flow determined to be Unit 1 flow calculated and (DW Purge A + DW Purge B +
recorded as 17,900 cfm on SBGT A)
17,900 CFM attachment 6 Unit 2 flow determined to be 950 Unit 2 flow determined to be cfm (SJAE A + SPE A)
950 cfm and recorded on Attachment 6 Common flow determined to be Common flow determined and 41,200 cfm (RW Fan B + AOG recorded as 41,200 cfm on Vent)
attachment 6 Total Stack flow estimated at Total Stack flow estimate (Unit 1 + Unit 2 + Common)
recorded as 60,050 cfm on 60,050 cfm attachment 6
Determine Release Rate (3.3E-2 Release Rate from Main Stack Critical X 60,050 X 472 = 9.35 E5 determined to be 9.3-9.4 E5
_C/sec)
_C/sec
Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: A.4 Task Title: NRC Reporting Requirements - Large Break LOCA Job Performance Measure No:
K/A Reference:
GEN 2.4.30 (2.2/3.6) Knowledge of which events related to system operations/status should be reported to outside agencies.
Examinee:_____
____
Date:
NRC Examiner:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room Applicant Performance: SAT/UNSAT Required Materials:
General References:
001-01.07, Rev 10 SRR-OJT-JP-201-D09 Time Critical Task: YES/NOV Plant Facility: BRUNSWICK Task No: A.4 Validation Time: 10 Mi Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. Unit One (1) was operating at rated powe. A line break in the drywell resulted in a Reactor scram. HPCI/RCIC initiated but were unable to maintain Reactor level. No circuit alterations were performed for HPCI or RCIC. Reactor level dropped below the Top of Active Fuel requiring Emergency Depressurization. Low pressure ECCS initiated and restored Reactor level to the normal ban. Current plant conditions are:
Reactor Level
+180" Reactor Pressure 25 psig Drywell Pressure 10 psig 4. Core Spray is injecting to maintain Reactor Level. One RHR Loop is operating in drywell and suppression chamber spray. One Loop of RHR is operating in suppression pool cooling and spra. All systems functioned as designed during the event. There are no significant releases of radioactivity in excess of 1 OCFR20 limits. There are no indications of fuel failur INITIATING CUE:
You are directed by the Shift Superintendent to determine reportability of this event per O1-01.07, complete Attachment 1, Reportability Evaluation Checklist, and inform the Shift Superintendent when Attachment 1 is complete READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. Unit One (1) was operating at rated powe. A line break in the drywell resulted in a Reactor scram. HPCI/RCIC initiated but were unable to maintain Reactor level. No circuit alterations were performed for HPCI or RCIC. Reactor level dropped below the Top of Active Fuel requiring Emergency Depressurization. Low pressure ECCS initiated and restored Reactor level to the normal ban. Current plant conditions are:
Reactor Level
+180" Reactor Pressure 25 psig Drywell Pressure 10 psig 4. Core Spray is injecting to maintain Reactor Level. One RHR Loop is operating in drywell and suppression chamber spray. One Loop of RHR is operating in suppression pool cooling and spra. All systems functioned as designed during the event. There are no significant releases of radioactivity in excess of 10CFR20 limits. There are no indications of fuel failur INITIATING CUE:
You are directed by the Shift Superintendent to determine reportability of this event per OI-01.07, complete Attachment 1, Reportability Evaluation Checklist, and inform the Shift Superintendent when Attachment 1 is complete PERFORMANCE CHECKLIST STAN DAR D SAT/U NSAT Current revision of 01-01.07 obtaine.
The following four hour reportability items are checked yes:.2.3.4
The Following eight hour reportability items are checked yes:.1..... 3...
NO 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reportability items Event is determined to be 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reportabl Critical Shift Superintendent informed of result Pass/fail criteria: Applicant must get step 5 correct; AND must get 10 of the 12 items correct on the reportability evaluation check lis.
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4 GROUPS I
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10 min -
ES-301 Administrative Topics Outline Form ES-301-1 Facility: BRUNSWICK Date of Examination:7130-813101 Examination Level (circle one): RO / SRQ Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions GEN Evaluate Overtime Eligibility 2.1.3(3.0/3.4)
GEN 2. Evaluate Off-site Power Source Operability per the CO DSR (3.7/4.4) GEN 2.2.30 Evaluate SRM I IRM Overlap (3.5/3.3) GEN 2. Calculate Worker Stay Time (2.5/3.1) GEN 2. Determine Communication Methods for E-Plan Activation (3.0/3.5)
(ou) BEL LNdr
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: A. Task Title: Evaluate Overtime Eligibilit Job Performance Measure No:
K/A Reference: GEN 2.1.3 (3.0/3.4) Knowledge of shift turnover practices Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room
-
Plant Applicant Performance: SAT/UNSAT Required Materials:
General References:
None OAP-001, Rev 9 Modified LOT-OJT-JP-201 COl Validation Time: 10 Min.
Time Critical Task: YES/NO
A. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outag INITIATING CUE:
Using the information in the schedule table, determine whether overtime guidelines have been violated; listing the violations (if any). Consider each case separately.
Operator # 1 Operator #2 Monday 0700-1900 0800- 2000 Came in late, stayed to make-up time Tuesday 0700-1900 0300-1900 (called in)
Wednesday 0700-2100 0700-1900 (held over, relief called in sick)
Thursday 1900-0700 0700-1900 (called in on off day)
Friday 1900-0100 OFF (went home sick)
Saturday 1900-0700 0700-1900 Sunday 1900-0700 0700-1900
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outag INITIATING CUE:
Using the information in the schedule table, determine whether overtime guidelines have been violated; listing the violations (if any). Consider each case separatel Operator # 1 Operator #2 Monday 0700-1900 0800- 2000 Came in late, stayed to make-up time Tuesday 0700-1900 0300-1900 (called in)
Wednesday 0700-2100 0700-1900 (held over; relief called in sick)
Thursday 1900-0700 0700-1900 (called in on off day)
Friday 1900-0100 OFF (went home sick)
Saturday 1900-0700 0700-1900 Sunday 1900-0700 0700-1900
Task Standard:
Step Description Standard SATIUNSAT 1 ItObtain a current Current Revision of 0AP-001 revision of OAP-001 obtained
Evaluate Operator I Determine Operator #1 exceeded:
Critical*
1. >24 in 48 (wed - thur)
2. > 72 in 7 days
Evaluate Operator 2 Determine Operator #2 exceeded:
Critical *
1. < 8 hr break (mon - tue)
2. >16 in 24 hrs (mon - tue)
3. >24 in 48 hrs (mon - wed)
4. >72 in 7 day I
Five out of six violations must be identified to be satisfactor JPM A.l.b (RO)
Form ES-C-1 Job Performance Measure Wnrk.*hAet Facility: BRUNSWICK Task No: A.l.b Task Title:
EVALUATE OFF-SITE POWER SOURCE OPERABILITY PER THE CO DSR Job Performance Measure No:
KIA Reference:
262001/A2.10 (2.9/3.4)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Classroom XX Required Materials:
Process Computer Calculator Simula Actual Performance tor Plant General References:
201-03.2 Rev. 67 Unit 2 Technical Specifications LOT-SIM-JP-201-D07 Validation Time: RO - 10 Min, SRO - 15 Min Appendix C Worksheet Time Critical Task: YESINO
Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: You are a Unit Two (2) Reactor Operato.
The load dispatcher has informed the Control Room that system reserve is lo.
The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-2.
Buses Common A and B are being supplied by their respective Unit powe.
Unit 2 is in Mode INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits established in the CO Daily Surveillance Report (DSR), and report the required actions for Unit 2.
A.1.b
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: You are a Unit Two (2) Reactor Operato.
The load dispatcher has informed the Control Room that system reserve is lo.
The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-2.
Buses Common A and B are being supplied by their respective Unit powe.
Unit 2 is in Mode INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits established in the CO Daily Surveillance Report (DSR), and report the required actions for Unit Task Standard:
Supervisor informed SAT is inoperable. If Applicant is an SRO, determine that Tech Spec actions are applicable per LCO 3.8.1. Action C.
Applicant Performance:
SAT/UNSAT
Appendix C
Form ES-C-1 PERFORMANCE INFORMATION Task Description Standard Sat/Unsat
Obtain current revision of 201-Current revision of 201-03.2 obtained 0 and verified if applicabl Determine Attachment 1 notes Determine Attachment 1 notes S, T, S, T, and U appl and U appl PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E008 (Bus 2C Amps): 129 Determine amps on Bus 2 NOTE: Bus 2C amps determined using computer point E00 PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E013 (Bus 2D Amps): 177 Determine amps on Bus 2 NOTE: Bus 2D amps determined using computer point E01 PROMPT:
When examinee demonstrates the ability to obtain computer point readings for BOP Bus amps, inform examinee that the readings are as follows:
E037 (Common B Amps): 33 Determine amps on Bus Common NOTE: Bus Common A amps determined using computer point E03 NOTE:
DO NOT PROVIDE THIS TO THE STUDENT:
The total of the above values is 3406.2 amp PROMPT:
If requested, inform examinee that the Motor Driven Fire Pump is being fed from E4 and is currently running for a PT on Unit I and that NSW 2B is running as indicated by the red lamp "on" on panel XU-PROMPT:
If requested, indicate to examinee that NSW Pump 2A, RHR 2A, RHR 2B, CS 2A and CS 2B are all in standby as indicated by green lights at the RTG Determine if the following loads PROMPT:
are running:
RHR 2A or 2 RHR 2A and 2B are NOT runnin Task Descriotion NSW 2A or 2 CS 2A or 2 Motor Driven Fire Pum Determine total amperage limi Determine current load exceeds the allowable limit and that the SAT shall be considered inoperable.
Standard NSW 2A is NOT running and NSW SaVUnsat NSW 2A is NOT running and NSW 2B IS runnin CS 2A and 2B are NOT runnin Motor Driven Fire Pump Ls runnin Total allowable load limit is 3389 amps (3315 + 40+34).
Determines total load of 340 exceeds limit of 3389 and that SAT is inop.
Critical
Supervisor informed SAT is inoperabl NOTE:
IF THE EXAMINEE IS AN RO, THE JPM IS COMPLETE AT THIS TIM PROMPT:
If the examinee is an SRO, direct examinee to determine the required actions per Technical Specifications for the current condition (no other equipment inoperable at this time)
Determines that LCO 3.8.1 Action C applies requiring performance of SR 3.8.1.1., correct breaker alignments and indicated power availability (PT-12.8.1) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafte NOTE:
Required Action C.2 only applies if one 4 KV E Bus can not be supplied from offsite power. It does not apply in this cas Determines that LCO 3.8.1 Action C.3 applies, requiring restoration of the inoperable offsite circuit to OPERABLE status within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Refer to Tech Secs Determine that Tech Spec actions are applicable per LCO 3.8.1. Action C.
Critical TERMINATING CUE: When the RO has determined that the SAT Is inoperable, and the SRO has determined the required Tech Spec actions, this JPM is complete.
Sat/Unsat
300.00 160.0 0.00 0.00 0.00 09:34 :34 08:34:34 07:34:44 OK nu
__.
U2EDE037 334.20 A UZEDE008 1294.7 A U2EDE013 1777.3 A GR U 32 BNPSI
TR N L T M D U 0 AG 72-010:43 I
WjIý 8 RN SIF TRE ID 3 TREND FASTC BASE
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10
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: Task Title: Evaluate SRM I IRM Overla Job Performance Measure No:
KIA Reference: 2.2.30 (3.5/3.3) Knowledge of RO duties in the control room during startup activitie Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room
-
Plant Applicant Performance: SAT/UNSAT Required Materials:
General References:
0GP-02, Rev 70 QGP-02, Rev 70 Time Critical Task: YES/NO Validation Time: 15 Mi Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserte. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings A
120 cps B
110 cps C
140 cps D
110 cps IRM Indicated Readings A
1/40, Range 1 B
1/40, Range 1 C
2/40, Range 1 D
1/40, Range 1 E
2/40, Range 1 F
1/40, Range 1 G
1/40, Range 1 H
2/40, Range 1 3. Following control rod withdrawal to criticality the following SRM and IRM count rates are observed:
SRM Indicated Readings A
5x102cps B
5 x 4 cps C
5x105 cps D
5 x 4 cps IRM Indicated Readings A
5/40, Range 1 B
4/40, Range 1 C
2/40, Range 1 D
6/40, Range 1 E
3/40, Range 1 F
6/40, Range 1 G
4/40, Range 1 H
5/40, Range 1 INITIATING CUE:
Assess the above SRM and IRM indications for proper overlap and determine applicable tech spec action(s) and whether the unit startup may continu READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
4. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserte. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings A
120 cps B
110 cps C
140 cps D
110 cps 6. Following control rod withdrawal observed:
SRM Indicated Readings A
5x102cps B
5 x 103 cps C
5x104cps D
5x103cps IRM Indicated Readings A
1/40, Range 1 B
1/40, Range 1 C
2/40, Range 1 D
1/40, Range 1 E
2/40, Range 1 F
1/40, Range 1 G
1/40, Range 1 H
2/40, Range 1 to criticality the following SRM and IRM count rates are IRM Indicated Readings A
5/40, Range 1 B
4/40, Range 1 C
2/40, Range 1 D
6/40, Range 1 E
3/40, Range 1 F
6/40, Range 1 G
4/40, Range 1 H
5/40, Range 1 INITIATING CUE:
Assess the above SRM and IRM indications for proper overlap and determine applicable tech spec action(s) and whether the unit startup may continu TASK STANDARD:
1. Determines IRMs "C" and "E" are inoperable. (SRO ONLY)
2. Tech Spec table 3.3.1.1-1 item la. not met. Per LCO 3.3.1.1 Condition A, place inoperable IRM channels in the trip condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Determines tech spec surveillance requirement SR 3.3.1.1.6 can not be satisfied. (SRO ONLY)
3. Procedure OGP-02 Caution prior to step 5.2.18 requires a reactor shutdown and notification of reactor engineer. (RO and SRO)
SATIUNSAT
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: Task Title: Calculate Worker Stay Time Job Performance Measure No:
K/A Reference: GEN 2.3.4 (2.5/3.1) Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorize Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator
_
Control Room Plant Applicant Performance: SAT/UNSAT Required Materials:
General References:
Calculator Time Critical Task: YES/NO Validation Time: 20 Mi A.3 Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
After Unit One refueling outage the 1 B RWCU pump requires maintenance on the north end of the pump. Two mechanics have been assigned the task. Listed below is the workers accumulated yearly dose following the refueling outag Worker 1 Description I Dose
CP&L Employee whose doses (CP&L and non-1800 mrem TEDE CP&L) for the current are known
New CP&L Employee whose CP&L dose for the 350 mrem TEDE current year is known. Non-CP&L dose has not yet been determined
_
Vendor representative whose CP&L dose for the 1400 mrem TEDE year is known. Non-CP&L dose has not yet been determined INITIATING CUE:
Using the survey map provided calculate how long each worker may remain in the area to perform the maintenance before reaching the administrative exposure limits. Assume no dose is received in transit to the work are BRUNSWICK NUCLEAR PLANT RADIOLOGICAL SURVEY SURVEY N TRN01 7-26-01 0812 DOSE RATE CONTAMINATION DATE:
TIME:
RO-2 A El ct E]
gr" ego Philip A. DeFoggi INST. TYPE SURVEYOR (SERIAL N TRN1245 N/A SURVEYORE P FACTOR 4-Unbagged INST/SN N/A NA S~viG=lNATURE H"_
RX POWER 100%_____39 EF ______________
391CPMj CPM REVIEWED
-tkx
,
H2SCFM
_.BKGD._______
U 1-L
A RWCU PUMP ROOMS UNITL-BLDG-B EL-0 AREA RWP NO.
N/A WR/JO N/A COMPONENT OR TAG N WORK PERFORMED Routine Radiation Survey RA -RADIATION AREA HRA -HIGH RADIATION AREA LHRA -LOCKED HIGH RADIATION AREA RCA -RADIATION CONTROL AREA Training Use Only!
CA -CONTAMINATION AREA HCA -HIGH CONTAMINATION AREA AA -AIRBORNE AREA S-ROPE BOUNDARY N/A
- 1099 I
SMEAR RESULTS IN DPMI100 CM2 B=BETA IN mRAD/HR/100CM 2 M=CPMI/MASLIN N RESULTS N/A N/A DOSE RATES IN mR/HR n o-NEUTRON (mRem/Hr)
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
After Unit One refueling outage the 1 B RWCU pump requires maintenance on the north end of the pump. Two mechanics have been assigned the task. Listed below is the workers accumulated yearly dose following the refueling outag Worker Description Dose
CP&L Employee whose doses (CP&L and non-1800 mrem TEDE CP&L) for the current are known
New CP&L Employee whose CP&L dose for the 350 mrem TEDE current year is known. Non-CP&L dose has not yet been determined
Vendor representative whose CP&L dose for the 400 mrem TEDE year is known. Non-CP&L dose has not yet been determined INITIATING CUE:
Using the survey map provided calculate how long each worker may remain in the area to perform the maintenance before reaching the administrative exposure limits. Assume no dose is received in transit to the work are Task Standard:
Each Maintenance workers maximum stay time calculated.
Step Description Standard I
SATIUNSAT
Obtain copy of Radiation Control and Protection Manual Determine stay time 2000 mrem admin limit - 1800 Critical for worker #1 mrem = 200 mrem 200mrem/45 mrem/hr = 4.44 hrs
Determine stay time 500 mrem admin limit - 350 Critical for worker #2 mrem = 150 mrem 150 mrem/45 mrem/hr = 3.33 hrs
Determine stay time 500 mrem-400 mrem 100 ICritical for worker #3 mrem 100 mrem/45 mrem/hr = 2.22 hrs
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: Task Title: Determine Communication Methods for E-Plan Activation Job Performance Measure No:
K/A Reference: GEN 2.3.4 (3.0/3.5) Knowledge of communications procedures associated with EOP implementatio Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom XX Simulator Control Room Plant Applicant Performance: SATIUNSAT Required Materials:
General References:
OPEP-03. OPEP-Appendix A Time Critical Task: YES/NO Validation Time: 10 Mi A.4 Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
You are an extra licensed operator assigned to Unit 2 when, at 0200, an Alert is declared due to a tornado striking inside protected area resulting in major damage to structures housing safety-relatdd systems. In addition to structural damage, both units have tripped off-line and a number of electrical problems have been identified, including inoperability of the following:
"* The Emergency Notification System
"* The Selective Signaling System
"* The BEN System
"* Commercial Telephone lines INITIATING CUE:
The Shift Superintendent has prepared the appropriate notification forms and has directed you to make notifications to the State and Counties, the Nuclear Regulatory Commission, and to initiate Emergency Response Organization callout in accordance with the appropriate OPE For each of these tasks, identify the way you would make the specified notification and, where appropriate, the phone number you would us READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
You are an extra licensed operator assigned to Unit 2 when, at 0200, an Alert is declared due to a tornado striking inside protected area resulting in major damage to structures housing safety-related systems. In addition to structural damage, both units have tripped off-line and a number of electrical problems have been identified, including inoperability of the following:
"* The Emergency Notification System
"* The Selective Signaling System
"* The BEN System
"* Commercial Telephone lines INITIATING CUE:
The Shift Superintendent has prepared the appropriate notification forms and has directed you to make notifications to the State and Counties, the Nuclear Regulatory Commission, and to initiate Emergency Response Organization callout in accordance with the appropriate OPE For each of these tasks, identify the way you would make the specified notification and, where appropriate, the phone number you would us TASK STANDARD:
Identify the following methods and phone numbers:
State and Counties: VHF Radio (no phone or channel number)
NRC: Cellular or satellite phone - 301-816-5100 ERO Callout: Cellular or satellite phone - 754-1098
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: BRUNSWICK Date of Examination: 7130-813101 Exam Level (circle one): RO I SRO(I) I SRO(U)
Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Code*
Safety Function Transfer RPS Bus B From Normal to Alternate Power M,S,A
(SROU) Place The Master Feedwater Controller In Service Per M,S,A
GP-02 (SROU) Emergency Equalization Around MSIV's -
Anticipate D,C,L
Emergency Depressurization (SROU) Establish UAT Backfeed D,S 6 HPCI Start Using the "Hard Card" - Steam Line Break D,S,A
With Auto Isolation Failure Recirculation Pump Start - Recirculation Pump Speed D,S,A
Control Failure (pressure control) Install Circuit Alterations For Drywell Cooling Per AOP-D,C
3 B.2 Facility Walk-Through Control Room Evacuation - AOP-32 - Scram and MSIV D, R
Closure From Outside the Control Room (SROU) Resetting a RCIC Mechanical Overspeed Trip (SROU)
D 4 Perform Actions Associated With Fires - Aligning the D
Fire Protection Alternate Water Supply
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
Administrative Topics Outline Form ES-301 -1 JPM B.1.a 1S-301 ES-301
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: An RPS MG Set B spurious trip has occurre.
No scram signal is present on RPS Bus.
No Tracking LCO exist on RPS EPA Breaker INITIATING CUE:
The Unit SCO has directed that you energize RPS Bus B from the alternate source per OP-03 and inform him when the applicable procedure section is complet Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B. Task Title: Transfer RPS Bus B From Normal to Alternate Power Job Performance Measure No:
KIA Reference: 212000/A2.02 (3.7, 3.9)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance Actual Performance XX Classroom Simulator XX Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie Initiating Cue: An RPS MG Set B spurious trip has occurre.
No scram signal is present on RPS Bus.
No Tracking LCO exist on RPS EPA Breaker The Unit SCO has directed that you energize RPS Bus B from the alternate source per OP-03 and inform him when the applicable procedure section is complet Task Standard:
Places RPS Bus B on alternate power supply, identifies ATWS as a result of Bus A failure, and scrams reactor.
Applicant Performance:
SATIUNSAT
Initial Conditions:
IC-11 Rx. Pwr. - 100%
Core Age - BOC RPS MG Set/Bus B tripped and initial plant response complet System Tag Title Value MI IAEPAALT RPS ALT EPA BKRS TRIPPED ED IBZNORM RPS ALT POWER E8 - ALT Trip RPS MG Set B via Malfunction, MF, RP004F, RPS B MG Set TRI.
Perform necessary actions to stabalize the plant following the loss of RPS Bus.
Acknowledge alarm.
RPS ALT Supply EPA breakers #5 and #6 and RPS ALT POWER SOURCE are positioned as required via Remote Functions when requeste.
Automatic scram prevented, manual scram possible.
Required Materials:
NONE Time Critical Task: YES/NO General References:
20P-03.0, Rev. 37 Modified LOR-SIM-JP-003-AO3 Validation Time: 10 Mi Appendix C
Form ES-C-1 Description PERFORMANCE INFORMATION Standard
Obtain current revision of 20P-03
Determine RPS Alternate Power source must be transferred.
Current revision of 20P-03 is reference Recognize RPS Alternate Power Source must be transferred to ALTERNATE (2E8).
NOTE:
Applicant may direct AO to perform per procedure Section 8.5 rather than differentiate steps 3,4, and 5.
Contact AO to open EPA #6 and EPA
- 5 breaker Direct AO to transfer RPS Alternate Power Throwover Switch to Alternat Direct AO to Close EPA breakers #5 and #6 per OP-0 Verify white ALT light above the RPS Power Source Select Switch is on.
AO directed to place EPA breakers #6 and #5 to OF Direct transfer of RPS Alternate Power Critical Throwover Switch to Alternate.
Direct EPA breakers #5 and #6 CLOSED per OP-0 RPS ALT Power available (center white light) on Panel P610 is o Proc step 8.5.10 Critical NOTE:
After RPS ALT power is restored, student must refer to Section 8.2 of OP-03 to transfer power for RPS B to Alternat PROMPT:
Inform the examinee that OP-03.0 Attachment 10 will be completed by other operators NOTE:
With RPS B deenergized, the MSIV SOL. COIL DC lights on Panel H12-P622 for the Inboard MSIVs, B21-F022A-D, and the MSIV SOL. COIL AC lights on Panel H12-P623 for the Outboard MSIVs, B21 F028A-D, will be extinguished. Likewise the Inboard MSIV LOGIC DC and Outboard MSIV LOGIC AC lights on panel H12-P601 will be extinguished. These lights should illuminate when RPS B is energized AND the Group 1 PCIS LOGIC has been reset.
7 PLACE RPS POWER SOURCE SELECT SWITCH on P610 to ALT Reset APRM setdowns RPS POWER SOURCE SELECT SWITCH on P610 placed to ALT proc. step:8.2. APRM SETDOWN TRIP SET-DN trips reset. White alarm lights not lit, Panel P603, APRM sectio Proc step 8.2.2.6 Critical Critical PROM PT:
Fail 1 Div I APRM Upscale with ATWS (allow manual SCRAM)
Identify RPS Bus A failure
Identify failure of reactor to automatically scram Declares ATWS Task Sat/Unsat Critical
Task Description Standard Sat/Unsat NOTE:
At this point applicant may stop to consider resetting the scram groups 1/4 and 2/3, as It is the next task in the procedure. Choosing to reset the scrams vice scramming the reactor on indication of an ATWS is grounds for an automatic UNSAT for this JP Manually scram reactor perform RO Verifies shut down reactor, etc Critical duties for scram TERMINATING CUE:
When immediate post-trip actions are complete, the JPM may be terminated:
Trip the turbine
° Mode switch to S/D (Terminate)
Master FW controller setdown to 170"
JPM B B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: Unit Two startup is in progress per GP-0.
Reactor Feedpump discharge pressure is greater than 900 psi.
GP-02 is completed up to step 5.3.5 INITIATING CUE:
You are directed to place the Feedwater Master Controller in Automatic per GP-02, step 5.3.57 and inform your supervisor when step 5.3.57 is complet TITLE:
NO:
BRUNSWICK NUCLEAR PLANT JOB PERFORMANCE MEASURE WORKSHEET Place The Master Feedwater Controller In Service Per GP-02 LOR-SIM-JP-032-C01 SUPERVISOR-OPERATOR TRAINING Time Required for Completion:
Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance:
Setting:
Time Critical:
Alternate Path:
Actual X
Simulate Classroom Yes Yes Plant No X
No X
Unit
Simulator X
Time Limit EVALUATION SSN:
Did Trainee Obtain and Verify Procedure?:
JPM:
Questions:
Pass Pass Yes Fail Fail Remedial Training Assessment Required?: Yes (See TAP-1.05)
Evaluator Signature:
Comments:
DATE Trainee:
N/A No N/A No Date:
SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions IC
Rx. Pw %
Core Age BOC Required Plant Conditions IC-06 Malfunctions/Overrides None Special Instructions None
SAFETY CONSIDERATIONS:
NONE EVALUATOR NOTES: (Do not read to trainee) The applicable procedure section will be provided to the trainee after the applicant identifies the location and correct procedur.
The examinee should be given a copy of GP-02 marked up through (but not including) step 5.3.7 Read the following to traine TASK CONDITIONS: Unit Two startup is in progress per GP-0.
Reactor Feedpuinp discharge pressure is greater than 900 psi.
GP-02 is completed up to step 5.3.5 INITIATING CUE:
You are directed to place the Feedwater Master Controller in Automatic per GP-02, step 5.3.57 and inform your supervisor when step 5.3.57 is complet PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
NO.
DESCRIPTION Verify or place the Master RFPT Sp/Rx Lvi Ctl station in manua.
Verify Feedwater Control mode selector in 1 Ele.
Depress select push button on on-line feed pump (RFPT A) control station until bias is displayed and ensure bias set at 0%. Depress select push button on on-line feed pump until pump demand is displaye * Depress select push button on Master Controller until Master Demand is displaye * Set Master Demand signal equal to the on line Feed Pump demand signal using increase push butto * Depress AIM push button on RFPT A control statio.
Depress select push button on off-line feed pump (B) until level error displaye * Depress AIM push button on Master Controller and verify automati Verify pump A demand and valve demand remain unchange * 1 Place SULCV control station in manual control.
STANDARD MSTR RFPT SP/RX LVL CTL C32-SIC R600 indicates M (Manual).
C32-CS-Z2 is in the 1 ELEM positio Bias for the on-line Feed Pump displays 0% at RFPT A SP CTL C32-SIC-R601A control statio Pump demand for Feed Pump A is displayed at RFPT SP CTL C32-SIC R601A control statio Master Demand is displayed on MSTR SP/RX LVL C32-SIC-R60 MASTR DEM display on C32-SIC-R600 is equal to PMP A DEM display on C32 SIC-R601 RFPT A SP CTL C32-SIC-R601A control station indicates A (auto).
LVL ERROR is displayed on the RFPT B SP CTL C32-SIC-R601B control statio A (Auto) is displayed on MSTR RFPT SP/RX LVL CTL C32-SIC-R600 control statio PMP A (C32-SIC-R601A) and VALVE DEM (FW-LIC-3269) remain constan FW-LIC-3269 control station indicates M (manual).
EVAL S/um
PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comments.
DESCRIPTION NO.
control.
"*1 Open SULCV using increase push button until valve demand is 100%
STANDARD (manual).
VALVE DEM on FW-LIC-3269 control station is 100%, Reactor level is 182 192".
Inform supervisor Master Controller is in service per GP-02.
Supervisor is informed.
(')Comments required for any steps found UNSAT.
EVAL S/U()
JPM Blc
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS 1. A scram and Group 1 Isolation have occurre. No fuel failure or main steam line breaks have occurre. The Main Condenser is available as a heat sin. The Unit SCO has determined that Anticipation of Emergency Depressurization is require INITIATING CUE:
You are directed by the Unit SCO to perform the control operator actions associated with Emergency Equalization around the MSIV's, open MSIVs when pressure is <200 psid using the Hard Card and then perform Anticipation of Emergency Depressurizatio Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: Emergency Equalization Around MSIV's/Anticipate Emergency Depressurization Job Performance Measure No:
K/A Reference:
239001/A4.01 (4.2/4.0)
Examinee:
Date:
Method of testina:
Simulated Performance XX Classroom Required Materials: None Time Critical Task: YES/NO NRC Examiner:
Actual Performance Simulator
-
Plant Unit 1 General References:
EOP-01 -RVCP, Reactor Vessel Control Procedure Hard Card for MSIV equalization and reopening (S/960)
LOT-SIM-JP-025-A03 Validation Time: 15 Mi READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cue When you complete the task successfully, the objective for this job performance measure will be satisfie Initiating Cue:
1. A scram and Group 1 Isolation have occurre. No fuel failure or main steam line breaks have occurre. The Main Condenser is available as a heat sin. The Unit SCO has determined that Anticipation of Emergency Depressurization is require You are directed by the Unit SCO to perform the control operator actions associated with Emergency Equalization around the MSIV's, open MSIVs when pressure is <200 psid using the Hard Card and then perform Anticipation of Emergency Depressurizatio Task Standard:
MSIVs have been reopened and the reactor has been depressurized <300 psig via BPVs.
Applicant Performance:
SAT/UNSAT
Annendix C~
PERFORMANCE INFORMATION Description Standard
Obtain "Hard Card" for MSIV equalizatio Place the condenser vacuum bypass switches in bypass position.
Place MSIV control switches to clos Reset Group 1 isolation. Resets Group 1 Isolation reset switches; A72-S32 and S33 on P601 are depressed and white PCIS/Group 1 status lights on P601 are O Outboard MSIV switches: B21 -F028A, B21-F028B, B21-F028C, B21-F028D placed in OPE Open MS-F020, MSL Drain Isolation Valv Open B21-F019, MSL Outboard drain Isolation Valv Close MS-V28, Steam supply to MSR's, SJAE's, RFP' Close MVD-F021, Common drain line orifice Bypass Valve to condenser
Open B21-F016,MSL Inboard drain Isolation Valve
Open MS-F038 A,B,C,D, MSL orifices bypass valves to increase steam line pressur Main turbine steam line pressure A/B indication on XU-1 verified to be increasin Close MSL drain valves MS-V46, MS-V47, MS-V48, MS-V49 &
MS-V35.
"Hard Card" obtained for MSIV equalization Note: Inform applicant no spare operators are available if a request for another operator is mad PROMPT: Inform examinee low condenser vacuum bypass switches are in Bypass PROMPT: All MSIV control switches in closed positio PROMPT: White PCIS/Group 1 status lights on P601 are O PROMPT: MSIVs are OPE PROMPT: MS-F020 indicates ope PROMPT: B21-FO19 indicates ope PROMPT: MS-V28 Indicates closed.
PROMPT:
closed.
MVD-F021 Indicates PROMPT: B21-F016 indicates ope PROMPT: MS-F038A,B,C, and D indicate open. Steam Line pressure increasing PROMPT: Main turbine steam line pressure indication is increasin PROMPT: MS-V46, V47, V48, V49 and V35 indicate close PROMPT: If asked SRO direction is to Task Sat/Unsat Critical Critical Critical Critica I
Critical Critical Critica
t-orm t*Lz-1-Ann*.ndix (3.
Critica Verify differential pressure between
Task
Description reactor and main turbine is less than or equal to 200 psid.on ERFIS, C32-R608, R609, or C32-PI-R605A or B on P-603/601 or any other available reactor pressure indication available.
Open Inboard MSIV's. Inboard MSIV switches for B21 -F022A, B21 -F022B, B21-F022C, B21-F022D placed in the OPEN positio Open MVD-F021, Common drain line orifice Bypass Valve to condense Direct AO to Open V5005
Open MS-V46, V47, V48, V49 and V35, MSL drain valve Ensure open MS-V43, MS-V44, MS-V45, MS-V37N39, MS-V41N42, MS-V36, MSL drain valves.
Standard use 200# differential with Rx pressure at 1000# and main steamline press is 900#
Inboard MSIVs B21-F022A, B21-F022B, B21-F022C, B21-F022D indicate open after the valve is repositioned PROMPT: MVD-F021 indicates ope PROMPT: Valve open PROMPT: MS-V46, MS-V47, MS-V48, MS-V49 & MS-V35 Indicate ope PROMPT: MS-V43, MS-V44, MS-V45, MS-V37N39, MS-V41N42, MS-V36 Indicate open NOTE:
If MS-V28 is not re-opened, vacuum will not be re-established for opening of bypass valves PROMPT:
If asked, inform examinee that opening MS-V28 is required at this time.
Open MS-V28.
PROMPT: MS-V28 indicates open and condenser vacuum is increasing above 7".
NOTE: The main turbine bypass valves will not open until condenser vacuum is above 7".
PROMPT: When informed actions to equalize and open MSIVs are complete, direct examinee to rapidly depressurize the reactor to the main condenser in excess of 100 degrees F/Hour while maintaining steam flow below 3 million Ibm/hou TERMINATING CUE: When MSIVs have been reopened this JPM may be terminated.
Sat/Unsat Critica I
Critical
Po V9 Idr
B3..d Applicant Sheet TASK CONDITIONS:
1. The Unit 2 Startup Auxiliary Transformer has tripped and locked out, requiring a manual Reactor scram and resulting in a Loss Of Off-Site Powe. 230 KV Bus 2B is energized. 230 KV Bus 2A is locked out due to the SAT lock ou. Diesel generators 3 and 4 are tied to 4KV Buses E3 and E. Unit 2 is in process of establishing a UAT backfeed per AOP-36.1 and 20P-50 to re energize BOP Buse.20P-50 Section 8.13, has been completed through step 1 INITIATING CUE:
You are directed by the Control Room Supervisor to complete the steps for UAT backfeed from 230 KV Bus 2B and inform the Supervisor when all BOP buses are energize BRUNSWICK NUCLEAR PLANT JOB PERFORMANCE MEASURE WORKSHEET TITLE:
Establish A UAT Backfeed Time Required for Completion:
15 Minutes (approximate).
Performance:
Setting:
Time Critical:
Alternate Path:
APPLICABLE METHOD OF TESTING Simulate Actual X
Classroom Plant Yes No X
Yes No X
Unit
Simulator X
Time Limit N/A Trainee:
Did Trainee Obtain and Verify Procedure?:
Ye JPM:
Pass Fail Questions:
Pass Fail Remedial Training Assessment Required?: Yes (See TM-1.05)
Evaluator Signature:
Comments:
EVALUATION SSN:
No N/A No Date:
s
SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions IC
Rx. Pw %
Core Age BOC Required Plant Conditions SAT tripped with at least one 230 KV Bus available to supply power through the UAT Malfunctions Event System Tag Title Value Activate Deactivate (ramp rate)
Time (see)
Time (sec)
A*
EE EE02OF Unit 2 SAT Relay Failure N/A 0 SEC N/A Remote Functions System Tag Title Value (ramp rate)
EG*
EGZMGDIS UAT Backfeed Logic & No Load Disconnect ENABLE
- = Required Special Instructions Initiate SAT failure and scram the reactor. Perform the scram immediate action Enter Remote Function for UAT backfeed. Reset the backup generator lockou SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to trainee) The applicable procedure section will be provided to the traine.
If this is the first JPM of the JPM set, read the JPM briefing contained in TM-4.06 or Operating Test briefing from NUREG 1021, ES-302 to the traine.
A copy of 2OP-50, Section 8.13, signed off to through step 13 should be provided to the examine Read the following to traine TASK CONDITIONS: The Unit 2 Startup Auxiliary Transformer has tripped and locked out, requiring a manual Reactor scram and resulting in a Loss Of Off-Site Powe.
230 KV Bus 2B is energized. 230 KV Bus 2A is locked out due to the SAT lock ou.
Diesel generators 3 and 4 are tied to 4KV Buses E3 and E.
Unit 2 is in process of establishing a UAT backfeed per AOP-36.1 and 2OP-50 to re-energize BOP Buse.
20P-50 Section 8.13, has been completed through step 1 INITIATING CUE:
You are directed by the Control Room Supervisor to complete the steps for UAT backfeed from 230 KV Bus 2B and inform the Supervisor when all BOP buses are energize PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comment EVAL N DESCRIPTION STANDARD S1U0 11 Obtain latest revision of 20P-50 section Current revision of 2OP-50 section 8.13 8.1 obtained NOTE: If asked Only 2B BUS is energized, however for this JPM this condition is adequate to meet initial caution intent Place the Synchroscope for Generator Syncroscope switch placed to ON for PCB 29B to the ON positio PCB 29.
Verify running voltage is approx. 120 Running voltage verified to be appro volt volt * Close generator PCB 29 Generator PCB 29B switch placed to CLOS.
Verify incoming volts increase to Incoming voltage verified at approximately 120 volts, approximately 120 volt.
Place synchroscope switch for PCB 29B to Synchroscope for 29B is placed to OF OFF.
Verify UAT to Bus 2C breaker is close Place Synchroscope switch for UAT to 2C breaker to OFF.
Synchroscope for UAT to Bus 2C breaker placed to O UAT to Bus 2C breaker is close UAT to Bus 2C breaker verified to be close Synchroscope switch for UAT to 2C breaker is placed to OF PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comment EVAL DESCRIPTION STANDARD S/U¢r)
Place Synchroscope for UAT to Bus 2D to ON.
Close the UAT to Bus 2D breake Verify UAT to Bus 2D breaker is closed.
Place Synchroscope switch for UAT to 2D breaker to OF "*1 Place Synchroscope for UAT to Bus 2B to O "*1 Close the UAT to Bus 2B breake Verify UAT to Bus 2B breaker is close Place Synchroscope switch for UAT to 2B breaker to OF Verify alarm UA-13 3-6 is clear.
Synchroscope, for UAT to Bus 21) breaker placed to O UAT to Bus 2D breaker is close UAT to Bus 2D breaker verified to be close Synchroscope switch for UAT to 2D breaker is placed to OF Synchroscope for UAT to Bus 2B breaker placed to O UAT to Bus 2B breaker is close UAT to Bus 2B breaker verified to be close Synchroscope switch for UAT to 2B breaker is placed to OF Alarm UA-13 3-6 is verified to be clear.
Inform system engineer Buses 2C, 2D and Engineer informed Buses 2C, 2D and 2B 2B have been energize have been energized.
NO.
"*1 (")Comments required for any steps found UNSA LIST OF REFERENCES RELATED TASKS:
262 002 B4 01 K/A REFERENCE AND IMPORTANCE RATING:
262001 A4.01 3.4/ REFERENCES:
20P-50, Section 8.13, Rev 55 TOOLS AND EQUIPMENT:
None CP&L REQUIREMENTS COMPLETED None
On [m V/%dr
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: MSIVs have close.
RCIC has been started for RPV level contro.
SRVs are being used for RPV pressure contro INITIATING CUE:
You are directed to start HPCI for pressure control using the "Hard Card" and inform your supervisor when HPCI has been started for pressure per the Hard Car Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: HPCI START USING THE "HARD CARD" - STEAM LINE BREAK WITH AUTO ISOLATION FAILURE Job Performance Measure No:
KIA Reference:
206000/A4.05 (4.4/4.4)
A2.14 (3.3, 3.4)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance
_
Actual Performance XX Classroom
_
Simulator XX
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie Initiating Cue: Reactor Feed pumps have trippe.
Reactor Vessel Level has decreased to below the low level 2 HPCI initiation setpoin.
HPCI did NOT auto star You are directed to start HPCI for injection to the RPV using the "Hard Card" and inform your supervisor when HPCI has been started per the Hard card and is injecting at rated flo Task Standard:
When HPCI has been manually isolated, this JPM is complete.
Applicant Performance:
SAT/UNSAT
Required Materials:
None General References:
HARD CARD "Emergency HPCI Operation" 2/0577S LOR-SIM-JP-19-A08 Time Critical Task: YES/NO Validation Time: 5 Mi SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions:
IC-11 Rx. Pwr. 100%
Core Age BOC Required Plant Conditions:
RPV level below LL2 with Feedwater not available and HPCI failed to auto star Malfunctions Event System Tag Title Value Activate Deactivate (ramp rate)
Time (sec)
Time (sec)
El ES ES047F HPCI Stm Brk HPCI Room 20%
0 SEC N/A (o SEC)
A ES ES040F HPCI Auto Start Failure NA 0 SEC N/A Overrides Remote Functions System Tag Title Value (ramp rate)
PC IAPCJP0 E41-F002 Auto Closure Disabled ON
PC IAPCJP0 E41-F003 Auto Closure Disabled ON 4 Special Instructions Trip Feed Pump.
When level is below +112", place the simulator in FREEZ Appendix u
F-orm *-
--
PERFORMANCE INFORMATION Task Description
Reference HPCI Pressure Control In EOPs Hard Car Ensure HPCI Auto Intiation is RESET
Verify Auxiliary Oil Pump is not running
Open E41-F011
Open E41 -F059
Start the HPCI Barometric Condenser Vacuum Pump (E41-S4) and leave in start
Open the Turbine Steam Supply, E41 F001
Start the Auxiliary Oil Pump.
NOTE:
10 Standard HPCI Pressure Control In EOPs Hard Card. reference Verifies or resets auto initiation Verifies AOP is not running Opens E41 -FOl 1 Opens E41-F059 The HPCI VACUUM PUMP is started and left in start TURBINE STEAM SUPPLY VLV, E41 F001, is opene AUXILIARY OIL PUMP, is started.
If asked the desired reactor pressure is 800 - 1000 psig Throttle Open E41 -F008 to maintain Throttles Open E41 -FOO8 to maintain desired reactor pressure pressure of 800 to 1000 psig Ensure E41-V8 and E41-V9 are closed Ensures E41-V8 and V9 are closed Sat/Unsat Critical Critical Critical
Ensure E41 -F7012 is closed when flow Closes E41 -F7012 when flow is > 800 has increased above 800 gpm gpm
)TE:
When the HPCI injection valve is opened, initiate Event Trigger El to activate HPCI Steam line Break
Recognize HPCI Turbine Trip and HPCI steam line break is diagnose isolation signal, diagnose steam line break with failure to auto isolat Close HPCI isolation valves E41-F002 E41 -F002 or E41 -F003 indicate full Critical and E41-F00 close Contact Supervisor Supervisor informed HPCI manually isolated due to steam line break with failure to auto isolate.
NO
Task Description Standard Sat/Unsat TERMINATING CUE: When HPCI has been manually isolated, this JPM is complet JPM BAJ
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: Reactor Recirculation Pump 2B has tripped, and the cause of trip has been correcte.
Reactor Recirculation Pump 2A is running at less than 23,500 gpm RWCU system is in operation with a suction from the bottom head and the Recirc loo.
An off-going control operator has completed steps in OP-02 Section 5.2 up to Step 5.2.2.22, and OP-02, Section 8.2 up to step 8.2..
Another operator is logging parameter per 8.2.2.2, step INITIATING CUE:
You are to continue the startup of Reactor Recirculation Pump 2B and inform the Unit SCO when OP-02 Sections 5.2 and 8.2 are complete Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: Recirculation Pump Start - Recirculation Pump Speed Control Failure Job Performance Measure No:
K/A Reference:
202001/A4.01 (3.7/3.7)
A2.05 (3.8/4.0)
Examinee:
NRC Examiner:
Date:
Method of testinq:
Simulated Performance Actual Performance XX Classroom
__
Simulator XX
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie Initiating Cue: Reactor Recirculation Pump 2B has tripped, and the cause of trip has been correcte.
Reactor Recirculation Pump 2A is running at less than 23,500 gpm RWCU system is in operation with a suction from the bottom head and the Recirc loo.
An off-going control operator has completed steps in OP-02 Section 5.2 up to Step 5.2.2.22, and OP-02, Section 8.2 up to step 8.2..
Another operator is logging parameter per 8.2.2.2, step You are to continue the startup of Reactor Recirculation Pump 2B and inform the Unit SCO when OP-02 Sections 5.2 and 8.2 are complete Task Standard:
When Recirculation Pump 2B scoop tube is locked, this JPM may be terminate Applicant Performance:
SAT/UNSAT Required Materials:
General References:
Steam Tables 2 OP-02, Rev. 99 LOR-SIM-JP-002-A07 Time Critical Task: YES/NO Validation Time: 20 Mi SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions IC - 09 Rx. Pwr. - 50%
Core Age - BOC Required Plant Conditions Recirculation Pump A secured with Pump B flow <23,500 gpm and rod line below 80%, at least 10% margin to APRM rod bloc Event Triggers Event Tdn er Description El Auto Initiated (Q2716SR7 Not Equal To True) (Recirc B Run Back Red Light Out) Malfunctions None Overrides Trip the 2B Recirc Pump from the RTGB with the control switc.
Place the B32-V17 Seal Staging Valve to "MANUAL/OPEN" positio.
Reduce 2A Recirc Pump Flow to less than 22,000 GPM (approx 32%
speed). Reduce 2B Recirc Flow Ctir output to approx. 16%
Appendix C2FomE-i Description PERFORMANCE INFORMATION Standard NOTE:
Provide applicant with marked up copies of OP-02 Sections 5.2 and 8.2 Obtain current revision of OP-0.
Determine the RPV Dome temperature.
Current revision of OP-02 obtaine RPV pressure is obtained Pressure reading is corrected for PSIA. Pressure reading is located on the Saturated Steam table (or process computor) and corresponding temperature obtaine.
Obtain bottom head drain temperatur Point 5 of G31-TI-R607 is read. Calculate differential temperatur.
Record the differential temperature.
Bottom head drain temperature is subtracted from Dome temperatur (<145 OF)
Differential temperature and time of verification logged in Control Operator's logbook.
PROMPT: If asked, it is NOT desired to place APRM normal setpoints in setup Determine the temperature differential between the idle and operating loop. Record the differential temperatur.
Verify that the operating loop flow is less than or equal to 23,500 gpm (50%
of rated flow). Record operating loop flowrate.
a.
Operating loop temperature is read off B32-R650 or process computer. Idle loop temperature is read off B32-R650 or process compute AT obtained verified <50 OF and recorde Differential temperature and time of verification logged in Control Operator's logboo Operating loop flow is read off recorder B32-R614 or meter B32-R617 and operating loop flow is verified to be less than or equal to 23,500 gp Operating loop flowrate and time of wanrifirnfinn Innnari in (.nntrni rlnarnfnr'a Task Sat/Unsat Form ES-C-1 Annendix C
Task Description Standard Sat/Unsat verification logged in Control Operator's logbook.
1 Close the Discharge valv.
Start the B Reciro MG se.
Verify proper start sequence of the Recirc MG set and Pump Motor.
1 Record time of pump star.
Open the Recirc B pump discharge valve.
Control switch for the B32-F031 B is taken to the CLOSE position or verified closed by B32-F031 B Green indication only is illuminate The B Recirc MG set switch is placed to the Start positio MG set B drive motor breaker closed by RED light indicatio MG set accelerate The Generator Field breaker closes (RED indication) 6 seconds after the Drive motor breaker close Recirc Loop B Flow increases on B32-R61 Time at which MG set drive motor breaker closed logged in Control Operator's logboo Take the B32-F031B valve control switch to the OPEN position for 2 seconds then release for 10 second Repeat this for at least the first minute of travel, then fully open B32-F031 B.
PROMPT: If asked, direct applicant tp reset runback 1 Reset the runback per section Lower speed demand on Pump 2B until control established with potentiometer.
Runback is reset as follows:
Speed control potentiometer lowered below runback limit. Monitor for speed increase on Pump speed monitored while runback Pump 2 is reset. Depress Runback Reset push button for pump 2B.
Recirc B Runback Reset is depressed.
NOTE : When Recirc Pump B runback is reset, (can be monitored on the Panel Mimics in the Instructor Console) ensure Event Trigger El activates the Recirc Pump B Speed Control Failure.
When examinee locks the scoop tube, Critical Critical Critical NOTE :
Standard Sat/Unsat Task Description
and informs the Unit SCO of the failure the JPM is complete. Since the examinee cannot complete the task, it is acceptable for the examiner to inform the examinee that the JPM is complet PROMPT:
If examinee informs supervisor of recirc pump speed control failure, inform examinee another operator has been directed to enter AOP-0 to perform required subsequent action.
Lock the scoop tub Recirc pump B scoop tube is locked, by Critical placing "Scoop Tube B Lock" to TRIP with < 10% power increas TERMINATING CUE:
When Recirculation Pump 2B scoop tube is locked, this JPM may be terminated.
Standard Sat/Unsat Task Description
JPM B.lg
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. Unit One (1) is in a Station Blackou.
Buses El and E2 have been energized from Unit Two (2) by cross-ti.
Sufficient load is available to reestablish drywell cooling on Unit One (1). Unit One (1) has a LOCA signal sealed in due to high drywell pressure concurrent with low Reactor pressur INITIATING CUES:
You are directed to install the circuit alterations per AOP-36.2, Section 3.2.13, Steps 8, 9 and 11 to allow reestablishing drywell cooling and inform the Control Room when 1 -SW V103 and 1-SW-V106 can be opened and RBCCW Pump 1A can be starte Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: Install Circuit Alterations For Drywell Cooling Per AOP-3 Job Performance Measure No:
K/A Reference:
295012IAA1.02 (3.8/3.8)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom
_
Simulator
_
Control Room U1 Required Materials:
General References:
Screwdriver, tape and jumper AOP-36.2, Rev 14 from RO desk locked drawer LOR-OJT-JP-303-A05 Time Critical Task: YES/NO Validation Time: 10 Mi READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie Initiating Cue: Unit One (1) is in a Station Blackou.
Buses El and E2 have been energized from Unit Two (2) by cross-ti.
Sufficient load is available to reestablish drywell cooling on Unit One (1). Unit One (1) has a LOCA signal sealed in due to high drywell pressure concurrent with low Reactor pressur You are directed to install the circuit alterations per AOP-36.2, Section 3.2.13, Steps 8, 9 and 11 to allow reestablishing drywell cooling and inform the Control Room when 1-SW-V103 and 1-SW-V106 can be opened and RBCCW Pump 1A can be starte Task Standard:
When circuit alterations have been performed per AOP-36.2 Section 3.2.11, this JPM is complete.
Applicant Performance:
SAT/UNSAT
Annendix C2FomE-i Description PERFORMANCE INFORMATION Standard Obtain current revision of AOP-3 Section 3.2.1.
Obtain screwdriver, tape and jumper from RO desk locked drawe.
Lift and tape white wire 1-DK7-26 in Panel 1-XU-24 (ESS Logic Cabinet H59) on terminal TA93.
Current revision of AOP-36.2 obtaine Screwdriver, tape and jumper obtained from RO desk locked drawe White wire 1 -DK7-26 in Panel 1 -XU-24 (ESS Logic Cabinet H59) on terminal TA93 is lifted.
PROMPT:
When informed wire in XU-24 is lifted, inform examinee that 1-SW-V103 has been opened. Lift and tape grey wire 1-DE3-26 in Grey wire 1-DE3-26 in Panel 1-XU-7 Panel 1-XU-7 (ESS Logic Cabinet H58) (ESS Logic Cabinet H58) on terminal on terminal TE2 TE24 is lifted.
PROMPT:
When Informed wire in XU-7 is lifted, inform examinee that 1-SW-V106 has been opene If asked, inform examinee that 480V MCC lXE is energized and RBCCW Pump lC control switch has been placed to OFF. Install jumper in Panel 1-XU-7 (ESS Logic cabinet H58) between terminals TB71 and TB72.
Jumper in Panel 1 -XU-7 (ESS Logic cabinet H58) between terminals TB71 and TB72 installed.
PROMPT:
When informed jumper is installed in XU-7, inform examinee RBCCW Pump 1A is runnin.
Notify Control Room circuit alterations Control Room notified circuit alterations installed, installe TERMINATING CUE:
When circuit alterations have been performed per AOP-36.2 Section 3.2.11, this JPM is complete Task Sat/Unsat Critical Critical Critical Form ES-C-1
Ann*.ndix
B.2.a JPM
B.2.a I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: The SS has made the determination that control room evacuation IS require.
Scram and MSIV closure could NOT be completed prior to evacuating the Control Roo.
This JPM will be performed for Unit (Designated by examiner)
INITIATING CUES:
A reactor scram and MSIV Closure could NOT be completed prior to evacuating the Control Room. You are directed by the Shift Superintendent to perform ALL the immediate actions called for in OAOP-32.0, from memory, and inform him when the required actions are complete Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: Control Room Evacuation - AOP-32 - Scram and MSIV Closure From Outside the Control Room Job Performance Measure No:
K/A Reference:
295016/AA1.01 (3.8/3.9)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom
_
Simulator Control Room Required Materials:
None OAOP-3 LOR-OJT-JP-302-EO1 Plant XX General References:
Time Critical Task: YES/NO Validation Time: 5 Mi START FROM CABLE SPREAD ROOM READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: The SS has made the determination that control room evacuation IS require.
Scram and MSIV closure could NOT be completed prior to evacuating the Control Roo.
This JPM will be performed for Unit (Designated by examiner)
A reactor scram and MSIV Closure could NOT be completed prior to evacuating the Control Room. You are directed by the Shift Superintendent to perform ALL the immediate actions called for in OAOP-32.0, from memory, and inform him when the required actions are complete Task Standard:
When the EPA Breakers have been opened, this JPM is complete.
Applicant Performance:
SATIUNSAT
Annndix C2FomECi Description PERFORMANCE INFORMATION Standard NOTE:
JPM TO BE PERFORMED WITHOUT PROCEDURE!
NOTE:
EPA Breakers should be opened in sequence specified to avoid duty cycle of downstream breaker, but sequence is not critical. If upstream breaker (EPA-1,3) is opened first that step becomes critical and the downstream breaker (EPA-2,4) non critica PROMPT:
If requested, Indicate EPA POWER OUT light indications going out as EPA breakers are opene NOTE 1: It is critical that as a minimum, either Bkrs 1 AND 3 OR Bkrs 2 AND 4 are opene NOTE 2: The breakers must be opened in the correct order (as written below) Open EPA-2 circuit breaker for "A" RPS MG se.
Open EPA-1 circuit breaker for "A" RPS MG se.
Open EPA-4 circuit breaker for "B" RPS MG se.
Open EPA-3 circuit breaker for "B" RPS MG se.
Open EPA-6 circuit breaker for RPS alternate power suppl.
Open EPA-5 circuit breaker for RPS alternate power suppl.
Inform Shift Superintenden TERMINATING CUE:
EPA-2 circuit breaker open as indicated when the red POWER OUT light is extinguishe EPA-1 circuit breaker open as indicated when the red POWER OUT light is extinguishe EPA-4 circuit breaker open as indicated when the red POWER OUT light is extinguishe EPA-3 circuit breaker open as indicated when the red POWER OUT light is extinguishe EPA-6 circuit breaker open as indicated when the red POWER OUT light is extinguishe EPA-5 circuit breaker open as indicated when the red POWER OUT light is extinguishe Shift Superintendent informed that EPA breakers are open.
When the EPA Breakers have been opened, this JPM is complete.
Task Sat/Unsat Critical Critical Critica Critical Form ES-C-1 AnnAndix (3
m Cý
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. The RCIC turbine has tripped due to the mechanical overspeed trip devic. RCIC speed has been verified to be less than 4000 rp. All applicable prerequisites have been satisfie. This task will be performed at the lab INITIATING CUE:
The Reactor Operator has directed you to locally reset the RCIC mechanical overspeed trip device per the operating procedure and inform the Control Room when the required actions are complet Appendix C Form ES-C-1 Job Performance Measure Worksheet Facility: BRUNSWICK Task No: B. Task Title: Resetting a RCIC Mechanical Overspeed Trip Job Performance Measure No:
217000/A4.02 (3.9/3/9)
SG #7 (3.8/3.7)
SG #9 (3.9/3.5)
K4.04 (3.0/3.1)
A2.02 (3.8/3.7)
Examinee:
Date:
Method of testing:
NRC Examiner:
Simulated Performance XX Actual Performance Classroom
_
Simulator Control Room __
Plant Required Materials:
Plant page Time Critical Task: YES/NO General References:
1. 1(2) OP-16 2. Vol II/SD-16 3. AOR-OJT-JP-01 6-AO1 Validation Time: 8 Min.
KIA Reference:
Lab XX
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: The RCIC turbine has tripped due to the mechanical overspeed trip devic.
RCIC speed has been verified to be less than 4000 rp.
All applicable prerequisites have been satisfie.
This task will be performed on Unit The Reactor Operator has directed you to locally reset the RCIC mechanical overspeed trip device per the operating procedure and inform the Control Room when the required actions are complet Task Standard:
All actions necessary to reset a RCIC mechanical overspeed trip have been performed.
Applicant Performance:
SATIUNSAT
A nnrndi (
2FomE-i PERFORMANCE INFORMATION Standard Obtain current revision of OP-16, Section.
Identifies the RCIC turbine trip and throttle valve is in the "Tripped condition.
Current revision of OP-16 Section obtaine States that the RCIC turbine trip and throttle valve is closed PROMPT: IF asked if the control room has closed the motor actuator, state that they tried but it didn't work and the applicant must do it locally. Closes the RCIC Turbine Trip and Throttle valv.
Depending on body position, either push or pull the emergency connection rod in the direction of the RCIC turbine trip and throttle valve (E51 -V8)
approximately one inch.
Uses the handwheel to close the actuator such that the collar is returned to the correct position to allow for rese Emergency connection rod moved in direction of RCIC turbine trip and throttle valve approximately one inch. Observe tappet and ball assembly drop Tappet and ball assembly drops down into plac into plac PROMPT:
Inform applicant that the tappet and ball assembly has NOT dropped into place. If the tappet and ball assembly does not drop in place, lightly depress the assembly.
Tappet and ball assembly lightly depressed and dropped into place.
PROMPT:
When required, inform applicant that tappet and ball assembly HAS dropped into place. Release the emergency connection ro.
Notify the control room that the mechanical trip device for the RCIC turbine is reset.
Emergency connection rod release Control room notified that RCIC mechanical trip device for the RCIC turbine has been reset.
Task Description Sat/Unsat Critical Critical Critical Critical TERMINATING CUE:
The JPM may be terminated when all actions necessary to reset a RCIC mechanical overspeed trip have been performed.
Form ES-C-1
Ann*nrliY B.2.c JPM
B. Applicant Sheet I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS: A seismic event has caused the structural integrity of the Fire Protection Storage Tank to become breache.
The Fire Protection System was in a normal operating configuration with some minor leaks and NO system demand before the seismic even.
All fire pumps have been secured per applicable sections of OP-4.
The Shift Supervisor has determined that the MUD Tank must now be lined up to supply the Fire Protection Header followed by Jockey Pump startu INITIATING CUES:
You are directed by the Control Operator to perform the Auxiliary Operator actions associated with transferring the Fire Protection System water supply to the MUD Tank, and then start the Jockey Pumps in accordance with OP-41. You are to inform the Control Operator when the task assignment is complet Form ES-C-1 Job Performance Measure Wnrk~h*.*t Facility: BRUNSWICK Task No: B. Task Title: PERFORM ACTIONS ASSOCIATED WITH FIRES - Aligning the Fire Protection Alternate Water Supply Job Performance Measure No:
K/A Reference:
286000/Al.01 (2.9/2.9)
A1.05 (3.2/3.2)
A2.06 (3.1/3.2)
A3.01 (3.4/3.4)
A3.02 (3.1/3.2)
K3.03 (3.6/3.8)
K4.01 (3.4/3.6)
K4.03 (3.3/3.4)
K5.04 (2.9/2.9)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom
_
Simulator Control Room Required Materials:
1. OOP-41, Sect 8.51, Att 47 2. SD-41 3. AOP-1. P&ID 9527-D-2043 5. AOR-OJT-JP-041-A02 Time Critical Task: YES/NO Plant XX General References:
1. OP-41 Validation Time: 18 Min.
Appendix C
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfie TASK CONDITIONS:
1. A seismic event has caused the structural integrity of the Fire Protection Storage Tank to become breache. The Fire Protection System was in a normal operating configuration with some minor leaks and NO system demand before the seismic even.
All fire pumps have been secured per applicable sections of OP-4. The Shift Supervisor has determined that the MUD Tank must now be lined up to supply the Fire Protection Header followed by Jockey Pump startu You are directed by the Control Operator to perform the Auxiliary Operator actions associated with transferring the Fire Protection System water supply to the MUD Tank, and then start the Jockey Pumps in accordance with OP-41. You are to inform the Control Operator when the task assignment is complet Task Standard:
When Auxiliary Operator actions necessary for transferring the Fire Protection System water supply to the MUD Tank, and the Jockey Pumps have been started in accordance with OP-41, this JPM is complete.
Applicant Performance:
SAT/UNSAT
A "ndFr EC.-i PERFORMANCE INFORMATION Standard Sat/Unsat Task Obtain current revision of OP-41 Applicant reviews index of OP-41 to determine the needed sections required to perform the task assignmen.
Applicant reviews OP-41 Section 3.0, Precautions and Limitations.
Applicant obtains copy of OP-4 Applicant determines from a review of OP-41 index that the following procedure sections are needed:
Section 8.51 Applicant determines from OP-41 Section 3.0 that there are no Precautions or Limitations directly applicable to the Auxiliary Operator for this task assignment.
PROMPT:
If asked as a member of the Control Room Operating Crew about determination of OP-41 Prerequisites being met, acknowledge the request and inform the applicant that all applicable prerequisites are met. Applicant reviews OP-41 Section 4.0, Prerequisites.
Applicant determines from a review of OP-41, Section 4.0 that several prerequisites are applicable.
PROMPT:
When the applicant begins to evaluate the Initial Conditions of OP-41, Section 8.51, as the Control Room Supervisor, inform the applicant that you have evaluated both Initial Conditions I and 2 as having been met as required and that you are directing the applicant to continue with Step.
Applicant reads the Initial Conditions of Applicant recognizes that Initial OP-41, Section 8.5 Conditions have been met as informed by the Control Room Superviso PROMPT:
If asked for valve operation feedback by the applicant for determination of valve position, provide applicant information consistent with actions being taken for the particular valve Ensure Upstream Drain Valve for 2 FP-V58, 2-FP-V59, is closed.
Applicant locates 2-FP-V59 in the northeast floor sump area of the Diesel The applicant is expected to demonstrate his/her ability to obtain the needed sections of OP-41. After the applicant has satisfactorily demonstrated their ability to do this, the evaluator may provide copies of the procedure sections to the applican The applicant may wish to execute performance of OP-41 Attachment 47 for the purposes of documentatio This is an acceptable practice and is not dependant upon direction from OP-41 Section 8.51, Step 8.51.2.9. If an NRCS revision check is being performed, Attachment 47 is included as part of the check.
Description NOTE:
NOTE:
Critical Form ES-C-1
Ann*_ndiY
Task Description Standard Sat/Unsat Unlock and close Combined Suction Valve From Fire Protection Storage Tank, 2-FP-V57. Unlock and open the Demineralized Water Storage Tank Outlet To The Fire Protection System, 2-MUD-V3.
Unlock and open Fire Pumps Suction Valve From The Demineralized Water Storage Tank, 2-FP-V58.
1 Applicant reads the NOTE immediately ahead of OP-41 Section 8.51, Step 8.51..
Places Jockey Pump P-4 in HAND Applicant removes locking devices from valve handwheel and closes 2-FP-V57 by turning the valve handwheel clockwise in the closed direction until the handwheel movement becomes firmly unable to move any further with normal forc Applicant locates 2-MUD-V37 on the west side of the MUD Tan Applicant removes locking devices from valve handwheel and opens 2-FP-V37 by turning the valve handwheel counter clockwise in the open direction until the handwheel movement becomes firmly unable to move any further with normal forc Applicant locates 2-FP-V58 in the Diesel Driven Fire Pump Room in the northeast comer of the MWT Buildin Applicant removes locking devices from valve handwheel and opens 2-FP-V58 by turning the valve handwheel counter clockwise in the open direction until the handwheel movement becomes firmly unable to move any further with normal forc Applicant reads the NOTE and determines that it is applicable to the next step; OP-41 Section 8.51, Step 8.51. Applicant locates the Jockey Pump Control Panel in the south central area of the MWT Buildin Applicant rotates the Jockey Pump P-4 Control Switch to the right into the HAND position, verifying that the associated indicator lights show that the red light is on and the green light is off.
Applicant locates the Jockey Pump Driven Fire Pump Roo Applicant removes locking devices from 2-FP-V59 and turns the valve handwheel clockwise in the closed direction until the handwheel movement becomes firmly unable to move any further with normal forc Applicant locates 2-FP-V57 in the area immediately behind the Motor Driven Fire Pump (P-2) in the north end of the MWT Building.
Critical Critical Critical Sat/Unsat Task Description Standard
Places Jockey Pump P-3 in HAND Control Panel in the south central area of the MWT Buildin Applicant rotates the Jockey Pump P-3 Control Switch to the right into the AUTO position., verifying that the associated indicator lights show that the red light is on and the green light is off.
12.
PROMPT:
If contacted as a member of the Control Room Operating Crew for guidance concerning the starting of Fire Pump P-1 and/or P-2, direct the applicant to follow his initial instructions for the assigned tas.
Applicant recognizes that he was not Applicant stops performance of OP-41 directed to perform OP-41 Step Section 8.51 and does not perform OP 8.51. Steps 8.51.2.7 through 8.51. PROMPT:
If applicant starts the Motor-Driven Fire Pump P-2 or the Diesel Driven Fire Pump P-l, and if the applicant checks a local Fire Protection Header Pressure Indicator, indicate to the applicant that pressure is 130 psig by pointing to the appropriate location on the gauge fac (Pressure will remain at this value for the duration of time that P-1 and/or P-2 are running.)
PROMPT:
If asked, if Control Room desires to isolate relief valves respond "NOT AT THIS TIME".
PROMPT:
If applicant reports that he erroneously started P-1 and/or P-2, inform the applicant that other Auxiliary Operators are enroute to secure the pumps and that he is to continue with Jockey Pump startu PROMPT:
If the applicant indicates that he would check the running pumps for proper operation, indicate to applicant as appropriate, that all pump and pump motor conditions appear to be norma PROMPT:
When Jockey Pump P-4 is In HAND and if applicant did not start the Motor-Driven Fire Pump P-2 and/or the Diesel Driven Fire Pump P-i, and if the applicant checks a local Fire Protection Header Pressure Indicator, indicate to the applicant that pressure is 40 psig by pointing to the appropriate location on the gauge fac PROMPT:
When Jockey Pump P-3 is in AUTO, and if applicant did not start the Motor-Driven Fire Pump P-2 and/or the Diesel Driven Fire Pump P-i, and if the applicant checks a local Fire Protection Header Pressure Indicator, indicate to the applicant that pressure Is 55 psig and very slowly rising* by pointing to the appropriate location on the gauge fac *Pressure should be rising about 3-5 pounds per minute TERMINATING CUE: When Auxiliary Operator actions necessary for transferring the Fire Protection System water supply to the MUD Tank, and the Jockey Pumps have been started in accordance with OP-41, this JPM is complete.
Sat/Unsat Task Description Standard
FINAL SUBMITTAL BRUNSWICK EXAM 50-325 & 324/2001-301 JULY27 - AUGUST 3,2001 FINAL SCENARIOS AND OUTLINES ES-D-1
Appendix D Scenario Outline Form ES-D-1 Facility:
Brunswick Scenario No.: NRC-1 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: The plant is operating at middle of cycle steady state condition Power is currently 90% per the Load Dispatchers request. CSW Pump 2C and SLC Pump 2A are under clearanc Turnover:
Perform Core Spray System Operability Test, PT-07.2.4A. Raise reactor power to 100% when contacted by the Load Dispatcher Event Mal Event Event N N Type*
Description
NA N-BOP Perform Core Spray system operability test PT-07.2.4A SRO-2
C-BOP Core Spray pump overload requires pump to be tripped SRO
2 I-BOP Reactor Building radiation monitor fails, Reactor Building SRO isolates, Standby Gas fails to start
3 R-RO System frequency lowers requiring power to be raised to SRO 100% per AOP-2 C-RO Feedwater heater 4B tube leak trips heater, power rises and SRO must be reduced per AOP-0 I-RO Steam leak in the turbine building, MSIVs fail to auto close SRO
6 M-ALL High Power ATWS
7 RWCU fails to isolate when SLC is initiated 9 -d1
RCIC fails to start, HPCI or RCIC must be manually started to stabilize RPV level
....
...
.
.
...
e.ctivity (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1
- (N)ormal, (R)eactivity,
SCENARIO DESCRIPTION The plant is operating at 90% power, Beginning Of Cycle. EHC Pump B is out of service for maintenance. APRM E is failed downscale and bypasse Core Spray Pump A flow test will be performed. After flow is established, a pump overload will alarm requiring the pump to be trippe Reactor Building Vent Rad Monitor B will spike upscale, then fail downscale. Reactor Building HVAC will isolate, but SBGT will fail to auto start. SBGT must be manually started to maintain Secondary Containment integrit The load dispatcher will request power be raised to 100% due to loss of generatio Frequency will drop to 59.8 Hz requiring the crew to enter AOP-22 and raise powe Frequency will return to norma A Feedwater Heater 4B tube leak will result in a Hi-Hi extraction trip for the heate Feedwater temperature will lower resulting in a power rise. The crew will respond per AOP-03.0 and reduce power as required to maintain <100%.
A steam leak will develop in the Turbine Building resulting in area radiation alarms in the Turbine Building. The crew will respond per AOP-05.0. The leak will result in elevated temperatures, causing an MSIV isolation signal. The Group I isolation will fail to initiate requiring manual isolation. The reactor will fail to scram due to SDV hydraulic bloc The MSIV closure coupled with the ATWS will require the use of SRVs for pressure control, causing suppression pool temperature to rise. When SLC is initiated, RWCU fails to auto isolate and must be manually isolate When RPS reset is attempted, scram groups 2/3 will fail to reset and rod insertion via manual scram actuations will be unavailable. RMCS is available to manually insert control rod RPV level should be initially lowered to <90". Suppression pool temperature reaching 1 10oF will require the operators to further lower RPV water level and suppress reactor powe After RPV level drops below LL2, RCIC will fail to auto initiate. RCIC can be manually started, or HPCI can be used to stabilize level once APRMs are downscal Once RPV level is stable, the RPS reset logic will be repaired, allowing rod insertion by RPS actuation. When all control rods have been inserted and RPV water level is being restored > +170", the scenario may be terminate NRC-01-1
Rev.00
OBJECTIVES SRO 344226B402, Direct Actions For A Low System Frequency Per AOP-2 B402, Direct Shift Response To A Moderator Temperature Decrease Per AOP-0 B402, Direct Actions For Radioactive Spills, High Radiation And Airborne Activity Per AOP-0 B502, Direct Actions When A Scram Has Been Initiated And Reactor Power Cannot Be Determined To Be Less Than 3% Per EOP-01-RSP 344201 B502, Direct Actions To Control Reactor Power Per EOP-01-LPC 344202B502, Direct Actions To Control Reactor Pressure Per EOP-01-LPC 344235B502, Direct Actions To Deliberately Lower Level Per EOP-01-LPC RO 209003B201, Perform Core Spray System Operability Test Per PT-07.2.4a (07.2.4b)
273002B401, Respond To A Process Radiation Monitoring Downscale/Inop Annunciator Per The Appropriate APP 261003B1301, Perform A Control Room Manual Startup Of SBGT Per OP-1 0 2622031B401, Respond To A Low System Frequency Condition Per AOP-22 202002B1301, Increase Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Stations Per OP-02 200210B401, Respond To A Moderator Temperature Decrease Per AOP-0 B401, Respond To An Area Radiation Annunciator Per APP UA-03 200601 B401, Respond to radioactive spills, high radiation and airborne activity per AOP-B501, Manually Initiate Standby Liquid Control Per OP-05 NRC-01-1 Rev.00
201041 B501, Insert Control Rods With Reactor ManUal Control System Per EOP 01-LEP-02 218003B501, Inhibit ADS Actuation Per EOP-01 239602B501, Operate SRVs To Maintain Reactor Pressure Per EOP-01-LPC 217003B101, Manually Startup The RCIC System Per OP-16 206001 B501, Terminate And Prevent HPCI Injection 25600713501, Terminate And Prevent Condensate System Injection To Reactor Vessel 205014B1301, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 NRC-01-1 Rev.00
SIMULATOR SETUP Initial Conditions IC Rx Pwr Core Age Event Triggers
90%
BOC Event Trigger Description El Manually Initiated (Core Spray A Motor Overload)
E2 Manually Initiated (Rx Bldg Vent Rad Monitor B Fails)
E3 Manually Initiated (Feedwater Heater 4B Tube Leak)
E4 Manually Initiated (Steam Line Break in the Turb Bldg)
E5 Auto Initiated (Deletes Override on SBGT A, SBGT A Switch ON)
E6 Auto Initiated (Deletes Override on SBGT B, SBGT B Switch ON)
Malfunctions Event System Tag Title Value Activate Deactivate (Ramp)
Time Time A
RP RP011F A'WS #4
- 4 0 SEC NA A
ES ES041 F RCIC Fail To Auto Start NA 0 SEC NA A
NI N1042F APRM E Fails Low NA 0 SEC NA A
RW RW015F G31-F001 Fail Auto Close NA 0 SEC NA A
RW RWO16F G31-FOOl Fail Auto Close NA 0 SEC NA A
MS MS006F MSIV Fail Auto Close NA 0 SEC NA El ES ES01 7F Core Spray Pump A Ovid NA 0 SEC NA E2 RM RM006F RB Vent Mon B Fails Up NA 0 SEC 5 SEC E2 RM RM005F RB Vent Mon B Fails Down NA 5 SEC NA E3 CF CF022F FW Htr 4B Tube Leak 920000 0 SEC NA 0 SEC E4 MS MS002F MSL Break In Turb Bldg 1%
0 SEC NA 5:00 NRC-01-1
Rev.00
Overrides Switches Event Panel Tag Title Value Activate Deactivate (Ramp)
Time Time A
XU-51 K6101A SBGT A Push Off ON 0 SEC NA A
XU-51 K6103A SBGT B Push Off ON 0 SEC NA A
P603 K2504A Scram Reset GP 2/3 OFF 0 SEC N/A A
XU-3 K5417A EHC Pump B OFF 0 SEC N/A Remote Functions Materials ENP-24 for IC-11 PT-07.2.4A, complete up to step 7.8 (Pump Testing)
Stopwatch NRC-01-1 Rev.00
Special Instructions Post Exam In Progress Stop Signs at all simulator entrance Reduce Power to 90% and zero DV Advance all chart recorders to indicate steady state condition Place all SPDS displays to the Critical Plant Variable display (#100).
Ensure appropriate keys have blanks in switche Exit shutdown screen on RWM and place the RWM key in the key locke Reset alarms on SJAE, MSL, and RWM NUMAC Ensure reference material is in appropriate locatio Verify all logbooks have blank sheets onl Bypass APRM Channel E and place EC tag on Bypass Switc Place EHC Pump B to OFF and place red cap on control switc Load malfunctions/override On command line type trc:5, did:k6101A (unless loaded in CAE).
On command line type trc:6, did:k6103A (unless loaded in CAE).
Load CAE file if availabl Ensure ENP-24 for IC-1 1 present @ P603.
NRC-01-1 Rev.00
SHIFT BRIEFING Plant Status The plant is operating at 90% power 2 weeks following a refueling outage (Beginning Of Cycle). Power is currently being maintained at 90% at the load dispatcher's reques Equipment Out of Service EHC Pump 2B is under clearance for motor replacement and is expected to remain out of service for two day APRM Channel Echo failed downscale last shift and is bypassed. I&C is currently investigatin No other equipment is out of service Plan of the Day Maintain 90% power until contacted by the load dispatcher, then raise power to 100%.
I&C is continuing troubleshooting on APRM Channel Ech PT-07.2.4A, Core Spray Pump Loop A operability is in progress and completed up to step 7.8 (Pump Testing). Complete PT-07.2.4A as soon as shift turnover is complet No other special activities are scheduled for this shift.
NRC-01-1 Rev.00
SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Revision 8, ES-301 and Appendix During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance NUREG-1021, ES-30 Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenari Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)
Manually close the MSIV Initiate SLC before suppression pool temperature exceeds 11 0o Insert control rods per LEP-0 Lower RPV water level to suppress power per EOP-01-LP Reason For Revision NRC 2001 Initial License Exam.
NRC-01-1 Rev.00
SIMULATOR SCENARIO SHIFT TURNOVER Instructor Activities o Set up the simulator per the setu l Plant Response
Operator Activities SCO o Conduct shift turnover shift briefin RO/BOP o Perform board walk-dow Monitor the plant.
Rev.00 NRC-01-1
EVENT 1 CORE SPRAY PTIPUMP OVERLOAD Instructor Activities o] When asked, as RBAO report CS suction pressure is 6 psig, lubricant level is normal, and you are stationed to monitor system pipin [o When requested, report SW-V1 28 is open (Room Cooler SW valve).
[o Monitor Core Spray flow on panel mimic. After flow exceeds 4100 gpm, initiate trigger El to activate Core Spray pump A Overloa [o If asked, as outside AO report 51 device on OB showing target at pump breaker on E o If asked as I&C to investigate, acknowledge the reques Plant Response O Core Spray Pump A Overload alarms, pump does not trip (should not for OB overload).
Operator Activities SCO
[] Direct continuation of PT-07.2.4 o Direct Core Spray A be tripped after overload alar [o Direct I&C to investigat o Refer to Tech Spec 3.5.1 and determine Action A (7 day) applie RO o Monitor plant during PT performanc BOP ol Record pump suction pressure (local reading).
o Align cooling to the vital header (open SW-Vl 11 or SW-V1 17).
[o Ensure SW-V1 18 is open and SW-V141 is close o Start Core Spray Pump A and verify discharge pressure >300 psig in < 5 second o Ensure room cooler starts (RTGB) and SW-V128 opens (local).
o Throttle open test return to >4100 gpm, ensure min flow valve closes, and ensure pump discharge pressure is > 280 psi o Recognize and report Core Spray overload, refer to APP and trip pum o Dispatch AO to investigate at Bus E3 (check for relay targets).
[I Return Core Spray to standby alignment (close E21-FO15A).
Rev.00 NRC-01-1
REACTOR BUILDING VENT RAD MONITOR FAILS Instructor Activities
"o When actions are complete for the Core Spray overload, initiate trigger E2 to fail RB Vent Rad Monitor "o Monitor SBGT A/B control switches on panel mimic, when switches are placed to ON, ensure switch overrides on SBGT automatically delete, or manually delete the "o If asked as I&C to investigate, acknowledge the reques "o NOTE: the SCO may conservatively declare SBGT Inoperable, but until I&C determines cause of failure to start (may be failed instrument input only) this should not be considered to be require Plant Response o D12-NO10B initially spikes upscale, then fails downscal [I Group 6 and Secondary Containment isolation [I SBGT fails to auto start, can be manually starte l Major alarms UA-3 3-5 (Rad Monitor Hi-Hi) and UA-5 6-7 (Reactor Building Low Pressure).
Operator Activities SCO
[o Direct verification of auto actions for rad monitor failur [I Direct SBGT be manually starte El Direct I&C to investigate failure of vent rad monitor and SBGT to auto star [o Refer to Tech Spec 3.3.6.2 (Function 3) and determine Action A is applicable (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
[o Refer to Tech Spec 3.3.6.1 (Function 2d) and determine Action A is applicable (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
[3 Recognize/report failure of vent rad monito [o Refer to APPs for vent rad monitor (UA-3 3-5).
0 Ensure Group 6 and Secondary Containment isolation Recognize/report loss of Secondary Containment negative pressure and failure of SBGT to auto star Manually start both SBGT trains A and B by placing to ON.
Rev.00 NRC-01-1 EVENT 2
LOWERING GRID FREQUENCY Instructor Activities o When the crew has responded to the rad monitor failure, call control room as load dispatcher, report loss of generation has resulted in unstable grid conditions and request power be raised to 100%, then modify remote function EDIAFGRID, 5 o If contacted as NE, recommend power be raised using flow, no restrictions to rate appl o When power has been raised to at least 99%, modify remote function EDIAFGRID, 60. Call control room as load dispatcher and report grid stability has been restore Plant Response 0 Generator under frequency alarms (UA-6 1-2).
o EHC Set Speed light goes ou o EHC Increasing Speed light illuminate Operator Activities SCO o Direct power be raised to 100%.
o Direct entry into AOP-2 RO 0 Raise power to 100% using Recirculation flo BOP El Enter and announce AOP-2 o Determine unrestricted operation at present frequency (5 minute time limit begins at 59.3 hertz).
Rev.00 NRC-01-1 EVENT3
FW HEATER 4B TUBE LEAK Instructor Activities
[o When power is >99% and grid frequency is restored, initiate trigger E3 to activate feedwater heater tube leak o If asked as TBAO to investigate, report indicated high level in FW Heater 4B and emergency drain opening by controller indicatio o If notified as NE, recommend power reduction to 90% until thermal limits are verifie Plant Response ol FW Heater 4B level rises initiating extraction trip ol FW temperature drops,20oF and reactor power rises =3% (without operator action to lower power)
[I Major alarms UA-4 5-9 (Heater Hi/Lo) and UA-4 1-9 (Extraction Trip)
Operator Activities SCO
[o Direct entry into AOP-0 [o Direct reactor power reduction to maintain power <100% per ENP-24 and AOP-0 immediate action [o Notify NE to monitor thermal limit [o Refer to OP-35 to evaluate heater performanc [I Direct further power reduction as recommended by the N o Direct bypassing of FW heater 4B & 5B per OP-3 RO
[o Reduce reactor power to maintain power <100% per ENP-24 and AOP-0 immediate action o Reduce reactor power per NE recommendation and SCO direction using ENP-2 BOP
[o Diagnose Heater alarms as high heater level and tube rupture in FW Heater 4B (May use PC Display 432).
[o Dispatch AO to investigate at Heater level controlle [o Enter and announce AOP-0 [o Refer to OP-35 to evaluate heater performanc [I Reduce power as directed by the SC l Refer to OP-32 for bypassing feedwater heaters.
NRC-01-1 EVENT4 Rev.00
MAIN STEAM LINE LEAK Instructor Activities o When the crew has responded to the tube break and power is being maintained
<100%, initiate event trigger E4 to activate MSL brea o After the Turbine Building ARM alarms, call the Control Room as Turbine Building AO and report sound of steam leak on hot side, you cannot tell where fro Plant Response
[o Turbine Building ARM alarm (UA-3 5-7)
[o Turbine Building area temperatures rise toward Group 1 isolation setpoin o MSIVs fail to auto close when tunnel temp hi alarms are received (A-6 3-6 and 4-6).
Operator Activities SCO o Enter and direct activities of AOP-0 [o Direct evacuation of Turbine Buildin o Consider manual scram and MSIV closur o Direct manual scram and MSIV closure when tunnel hi temp alarms are receive RO o Monitor the plant
[o Reduce reactor power and/or scram reactor as directed by the SC [o Recognize report alarms A-6 3-6 and 4-6 (Hi Temp) and failure of MSIVs (Group 1)
to auto clos ol Insert manual scra o Recognize/report ATW BOP
"o Monitor the plan "o Report Turbine Building ARM alar [I Determine ARM readings (back panel).
[I Enter, announce and execute AOP-0 [I Evacuate Turbine Building as directed by SCO.
NRC-01-1 EVENTS Rev.00
MSIV CLOSURE FAILUREIINITIAL ATWS ACTIONS Instructor Activities
[o None Plant Response o] MSIVs fail to auto close on valid Group 1 signal, must be manually close [] Most Control Rods fail to inser o] Pressure rises rapidly lifting SRVs, initiating ARI and tripping Recirc Pump o RWCU fails to auto isolate when SLC is initiated Operator Activities SCO o Direct manual scram and closure of MSIV o Enter and direct EOP-01-RSP, transition to Level/Power Control EOP-01-LP o Direct Mode Switch to Shutdow [I Direct ARI initiated and Recirc Pumps trippe o Direct ADS inhibite o Direct pressure control using SRV o Direct initiation of SLC (prior to 11 0OF) and verification of RWCU (Group 3) isolatio o Direct LEP-02 performe o Transition to EOP-01-LP RO/BOP (Circle candidate performing action)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
(RO/BOP)
Diagnose failure of MSIVs to auto close and manually clos Recognize and report ATW Place Mode Switch to Shutdow Verify ARI initiated and Recirc pumps trippe Inhibit AD Operate SRVs to control pressure as directed by the SC Initiate SLC (prior to 110oF).
Manually isolate RWCU (Group 3).
Enter LEP-02 and drive control rods using RMCS:
Start 2nd CRD Pum Place CRD FCV in manual and open to establish drive pressur Bypass RW Select and drive rods using Emergency In.
NRC-01-1
0
0
0
0
EVENT-6 Rev.00
EVENT 7 LEVELIPOWER CONTROL ACTIONS Instructor Activities o If requested to install jumpers for LEP-02, Section 3, wait 3 minutes and insert MF RP005F (Auto Scram Defeat), and report jumpers installe o If requested as I&C to investigate RPS reset failure, acknowledge reques Plant Response 0l Suppression Pool starts heating up o Power remains above 4%.
El RCIC fails to initiate at LL2 Operator Activities SCO o Enter and execute EOP-01-LP "El Determine level >90" and power >4%.
"El Direct injection to the Reactor be terminated and prevented (HPCI and Condensate/Feedwater).
"o When level reaches +90", evaluate Table 3, if Table 3 not yet met, establish a level band of LL4 to +90". (may choose to not establish injection at this time if Table 3 conditions are imminent to prevent having to terminate and prevent injection a second time).
RO/BOP (Circle candidate performing action)
"El (RO/BOP) Terminate and prevent Condensate/Feedwater:
Trip Reactor Feed Pumps A and Close FW Heater outlet isolation valves FW-V6 and V "El (RO/BOP) Continue to drive control rods per LEP-0 [I (RO/BOP) Terminate and prevent HPCI:
If HPCI not running, place Aux Oil Pump to Pull-To-Loc If HPCI running, depress and hold Trip push button, when HPCI turbine speed reaches 0 RPM, place Aux Oil Pump to Pull-To-Lock, then release Trip push button and ensure E41-V8 & V9 remain close [o (RO/BOP) Continue to operate SRVs to control pressur (RO/BOP) If directed, control level as directed by SC [E (RO/BOP) Recognize failure of RCIC to auto start @ LL [E (RO/BOP) Manually start RCIC per the Hard Card if required for level control:
Open cooling valve E51-F04 Start vacuum pum Open steam supply E51-F04 Open injection valve E51-F01 Adjust Flow Control as needed.
NRC-01-1 Rev.00
EVENT 8 SUPPRESSION POOL TEMPERATURE >95oF Instructor Activities o If requested to defeat Drywell Cooler LOCA lockout, wait 3 minutes and execute batch file to defeat the LOCA lockou Plant Response
[I Suppression pool temperature continues to ris [o If level lowered to LL3, drywell temperature and pressure rises until drywell coolers restarte Operator Activities SCO
[I Enter and execute Primary Containment Control, EOP-02-PCC [I Direct actions to maximize suppression pool coolin RO/BOP (Circle candidate performing action)
[I (RO/BOP) Continue to insert control rod o (RO/BOP) Place both loops of RHR in suppression pool cooling per the Hard Car [I (RO/BOP) Continue to control reactor pressure.
NRC-01-1 Rev.00
EVENT 9 TABLE 3 CONDITIONS MET Instructor Activities o None Plant Response o Suppression pool temperature rises >1 10oF o] Reactor power remains >4%.
Operator Activities SCO o Determine level must be lowered until Table 3 conditions no longer me [o Direct injection be or remain terminate o] If LOCA signal received, direct Core Spray terminated and prevente [o If LOCA signal received, direct drywell cooling be restored per SEP-1 o Evaluate TAF and LL4 using Caution 1 graph RO/BOP (Circle candidate performing action)
"o (RO/BOP) Continue to drive control rods using RMCS
"o (RO/BOP) Monitor APRMs for downscale [o (RO/BOP) If necessary terminate and prevent HPC [o (RO/BOP) Override Core Spray pumps if LOCA signal receive [o (RO/BOP) Return RHR to Suppression Pool cooling if LOCA signal receive [o (RO/BOP) Continue to control pressure using SRV [I (RO/BOP) Monitor Reactor level for TAF.
NRC-01-1 Rev.00
EVENT 10 APRMs DOWNSCALE OR RPV LEVEL AT TAF Instructor Activities o If requested to defeat HPCI hi torus level transfer, wait 3 minutes and insert RF EPIAEOPJP4, and report HPCI hi torus level transfer defeate Plant Response o APRMs reading <4%, or RPV level at TA [I Based on power level if at TAF, HPCI may be required to maintain level above LL Operator Activities SCO
[o Direct injection be established to maintain RPV level LL4 to the level where APRMs downscales were received or TA o Determine level must remain in this band until SLC tank level @40% (or reactor shutdown under all conditions by control rod insertion).
RO/BOP (Circle candidate performing action)
o Report APRM downscales when i o Continue rod insertion per LEP-0 o Monitor SLC tank level and SLC operatio o Report level at TAF (if APRM downscales not in).
[o Operate HPCI and/or RCIC as required to maintain level between LL4 and the level to which it was lowere Continue to operate SRVs to control pressure.
NRC-01-1 Rev.00
EVENT 11 REACTOR LEVEL STABILIZEDICONTROL ROD INSERTION Instructor Activities 0 After level has been stabilized, if I&C has been requested to investigate RPS, delete switch override K2504A (RPS Reset) and report problem has been fixed (if asked a loose wire re-landed).
E] When RPS is reset, and scram discharge volume level is lowering, insert MFRP009F (ATWS #2), then delete MFRP011 F (ATWS #4).
o When RPS and ARI are reset for the 2nd time, and scram discharge volume level is lowering, insert MFRP008F (ATWS #1), then delete MFRP009F (ATWS #2).
Plant Response
[I Rod motion on manual scra Operator Activities SCO
[o Direct I&C to investigate RPS reset failur [o Exit LPC and enter RVCP and RS ol Direct level to be restored +170-200 inche o Direct cooldown be maintained <1 00oF/Hr during level restoratio RO/BOP (Circle candidate performing action)
o (RO/BOP) Enter LEP-02, Section 3:
Place ARI to INOP and rese Place SDV Test Switch to ISOLAT Attempt to reset RP Diagnose/report RPS reset logic failur When RPS repaired, reset RP Place SDV Test switch to NORMAL and ensure SDV vent & drain valves ope After 2 minutes, insert manual scra Recognize rod movement and repeat action Insert any remaining rods with RMC (RO/BOP) Report when all rods in (or all rods in but one).
[o (RO/BOP) Restore level +170-200 inches while maintaining cooldown <100oF/H o (RO/BOP) Terminate SLC operation.
NRC-01-1 Rev.00
TERMINATING CUE Instructor Activities
"© When level is being restored to normal band, the scenario may be terminate "© If desired, complete Administrative category A.4 (E-Plan) requirements with SRO.
NRC-01-1 Rev.00
Appendix D Scenario Outline Form ES-D-1 Facility:
Brunswick Scenario No.: NRC-2 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: The plant is operating at middle of cycle steady state condition Power is currently 75% per the Load Dispatchers request. CSW Pump 2C and SLC Pump 2A are under clearanc Turnover:
Maintain present power until contacted by the Load Dispatcher, then raise power at the Load Dispatchers reques Event Mal Event Event N N Type*
Description
NA R-RO Power increase at load dispatchers request I SRO
1 I-BOP Inadvertent HPCI initiation requires HPCI operation SRO terminated per AOP-0 C-RO Reactor Feed Pump trip places plant in restricted region of SRO power to flow map requiring exit per AOP-0 N-BOP Transfer BOP Buses 2C and 2D to the SAT per OP-50 SRO
4 C-BOP Failure of Air Compressor to load and standby Air SRO Compressors to auto star I-RO EHC pressure regulator fails high SRO
6 M-ALL SRV Fails Open, SRV Tail Pipe Ruptures
7 Containment spray logic fails
Pressure suppression pressure limit exceeded requiring emergency depressurization I_
_
I I
I L
Ij I
39 of 40 NUREG-1021, Revision 8, Supplement I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
SCENARIO DESCRIPTION The plant is operating at 75% power, middle of cycle with CSW Pump 2C and SLC Pump 2A under clearanc The crew will begin to raise power toward 100% per GP-1 When power has been increased to 80%, HPCI will inadvertently initiate. The crew will respond per AOP-03.0 and terminate HPCI operation. A scram on high flux may occur if HPCI is not terminated. HPCI will be declared Inoperable and Tech Specs addresse Reactor Feed Pump 2A will trip resulting in a Recirc runback to Limiter #2. The flow reduction will place the unit in the Restricted Region of the power to flow map. The crew will respond per AOP-23.0, AOP-04.0 and Tech Specs. Control rods must be inserted to exit the Restricted Regio A UAT ground alarm will be received and verified to be valid by maintenance. The crew will respond per the APP and transfer BOP Buses 2C and 2D to the SA Air Compressor D loading valve will fail and instrument air pressure will drop. Service Air will isolate and Air Compressors NB/C will fail to auto start. The crew should respond per AOP-20.0 and start Air Compressors NB/C. If the standby compressors are not started and air pressure continues to lower, feedwater flow will be lost to the RP The EHC pressure regulator will fail resulting in opening of Turbine Control and Bypass valves to the Max Combined Flow limit (110%). Steam line pressure drops to the MSIV isolation setpoint and the MSIVs close. The reactor fails to auto scram. Manual scram channel B push button will fail. ARI will fail to auto initiate on high RPV pressure. The rods can be inserted by placing the Mode Switch to Shutdown (steam flow is less than 3 mlb/hr due to the MSIV closure) or by manually initiating AR RPV pressure will spike high due to the MSIV closure and RPS failure. SRVs will lift on high pressure. SRV F will fail to reclose when rods are inserted and RPV pressure lowers. The tail pipe on SRV F will rupture in the suppression chamber airspace shortly after the valve sticks open resulting in rapidly rising containment pressure and temperatur Feed flow is lost to the RPV due to MSIV closure. HPCI may be manually started to restore RPV level but will fail shortly after being starte If containment spray is attempted the logic will fail. Suppression chamber pressure will rise above the safe value for Pressure Suppression Pressure requiring emergency depressurization. Low pressure ECCS and Condensate must be operated during depressurization to prevent uncontrolled injectio When the reactor has been depressurized, the scenario may be terminated.
NRC-01-2 Rev.00
OBJECTIVES SRO 344205B402, Direct Shift Response To A Moderator Temperature Decrease Per AOP-0 B402, Direct Action For Condensate/Feedwater System Failures Per AOP 2 B402, Direct Shift Response To A Recirculation Flow Control Failure Causing A Decreasing Flow Per AOP-0 B402, Direct Actions For Pneumatic Air System Failures Per AOP-2 B402, Direct Actions For Safety/Relief Valve Failures Per AOP-3 B502, Direct Actions To Control RPV Level Per EOP-01-RVCP 344220B502, Direct Actions To Emergency Depressurize The RPV Per EOP-01 RVCP 344214B502, Direct Actions To Control Primary Containment Pressure Per EOP-02 PCCP 344216B502, Direct Actions To Control Suppression Pool Temperature Per EOP 02-PCCP RO 202002B1301, Increase Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Stations Per OP-02 200210B401, Respond To A Moderator Temperature Decrease Per AOP-0 B401, Respond To A Condensate/Feedwater System Failure Per AOP-23 202014B401, Respond To A Recirc Flow Control Failure Decreasing Per AOP-0 B1301, Transfer Auxiliary Power From The SAT To The UAT Per OP-50 248002B401, Respond to an EHC failure causing Low Reactor Pressure 239008B401, Respond To An SRV Failure Per AOP-3 B501, Operate ADS/SRVs To Emergency Depressurize The Reactor Per EOP-01-RVCP 205014B101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 NRC-01-2 Rev.00
SIMULATOR SETUP Initial Conditions IC Rx Power Core Age Event Triggers
75%
MOC Malfunctions Event System Tag Title Value Activate Deactivate (Ramp)
Time Time El ES ES014F Inadvertent HPCI NA 0 SEC NA E2 CF CF036F RFP A Low Suct Press NA 0 SEC NA E4 IA IA009F Air Compr D Fails To Load NA 0 SEC NA E5 MS MS003 Press Reg Fails High NA 0 SEC NA F
.E5 RP RP005F Auto Scram Defeat NA 0 SEC NA E6 ES ES004F SRV F Fails Open NA 0 SEC NA E6 CA CA020F SRV F Broke Tailpipe NA 60 SEC NA E8 ES ES015F HPCI Power Supply Loss NA 0 SEC NA NRC-01-2 Event Trigger Description El Manually Initiated (HPCI Initiation)
E2 Manually Initiated (RFP A Trips)
E3 Manually Initiated (UAT Winding Y Ground)
E4 Manually Initiated (Air Compressor D Fails)
E5 Manually Initiated (EHC Regulator Fails High)
E6 Auto Initiated (SRV F Red = TRUE)
E7 Auto Initiated (ARI Keylock Switch = TRIP)
E8 Manually Initiated (HPCI Power Supply Loss)
Rev.00
Overrides Switches Event Panel Tag Title Value Activate Deactivate (Ramp)
Time Time A
XU-2 K4A01A Air Compr A Auto OFF 0 SEC NA A
XU-2 K4A02A Air Compr B Auto OFF 0 SEC NA A
XU-2 K4AO3A Air Compr C Auto OFF 0 SEC NA A
P603 K2625A ARI CS-5560 INOP 0 SEC NA A
P603 K2503A Rx Manual Scram B OFF 0 SEC NA A
P601 K1227A Cont Spray A Control AS IS 0 SEC NA A
P601 K1727A Cont Spray B Control AS IS 0 SEC NA Lamps Event Panel Tag Title Value Activate Deactivate (Ramp)
Time Time A
P603 Q2625SRE ARI Inop White OFF 0 SEC NA A
P603 Q2625SWE ARI Auto Green ON 0 SEC NA Alarms Event Panel Tag Title Value Activate Deactivate (Ramp)
Time Time E3 XU-1 ZUA1 3210 UAT Winding Y Ground ON 0 SEC NA Remote Functions Event System Tag Title Status Activate A
ED IABKCF DC Fuses CSW Pump 2A OUT 0 SEC A
SL IASLRA SLC Pump A Motor Breaker OPEN 0 SEC Materials ENP-24 for IC-13 NRC-01-2 Rev.00
SPECIAL INSTRUCTIONS Ensure exam security requirements are me Reduce power to 75%, allow conditions to stabilize, zero DVM and adjust APRM GAFs (activate GAF Pots under NI Remote Function).
Advance all chart recorders to indicate steady state condition Place all SPDS displays to the Critical Plant Variable display (#100).
Ensure appropriate keys have blanks in switche Exit shutdown screen on RWM and place the RWM key in the key locke Reset alarms on SJAE, MSL and RWM NUMAC Ensure reference material is in appropriate locatio Verify all logbooks have blank sheets onl Load malfunctions/override In expert command line enter "trc:7, did:k2625a" (unless loaded in CAE file).
Load CAE file if availabl Place red caps on CSW Pump 2C control switch and SLC Pump 2A indicating ligh Ensure ENP-24 for IC-13 @ P603.
NRC-01-2 Rev.00
SHIFT BRIEFING Plant Status The plant is operating at approximately 75% power, 166 days following refueling (middle of cycle). Power is currently being held at 75% per the Load Dispatcher's directio Equipment Out Of Service CSW Pump 2C is under clearance for routine maintenance and will remain out of service this shif SLC Pump 2A is under clearance after tripping during a PT last shift. Maintenance is investigating the cause of the tri No other equipment is out of servic Plan of the Day Maintain 75% power until contacted by the Load Dispatcher, then raise power to 100% per GP-12. The Load Dispatcher is expected to request power ascension shortly after shift turnover is complet No other activities are scheduled for this shift.
NRC-01-2 Rev.00
SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Revision 8, ES-301 and Appendix During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with NUREG-1021, ES-30 Common Student Problems/Errors None noted to dat Simulator Deficiencies There are no known simulator deficiencies applicable to this scenari Critical Tasks Insert control rods by placing the Mode Switch to Shutdown or by manually initiating AR Emergency depressurize the reactor when suppression chamber pressure cannot be maintained in the Safe region of the Pressure Suppression Pressure Limi Reason For Revision New scenario developed for HLC 2001 NRC exam.
NRC-01-2 Rev.00
SIMULATOR SCENARIO SHIFT TURNOVER Instructor Activities o Set up the simulator per the setu Plant Response 0l Operator Activities SCO
[I Conduct shift turnover shift briefin RO El Perform board walk-dow [E Monitor the plant BOP
[I Perform board walk-dow l Monitor the plant.
NRC-01-2 Rev.00
EVENT I POWER INCREASE Instructor Activities o3 When the crew has the watch, call control room as load dispatcher and request BNP2 raise power to 100%.
o If contacted as NE report rods at desired pattern and power should be raised to 100% using flo o Ensure RO (Not the BOP) performs alternate power verification at 80% per GP-1 Plant Response
Operator Activities SCO
"o Direct power be raised using Recirc flow per GP-1 "o Direct alternate power verification at 80% powe RO
"0 Raise reactor power by increasing Recirc flow per GP-12 and OP-0 "o Perform alternate power verification per GP-1 BOP 0 Monitor the plant.
Rev.00 NRC-01-2
EVENT 2 HPCI INITIATION Instructor Activities
"o While the RO is performing the alternate power verification at 80%, initiate Trigger El to initiate the HPCI syste "o If asked as I&C to investigate, acknowledge the reques Plant Response
"o HPCI Initiation causes power to rise if HPCI is allowed to inject to the RP "o HPCI Low Flow (A-1 1-4) alarms 15 seconds after steam supply (E41-FO01) begins to ope Operator Activities SCO
"o Direct entry into AOP-0 "o Direct termination of HPCI operatio "o Direct reduction of reactor power if necessary to prevent a scra "o Contact I&C to investigate HPCI failur "o Refer to Tech Spec 3.5.1. Determine Action D applies (Verify RCIC Operable and restore HPCI to Operable within 14 days).
"o Refer to 01-01.07 and determine reportability requirements (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for loss of single train, item 3.4 on Attachment 1).
"o Reduce reactor power as required to prevent a reactor scram if directed by the SCO
"o Monitor the plan BOP o Diagnose and report inadvertent HPCI initiatio o Enter and announce AOP-0 Verify by two independent methods the initiation is not valid and terminate HPCI operation as follows:
Depress and hold turbine trip push butto When HPCI turbine coasts to 0 RPM, place Aux Oil Pump to Pull-To-Loc Release trip push button and ensure HPCI remains shutdown.
NRC-01-2 Rev.00
EVENT 3 RFPT TRIP Instructor Activities
"o When actions for the inadvertent HPCI initiation are complete, initiate Trigger E2 to activate the RFP A tri "El If asked as TBAO to investigate, report nothing apparent you can se "El If asked as I&C to investigate, acknowledge the reques Plant Response El Reactor Water Level Hi/Lo (A-7 2-2) alarms and recirc runs back to limiter # El APRM Upscale alarms (A-6 2-8) indicating entry into the restricted region of the power to flow ma El Plant operating in Monitored Region after Restricted Region exi Operator Activities El SCO El Direct entry into AOP-2 El Direct entry into AOP-0 El Contact I&C to investigate RFPT tri "El Determine region of operation per COLR power to flow ma "El Direct control rod insertion per ENP-24 to exit the restricted regio El Ensure Tech Spec requirements met for Restricted/Monitored Region entry (TS 3.2.3 for FCCB determine FCCB within 15 minutes or exit restricted region, TS 3.3.1.3 for PBDS-required in Restricted or Monitored Regions - NOTE: Tech Spec actions contained in AOP-04.0).
[o Recognize and report runback to Limiter # J Ensure RFP B responds to restore and maintain RPV leve ol Recognize and report APRM Upscale alarm (Restricted Region Entry Alarm).
[I Monitor for indications of Thermal Hydraulic Instability (THI).
[o Insert control rods per ENP-24 to exit restricted regio BOP El Recognize and announce RFPT tri El Enter and announce AOP-2 El Enter and announce AOP-0 El Determine region of operation per COLR power to flow ma El Execute Core Mon to determine FCCB.
Rev.00 NRC-01-2
EVENT 4 BOP BUS TRANSFER Instructor Activities o When the restricted region has been exited, initiate Trigger E3 to activate UAT Ground alar o If contacted as TBAO, report no ground relays are picked up on Bus 2C or 2 o If contacted as I&C to investigate, report ground relay for UAT is picked up and the ground alarm is vali Plant Response o UA-13 2-10, UAT Winding Y Ground alar Operator Activities SCO o Direct actions of APP UA-13 2-1 o Direct I&C to investigate if ground alarm is vali Direct transfer of Buses 2C and 2D from UAT to SAT per OP-5 RO o Monitor the plan BOP El Enter APP UA-13 2-1 o Direct AO to check Buses 2C and 2D for ground indication Transfer BOP Buses 2C and 2D from UAT to SAT per OP-50:
For Bus 2C and 2D, turn sync switch on for SAT supply breake Close SAT supply breaker and verify UAT supply breaker open Turn SAT supply breaker sync switch off.
NRC-01-2 Rev.00
AIR COMPRESSOR D FAILS Instructor Activities o When the crew has transferred BOP Buses 2C and 2D to the SAT, initiate Trigger E4 to fail Air Compressor o If asked to investigate, report Air Compressor D is running unloaded and will not load. Report no indications of any air leak o If requested to reset service air isolation, modify Remote Function AIIAA1706, RESET Eo If requested, as Unit I grant permission to crosstie air if Unit 2 is sure there are no air leaks, if directed to open service air crosstie, wait 2 minutes and modify Remote Function AIVHAI007L, OPE Plant Response o Air header pressure lower o Air Compressors A, B & C fail to start, can be manually started (should start at,1 10 psig).
o Service Air Low Pressure (UA-1 5-4) alarms at 107 psi o When pressure lowers to 105 psig, service air isolate ol If pressure drops to 100 psig, Instrument Air Low Pressure (UA-1 4-4) alarm o If air pressure not restored, Condensate/Feedwater recirc valves fail open and Feedwater is los Operator Activities SCO o Direct entry into AOP-2 Direct verification of automatic action o Direct Air Compressors A/B/C be manually started (may also choose to direct service air crosstie).
o Direct Service Air restore o Direct I&C to investigate air compressor failure RO
[] Monitor the plan BOP
[I Recognize/report lowering air header pressur El Enter/announce AOP-2 El Verify auto action El Manually start air compressors NB/ El Dispatch AO to investigat El Direct AO to reset service air isolatio If directed, direct crosstie of service air.
NRC-01-2 EVENT5 Rev.00
EHC FAILUREIELECTRICAL ATWS Instructor Activities o When the crew has responded to the air compressor failure, initiate Trigger E5 to fail EH o Monitor SRV operation (panel mimics). If SRV F does not open to control pressure, manually initiate E Plant Response
[o Turbine and bypass valves open to Max Combined flow limit (110%).
[o Steam line pressure lowers to 850 psig closing MSIVs (Group 1).
0l Pressure rapidly rises lifting SRV o RPS fails to initiate an auto scra o ARI fails to auto actuate on high pressur El RPS manual scram B push button fail o SRV F fails to close after openin El Rods inserted by placing Mode Switch to Shutdown or by manually initiating AR Operator Activities SCO
[] Enter and direct scram procedure, EOP-01-RS El If rods not yet inserted, transition to Level/Power Control, EOP-01-LP El Direct manual scra Direct Mode Switch to Shutdown when steam flow is <3 mlb/h [I If EOP-01-LPC has been entered, when control rods inserted, exit LPC and enter Reactor Vessel Control Procedure, EOP-01-RVC RO
"El Diagnose and report loss of EHC pressure contro "El Recognize MSIV closure and failure to auto scram, insert manual reactor scra "El Recognize/report failure of RPS manual scra [E Place Mode Switch to Shutdown and/or manually initiate AR El Recognize and report when control rods are inserte BOP
[E Diagnose and report failed open SRV and perform actions of AOP-30 (cycle control switch several times leaving switch in CLOSE).
NRC-01-2 EVENT6 Rev.00
BROKEN SRV TAILPIPE Instructor Activities o If requested as I&C to investigate spray logic, acknowledge the reques o After HPCI is started, wait approximately 30 seconds and initiate Trigger E8 to fail HPCI controller power suppl ol If asked as I&C to investigate HPCI power loss, acknowledge the reques Plant Response
[o SRV F tail pipe ruptures in the suppression chamber air space 1 minute after openin [I HPCI available for injection by taking Aux Oil Pump out of Pull-To-Loc o] Suppression chamber and drywell pressure rapidly ris [o Suppression chamber pressure leads drywell pressure and torus-drywell vacuum breakers lifting indicate broken SRV tailpip [o RHR unavailable for spray due to failure of spray logi ol Pressure suppression pressure limit is exceede Operator Activities SCO El Enter Reactor Vessel Control Procedure, EOP-01-RVCP (if not already entered) and Primary Containment Control Procedure, EOP-02-PCC o Direct RPV level be restored and maintained +170-200".
o Direct initiation of suppression chamber spra o Direct initiation of drywell spra o Direct I&C to investigate failure of spray logi [
Determine leak is in suppression chamber based on higher suppression chamber pressure and/or vacuum breaker operatio [o When PSPL exceeded, determine emergency depressurization is require RO/BOP (Circle candidate performing action)
[o (RO/BOP) Start HPCI (start Aux Oil Pump) to restore and maintain RPV level +170 200".
[o (RO/BOP) Diagnose and report rapidly rising containment pressure (RO/BOP) Determine leak is in suppression chamber based on higher suppression chamber pressure and/or vacuum breaker operatio o (RO/BOP) Attempt to initiate spray per SEP-02 and/or SEP-0 o (RO/BOP) Diagnose and report failure of RHR Loop A and/or B spray logi (RO/BOP) Diagnose and report failure of HPCI controller power supply.
NRC-01-2 EVENT7 Rev.00
EVENT 8 EMERGENCY DEPRESSURIZATION Instructor Activities o After ADS valves have been opened, if both spray logics have not yet been attempted, delete switch override on spray logic not yet attempted, or if I&C has been directed to investigate RHR spray logic, delete switch override K1227A or K1727A and report logic repaire Plant Response
[o RCIC may trip due to elevated suppression chamber pressur [o Low pressure ECCS initiates when RPV pressure drops below 410 psig (Core Spray injects at 300 psig, RHR injects at 200 psig).
o Condensate begins to inject at approximately 400 psig if FW-V6 and FW-V8 (Feedwater Heater outlet isolation valves) are not close Operator Activities SCO
"o Direct low pressure ECCS be operated to prevent uncontrolled injectio "o Direct Condensate be operated to prevent uncontrolled injectio [o Direct 7 ADS valves opene RO/BOP (Circle candidate performing action)
[o (RO/BOP) Open 7 ADS valve (RO/BOP) Override RHR and Core Spray Pumps off when RPV pressure drops below 410 psig if injection is not required for RPV level contro [o (RO/BOP) Verify LOCA actuation [I (RO/BOP) Operate the condensate system to prevent uncontrolled injection (close FW-V6 and FW-V8).
NRC-01-2 Rev.00
REACTOR DEPRESSURIZED Instructor Activities
[] None Plant Response ol RHR Outboard Injection valves E11-F017A/B can be closed 5 minutes after openin [o Only one loop of RHR available for containment cooling/spray since a LPCI signal present and one loop's spray logic is faile Operator Activities SCO o Direct RPV level be maintained +170-200".
o Direct RHR be placed in drywell and suppression chamber spray when injection valves E 11-F017A and/or B can be closed (whichever loop has spray logic).
o Refer to Caution 1 for level instrument operabilit [o As time permits direct placing H2/02 monitors (4409 & 4410) in servic RO/BOP (Circle candidate performing action)
[o (RO/BOP) Operate available injection systems (Condensate, RHR, Core Spray) to maintain +170-200".
0 (RO/BOP) Place RHR Loop A(B) into drywell and suppression chamber spray per SEP-02 and SEP-03:
Close E 11-F017A(B).
Verify Drywell Coolers and Recirc Pumps trippe Place "Think Switch" to Manua Start RHR Pum Verify safe region of spray initiation limit and torus level <+21".
Open El 1-F021A(B).
Open El 1-F016 A(B). to establish flow 8000-10,000 GPM-(drywell spray)
Start RHR Service Water (open service water supply valve, place LPCI override switch to override, start RHR SW Pumps and throttle open El 1-F068A or B (4000 GPM max - 1 pump, 8000 GPM max - 2 pump).
Close RHR HX Bypass El 1-F048A(B).
Open E 11-F028 A(B) and E 11-F027A(B) (torus spray - SEP-03)
Eo (RO/BOP) If directed, place H2/02 (4409 & 4410) monitors in service.
NRC-01-2 EVENT9 Rev.00
TERMINATING CUE Instructor Activities
© When the Reactor has been depressurized, the scenario may be terminate © If desired, complete Administrative Category A.4 (E Plan) requirements with the SRO.
NRC-01-2 Rev.00 19