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: 1 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.1.a Task Title: Evaluate Overtime Eligibility.
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 A.1 .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 satisfied.
TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outage.
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
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 satisfied.
TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outage.
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 I SAT/UNSAT 1 Obtain a current Current Revision of OAP-001 revision of OAP-001 obtained 2 Evaluate Operator 1 Determine Operator #1 exceeded: Critical *
1. >24 in 48 (wed - thur)
2. > 72 in 7 days 4 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)
Appendix C Job Performance Measure Form ES-C-1 Wn rk.*h*pt Worksheet 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: NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom XX Simulator _ Plant Required Materials: General References:
Process Computer 201-03.2 Rev. 67 Calculator Unit 2 Technical Specifications LOT-SIM-JP-201 -D07 Time Critical Task: YES/N.OO Validation Time: RO - 10 Min, SRO - 15 Min
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 satisfied.
TASK CONDITIONS: You are a Unit Two (2) Reactor Operator. The load dispatcher has informed the Control Room that system reserve is low. The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-29.0. Buses Common A and B are being supplied by their respective Unit power. Unit 2 is in Mode 1.
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 satisfied.
TASK CONDITIONS: You are a Unit Two (2) Reactor Operator. The load dispatcher has informed the Control Room that system reserve is low. The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-29.0. Buses Common A and B are being supplied by their respective Unit power. Unit 2 is in Mode 1.
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.
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 Applicant Performance: SAT/UNSAT
Appendix C 2 Form ES-C-1 PERFORMANCE INFORMATION Task Description Standard Sat/U nsat 1 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 runnin NSW 2A or 2 Task Description Standard Sat/Unsat 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).
8 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 inoperable.
NOTE: IF THE EXAMINEE IS AN RO, THE JPM IS COMPLETE AT THIS TIME.
PROMPT: Ifthe 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 C.
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 complet .00 U2EDE037 334.20 A 160 .0 U2EDE008 1294.7 A U2EDE013 1777.3 A 0.00 0.0 0 0.0 0 08:34:34 09:34:34 07:34:44 m OK TRN TE4 3FAT 1 AIE 15 "U 17 MONT H I_
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: A.2 Task Title: Evaluate SRM / IRM Overlap.
K/A Reference: 2.2.30 (3.5/3.3) Knowledge of RO duties in the control room during startup activities.
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 satisfied.
TASK CONDITIONS:
1. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserted.
2. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings IRM Indicated Readings A 120 cps A 1/40, Range 1 B 110 cps B 1/40, Range 1 C 140 cps C 2/40, Range 1 D 110 cps 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 IRM Indicated Readings A 5 x 102 cps A 5/40, Range 1 B 5 x 104 cps B 4/40, Range 1 C 5 x 105 cps C 2/40, Range 1 D 5 x 104 cps 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 satisfied.
TASK CONDITIONS:
4. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserted.
5. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings IRM Indicated Readings A 120 cps A 1/40, Range B 110 cps B 1/40, Range C 140 cps C 2/40, Range D 110 cps D 1/40, Range E 2/40, Range F 1/40, Range G 1/40, Range H 2/40, Range 6. Following control rod withdrawal to criticality the following SRM and IRM count rates are observed:
SRM Indicated Readings IRM Indicated Readings A 5 x 102 cps A 5/40, Range 1 B 5 x 103 cps B 4/40, Range 1 C 5 x 104 cps C 2/40, Range 1 D 5 x 103 cps 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: A.3 Task Title: Estimate Source Term for a Release from the Main Stack per PEP-03.6.1.
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 cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
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-01.
2. 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 Release.
3. The Main Stack flow transmitter (2-VA-FT-3359) is not operational. Main Stack flow indication is not available.
4. 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 satisfied.
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-01.
2. 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 Release.
3. The Main Stack flow transmitter (2-VA-FT-3359) is not operational. Main Stack flow indication is not available.
4. 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 A.
5. Unit One (1) releases to the Main Stack consist of two drywell purge fans in operation and one Standby Gas Train (A) in operation.
6. Plant common releases to the Main Stack consist of AOG Building Ventilation and one Radwaste Exhaust Fan (B) in operation.
7. 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 1 Obtain current revision of PEP- Current Revision of OPEP03. . obtained 2 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 5 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 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 Job Performance Measure Form ES-C-1 Worksheet No: BRUNSWICK Facility:
Facility:
Task 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:_____ ____ 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:
001-01.07, Rev 10 SRR-OJT-JP-201-D09 Time Critical Task: YES/NOV Validation Time: 10 Mi 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 satisfied.
TASK CONDITIONS:
1. Unit One (1) was operating at rated power.
2. 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 band.
3. 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 spray.
5. 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 failure.
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 cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
TASK CONDITIONS:
1. Unit One (1) was operating at rated power.
2. 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 band.
3. 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 spray.
5. 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 failure.
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 3 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 results.
Pass/fail criteria: Applicant must get step 5 correct; AND must get 10 of the 12 items correct on the reportability evaluation check lis . TR N PLO MEIU 1s GOP3 N IM I
[m1 300.00 U2ED _E037 1600 .0 334.20 A 200 U2ED E008 1294.7 A U2ED_ E013 1777.3 A 0.00 0 .00 0.00 07:34:44 08:34:34 09 34 34 OK TREND 3 TREND FAST BAS HOUR c 4 GROUPS I2 WINDONS 13 1 1 se 1 10 min - p y Na
Administrative Topics Outline Form ES-301-1 ES-301 Facility: BRUNSWICK Date of Examination:7130-813101 Operating Test Number: 1 Examination Level (circle one): RO / SRQ 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.l.a Task Title: Evaluate Overtime Eligibility.
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 Time Critical Task: YES/NO Validation Time: 10 Mi 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 satisfied.
TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outage.
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
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 satisfied.
TASK CONDITIONS:
The following is the schedule of 2 operators for a seven day period during the spring outage.
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 Determine Operator #1 exceeded: Critical*
2 Evaluate Operator I 1. >24 in 48 (wed - thur)
2. > 72 in 7 days exceeded: Critical *
< 8 hr break Determine (mon #2 Operator - tue)
4 Evaluate Operator 2 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)
Job Performance Measure Form ES-C-1 Appendix C Wnrk.*hAet Worksheet 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)
NRC Examiner:
Examinee:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom XX Simula tor Plant Required Materials: General References:
201-03.2 Rev. 67 Process Computer Unit 2 Technical Specifications Calculator LOT-SIM-JP-201-D07 Time Critical Task: YESINO Validation Time: RO - 10 Min, SRO - 15 Min
A.1 .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 satisfied.
TASK CONDITIONS: You are a Unit Two (2) Reactor Operator. The load dispatcher has informed the Control Room that system reserve is low. The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-29.0. Buses Common A and B are being supplied by their respective Unit power. Unit 2 is in Mode 1.
INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits Unit established in the CO Daily Surveillance Report (DSR), and report the required actions for READ TO THE EXAMINEE initiating cues. When I will explain the initial conditions, which steps to simulate or discuss, and provide measure will be satisfied.
you complete the task successfully, the objective for this job performance TASK CONDITIONS: You are a Unit Two (2) Reactor Operator. The load dispatcher has informed the Control Room that system reserve is low. The fourth Circulating Water Intake Pump has been started on Unit Two (2) per guidance of 20P-29.0. Buses Common A and B are being supplied by their respective Unit power. Unit 2 is in Mode INITIATING CUE:
You are directed by the Unit SCO to determine if electrical loading is within the limits actions for Unit established in the CO Daily Surveillance Report (DSR), and report the required Task Standard:
Tech Spec Supervisor informed SAT is inoperable. If Applicant is an SRO, determine that actions are applicable per LCO 3.8.1. Action Applicant Performance: SAT/UNSAT
2 Form ES-C-1 Appendix C PERFORMANCE INFORMATION Task Description Standard Sat/Unsat 1 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 determinedusing 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 by the E4 and is currently running for a PT on Unit I and that NSW 2B is running as indicated 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 NSW 2A is NOT running and NSW SaVUnsat Task Descriotion Standard Sat/Unsat 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 Ls runnin Determine total amperage limi Total allowable load limit is 3389 amps (3315 + 40+34).
Determines total load of 340 Critical 8 Determine current load exceeds the allowable limit and exceeds limit of 3389 and that SAT is that the SAT shall be ino considered inoperabl Supervisor informed SAT is inoperable.
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 at this time)
Technical Specifications for the current condition (no other equipment inoperable correct breaker Determines that LCO 3.8.1 Action C applies requiring performance of SR 3.8.1.1.,
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 /> alignments and indicated thereafte from offsite NOTE: Required Action C.2 only applies if one 4 KV E Bus can not be supplied power. It does not apply in this cas offsite circuit to Determines that LCO 3.8.1 Action C.3 applies, requiring restoration of the inoperable 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 10 applicable per LCO 3.8.1. Action and the SRO has TERMINATING CUE: When the RO has determined that the SAT Is inoperable, determined the required Tech Spec actions, this JPM is complet TR N LTMDU 0 GR U 32 AG BNPSI 72-010:43 300.00 U2EDE037 160 .20 A 200 _ UZEDE008 1294.7 A U2EDE013 1777.3 A 0.00 0.00 0.00 I
08:34:34 09:34 :34 OK 07:34:44 1 GR01UPS TRE ID 12 3 TREND 13 WINDCWS 1FASTC se 14 10 BASE 5 Ho WjIý 8 RN SIF nu
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: A.2 Task Title: Evaluate SRM I IRM Overlap.
startup KIA Reference: 2.2.30 (3.5/3.3) Knowledge of RO duties in the control room during activities.
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 satisfied.
TASK CONDITIONS:
1. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserted.
2. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in the Rector Operating Log are as follows:
SRM Indicated Readings IRM Indicated Readings 120 cps A 1/40, Range 1 A
110 cps B 1/40, Range 1 B
140 cps C 2/40, Range 1 C
110 cps D 1/40, Range 1 D
E 2/40, Range 1 F 1/40, Range 1 G 1/40, Range 1 H 2/40, Range 1 rates are 3. Following control rod withdrawal to criticality the following SRM and IRM count observed:
SRM Indicated Readings IRM Indicated Readings 5x102cps A 5/40, Range 1 A
5x 4 cps B 4/40, Range 1 B
5x10 5 cps C 2/40, Range 1 C
5x 4 cps D 6/40, Range 1 D
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 satisfied.
TASK CONDITIONS:
4. Unit startup is in progress per OGP-02 with SRMs and IRMs fully inserte the Rector 5. Prior to control rod withdrawal, SRM and IRM indicated readings recorded in Operating Log are as follows:
SRM Indicated Readings IRM Indicated Readings 120 cps A 1/40, Range 1 A
B 1/40, Range 1 B 110 cps 140 cps C 2/40, Range 1 C
110 cps D 1/40, Range 1 D
E 2/40, Range 1 F 1/40, Range 1 G 1/40, Range 1 H 2/40, Range 1 the following SRM and IRM count rates are 6. Following control rod withdrawal to criticality observed:
SRM Indicated Readings IRM Indicated Readings A 5/40, Range 1 A 5x102cps B 4/40, Range 1 B 5 x 103 cps C 2/40, Range 1 C 5x104cps D 6/40, Range 1 D 5x103cps E 3/40, Range 1 F 6/40, Range 1 G 4/40, Range 1 H 5/40, Range 1 INITIATING CUE:
tech Assess the above SRM and IRM indications for proper overlap and determine applicable spec action(s) and whether the unit startup may continu TASK STANDARD:
1. Determines IRMs "C" and "E" are inoperable. (SRO ONLY)
place inoperable 2. Tech Spec table 3.3.1.1-1 item la. not met. Per LCO 3.3.1.1 Condition A, 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)
and notification of 3. Procedure OGP-02 Caution prior to step 5.2.18 requires a reactor shutdown reactor engineer. (RO and SRO)
SATIUNSAT
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: A.3 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 authorized.
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 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 satisfied.
TASK CONDITIONS:
After Unit One refueling outage the 1B 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 1Description I Dose 1 CP&L Employee whose doses (CP&L and non- 1800 mrem TEDE CP&L) for the current are known 2 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 _
3 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 I BRUNSWICK NUCLEAR PLANT RADIOLOGICAL SURVEY SURVEY N TRN01 - 1099 7-26-01 0812 DOSE RATE CONTAMINATION DATE: TIME: RO-2 A El ct E] gr" ego Philip A. DeFoggi INST. TYPE SURVEYOR (SERIAL NO. TRN1245 N/A N/A NA SURVEYORE P FACTOR 4- Unbagged INST/SN S~viG=lNATURE RX POWER 100%_____39 H"_ EF CPM 391CPMj REVIEWED ______________
, -tkx H2SCFM _.BKGD._______
U 1- L 5 A RWCU PUMP ROOMS N/A EL AREA RWP N UNITL- BLDG -B -0 N/A N/A WR/JO COMPONENT OR TAG N SMEAR RESULTS 2 WORK PERFORMED Routine Radiation Survey IN DPMI100 CM B=BETA IN mRAD/HR/100CM 2 M=CPMI/MASLIN N RESULTS N/A N/A Training Use Only!
RA -RADIATION AREA CA -CONTAMINATION AREA HCA -HIGH CONTAMINATION AREA DOSE RATES IN mR/HR HRA -HIGH RADIATION AREA AA -AIRBORNE AREA LHRA -LOCKED HIGH RADIATION AREA n o -NEUTRON (mRem/Hr)
RCA -RADIATION CONTROL AREA S- ROPE BOUNDARY
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 satisfied.
TASK CONDITIONS:
north end of After Unit One refueling outage the 1B RWCU pump requires maintenance on the the pump. Two mechanics have been assigned the tas Listed below is the workers accumulated yearly dose following the refueling outag Worker Description Dose 1 CP&L Employee whose doses (CP&L and non- 1800 mrem TEDE CP&L) for the current are known 2 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 3 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:
in the area to Using the survey map provided calculate how long each worker may remain Assume no dose limit perform the maintenance before reaching the administrative exposure is received in transit to the work are Task Standard:
Each Maintenance workers maximum stay time calculate Step Description Standard I SATIUNSAT 0 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 2 Determine stay time 500 mrem admin limit - 350 Critical for worker #2 mrem = 150 mrem 150 mrem/45 mrem/hr = 3.33 hrs 3 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: A.4 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 implementation.
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 Applicant Sheet Iwill 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 satisfied.
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 satisfied.
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 a and safety-related systems. In addition to structural damage, both units have tripped off-line 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:
you The Shift Superintendent has prepared the appropriate notification forms and has directed to and to make notifications to the State and Counties, the Nuclear Regulatory Commission, OPE initiate Emergency Response Organization callout in accordance with the appropriate where For each of these tasks, identify the way you would make the specified notification and, 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 7 (SROU) Place The Master Feedwater Controller In Service Per M,S,A 2 GP-02 (SROU) Emergency Equalization Around MSIV's - Anticipate D,C,L 3 Emergency Depressurization (SROU) Establish UAT Backfeed D,S 6 HPCI Start Using the "Hard Card" - Steam Line Break D,S,A 4 With Auto Isolation Failure Recirculation Pump Start - Recirculation Pump Speed D,S,A 1 Control Failure (pressure control) Install Circuit Alterations For Drywell Cooling Per AOP- D,C 5 3 B.2 Facility Walk-Through Control Room Evacuation - AOP-32 - Scram and MSIV D, R 1 Closure From Outside the Control Room (SROU) Resetting a RCIC Mechanical Overspeed Trip (SROU) D 4 Perform Actions Associated With Fires - Aligning the D 8 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
1S-301 Administrative Topics Outline Form ES-301 -1 ES-301 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 satisfied.
TASK CONDITIONS: An RPS MG Set B spurious trip has occurred. No scram signal is present on RPS Bus A. No Tracking LCO exist on RPS EPA Breakers.
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.1.a 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 satisfied.
Initiating Cue: An RPS MG Set B spurious trip has occurred. No scram signal is present on RPS Bus A. No Tracking LCO exist on RPS EPA Breakers.
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 complete.
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 TRIP. Perform necessary actions to stabalize the plant following the loss of RPS Bus B. Acknowledge alarms. RPS ALT Supply EPA breakers #5 and #6 and RPS ALT POWER SOURCE are positioned as required via Remote Functions when requested. Automatic scram prevented, manual scram possible.
Required Materials: General References:
NONE 20P-03.0, Rev. 37 Modified LOR-SIM-JP-003-AO3 Time Critical Task: YES/NO Validation Time: 10 Mi Appendix C 2 Form ES-C-1 PERFORMANCE INFORMATION Task Description Standard Sat/Unsat 1 Obtain current revision of 20P-03 Current revision of 20P-03 is reference Determine RPS Alternate Power Recognize RPS Alternate Power source must be transferre 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 Contact AO to open EPA #6 and EPA AO directed to place EPA breakers #6
- 5 breaker and #5 to OF Direct AO to transfer RPS Alternate Direct transfer of RPS Alternate Power Critical Power Throwover Switch to Alternat Throwover Switch to Alternat Direct AO to Close EPA breakers #5 Direct EPA breakers #5 and #6 Critical and #6 per OP-0 CLOSED per OP-0 Verify white ALT light above the RPS RPS ALT Power available (center Power Source Select Switch is o white light) on Panel P610 is o Proc step 8.5.10 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 rese PLACE RPS POWER SOURCE RPS POWER SOURCE SELECT Critical SELECT SWITCH on P610 to ALT SWITCH on P610 placed to ALT proc. step:8.2. Reset APRM setdowns APRM SETDOWN TRIP SET-DN trips Critical reset. White alarm lights not lit, Panel P603, APRM sectio Proc step 8.2. PROM PT:
Fail 1 Div I APRM Upscale with ATWS (allow manual SCRAM)
9 Identify RPS Bus A failure 10 Identify failure of reactor to Declares ATWS Critical automatically scram
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 Bl.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 satisfied.
TASK CONDITIONS: Unit Two startup is in progress per GP-02. Reactor Feedpump discharge pressure is greater than 900 psig. GP-02 is completed up to step 5.3.57.
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 BRUNSWICK NUCLEAR PLANT JOB PERFORMANCE MEASURE WORKSHEET TITLE: Place The Master Feedwater Controller In Service Per GP-02 NO: LOR-SIM-JP-032-C01 SUPERVISOR-OPERATOR TRAINING DATE Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit 2 Setting: Classroom Plant Simulator X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee: SSN:
Did Trainee Obtain and Verify Procedure?: Yes No JPM: Pass Fail Questions: Pass Fail N/A Remedial Training Assessment Required?: Yes No (See TAP-1.05)
Evaluator Signature: Date:
Comments:
SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions IC 06 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 trainee.
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 5.3.57.
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 Comment EVAL N DESCRIPTION STANDARD S/um Verify or place the Master RFPT Sp/Rx MSTR RFPT SP/RX LVL CTL C32-SIC Lvi Ctl station in manua R600 indicates M (Manual). Verify Feedwater Control mode selector in C32-CS-Z2 is in the 1 ELEM positio Ele . Depress select push button on on-line feed Bias for the on-line Feed Pump displays pump (RFPT A) control station until bias 0% at RFPT A SP CTL C32-SIC-R601A is displayed and ensure bias set at 0%. control statio . Depress select push button on on- line feed Pump demand for Feed Pump A is pump until pump demand is displaye displayed at RFPT SP CTL C32-SIC R601A control station.
- Depress select push button on Master Master Demand is displayed on MSTR Controller until Master Demand is SP/RX LVL C32-SIC-R60 displayed.
- Set Master Demand signal equal to the on MASTR DEM display on C32-SIC-R600 line Feed Pump demand signal using is equal to PMP A DEM display on C32 increase push butto SIC-R601A.
- Depress AIM push button on RFPT A RFPT A SP CTL C32-SIC-R601A control control statio station indicates A (auto). Depress select push button on off-line feed LVL ERROR is displayed on the RFPT B pump (B) until level error displaye SP CTL C32-SIC-R601B control station.
- Depress AIM push button on Master A (Auto) is displayed on MSTR RFPT Controller and verify automati SP/RX LVL CTL C32-SIC-R600 control statio Verify pump A demand and valve demand PMP A (C32-SIC-R601A) and VALVE remain unchange DEM (FW-LIC-3269) remain constant.
- 1 Place SULCV control station in manual FW-LIC-3269 control station indicates M contro (manual).
PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comment EVAL DESCRIPTION STANDARD S/U()
N contro (manual).
"*1 Open SULCV using increase push button VALVE DEM on FW-LIC-3269 control until valve demand is 100% station is 100%, Reactor level is 182 192".
13 Inform supervisor Master Controller is in Supervisor is informe service per GP-02.
(')Comments required for any steps found UNSA 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 satisfied.
TASK CONDITIONS 1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or main steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
4. The Unit SCO has determined that Anticipation of Emergency Depressurization is required.
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 Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B.l.c 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: NRC Examiner:
Date:
Method of testina:
Simulated Performance XX Actual Performance Classroom Simulator - Plant Unit 1 Required Materials: None General References:
EOP-01 -RVCP, Reactor Vessel Control Procedure Hard Card for MSIV equalization and reopening (S/960)
LOT-SIM-JP-025-A03 Time Critical Task: YES/NO 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 satisfied.
Initiating Cue:
1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or main steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
5. 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 Depressurization.
Task Standard:
MSIVs have been reopened and the reactor has been depressurized <300 psig via BPVs.
Applicant Performance: SAT/UNSAT
Ann*.ndix ( t-orm t*Lz-1-Annendix C~
PERFORMANCE INFORMATION Task Description Standard Sat/Unsat 1 Obtain "Hard Card" for MSIV "Hard Card" obtained for MSIV equalizatio equalization 2 Place the condenser vacuum bypass Note: Inform applicant no spare Critical switches in bypass positio operators are available if a request for another operator is mad PROMPT: Inform examinee low condenser vacuum bypass switches are in Bypass 3 Place MSIV control switches to clos PROMPT: All MSIV control switches Critical in closed positio Reset Group 1 isolation. Resets PROMPT: White PCIS/Group 1 status Critical Group 1 Isolation reset switches; lights on P601 are O A72-S32 and S33 on P601 are depressed and white PCIS/Group 1 status lights on P601 are O Outboard MSIV switches: B21 -F028A, PROMPT: MSIVs are OPE Critica B21-F028B, B21-F028C, B21-F028D I placed in OPE Open MS-F020, MSL Drain Isolation PROMPT: MS-F020 indicates ope Valv Open B21-F019, MSL Outboard drain PROMPT: B21-FO19 indicates ope Critical Isolation Valv Close MS-V28, Steam supply to PROMPT: MS-V28 Indicates close MSR's, SJAE's, RFP' Close MVD-F021, Common drain PROMPT: MVD-F021 Indicates line orifice Bypass Valve to condenser close Open B21-F016,MSL Inboard drain PROMPT: B21-F016 indicates ope Critical Isolation Valve 11 Open MS-F038 A,B,C,D, MSL orifices PROMPT: MS-F038A,B,C, and D Critica bypass valves to increase steam line indicate open. Steam Line pressure pressur increasing 12 Main turbine steam line pressure A/B PROMPT: Main turbine steam line indication on XU-1 verified to be pressure indication is increasin increasin Close MSL drain valves MS-V46, PROMPT: MS-V46, V47, V48, V49 MS-V47, MS-V48, MS-V49 & and V35 indicate close MS-V3 Verify differential pressure between PROMPT: If asked SRO direction is to Critica
Task Description Standard Sat/Unsat 14 reactor and main turbine is less than use 200# differential with Rx pressure or equal to 200 psid.on ERFIS, at 1000# and main steamline press is C32-R608, R609, or C32-PI-R605A 900#
or B on P-603/601 or any other available reactor pressure indication availabl Open Inboard MSIV's. Inboard MSIV Inboard MSIVs B21-F022A, Critica switches for B21 -F022A, B21 -F022B, B21-F022B, B21-F022C, B21-F022D indicate open after the valve is I B21-F022C, B21-F022D placed in the OPEN positio repositioned 16 Open MVD-F021, Common drain line PROMPT: MVD-F021 indicates ope orifice Bypass Valve to condense Direct AO to Open V5005 PROMPT: Valve open 18 Open MS-V46, V47, V48, V49 and PROMPT: MS-V46, MS-V47, V35, MSL drain valve MS-V48, MS-V49 & MS-V35 Indicate ope Ensure open MS-V43, MS-V44, PROMPT: MS-V43, MS-V44, MS-V45, MS-V37N39, MS-V41N42, MS-V45, MS-V37N39, MS-V41N42, MS-V36, MSL drain valve 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 tim Open MS-V2 PROMPT: MS-V28 indicates open Critical 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 terminate 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 Power.
2. 230 KV Bus 2B is energized. 230 KV Bus 2A is locked out due to the SAT lock out.
3. Diesel generators 3 and 4 are tied to 4KV Buses E3 and E4.
4. Unit 2 is in process of establishing a UAT backfeed per AOP-36.1 and 20P-50 to re energize BOP Buses.
5.20P-50 Section 8.13, has been completed through step 13.
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).
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit 2 Setting: Classroom Plant Simulator X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee: SSN:
Did Trainee Obtain and Verify Procedure?: Ye s No JPM: Pass Fail Questions: Pass Fail N/A Remedial Training Assessment Required?: Yes No (See TM-1.05)
Evaluator Signature: Date:
Comments:
SIMULATOR SETUP: Initial Conditions: Recommended Initial Conditions IC 11 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 trainee.
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 13.
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 29B. Verify running voltage is approx. 120 Running voltage verified to be appro volt volts.
- 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 OF * Place Synchroscope for UAT to Bus 2C to Synchroscope for UAT to Bus 2C breaker O placed to O * Close the UAT to Bus 2C breake UAT to Bus 2C breaker is close Verify UAT to Bus 2C breaker is close UAT to Bus 2C breaker verified to be close Place Synchroscope switch for UAT to 2C Synchroscope switch for UAT to 2C breaker to OF breaker is placed to OF PERFORMANCE CHECKLIST NOTE: Critical items denoted by (*). Sequence is assumed unless denoted in the Comment EVAL STANDARD S/U¢r)
N DESCRIPTION 9 Place Synchroscope for UAT to Bus 2D to Synchroscope, for UAT to Bus 21) breaker O placed to O Close the UAT to Bus 2D breake UAT to Bus 2D breaker is closed.
"*1 Verify UAT to Bus 2D breaker is close UAT to Bus 2D breaker verified to be close Place Synchroscope switch for UAT to 2D Synchroscope switch for UAT to 2D breaker to OF breaker is placed to OF Synchroscope for UAT to Bus 2B breaker
"*1 Place Synchroscope for UAT to Bus 2B to O placed to ON.
"*1 Close the UAT to Bus 2B breake UAT to Bus 2B breaker is close Verify UAT to Bus 2B breaker is close UAT to Bus 2B breaker verified to be close Place Synchroscope switch for UAT to 2B Synchroscope switch for UAT to 2B breaker to OF breaker is placed to OF Verify alarm UA-13 3-6 is clea Alarm UA-13 3-6 is verified to be clea Inform system engineer Buses 2C, 2D and Engineer informed Buses 2C, 2D and 2B 2B have been energize have been energize (")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 3.4/3.7 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 satisfied.
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 Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B.1.e 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 satisfied.
Initiating Cue: Reactor Feed pumps have tripped. Reactor Vessel Level has decreased to below the low level 2 HPCI initiation setpoint. 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 flow.
Task Standard:
When HPCI has been manually isolated, this JPM is complet Applicant Performance: SAT/UNSAT
Required Materials: General References:
None HARD CARD "Emergency HPCI Operation" 2/0577S LOR-SIM-JP-19-A08 Time Critical Task: YES/NO Validation Time: 5 Min.
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 start. Malfunctions System Tag Title Value Activate Deactivate Event (ramp rate) Time (sec) Time (sec)
ES047F HPCI Stm Brk HPCI Room 20% 0 SEC N/A El ES (o SEC)
ES040F HPCI Auto Start Failure NA 0 SEC N/A A ES Overrides Remote Functions System Tag Title Value (ramp rate)
E41-F002 Auto Closure Disabled ON PC IAPCJP0
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 2 F-orm *- --
PERFORMANCE INFORMATION Task Description Standard Sat/Unsat 1 Reference HPCI Pressure Control In HPCI Pressure Control In EOPs Hard EOPs Hard Car Card. reference Ensure HPCI Auto Intiation is RESET Verifies or resets auto initiation 3 Verify Auxiliary Oil Pump is not running Verifies AOP is not running 4 Open E41-F011 Opens E41 -FOl 1 5 Open E41 -F059 Opens E41-F059 6 Start the HPCI Barometric Condenser The HPCI VACUUM PUMP is started Vacuum Pump (E41-S4) and leave in and left in start start TURBINE STEAM SUPPLY VLV, E41 Critical 7 Open the Turbine Steam Supply, E41 F001 F001, is opene AUXILIARY OIL PUMP, is starte Critical 8 Start the Auxiliary Oil Pum NOTE: If asked the desired reactor pressure is 800 - 1000 psig 9 Throttle Open E41 -F008 to maintain Throttles Open E41 -FOO8 to maintain desired reactor pressure pressure of 800 to 1000 psig 10 Ensure E41-V8 and E41-V9 are closed Ensures E41-V8 and V9 are closed Critical 11 Ensure E41 -F7012 is closed when flow Closes E41 -F7012 when flow is > 800 has increased above 800 gpm gpm NO)TE: When the HPCI injection valve is opened, initiate Event Trigger El to activate HPCI Steam line Break 12 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 isolat 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 satisfied.
TASK CONDITIONS: Reactor Recirculation Pump 2B has tripped, and the cause of trip has been corrected. 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 loop. 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 8.2.2.4. 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 Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B.1.f 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 satisfied.
Initiating Cue: Reactor Recirculation Pump 2B has tripped, and the cause of trip has been corrected. 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 loop. 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 8.2.2.4. 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 completed.
Task Standard:
When Recirculation Pump 2B scoop tube is locked, this JPM may be terminated.
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 Min.
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)
C. Malfunctions None D. 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%
Annendix C 2 Form ES-C-1 Appendix C2FomE-i PERFORMANCE INFORMATION Task Description Standard Sat/Unsat NOTE:
Provide applicant with marked up copies of OP-02 Sections 5.2 and . Obtain current revision of OP-0 Current revision of OP-02 obtained. Determine the RPV Dome RPV pressure is obtained temperatur Pressure reading is corrected for PSI 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 rea . Calculate differential temperatur Bottom head drain temperature is subtracted from Dome temperatur (<145 OF) Record the differential temperatur Differential temperature and time of verification logged in Control Operator's logboo PROMPT: If asked, it is NOT desired to place APRM normal setpoints in setup Determine the temperature differential Operating loop temperature is between the idle and operating loo read off B32-R650 or process compute Idle loop temperature is read off B32-R650 or process compute AT obtained verified <50 OF and recorde . Record the differential temperatur Differential temperature and time of verification logged in Control Operator's logboo . Verify that the operating loop flow is Operating loop flow is read off recorder less than or equal to 23,500 gpm (50% B32-R614 or meter B32-R617 and of rated flow). operating loop flow is verified to be less than or equal to 23,500 gp . Record operating loop flowrat Operating loop flowrate and time of wanrifirnfinn Innnari in (.nntrni rlnarnfnr'a
Task Description Standard Sat/Unsat Task Description Standard Sat/Unsat verification logged in Control Operator's logbook.
1 Close the Discharge valv Control switch for the B32-F031 B is Critical taken to the CLOSE position or verified closed by B32-F031 B Green indication only is illuminated.
1 Start the B Reciro MG se The B Recirc MG set switch is placed to Critical the Start positio MG set B drive motor breaker 1 Verify proper start sequence of the Recirc MG set and Pump Moto 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-R614.
1 Record time of pump star Time at which MG set drive motor breaker closed logged in Control Operator's logbook.
1 Open the Recirc B pump discharge Take the B32-F031B valve control Critical valv 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 Runback is reset as follows: Lower speed demand on Speed control potentiometer lowered Pump 2B until control below runback limi established with potentiomete Monitor for speed increase on Pump speed monitored while runback Pump 2 is rese Depress Runback Reset push Recirc B Runback Reset is depresse button for pump 2B.
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 Failur NOTE : When examinee locks the scoop tube,
Task Description Standard Sat/Unsat 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 complete.
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 actions.
1 Lock the scoop tub Recirc pump B scoop tube is locked, by Critical placing "Scoop Tube B Lock" to TRIP with < 10% power increase.
TERMINATING CUE:
When Recirculation Pump 2B scoop tube is locked, this JPM may be terminate 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 satisfied.
TASK CONDITIONS:
1. Unit One (1) is in a Station Blackout. Buses El and E2 have been energized from Unit Two (2) by cross-tie. Sufficient load is available to reestablish drywell cooling on Unit One (1).
4. Unit One (1) has a LOCA signal sealed in due to high drywell pressure concurrent with low Reactor pressure.
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 Job Performance Measure Form ES-C-1 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 satisfied.
Initiating Cue: Unit One (1) is in a Station Blackout. Buses El and E2 have been energized from Unit Two (2) by cross-tie. 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 started.
Task Standard:
When circuit alterations have been performed per AOP-36.2 Section 3.2.11, this JPM is complet Applicant Performance: SAT/UNSAT
Ann*.ndix 2 Form ES-C-1 Annendix C2FomE-i PERFORMANCE INFORMATION Task Description Standard Sat/Unsat Obtain current revision of AOP-3 Current revision of AOP-36.2 obtaine Section 3.2.1 . Obtain screwdriver, tape and jumper Screwdriver, tape and jumper obtained from RO desk locked drawe from RO desk locked drawe . Lift and tape white wire 1-DK7-26 in White wire 1 -DK7-26 in Panel 1-XU-24 Critical Panel 1-XU-24 (ESS Logic Cabinet (ESS Logic Cabinet H59) on terminal H59) on terminal TA9 TA93 is lifted.
PROMPT:
When informed wire in XU-24 is lifted, inform examinee that 1-SW-V103 has been opene . Lift and tape grey wire 1-DE3-26 in Grey wire 1-DE3-26 in Panel 1-XU-7 Critical 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 opened.
Ifasked, inform examinee that 480V MCC lXE is energized and RBCCW Pump lC control switch has been placed to OF . Install jumper in Panel 1-XU-7 (ESS Jumper in Panel 1 -XU-7 (ESS Logic Critical Logic cabinet H58) between terminals cabinet H58) between terminals TB71 TB71 and TB7 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, installed.
TERMINATING CUE:
When circuit alterations have been performed per AOP-36.2 Section 3.2.11, this JPM is complete
JPM B.2.a 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 satisfied.
TASK CONDITIONS: The SS has made the determination that control room evacuation IS required.
2. Scram and MSIV closure could NOT be completed prior to evacuating the Control Room. 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 Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B.2.a 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 Plant XX Required Materials: General References:
None OAOP-3 LOR-OJT-JP-302-EO1 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 satisfied.
TASK CONDITIONS: The SS has made the determination that control room evacuation IS required. Scram and MSIV closure could NOT be completed prior to evacuating the Control Room. 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 completed.
Task Standard:
When the EPA Breakers have been opened, this JPM is complete.
Applicant Performance: SATIUNSAT
AnnAndix (3 2 Form ES-C-1 Annndix C2FomECi PERFORMANCE INFORMATION Task Description Standard Sat/Unsat 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. Ifupstream breaker (EPA-1,3) is opened first that step becomes critical and the downstream breaker (EPA-2,4) non critical.
PROMPT:
If requested, Indicate EPA POWER OUT light indications going out as EPA breakers are opened.
NOTE 1: It is critical that as a minimum, either Bkrs 1 AND 3 OR Bkrs 2 AND 4 are opened.
NOTE 2: The breakers must be opened in the correct order (as written below) Open EPA-2 circuit breaker for "A" EPA-2 circuit breaker open as indicated Critical RPS MG se when the red POWER OUT light is extinguishe EPA-1 circuit breaker open as indicated Critical Open EPA-1 circuit breaker for "A" RPS MG se when the red POWER OUT light is extinguishe EPA-4 circuit breaker open as indicated Critica Open EPA-4 circuit breaker for "B" RPS MG se when the red POWER OUT light is extinguished. Open EPA-3 circuit breaker for "B" EPA-3 circuit breaker open as indicated Critical RPS MG se when the red POWER OUT light is extinguishe . Open EPA-6 circuit breaker for RPS EPA-6 circuit breaker open as indicated alternate power suppl when the red POWER OUT light is extinguishe . Open EPA-5 circuit breaker for RPS EPA-5 circuit breaker open as indicated alternate power suppl when the red POWER OUT light is extinguishe . Inform Shift Superintenden Shift Superintendent informed that EPA breakers are ope TERMINATING CUE:
When the EPA Breakers have been opened, this JPM is complet 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 satisfied.
TASK CONDITIONS:
1. The RCIC turbine has tripped due to the mechanical overspeed trip device.
2. RCIC speed has been verified to be less than 4000 rpm.
3. All applicable prerequisites have been satisfied.
4. 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 Job Performance Measure Form ES-C-1 Worksheet Facility: BRUNSWICK Task No: B.2.b Task Title: Resetting a RCIC Mechanical Overspeed Trip Job Performance Measure No:
KIA Reference: 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: NRC Examiner:
Date:
Method of testing:
Simulated Performance XX Actual Performance Classroom _ Simulator Control Room __ Plant Lab XX Required Materials: General References:
Plant page 1. 1(2) OP-16 2. Vol II/SD-16 3. AOR-OJT-JP-01 6-AO1 Time Critical Task: YES/NO Validation Time: 8 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 satisfied.
TASK CONDITIONS: The RCIC turbine has tripped due to the mechanical overspeed trip device. RCIC speed has been verified to be less than 4000 rpm. All applicable prerequisites have been satisfied. 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 complete.
Task Standard:
All actions necessary to reset a RCIC mechanical overspeed trip have been performe Applicant Performance: SATIUNSAT
Ann*nrliY Form ES-C-1 A nnrndi ( 2FomE-i PERFORMANCE INFORMATION Task Description Standard Sat/Unsat Obtain current revision of OP-16, Current revision of OP-16 Section Section obtained. Identifies the RCIC turbine trip and States that the RCIC turbine trip and throttle valve is in the "Tripped throttle valve is closed condition.
PROMPT: IF asked ifthe control room has closed the motor actuator, state that they tried but it didn't work and the applicant must do it locall Closes the RCIC Turbine Trip and Uses the handwheel to close the Critical Throttle valv actuator such that the collar is returned to the correct position to allow for rese Emergency connection rod moved in Critical Depending on body position, either push or pull the emergency connection direction of RCIC turbine trip and throttle rod in the direction of the RCIC turbine valve approximately one inc trip and throttle valve (E51 -V8)
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 plac Ifthe tappet and ball assembly does Tappet and ball assembly lightly Critical not drop in place, lightly depress the depressed and dropped into plac assembl PROMPT:
When required, inform applicant that tappet and ball assembly HAS dropped into plac Emergency connection rod release Critical Release the emergency connection ro Notify the control room that the Control room notified that RCIC mechanical trip device for the RCIC mechanical trip device for the RCIC turbine is rese turbine has been rese TERMINATING CUE:
The JPM may be terminated when all actions necessary to reset a RCIC mechanical overspeed trip have been performe JPM B.2.c 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 satisfied.
TASK CONDITIONS: A seismic event has caused the structural integrity of the Fire Protection Storage Tank to become breached. The Fire Protection System was in a normal operating configuration with some minor leaks and NO system demand before the seismic event. All fire pumps have been secured per applicable sections of OP-41. The Shift Supervisor has determined that the MUD Tank must now be lined up to supply the Fire Protection Header followed by Jockey Pump startup.
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 Appendix C Job Performance Measure Form ES-C-1 Wnrk~h*.*t Facility: BRUNSWICK Task No: B.2.c 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 Plant XX Required Materials: General References: OOP-41, Sect 8.51, Att 47 1. OP-41 SD-41 3. AOP-13.0 P&ID 9527-D-2043 AOR-OJT-JP-041-A02 Time Critical Task: YES/NO Validation Time: 18 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 satisfied.
TASK CONDITIONS:
1. A seismic event has caused the structural integrity of the Fire Protection Storage Tank to become breached.
2. The Fire Protection System was in a normal operating configuration with some minor leaks and NO system demand before the seismic event.
3. All fire pumps have been secured per applicable sections of OP-41.
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 startup.
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 complete.
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 complet Applicant Performance: SAT/UNSAT
Ann*_ndiY 2 Form ES-C-1 A"ndFr EC.-i PERFORMANCE INFORMATION Task Description Standard Sat/Unsat NOTE: 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 applicant.
NOTE: 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. Ifan NRCS revision check is being performed, Attachment 47 is included as part of the chec . Obtain current revision of OP-41 Applicant obtains copy of OP-4 . Applicant reviews index of OP-41 to Applicant determines from a review of determine the needed sections OP-41 index that the following required to perform the task procedure sections are needed:
assignmen Section 8.51 Applicant reviews OP-41 Section 3.0, Applicant determines from OP-41 Precautions and Limitation Section 3.0 that there are no Precautions or Limitations directly applicable to the Auxiliary Operator for this task assignmen 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 me . Applicant reviews OP-41 Section 4.0, Applicant determines from a review of Prerequisite OP-41, Section 4.0 that several prerequisites are applicabl 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 Applicant locates 2-FP-V59 in the Critical FP-V58, 2-FP-V59, is close northeast floor sump area of the Diesel
Task Description Standard Sat/Unsat Task Description Standard Sat/Unsat 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 . Unlock and close Combined Suction Applicant locates 2-FP-V57 in the area Critical Valve From Fire Protection Storage immediately behind the Motor Driven Tank, 2-FP-V5 Fire Pump (P-2) in the north end of the MWT Buildin 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 . Unlock and open the Demineralized Applicant locates 2-MUD-V37 on the Critical Water Storage Tank Outlet To The Fire west side of the MUD Tan Protection System, 2-MUD-V3 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 . Unlock and open Fire Pumps Suction Applicant locates 2-FP-V58 in the Diesel Critical Valve From The Demineralized Water Driven Fire Pump Room in the Storage Tank, 2-FP-V5 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 immediately Applicant reads the NOTE and ahead of OP-41 Section 8.51, Step determines that it is applicable to the 8.51. next step; OP-41 Section 8.51, Step 8.51. . Places Jockey Pump P-4 in HAND 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 of Applicant locates the Jockey Pump
Task Description Standard Sat/Unsat 1 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.
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 8.51.2.8.
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 face.
(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 startup.
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 complet 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 1 NA N-BOP Perform Core Spray system operability test PT-07.2.4A SRO-2 1 C-BOP Core Spray pump overload requires pump to be tripped SRO 3 2 I-BOP Reactor Building radiation monitor fails, Reactor Building SRO isolates, Standby Gas fails to start 4 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 7 6 M-ALL High Power ATWS 8 7 RWCU fails to isolate when SLC is initiated 9 -d1 8 RCIC fails to start, HPCI or RCIC must be manually started to stabilize RPV level
- e.ctivity
.... ... . . ...
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1
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 bypassed.
Core Spray Pump A flow test will be performed. After flow is established, a pump overload will alarm requiring the pump to be tripped.
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 integrity.
The load dispatcher will request power be raised to 100% due to loss of generation.
Frequency will drop to 59.8 Hz requiring the crew to enter AOP-22 and raise power.
Frequency will return to normal.
A Feedwater Heater 4B tube leak will result in a Hi-Hi extraction trip for the heater.
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 block.
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 isolated.
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 power.
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 2 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 3 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 4 Rev.00
SIMULATOR SETUP Initial Conditions IC 11 Rx Pwr 90%
Core Age BOC Event Triggers 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 5 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 6 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 @ P60 NRC-01-1 7 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 request.
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 shif NRC-01-1 8 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-303.
Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
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-LPC.
Reason For Revision NRC 2001 Initial License Exa NRC-01-1 9 Rev.00
SIMULATOR SCENARIO SHIFT TURNOVER Instructor Activities o Set up the simulator per the setup.
0l Plant Response
Operator Activities SCO o Conduct shift turnover shift briefing.
RO/BOP o Perform board walk-down.
0 Monitor the plan NRC-01-1 10 Rev.00
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 piping.
[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 Overload.
[o If asked, as outside AO report 51 device on OB showing target at pump breaker on E3.
o Ifasked as I&C to investigate, acknowledge the request.
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).
NRC-01-1 11 Rev.00
EVENT 2 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 B.
"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 them.
"o If asked as I&C to investigate, acknowledge the request.
"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 required.
Plant Response o D12-NO10B initially spikes upscale, then fails downscale.
[I Group 6 and Secondary Containment isolations.
[I SBGT fails to auto start, can be manually started.
0l 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 O NRC-01-1 12 Rev.00
EVENT3 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, 59.8.
o Ifcontacted as NE, recommend power be raised using flow, no restrictions to rate apply.
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 restored.
Plant Response 0 Generator under frequency alarms (UA-6 1-2).
o EHC Set Speed light goes out.
o EHC Increasing Speed light illuminates.
Operator Activities SCO o Direct power be raised to 100%.
o Direct entry into AOP-22.0.
RO 0 Raise power to 100% using Recirculation flow.
BOP El Enter and announce AOP-22.0.
o Determine unrestricted operation at present frequency (5 minute time limit begins at 59.3 hertz).
NRC-01-1 13 Rev.00
EVENT4 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 indication.
o If notified as NE, recommend power reduction to 90% until thermal limits are verified.
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-03.0.
[o Direct reactor power reduction to maintain power <100% per ENP-24 and AOP-0 immediate actions.
[o Notify NE to monitor thermal limits.
[o Refer to OP-35 to evaluate heater performance.
[I Direct further power reduction as recommended by the NE.
o Direct bypassing of FW heater 4B & 5B per OP-32.
[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 heater NRC-01-1 14 Rev.00
EVENTS 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 break.
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 from.
Plant Response
[o Turbine Building ARM alarm (UA-3 5-7)
[o Turbine Building area temperatures rise toward Group 1 isolation setpoint.
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-05.0.
[o Direct evacuation of Turbine Building.
o Consider manual scram and MSIV closure.
o Direct manual scram and MSIV closure when tunnel hi temp alarms are received.
RO o Monitor the plant
[o Reduce reactor power and/or scram reactor as directed by the SCO.
[o Recognize report alarms A-6 3-6 and 4-6 (Hi Temp) and failure of MSIVs (Group 1)
to auto close.
ol Insert manual scram.
o Recognize/report ATWS.
"o Monitor the plant.
"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 SC NRC-01-1 15 Rev.00
EVENT-6 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 closed.
[] Most Control Rods fail to insert.
o] Pressure rises rapidly lifting SRVs, initiating ARI and tripping Recirc Pumps.
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)
0 (RO/BOP) Diagnose failure of MSIVs to auto close and manually clos (RO/BOP) Recognize and report ATW (RO/BOP) Place Mode Switch to Shutdow (RO/BOP) Verify ARI initiated and Recirc pumps trippe (RO/BOP) Inhibit AD (RO/BOP) Operate SRVs to control pressure as directed by the SC (RO/BOP) Initiate SLC (prior to 110oF).
0 (RO/BOP) Manually isolate RWCU (Group 3).
0 (RO/BOP) 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 I NRC-01-1 16 Rev.00
EVENT 7 LEVELIPOWER CONTROL ACTIONS Instructor Activities o Ifrequested to install jumpers for LEP-02, Section 3, wait 3 minutes and insert MF RP005F (Auto Scram Defeat), and report jumpers installed.
o Ifrequested as I&C to investigate RPS reset failure, acknowledge request.
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-LPC.
"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 V8.
"El (RO/BOP) Continue to drive control rods per LEP-02.
[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 neede NRC-01-1 17 Rev.00
EVENT 8 SUPPRESSION POOL TEMPERATURE >95oF Instructor Activities o Ifrequested to defeat Drywell Cooler LOCA lockout, wait 3 minutes and execute batch file to defeat the LOCA lockout.
Plant Response
[I Suppression pool temperature continues to rise.
[o If level lowered to LL3, drywell temperature and pressure rises until drywell coolers restarted.
Operator Activities SCO
[I Enter and execute Primary Containment Control, EOP-02-PCCP.
[I Direct actions to maximize suppression pool cooling.
RO/BOP (Circle candidate performing action)
[I (RO/BOP) Continue to insert control rods.
o (RO/BOP) Place both loops of RHR in suppression pool cooling per the Hard Card.
[I (RO/BOP) Continue to control reactor pressur NRC-01-1 18 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 met.
[o Direct injection be or remain terminated.
o] If LOCA signal received, direct Core Spray terminated and prevented.
[o If LOCA signal received, direct drywell cooling be restored per SEP-10.
o Evaluate TAF and LL4 using Caution 1 graphs.
RO/BOP (Circle candidate performing action)
"o (RO/BOP) Continue to drive control rods using RMCS
"o (RO/BOP) Monitor APRMs for downscales.
[o (RO/BOP) If necessary terminate and prevent HPCI.
[o (RO/BOP) Override Core Spray pumps if LOCA signal received.
[o (RO/BOP) Return RHR to Suppression Pool cooling if LOCA signal received.
[o (RO/BOP) Continue to control pressure using SRVs.
[I (RO/BOP) Monitor Reactor level for TA NRC-01-1 19 Rev.00
EVENT 10 APRMs DOWNSCALE OR RPV LEVEL AT TAF Instructor Activities o Ifrequested to defeat HPCI hi torus level transfer, wait 3 minutes and insert RF EPIAEOPJP4, and report HPCI hi torus level transfer defeated.
Plant Response o APRMs reading <4%, or RPV level at TAF.
[I Based on power level if at TAF, HPCI may be required to maintain level above LL4.
Operator Activities SCO
[o Direct injection be established to maintain RPV level LL4 to the level where APRMs downscales were received or TAF.
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 in.
o Continue rod insertion per LEP-02.
o Monitor SLC tank level and SLC operation.
o Report level at TAF (ifAPRM downscales not in).
[o Operate HPCI and/or RCIC as required to maintain level between LL4 and the level to which it was lowered.
0 Continue to operate SRVs to control pressur NRC-01-1 20 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 2 nd time, and scram discharge volume level is lowering, insert MFRP008F (ATWS #1), then delete MFRP009F (ATWS #2).
Plant Response
[I Rod motion on manual scram.
Operator Activities SCO
[o Direct I&C to investigate RPS reset failure.
[o Exit LPC and enter RVCP and RSP.
ol Direct level to be restored +170-200 inches.
o Direct cooldown be maintained <1 00oF/Hr during level restoration.
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 RMCS.
0 (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/Hr.
o (RO/BOP) Terminate SLC operatio NRC-01-1 21 Rev.00
TERMINATING CUE Instructor Activities
"© When level is being restored to normal band, the scenario may be terminated.
"© If desired, complete Administrative category A.4 (E-Plan) requirements with SRO.
NRC-01-1 22 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 1 NA R-RO Power increase at load dispatchers request I SRO 2 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 5 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 7 6 M-ALL SRV Fails Open, SRV Tail Pipe Ruptures 8 7 Containment spray logic fails 9 Pressure suppression pressure limit exceeded requiring emergency depressurization
_ I_ I I I L Ij I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement I
SCENARIO DESCRIPTION The plant is operating at 75% power, middle of cycle with CSW Pump 2C and SLC Pump 2A under clearance.
The crew will begin to raise power toward 100% per GP-12.
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 addressed.
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 Region.
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 SAT.
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. Ifthe standby compressors are not started and air pressure continues to lower, feedwater flow will be lost to the RPV.
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 Ifcontainment 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 terminate NRC-01-2 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 3 Rev.00
SIMULATOR SETUP Initial Conditions IC 13 Rx Power 75%
Core Age MOC Event Triggers 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)
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 4 Rev.00
Overrides Switches Event Panel Tag Title Value Activate Deactivate (Ramp) Time Time XU-2 K4A01A Air Compr A Auto OFF 0 SEC NA A
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 P603 K2503A Rx Manual Scram B OFF 0 SEC NA A
A P601 K1227A Cont Spray A Control AS IS 0 SEC NA P601 K1727A Cont Spray B Control AS IS 0 SEC NA A
Lamps Tag Title Value Activate Deactivate Event Panel (Ramp) Time Time P603 Q2625SRE ARI Inop White OFF 0 SEC NA A
P603 Q2625SWE ARI Auto Green ON 0 SEC NA A
Alarms Tag Title Value Activate Deactivate Event Panel (Ramp) Time Time E3 XU-1 ZUA1 3210 UAT Winding Y Ground ON 0 SEC NA Remote Functions System Tag Title Status Activate Event 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 5 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 @ P60 NRC-01-2 6 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 direction.
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 service.
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 shif NRC-01-2 7 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-303.
Common Student Problems/Errors None noted to date.
Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
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 Limit.
Reason For Revision New scenario developed for HLC 2001 NRC exa NRC-01-2 8 Rev.00
SIMULATOR SCENARIO SHIFT TURNOVER Instructor Activities o Set up the simulator per the setup.
Plant Response 0l Operator Activities SCO
[I Conduct shift turnover shift briefing.
RO El Perform board walk-down.
[E Monitor the plant BOP
[I Perform board walk-down.
0l Monitor the plan NRC-01-2 9 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 flow.
o Ensure RO (Not the BOP) performs alternate power verification at 80% per GP-12.
Plant Response
Operator Activities SCO
"o Direct power be raised using Recirc flow per GP-12.
"o Direct alternate power verification at 80% power.
"0 Raise reactor power by increasing Recirc flow per GP-12 and OP-02.
"o Perform alternate power verification per GP-12.
BOP 0 Monitor the plan NRC-01-2 10 Rev.00
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 system.
"o If asked as I&C to investigate, acknowledge the request.
Plant Response
"o HPCI Initiation causes power to rise if HPCI is allowed to inject to the RPV.
"o HPCI Low Flow (A-1 1-4) alarms 15 seconds after steam supply (E41-FO01) begins to open.
Operator Activities SCO
"o Direct entry into AOP-03.0.
"o Direct termination of HPCI operation.
"o Direct reduction of reactor power if necessary to prevent a scram.
"o Contact I&C to investigate HPCI failure.
"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 plant.
BOP o Diagnose and report inadvertent HPCI initiation.
o Enter and announce AOP-03.0.
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 shutdow NRC-01-2 11 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 trip.
"El If asked as TBAO to investigate, report nothing apparent you can see.
"El If asked as I&C to investigate, acknowledge the request.
Plant Response El Reactor Water Level Hi/Lo (A-7 2-2) alarms and recirc runs back to limiter #2.
El APRM Upscale alarms (A-6 2-8) indicating entry into the restricted region of the power to flow map.
El Plant operating in Monitored Region after Restricted Region exit.
Operator Activities El SCO El Direct entry into AOP-23.0.
El Direct entry into AOP-04.0.
El Contact I&C to investigate RFPT trip.
"El Determine region of operation per COLR power to flow map.
"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 FCC NRC-01-2 12 Rev.00
EVENT 4 BOP BUS TRANSFER Instructor Activities o When the restricted region has been exited, initiate Trigger E3 to activate UAT Ground alarm.
o Ifcontacted as TBAO, report no ground relays are picked up on Bus 2C or 2D.
o If contacted as I&C to investigate, report ground relay for UAT is picked up and the ground alarm is valid.
Plant Response o UA-13 2-10, UAT Winding Y Ground alarm.
Operator Activities SCO o Direct actions of APP UA-13 2-10.
o Direct I&C to investigate if ground alarm is valid.
0 Direct transfer of Buses 2C and 2D from UAT to SAT per OP-50.
RO o Monitor the plant.
BOP El Enter APP UA-13 2-10.
o Direct AO to check Buses 2C and 2D for ground indications.
0 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 of NRC-01-2 13 Rev.00
EVENT5 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 D.
o Ifasked to investigate, report Air Compressor D is running unloaded and will not load. Report no indications of any air leaks.
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, OPEN.
Plant Response o Air header pressure lowers.
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 psig.
o When pressure lowers to 105 psig, service air isolates.
ol If pressure drops to 100 psig, Instrument Air Low Pressure (UA-1 4-4) alarms.
o If air pressure not restored, Condensate/Feedwater recirc valves fail open and Feedwater is lost.
Operator Activities SCO o Direct entry into AOP-20.0.
0 Direct verification of automatic actions.
o Direct Air Compressors A/B/C be manually started (may also choose to direct service air crosstie).
o Direct Service Air restored.
o Direct I&C to investigate air compressor failures.
[] Monitor the plant.
[I Recognize/report lowering air header pressure.
El Enter/announce AOP-20.0.
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 ai NRC-01-2 14 Rev.00
EVENT6 EHC FAILUREIELECTRICAL ATWS Instructor Activities o When the crew has responded to the air compressor failure, initiate Trigger E5 to fail EHC.
o Monitor SRV operation (panel mimics). If SRV F does not open to control pressure, manually initiate E6.
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 SRVs.
o RPS fails to initiate an auto scram.
o ARI fails to auto actuate on high pressure.
El RPS manual scram B push button fails.
o SRV F fails to close after opening.
El Rods inserted by placing Mode Switch to Shutdown or by manually initiating ARI.
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 15 Rev.00
EVENT7 BROKEN SRV TAILPIPE Instructor Activities o If requested as I&C to investigate spray logic, acknowledge the request.
o After HPCI is started, wait approximately 30 seconds and initiate Trigger E8 to fail HPCI controller power supply.
ol If asked as I&C to investigate HPCI power loss, acknowledge the request.
Plant Response
[o SRV F tail pipe ruptures in the suppression chamber air space 1 minute after opening.
[I HPCI available for injection by taking Aux Oil Pump out of Pull-To-Lock.
o] Suppression chamber and drywell pressure rapidly rise.
[o Suppression chamber pressure leads drywell pressure and torus-drywell vacuum breakers lifting indicate broken SRV tailpipe.
[o RHR unavailable for spray due to failure of spray logic.
ol Pressure suppression pressure limit is exceeded.
Operator Activities SCO El Enter Reactor Vessel Control Procedure, EOP-01-RVCP (if not already entered) and Primary Containment Control Procedure, EOP-02-PCCP.
o Direct RPV level be restored and maintained +170-200".
o Direct initiation of suppression chamber spray.
o Direct initiation of drywell spray.
o Direct I&C to investigate failure of spray logic.
[ Determine leak is in suppression chamber based on higher suppression chamber pressure and/or vacuum breaker operation.
[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 suppl NRC-01-2 16 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 repaired.
Plant Response
[o RCIC may trip due to elevated suppression chamber pressure.
[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 closed.
Operator Activities SCO
"o Direct low pressure ECCS be operated to prevent uncontrolled injection.
"o Direct Condensate be operated to prevent uncontrolled injection.
[o Direct 7 ADS valves opened.
RO/BOP (Circle candidate performing action)
[o (RO/BOP) Open 7 ADS valves.
0 (RO/BOP) Override RHR and Core Spray Pumps off when RPV pressure drops below 410 psig if injection is not required for RPV level control.
[o (RO/BOP) Verify LOCA actuations.
[I (RO/BOP) Operate the condensate system to prevent uncontrolled injection (close FW-V6 and FW-V8).
NRC-01-2 17 Rev.00
EVENT9 REACTOR DEPRESSURIZED Instructor Activities
[] None Plant Response ol RHR Outboard Injection valves E11-F017A/B can be closed 5 minutes after opening.
[o Only one loop of RHR available for containment cooling/spray since a LPCI signal present and one loop's spray logic is failed.
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 operability.
[o As time permits direct placing H2/02 monitors (4409 & 4410) in service.
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 El1-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 servic NRC-01-2 18 Rev.00
TERMINATING CUE Instructor Activities
© When the Reactor has been depressurized, the scenario may be terminated.
© If desired, complete Administrative Category A.4 (E Plan) requirements with the SR NRC-01-2 19 Rev.00