ML112160585
| ML112160585 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/03/2011 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML112160585 (199) | |
Text
JPM Sim A Page 1 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIMA Rod Control Urgent Failure Alarm During Reactor Startup
JPM Sim A Page 2 of 13 Rev0 ROISRO JOB PERFORMANCE MEASURE Task: Rod Control Urgent Failure Alarm During Reactor Startup Task#: 0010190101 Task Standard: .
Examinee manually trips the reactor after they determine that reactor power is INCREASING resulting in an uncontrolled transient and Control rods cannot be moved.
Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X KIA ReferencelRatings: K/A 001A1 .06 (4.1/4.4)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim A Page 3 of 13 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize to IC 210, Mode 2 to 10-3% power
- 4. Select N45 to one IR channel and 1 PR channel
- 5. Ensure the following is inserted and linked to KEY 1
- a. AN_OV_306, Rod Control System Urgent Failure Alarm Override ON
- b. IMF RDO8 Rods Fail to Move
- 6. An extra operator will be required to acknowledge alarms.
- 7. ACKNOWLEDGE ALARMS
- 8. FREEZE SIMULATOR.
- 9. Provide a copy of Section 5.2 Step 1 of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%.
- 10. PLACE SIMULATOR IN RUN
- 11. Insert KEY 1 at the Evaluators Cue.
SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
References:
Reference Title Rev No.
- 1. 1-AR-M4-B Rod Control System Urgent Failure Annunciator 28 2 AOP-C.01 Rod Control System Malfunction 20 3 0-GO-3 Power Ascension From Reactor Critical to Less Than 5% 25 Reactor Power
JPMSimA Page 4 of 13 Rev. 0 DIRECTIONS TO TRAINEE -
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is recovering from a reactor trip.
- 2. The cause of the trip has been identified.
- 3. The Reactor is now critical at 1 .OE-3% Power. 0-GO-3, Power Ascension from Reactor Critical to less than 5 Percent Reactor Power, is in progress.
- 4. All prerequisites, precautions and limitations are met.
INITIATING CUES:
- 1. You have been directed to perform Section 5.2 Step 1 of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%.
- 2. Other members of the control room team will address concurrent activities associated with Section 5.2.
- 3. The SRO has directed you to withdraw control rods to obtain a positive 0.3 to 0.5 dpm startup rate.
- 4. The SRO has directed you to stabilize Reactor Power at 1-2%
- 5. Inform the SRO when reactor power is stable at 1-2%.
JPM Sim A Page 5 of 13 Rev. 0 Start Time STEP Obtain a copy of 0-GO-3 POWER ASCENSION FROM REACTOR 1
- CRITICAL TO LESS THAN 5 PERCENT REACTOR POWER SAT UNSAT Standard: Examinee obtains a copy marked-up to Section 5.2, Step 1 of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%,
Provide a marked up copy of Section 5.2, Step 1 of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%
Comment
JPM Sim A Page 6 of 13 Rev. 0 NOTE Procedure Average loop xT (U0485) is considered to be the most accurate power indication below Note 15% power but greater than the Point of Adding Heat. IRM should be used at or below Point of Adding Heat. NIS power range and steam dump demand should also be monitored. (Refer to O-SO-1-2 for steam dump demand program.) [C.3]
STEP 2 [11 WITHDRAW RODS OR DILUTE to bring reactor power to
. between 1 and 2% RTP, while continuing with this instruction SAT UNSAT Critical Step Standard Examinee places the Rod Control switch 1-HS-85-51 11 to out and establishes a constant positive SUR of less than I DPM.
Comment Examiner . . ..
Note This step is critical in order to increase reactor power using rods.
Examinee may determine that the reactor has a positive SUR, control rods will not move and may make the determination that either:
. the reactor is uncontrolled and manually trips the Reactor, which Examiner meets the critical step performance requirements of Step 14, Note OR continues, pursuing actions of ARP 1 -AR-M4-B window A-6 and AOP C.01 actions.
Examiner Cue the console operator to insert the Rod Control Urgent failure after Note a stable positive SUR is obtained.
JPM Sim A Page 7 of 13 Rev. 0 STEP 3 NIS/ROD CONTROL I -XA-.55-4B SAT 6 (A-6) UNSAT ROD CONTROL SYSTEM URGENT FAILURE Corrective [1] PLACE rod control in manuaL Actions Standard Examinee acknowledges alarm and places Rod control switch 1-HS-85-511OtoMAN.
Comment Procedure CAUTION Attempting to reset rod control urgent tailure alarm using M-4 Note pushbutton, [i-RCASI. pnor to determining and correcting cause could result in dropped rods.
[2] DISPATCH MIG personnel to MG Set Room to investigate cause.
STEP 4 : SAT U NSAT Standard: Examinee contacts MIG to investigate cause of alarm.
Respond as Unit Supervisor MIG will be contacted Comment
JPM Sim A Page 8 of 13 Rev. 0 STEP 5
- [31 NOTIFY MIG to document, in Work Order, the status of the lights on and in the affected power and logic cabinet(s) SAT U N SAT Standard: Examinee contacts MIG to investigate cause of alarm.
JLc Respond as Unit Supervisor MIG will be contacted Comment STEP 6 : [4J WHEN rod control urgent failure is in alarm, THEN NOTE the following: SAT
[al It problem is in the Power cabinet control rods in that UNSAT cabinet will not move.
[bJ If problem is in the Logic cabinet no rods will move.
Standard Examinee determines that location of urgent failure is presently indeterminate and proceeds to step 5.
Comment STEP 7 [51 IF alarm is unexpected, THEN GO TO AOP-C01, Rod Control System Malfunction& SAT U N SAT Standard Examinee recognizes alarm as unexpected and transitions to AOP C.01.
Comment Examiner Note: Examinee transitions to AOP-C.01
JPM Sim A Page 9 of 13 Rev. 0 STEP Implement AOP-C.01, Section 2.5 for Rod Control System Urgent 8 SAT
- Failure Alarm.
UNSAT Standard: Examinee implements AOP-C.01.
Comment STEP 9 . 1. DIAGNOSE the failure:
SAT Failure of control bank to move on demand (AUTO0rMANUAL) UNSAT 25 52 OR ROD CONTROL SYSTEM URGENT FAILURE alarm LIT. [M-43 window A-6]
Standard: Examinee observes M-4B, Window A-6 LIT and transitions to Sect 2.5, of AOP-C.01.
Comment
JPM Sim A Page 10 of 13 Rev. 0 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move CAUTION 1: Control Rods should NOT be manually withdrawn during a transient.
Procedure CAUTION 2: Attempting to move control rods with ROD CONTROL SYSTEM Caution URGENT FAILURE alarm could result in dropped or misaligned rods.
CAUTION 3: Depressing ROD URGENT FAILURE RESET pushbutton on M-4 prior to determining and correcting cause could result in dropped rods.
STEP 10 CHECK ROD CONTROL SYSTEM URGENT FAILURE arrn LIL SAT IM-46. window A-6] UNSAT Standard: Examinee observes M-4B, Window A-6 LIT.
Comment
- 2. DETERMINE if rod control should be STEP 11 : placed in MANUAL: SAT
- a. CHECK rod control in AUTO. a. MAINTAIN rod control mode selector switch in current position.
GO TO Step 3.
Standard Examjnee observes Rod control switch 1-HS-85-5110 is selected to MAN goes to the RNO column and transitions to Step 3.
Comment
JPM Sim A Page 11 ofl3 Rev. 0 STEP 12 : CONTROL T-avg within 3F of T-ref SAT by performing one of the following:
U N SAT
. ADJUST turbine load OR
. ADJUST RCS boron concentration USING 0-SO-62-7.
Standard Examinee determines that Tavg is within 3F of Tref by observing installed instrumentation.
Comment 4 MONITOR following parameters IF uncontrolled transient in progress STEP 13 . STASLE or CONTROLLED: AND control rods CANNOT be moved. SAT THEN
. reactor power TRIP reactor and UNSAT GO TO E-O. Reactor Trip
- T-avg or Safety Injection.
Standar& Examinee determines that reactor power is increasing and is not controlled and goes to RNO column.
Comment
JPM Sim A Page 12 of 13 Rev. 0 STEP 14 : Alternate path SAT 4 MONITOR following parameters IF uncontrolled transient in progress STABLE or CONTROLLED: AND control rods CANNOT be moved, UNSAT THEN e reactor power TRIP reactor and Critical Step GO TO E-O. Reactor Trip
. T-avg or Safety Injection.
Operator determines that reactor power is INCREASING resulting in an uncontrolled transient And Standard:
Control rods cannot be moved And Places the reactor trip switch 1-RT-1 or 1-RT-2 to TRIP.
Comment Examiner This step is critical to terminate the power increase and place the Note reactor in a safe shut down mode.
Terminating Provide the following cue Another operator will perform the Cue. remaining steps of this procedure. STOP Stop Time
JPM Sim A Page 13 of 13 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. Unit 1 is recovering from a reactor trip.
- 2. The cause of the trip has been identified.
- 3. The Reactor is now critical at 1 .OE-3% Power. 0-GO-3, Power Ascension from Reactor Critical to less than 5 Percent Reactor Power, is in progress.
- 4. All prerequisites, precautions and limitations are met.
INITIATING CUE:
- 1. You have been directed to perform Section 5.2 Step 1 of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%.
- 2. Other members of the control room team will address concurrent activities associated with Section 5.2.
- 3. The SRO has directed you to withdraw control rods to obtain a positive 0.3 to 0.5 dpm startup rate.
- 4. The SRO has directed you to stabilize Reactor Power at 1-2%
- 5. Inform the SRO when reactor power is stable at 1-2%.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
j Sequoyah Nuclear Plant Unit 1&2 General Operating Instructions O-GO-3 POWER ASCENSION FROM REACTOR CRITICAL TO LESS THAN 5 PERCENT REACTOR POWER Revision 0025 Quality Related Level of Use: Continuous Use Effective Date: 10-21-2010 Responsible Organization: OPS, Operations Prepared By: A. K, Caidwell Approved By: W. T. Leary Current Revision Description Revised to incorporate changes associated with the Ui Digital Feedwater System under DON 22238A. Revised page 4 to add performance reference in Section 2.1, revised note prior to step 1 and deleted note prior to step 2 on page 20, revised note 3 on page 21, and deleted step for UI Only concerning old MFW Bypass controller tuning adjustments on page 24. Revised Attachment 1 to reflect procedure checklist addition per DON A
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0025 REACTOR POWER Page 8 of 28 StartupNumber >>c Unit DateTzb4.1 4 PREREQUISITES Throughout this Instruction where an IFITHEN statement exists, the step should be N/Ad if condition does NOT exist.
Prerequisites may be completed in any order.
This instruction may be entered from a partial shutdown, N/A sections NOT applicable annotate reason.
ENSURE Instruction to be used is the latest copy of effective version.
ENSURE Precautions and Limitations have been reviewed, ENSURE main steam system aligned with MSIVs open in accordance with 1, 2-SO-i -1.
ENSURE the reactor is critical with power at approximately 1 X 10%,
MAINTAIN pressurizer pressure within the normal operating band by use of the pressurizer heaters and spray valves.
MAINTAIN pressurizer level greater than or equal to 25%.
Due to instrument inaccuracies the steam ump or SG atmospheric relief valve setpoint of 84% or 1005 psig may be +/- 1 % or +/- 12 psig off, (1I t
MAINTAIN TA\iG stable with the steam dumps in pressure mode or with the SG atmospheric relief valves set at 84%
or 1005 psig.
,4J.j MAINTAIN SG levels within the normal operating range using Auxiliary Feedwater.
rDuring start up after a cold shutdown the Condensate Dl normally will be aligned for full flow polishing until the MSRs are in service.
ENSURE Condensate Dl polishing operation in accordance with RCL recommendations.
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0025 REACTOR POWER Paqe 9 of 28 Startup Number_______ Unit I Date ioI4/
4.0 PREREQUISITES (continued)
ENSURE each performer documents their name and initials:
F Print Name Initials Print Name Initials L/LAA End of Section
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0025 REACTOR POWER Page 10 of 28 Startup Number ? Unit Date tO INSTRUCTIONS CN Steps of this procedure must be performed sequentially, unless specifically stated otherwise.
Actions To Be Performed Prior To Increasing Reactor Power ENSURE Section 4.0, Prerequisites complete.
[ps 5,1[2] through 5.1[7] may be performed in any order.
ENSURE two Hotwell pumps in service in accordance with 12-SO-2/3-1.
ENSURE one condensate booster pump in service in K accordance with 1, 2-50-2/3-1.
C9ION The potential exists for condensation formation in steam extraction lines when feedwater heaters are isolated.
Step 5.1[4] may be performed out of sequefce (later) due to plant conditions as approved by the SM.
ENSURE secondary plant is aligned for startup in accordance with the following:
iNSTRUCTIONS INiTIALS 1 ,2-S0-5-1, Feedwater Heaters and Moisture Separator Reheaters I ,2-S0-5-2, No. 3 Heater Drain Tank and Pumps 1 2-S0-5-3, No, 7 Heater Drain Tank and Pumps 1 ,2-S0-5-4, Feedwater Turbine Condenser Drain Tank and Pumps
l UnitSON I &2 POWER ASCENSION FROM REACTOR 0-00-3 CRITICAL TO LESS THAN 5 PERCENT Rev. 0025 REACTOR POWER Page 11 of 28 Startup Number_______ Unit ( Date 5.1 Actions To Be Performed Prior To Increasing Reactor Power (continued)
TE Steps to prepare for MFPT startup may be performed in parallel with power ascension to 1-2%.
[5] IF any MFPT trip buss is NOT energized, THEN
[5.11 REFER to 0-TI-OPS-000-91 1.0, Instructions for using TS/TR 3.0.4 (b).
[5.2] NOTIFY US/SRO that no MFWP may be placed in service UNLESS LCO 3.0.4 (b) can be invoked.
[6] WHEN MFPT designated for startup is available, THEN PERFORM 1, 2-SO-213-1, Preparation of Main Feedwater Pumps for Startup. (NIA if previously performed) D 4,, [7] IF startup is on Unit 2, AND Secondary System Boric Acid Injection has been in service, THEN ENSURE System has been removed from service in accordance with 0-SO-36-3, Secondary System Boric Acid Injection.
S
- 1) Technical Specifications LCQ 3.6.1.5 requires 85-105°F average upper compartment temperature and 100-125°F average lower compartment temperature in Mode 1.
- 2) Step 5.1[8] may be performed out of sequence (later) due to plant conditions as approved by the SM.
[8] IF Upper Compartment temperature increase is desired, THEN PERFORM applicable sections of 0-SO-83-1, Containment Hydrogen Re combiner System.
End of Section
Startup Number >? Umt____ Date Power Ascension To Approximately 1% RTP Average loop AT (U0485) is considered to be the most accurate power indication below 15% power but greater than the Point of Adding Heat. IRM should be used at or below Point of Adding Heat. NIS power range and steam dump demand should also be monitored. (Refer to 0-SO1-2 for steam dump demand program.) [C.3]
[1] WITHDRAW RODS OR DILUTE to bring reactor power to between 1 and 2% RTP, while continuing with this instruction. D NOTE After refueling operations the Initial Startup System Parameter Log is performed during power escalations to provide the operator with alternate indications of power level (indications independent of calorimetric calculations). If significant differences occur (approx. 5%) between the alternate power indications then Engineering should be notified.
[2] IF startup is after a refueling or maintenance on NIS, THEN INITIATE performance of 0-P[-OPS-000-001 .0, Initial Startup System Parameter Log. [C.3] D
[3] COMPARE NIS power range instrumentation with loop AT indicators and steam dump demand to evaluate accuracy of PRMs. [C.3] D
[4] SELECT the highest reading IRM or Al and PRM channels to be recorded on NR 45. [C3] LI
[5j REVIEW plant parameters and indications to determine plant stability prior to startup of Main Feed Pump.
[6] MAINTAIN reactor power approximately I %. LI
NIS/ROD CONTROL I -XA-55-4B I I 2 I I 5 1617 SOURCE/INTERMED SOURCE/INTERMED INCORE TEMP REACTOR ROD CONTROL ROD CONTROL ZB-412A RANGE CH I RANGE CH II MONITOR SYSTEM COOLANT M-G SETS SYSTEM ROD CONTROL TROUBLE TROUBLE TROUBLE SATURATION A TRIPPED OR URGENT BANKS LIMIT A
MARGIN TROUBLE GROUNDED FAILURE LOW SOURCE RANGE IRS NIS POWER RANGE TRAIN A 52a/BYP ROD CONTROL ZB-412B HIGH FLUX LEVEL INTERMED RANGE UPPER DETECTOR BYPASS BREAKER TRAIN A SYSTEM ROD CONTROL AT SHUTDOWN HI FLUX LVL ROD HI FLUX DEVN IN OPERATE BYPASS BREAKER NON URGENT BANKS LIMIT WITHDRAWAL OR AUTO DEFEAT CLOSED FAILURE LOW-LOW B STOP SOURCE RANGE SPARE NIS POWER RANGE TRAIN B 52a/BYP SPARE ZB-442C HIGH SHUTDOWN LOWER DETECTOR BYPASS BREAKER TRAIN B BANK D FLUX ALARM HI FLUX DEVN IN OPERATE BYPASS BREAKER AUTO ROD c BLOCK OR AUTO DEFEAT CLOSED WITHDRAWAL BLOCKED C XIS-68-387 SPARE IPRS COMPUTER SPARE ROD POSITION FULL LENGTH REAC LEVEL CH-I NIS POWER RANGE ALARM D.C. AUX POWER RODS HYDR ISOLATOR OVERPOWER ROD ROD DEV & SEQ ON RODS AT BOTTOM TROUBLE WITHDRAWAL STOP NIS PWR RANGE D TILTS D XIS-68-390 NIS NC-46B R.M.S. SPARE ROD POSITION TS-68-398 REAC LVL CH-II CHANNEL NIS POWER RANGE CHANNEL SYSTEM REACTOR VESSEL HYDR ISOLATOR TEST CHANNEL ON TEST IN TEST VENT TEMP HI TROUBLE DEVIATION E E I I 2 T 3 4 15 16 7 SQN 1-AR-M4-B Page 2 of 46 I Rev. 28
6 (A-6)
Source SER 306 ROD CONTROL Logic Cabinet:
SYSTEM
- 1. Card removed.
URGENT
- 2. Pulser did not pulse.
FAILURE
- 3. Slave cycler received go signal while in cycle.
Power Cabinet:
- 1. Phase failure.
- 2. Regulation failure.
- 3. Logic error.
- 4. Multiplexing error.
- 5. Card removed.
- 6. Reactor trip breaker open.
- 7. Loss of power to MG sets.
Probable 1. Blown fuse or component failure.
Causes 2. Reactor trip breakers open.
- 3. Loss of power to MG sets.
- 4. Rod testing (e.g. 0-Sl-OPS-085-01 1 .0 or low power physics testing).
- 5. Misaligned I dropped rod recovery.
Corrective [1] PLACE rod control in manual.
Actions CAUTION Attempting to reset rod control urgent failure alarm using M-4 pushbutton, [1-RCAS1, prior to determining and correcting cause could result in dropped rods.
[2] DISPATCH MIG personnel to MG Set Room to investigate cause.
CORRECTIVE ACTIONS CONTINUED ON NEXT PAGE SQN 1-AR-M4-B Page 9 of 46 I Rev. 28
6 (A-6)
ROD CONTROL SYSTEM URGENT FAILURE NOTE The table below provides information on Control Rod Bank power supplies.
Bank Group Power Cabinet # of Rods Core Location Cntrl A 1 1AC 2 H-6, H-b 2 2AC 2 F-8, K-8 Cntrl B 1 1BD 4 F-2, P-6, B-b, K-14 2 2BD 4 K-2, B-6, P-1O, F-14 Cntrl C 1 1AC 4 H-2, P-8, B-8, H-14 2 2AC 4 K-6, F-6, K-b, F-lU Cntrl D 1 1BD 4 M-4, D-4, M-12, D-l2 2 2BD 5 H-4, M-8, H-8, D-8, H-12 SDA 1 1AC 4 E-5, L-5, E-i1, L-11 2 2AC 4 M-2, B-4, P-12, D-14 SD B 1 1RD 4 G-3, C-9, J-13, N-7 2 2BD 4 J-3, N-9, G-13, C-7 SD C 1 SCD 4 E-3, C-il, L-1 3, N-5 SD D 1 SCD 4 C-5, E-13, N-il, L-3 Corrective Actions [3] NOTIFY MIG to document, in Work Order, the status of the lights (Continued) on and in the affected power and logic cabinet(s).
[4] WHEN rod control urgent failure is in alarm, THEN NOTE the following:
[a] If problem is in the Power cabinet - control rods in that cabinet will not move.
[b] If problem is in the Logic cabinet - no rods will move.
[5] IF alarm is unexpected, THEN GO TO AOP-C.Oi, Rod Control System Malfunctions.
[6] MONITOR Plant Computer Rod Insertion Limit Display for abnormalities.
[7] EVALUATE Technical Specifications (3.1.3.1).
References 45B655-04B-O
SQN ROD CONTROL SYSTEM MALFUNCTIONS AQP-C.0.1 Rev. 20 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move CAUTION 1: Control Rods should NOT be manually withdrawn during a transient.
CAUTION 2: Attempting to move control rods with ROD CONTROL SYSTEM URGENT FAILURE alarm could result in dropped or misaligned rods.
CAUTION 3: Depressing ROD URGENT FAILURE RESET pushbutton on M-4 prior to determining and correcting cause could result in dropped rods.
CHECK ROD CONTROL SYSTEM IF ROD CONTROL SYSTEM URGENT URGENT FAILURE alarm LIT. FAILURE alarm is NOT LIT,
[M-4B, window A-6] THEN PERFORM the following:
- a. ENSURE rod control in MAN.
- b. GOTOStep17.
- 2. DETERMINE if rod control should be placed in MANUAL:
- a. CHECK rod control in AUTO. a. MAINTAIN rod control mode selector switch in current position.
GO TO Step 3.
- b. PLACE rod control in MAN.
Page 52 of 71
STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 3. CONTROL T-avg within 3°F of T-ref by performing one of the following:
. ADJUST turbine load OR
- 4. MONITOR following parameters IF uncontrolled transient in progress STABLE or CONTROLLED: AND control rods CANNOT be moved, THEN
- reactor power TRIP reactor and GO TO E-O, Reactor Trip
- Tavg or Safety Injection.
Page 53 of 71
JPM Sim B Page 1 of 14 Rev. 0
- SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIMB Align ECCS Pumps to the Containment Sump
JPM Sim B Page 2 of 14 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Align ECCS Pumps to the Containment Sump Task#: 3010060601 Task Standard: Align CCP and SI pump flowpath for sump recirc using ES-i .3 TRANSFER TO RHR CONTAINMENT SUMP within 8 minutes of the RWST Level Lo Alarm.
Alternate Path: YES: NO: X Time Critical Task: YES: X NO:
KIA Reference/Ratings: 006 A4.07 (4.4/4.4)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim B Page 3 of 14 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize to IC 215
- 4. Override annunciators an:ovrdn[304] to ON and an:ovrdn[420] to OFF, to silence nuisance alarms on Saturation Monitor and Cntmt Hi Moisture.
- 5. An extra operator will be required to acknowledge alarms.
- 6. ACKNOWLEDGE ALARMS
- 7. FREEZE SIMULATOR.
- 9. PLACE SIMULATOR IN RUN SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
Tools/Equipment/Procedures Needed:
References:
Reference Title ri. ES-i.3 TRANSFER TO RHR CONTAINMENT SUMP Rev No.
17
JPMSimB Page 4 of 14 Rev. 0 DIRECTIONS-TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. A LOCA is in progress on Unit 1
- 1. When conditions permit, you are directed perform ES-i .3, Transfer to Cold Leg Recirculation.
- 2. Notify the SRO when complete.
- 3. There is an element of this task that is time critical.
JPM Sim B Page 5 of 14 Rev. 0 Start Time STEP 1 : MISCELLANEOUS SAT I -XA-55-6E UNSAT LS-63-50A RWST LVL LO Corrective II] IF S1S has occurred with RWST level decreasing to 27%, THEN Actions PERFORM ES-i .3, Trasisfer 10 RI-IR Confainment Sump, as applicable.
Standard: Examinee acknowledges alarm and transitions to ES-i .3 TRANSFER TO RHR CONTAINMENT SUMP.
Provide a copy of ES-i .3 TRANSFER TO RHR CONTAINMENT SUMP.
Comment STEP Obtain a copy of ES-i .3 TRANSFER TO RHR CONTAINMENT SUMP 2
SAT UNSAT Standard: Examinee obtains a copy of ES-I .3 TRANSFER TO RHR CONTAINMENT SUMP.
Provide a copy of ES-i .3 TRANSFER TO RHR CONTAINMENT SUMP.
Comment
JPM Sim B Page 6 of 14 Rev. 0 STEP 3 : 1 SUSPEND FRP rnpementition. SAT UNSAT Standard: Examinee addresses procedure step.
If directed, acknowledge direction.
Comment STEP 4 : DETERMINE if contanrnent spriy SAT shoidd be stopped:
UNSAT a CHECK any containment spray pump RUNNING.
Standard Examnee verifies both Containment Spray pumps running by observing red indicating lights above pump handswitches ON.
Comment
JPM Sim B Page 7 of 14 Rev. 0 STEP 5 : 2 DETERMINE if containment spray SAT should be stopped:
UNSAT
- h. ENSURE the following:
Critical Step
- one Cntrnt Spray pump in PULL-TO-LOCK
- remaining Cntrnt Spray pump RUNNING.
Examinee ONLY places the A OR B Containment Spray 1-HS-72-27A Standard: or 1-HS-72-1 OA handswitch in PULL-TO-LOCK within 2 minutes of the RWST Level Lo Alarm, Comment Examiner This step is critical because by minimizing Containment Spray flow, Note. RWST will be reduced.
STEP 6 : 2. DETERMINE if containment spray SAT should be stopped:
- c. CHECK containment pressure UNSAT greater than or equal to 2.0 psig Examinee verifies containment pressure greater than or equal to 2.0 Standard: psig by observing PDI-30-45, PDI-30-44, PDI-30-43, or PDI-30-42 and proceeds to step 3.
Comment STEP 7 : 3. MONITOR RHR automatic switchover: SAT
- a. CHECK containment sump level UNSAT greater than 11%.
Standard Examinee checks containment sump level greater than 11% by observing LI-63-176, Ll-63-177, Ll-63-178, or Ll-63-179.
Comment
JPM Sirn B Page 8 of 14 Rev. 0 STEP 8 : 3. MONITOR RHR automatic switchover: SAT
- b. CHECK containment sump valves UNSAT FC\/-63-72 and FCV-63-73 OPEN.
Exarninee checks containment sump valves FCV-63-72 and FCV Standard: 73 OPEN by observing the red lights above 1-HS-63-72A and 1-HS-63-72A ON.
Corn ment STEP 9 : 3. MONITOR RHR automatic switc.hover: SAT
- c. CHECK RHR suction valves UNSAT FCV-74-3 and FCV-74-21 CLOSING.
Exarninee checks RHR suction valves FCV-74-3 and FCV-74-21 Standard: CLOSING by observing the red and green lights above 1-HS-74-3A and 1-HS-74-21A ON.
Corn ment STEP 10 : 4. MONITOR RWST supply to ECCS SAT pumps:
U N SAT
- RWST LVL LO-LO alarm DARK
[M-6E, E4J.
- RWSJ level greater than 8%.
Examinee monitors RWST LVL LO-LO alarm DARK on [M-6E, E4} by Standard: observing alarm window OFF and RWST level greater than 8% by observing LI-63-50, LI-63-51 LI-63-52, or LI-63-53.
Comment
JPM Sim B Page 9 of 14 Rev. 0 STEP 11 5. MONITOR RHR pumps RUNMNG. SAT U N SAT Standard Examinee monitors RHR pumps RUNNING by observing the red lights above 1-HS-74-1OA and 1-HS-74-20A ON.
Comment CAUTiON Transfer to sump recirculation may cause high radiation Procedure in Aux Building.
Note NOTE Step 6 should be handed off to a Unit 0pertor.
STEP 12 PERFORM the following: SAT UNSAT Standard Examinee directs another operator to perform step 6 and proceeds to step 7.
Acknowledge direction from the examinee Comment Examiner The station standard practice is for the BOP operator to perform Note manipulations outside the At The Controls Area during this evolution.
JPM Sim B Page 10 of 14 Rev. 0 STEP 13 : T VERIFY RHR automatic switchover: SAT UNSAT
- a. VERIFY containment sump valves FCV-63-72 and FCV-63-73 OPEN.
Examinee monitors containment sump valves FCV-63-72 and FCV Standard: 73 OPEN by observing the red indicating lights above 1-HS-63-72A and 1-HS-63-73A ON.
Comment STEP 14 : T VERIFY RHR automatic switchover: SAT
Examinee ensures RWST to RHR suction valves FCV-74-3 and FCV Standard: 74-21 CLOSED by observing the green indicating lights above 1-HS-74-3A and 1-HS-74-21A ON.
Comment CAUTION SI pump operation with miniflow isolated and RCS pressure above shutoff head will result in SI pump damage.
Procedure Note NOTE The foHowinq continuous action applies even after this procedure is exited.
STEP 15 : 8. MONITOR RCS pressure SAT less than 1500 psig.
U N SAT Standard Examinee monitors RCS pressure less than 1500 psig by observing P1-68-62, P1-68-69 or other installed plant instrumentation.
Comment
JPM Sim B Page 11 of 14 Rev. 0 STEP 16 CLOSE SI pump miniflow to RWST SAT valves:
UNSAT
- FCV-63-3 Critical Step FCV-63-4
- FCV-63-175 Standar& Examinee paces 1HS-63-3A AND 1-HS-63-4A AND 1-HS-63-175A to CLOSE Comment Examiner This step is critical because it prevents injection of radioactive Note recirculation water into the RWST STEP 17 : CLOSE RHR crosstie valves: SAT
- FC*V-74-33 UNSAT Critical Step
- FCV-74-35 Standard: Examirtee places 1-HS-74-33A AND iHS-74-35Ato CLOSE Comment Examiner This step is critical because it establish the cold leg recirculation flow Note path and isolates the RHR trains to protect against a passive single failure later in the accident.
JPM Sim B Page 12 of 14 Rev. 0 STEP 18 : I OPEN CCP and SI pump suction valves SAT from RHR:
U N SAT
- FCV-63-7 Critical Step
- FCV-G3-6 Standard: Examinee places 1-1-IS-63-7A AND 1-HS-63-6A to OPEN Comment This step is critical because it establish the cold leg recirculation flow Examiner path and aligns CCP and SI pump suctions to the discharge of the Note RHR pumps ensure injection during small break LOCAs when RCS pressure remains above the RHR pump shutoff head.
STEP 19 : IZ ALIGN RHR discharge to CCP and SI SAT pump suction:
UNSAT a OPEN RHR discharge to CCP suction Critical Step FCV-63-8.
Standard Examinee. places 1-HS-63-8A to OPEN within .8 minutes of the RWST Level LoAlarm, Comment This step is critical because it establish the cold leg recirculation flow Examiner path and aligns CCP and SI pump suctions to the discharge of the Note RHR pumps ensure injection during small break LOCAs when RCS pressure remains above the RHR pump shutoff head.
JPM Sim B Page 13 of 14 Rev. 0 STEP 20 : 12. ALIGN RHR discharge to COP and SI SAT pump suction:
U N SAT b OPEN RHR discharge to SI pump Critical Step sucPon FCV-63-i 1 Standard Examinee places 1-HS-63-1 IA to. OPEN within 6 minutes of the RWST Level Lo Alarm.
Comment This step is critical because it establish the cold leg recirculation flow Examiner path and aligns CCP and SI pump suctions to the discharge of the Note RHR pumps ensure injection during small break LOCAs when RCS pressure remains above the RHR pump shutoff head.
Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPM Sim B Page 14 of 14 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. A LOCA is in progress on Unit 1
- 1. When conditions permit, you are directed perform ES-i .3, Transfer to Cold Leg Recirculation.
- 2. Notify the SRO when complete.
- 3. There is an element of this task that is time critical.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
I MISCELLANEOUS I -XA-55-6E 1 2 I 3 4 5 6 17 481W DIESEL AUX 480V DIESEL AUX 480V REAC MOV 480V REAC MOV 480V SHUTDOWN 480V SHUTDOWN REACTOR COOLANT BD 1A1-AJ1A2-A BD 1B1-B/1B2-B BD 1A1-A/1A2-A BD 1B1-B/182-B BD 1A1-AI1A2-A BD 1B1-B/1B2-B PMP lA/lB/iC/iD TRANSFER SWITCH TRANSFER SWITCH TRANSFER SWITCH TRANSFER SWITCH TRANSFER SWITCH TRANSFER SWITCH TRANSFER SWITCH A IN AUX MODE IN AUX MODE IN AUX MODE IN AUX MODE IN AUX MODE IN AUX MODE IN AUX MODE A
6900V SHUTDOWN 6900V SHUTDOWN PANEL i-L-1 1A PANEL O-L-6 HS-61--191B TS-61-99A/B T5-61-99B1A BOARD lA-A BOARD lB-B TRANSFER SWITCH AUX BOILER A HS-61-193B FLOOR COOLANT FLOOR COOLANT TRANSFER SWITCH TRANSFER SWITCH IN AUX MODE SYSTEM MISALIGNMENT TEMP HI TEMP LO IN AUX MODE IN AUX MODE ABNORMAL B B
PANEL 1-R-73 PANEL l-L-11A PANEL l-L-11B PANEL O-L-7 ICE CONDENSER ZS-61-186 PDIS61-128 OR l-R-74 FUSE TRANSFER SWITCH AUX BOILER B BACK DRAFT ICE CONDENSER FLOOR COOLANT FUSE BLOWN BLOWN IN AUX MODE SYSTEM DAMPER CLOSED LOWER INLET P LO c ABNORMAL DOOR OPEN c
PANEL 1-R-77 PANEL 1-L-11B LS-63-46B LS-63-46A LIS-61-195A/B LIS-61-195B/A TIS-74-7 OR i-R-78 FUSE RWST RWST GLYCOL EXP GLYCOL EXP RHR PUMP IA-A FUSE BLOWN BLOWN FILL MAKE-UP TANK LEVEL TANK LEVEL SEAL HTX OUT SHUTOFF HI-HI-HI LOW-LOW-LOW TEMP HI/HI-HI D D NON-DIV AUX PANEL 1-L-1O LS-63-50A LS-63-50B MOTOR CALORIMETRIC TIS-74-19 RELAYRACK FUSE RWST RWST TRIPOUT U2I18OR RHRPUMP1B-B FUSE BLOWN BLOWN LVL LO LVL LO-LO PANEL l-M-9 PLANT COMPUTER SEAL HTX OUT TROUBLE TEMP HI/HI-HI E E II I I 2 I 3 4 5 I 6 17 SQN I -AR-M6-E Page 2 of 41 I Rev. 22
31 (E-3)
Source Setpoint SER 631 SER 863 LS-63-50A SER 864 RWST SER 865 LVL LO LS-63-50A 27% level decreasing LS-63-5 1 A LS-63-52A LS-63-53A Probable 1. Tank in use for refueling operations.
Causes 2. Safety injection.
- 3. Instrument malfunction.
NOTE If low level due to safety injection, then the RHR pump suction auto swapover from the RWST to containment sump should have occurred.
Corrective [1] IF SIS has occurred with RWST level decreasing to 27%, THEN Actions PERFORM ES-i .3, Transfer to RHR Containment Sump, as appiicable.
[2] VERIFY RWST level by observing F1-LI-63-501, F1-LI-63-511, 11-LI-63-521, or 11-LI-63-531.
[3] IF unit in refueling operation, THEN NOTE that this is a normal condition.
[4] IF need to increase level in RWST, THEN GO TO O-SO-62-7, Boron Concentration Control.
[5] IF RWST level instrument (i-L-63-50, 51, 52, or 53) has failed, THEN GO TO AOP-l.09, RWST Level Instrument Malfunction.
[6] EVALUATE Technical Specifications.
References 45B655-06E-O, 47W304-3 SQN I -AR-M6-E Page 34 of 41 I Rev. 22
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY SUBPROCEDURE ES-I .3 TRANSFER TO RHR CONTAINMENT SUMP Revision 17 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 02/16/10 REVISION DESCRIPTION: Swapped order of Step 2 and 3 to gain margin with respect to 2 minute time limit for stopping one CS pump (PER 213553, PCR 09001641). Changed Substep 14.a to NOT be a continuous action. Made other minor editorial changes.
This procedure contains a Handout Page (2 copies).
THIS PROCEDURE HAS TIME-CRITICAL ACTIONS
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-I .3 Rev. 17 HANDOUT Page 1 of 2 STEP__[ ACTION 2.d (if one containment spray pump was stopped)
MONITOR one cntmt spray pump RUNNING and delivering flow.
- 3. MONITOR RHR automatic switchover:
- 4. WHEN RWST level is less than or equal to 8%,
RNO THEN PULL TO LOCK any pumps taking suction from RWST.
- 5. MONITOR RHR pumps RUNNING.
6.c. (if CCS flow to RHR HX less than 5050 gpm)
RNO WHEN transfer to containment sump completed, THEN RAISE CCS flow to affected units RHR heat exchangers.
6.d. MONITOR CCS temperature and surge tank level.
7.a (if containment sump valve fails to open)
RNO WHEN containment sump valve FCV-63-72 or FCV-63-73 is OPEN, THEN ENSURE RHR pump on associated train RUNNING.
7.b (if RHR suction valve and containment sump valve on same train OPEN)
RNO WHEN power restored to FCV-63-1, THEN CLOSE FCV-63-1
- 8. MONITOR RCS pressure less than 1500 psig.
IF RCS pressure greater than or equal to 1500 psig, THEN STOP SI pumps.
- 15. MONITOR shutdown boards continuously energized.
- 15. IF shutdown board power lost, RNO THEN PULL TO LOCK affected CCP(s).
WHEN shutdown board(s) re-energized, THEN RESTART ECCS pumps.
1 a of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 HANDOUT Page 2 of 2 STEP
[ ACTION 1 9.a. (if power not yet restored to FCV-63-1)
RNO WHEN power restored, THEN CLOSE FCV-63-1.
21 .a WHEN RWST level is less than or equal to 8%
RNO OR containment sump level greater than or equal to 56%,
THEN ALIGN containment spray suction to sump USING applicable substeps in Step 21.
21 .f (if containment pressure less than or equal to 2.0 psig) and WHEN containment sump level greater than 18% [22% ADV],
21.1 THEN PLACE containment spray pumps aligned for sump recirc in A-AUTO.
RNO 21 .g (if containment pressure greater than 2.0 psig) and WHEN containment sump level greater than 18% [22% ADVI, 21 .m THEN ESTABLISH containment spray flow USING Substep 21 .h and 21 .n RNO 21 .h WHEN Train A containment spray alignment established, RNO THEN START Containment Spray pump A-A.
(if cntmt pressure greater than 2.0 psig and sump level greater than 18% [22% ADV])
21 .n. WHEN Train B containment spray alignment established, RNO THEN START Containment Spray pump B-B.
(if cntmt pressure greater than 2.0 psig and sump level greater than 18% [22% ADVI) 21.0 WHEN any cntmt spray pump RUNNING, RNO THEN PERFORM Substeps 21.p and q.
- 22. MONITOR if RHR spray should be placed in service:
. Containment pressure greater than 9.5 psig
. At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident a At least one CCP AND one SI pump RUNNING
- 23. MONITOR for containment sump blockage.
- 27. (if RCS pressure less than 300 psig)
RNO WHEN TSC staffed, THEN NOTIFY TSC to evaluate whether hot leg recirc will be required.
lb of 24
SQN TRANSFERTORHR CONTAINMENT SUMP - ES-1.3 Rev. 17 HANDOUT Page 1 of 2 STEP ACTION 2.d (if one containment spray pump was stopped)
MONITOR one cntmt spray pump RUNNING and delivering flow.
- 3. MONITOR RHR automatic switchover:
- 4. WHEN RWST level is less than or equal to 8%,
RNO THEN PULL TO LOCK any pumps taking suction from RWST.
- 5. MONITOR RHR pumps RUNNING.
6.c. (if CCS flow to RHR HX less than 5050 gpm)
RNO WHEN transfer to containment sump completed, THEN RAISE CCS flow to affected units RHR heat exchangers.
6.d. MONITOR CCS temperature and surge tank level.
7.a (if containment sump valve fails to open)
RNO WHEN containment sump valve FCV-63-72 or FCV-63-73 is OPEN, THEN ENSURE RHR pump on associated train RUNNING.
Tb (if RHR suction valve and containment sump valve on same train OPEN)
RNO WHEN power restored to FCV-63-1, THEN CLOSE FCV-63-1
- 8. MONITOR RCS pressure less than 1500 psig.
IF RCS pressure greater than or equal to 1500 psig, THEN STOP SI pumps.
- 15. MONITOR shutdown boards continuously energized.
- 15. IF shutdown board power lost, RNO THEN PULL TO LOCK affected COP(s).
WHEN shutdown board(s) re-energized, THEN RESTART ECCS pumps.
1 c of 24
SQN I TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 HANDOUT Page 2 of 2 STEP ACTION 1 9.a. (if power not yet restored to FCV-63-1)
RNO WHEN power restored, THEN CLOSE FCV-63-1.
21 .a WHEN RWST level is less than or equal to 8%
RNO OR containment sump level greater than or equal to 56%,
THEN ALIGN containment spray suction to sump USING applicable substeps in Step 21.
21 .f (if containment pressure less than or equal to 2.0 psig) and WHEN containment sump level greater than 18% [22% ADV],
21 .1 THEN PLACE containment spray pumps aligned for sump recirc in A-AUTO.
RNO 21 .g (if containment pressure greater than 2.0 psig) and WHEN containment sump level greater than 18% [22% ADV],
21 .m THEN ESTABLISH containment spray flow USING Substep 21 .h and 21 .n RNO 21 .h WHEN Train A containment spray alignment established, RNO THEN START Containment Spray pump A-A.
(if cntmt pressure greater than 2.0 psig and sump level greater than 18% [22% ADVI) 21 .n. WHEN Train B containment spray alignment established, RNO THEN START Containment Spray pump B-B.
(if cntmt pressure greater than 2.0 psig and sump level greater than 18% [22% ADVI) 21.0 WHEN any cntmt spray pump RUNNING, RNO THEN PERFORM Substeps 21.p and q.
- 22. MONITOR if RHR spray should be placed in service:
. Containment pressure greater than 9.5 psig
. At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident
. At least one CCP AND one SI pump RUNNING
- 23. MONITOR for containment sump blockage.
- 27. (if RCS pressure less than 300 psig)
RNO WHEN TSC staffed, THEN NOTIFY TSC to evaluate whether hot leg recirc will be required.
1 d of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP -
ES-1.3 Rev.17 1.0 PURPOSE This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode.
This procedure includes the following time-critical actions:
DESCRIPTION OF ACTION TIME LIMIT Stop one Cntmt Spray Pump when RWST level reaches 27% 2 minutes Stop running Cntmt Spray pump if RWST level reaches 8% 1.5 minutes Align CCP and SI pump flowpath for sump recirc 8 minutes when RWST level reaches 27%
Align Cntmt Spray Pump for recirculation and restore flow 5 minutes Initiate RHR spray flow when conditions met 10 minutes 2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS E-1 Loss of Reactor or Secondary Coolant:
- RWST level less than 27%.
ECA-2. I Uncontrolled Depressurization of All Steam Generators:
- RWST level less than 27%.
Other EOPs:
- When RWST level reaches the switchover setpoint.
3.0 OPERATOR ACTIONS 2 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-I .3 Rev. 17 ISTEPI IACTIONIEXPECTED RESPONSE J IRESPONSE NOT OBTAINED I SUSPEND FRP implementation.
- 2. DETERMINE if containment spray should be stopped:
- a. CHECK any containment spray pump a. GO TO Step 3.
RUNNING.
- b. ENSURE the following:
- one Cntmt Spray pump in PULL-TO-LOCK
- remaining Cntmt Spray pump RUNNING.
- c. CHECK containment pressure c. PERFORM the following:
greater than or equal to 2.0 psig.
- 1) RESET containment spray signal.
- 2) ENSURE both cntmt spray pumps STOPPED and PLACE n A-AUTO.
- 3) CLOSE cntmt spray discharge valves FCV-72-39 and FCV-72-2.
- 4) GO TO Step 3.
(step continued on next page) 3 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 ISTEPI ACTION/EXPECTED RESPONSE RESPONSE NOTOBTAINED
- 2. d. MONITOR one cntmt spray pump d. IF ALL of following conditions met:
RUNNING and delivering flow.
. RWST level is greater than 8%
- containment pressure greater than 2.8 psig
- Step 21 NOT in progress THEN START one cntmt spray pump and ENSURE discharge valve OPEN.
- 3. MONITOR RHR automatic switchover:
- a. CHECK containment sump level a. PERFORM the following:
greater than 11%.
- 1) RESUME FRP implementation.
- b. CHECK containment sump valves b. IF any sump valve is CLOSED, FCV-63-72 and FCV-63-73 OPEN. THEN ATTEMPT to open affected sump valve from MCR.
- c. CHECK RHR suction valves c. IF sump valve on affected train FCV-74-3 and FCV-74-21 is opening, CLOSING. THEN ATTEMPT to close RHR suction valve from MCR.
4 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-13 Rev. 17 ISTEPI ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED
THEN
- RWST LVL LO-LO alarm DARK PULL TO LOCK any pumps
[M-6E, E4]. taking suction from RWST:
- RWST level greater than 8%. a. Containment spray pumps.
- b. SI pumps.
- c. CCPs.
- 5. MONITOR RHR pumps RUNNING. IF NO RHR pump running AND COPs or SI pumps have lost suction, THEN STOP affected CCPs and SI pumps.
START RHR pumps.
IF NO RHR pump can be started, THEN PERFORM the following:
- a. RESUME FRP implementation.
5 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED CAUTION Transfer to sump recirculation may cause high radiation in Aux Building.
NOTE Step 6 should be handed off to a Unit Operator.
- 6. PERFORM the following:
- a. DISPATCH personnel to restore power to FCV-63-1 USING EA-201-1, 480 V Board Room Breaker Alignments.
- b. OPEN RHR heat exchanger outlet b. DISPATCH operator with Radcon valves FCV-70-156 and FCV7O-153. to OPEN valves locally.
[AB el. 690, near elevator]
- c. VERIFY CCS flow Fl-70-1 59A and c. WHEN transfer to containment sump Fl-70-165A greater than 5050 gpm. completed, THEN RAISE CCS flow to affected units RHR heat exchangers USING EA-70-1, Component Cooling System Operation.
- d. MONITOR CCS temperature and surge tank level.
6 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 ISTEPI IACTIONIEXPECTED RESPONSE I IRESPONSENOTOBTAINED I
- 7. VERIFY RHR automatic switchover:
FCV-63-72 and FCV-63-73 OPEN. CANNOT be opened, THEN PULL TO LOCK RHR pump on affected train(s).
IF Train A containment sump valve FCV-63-72 CANNOT be opened, THEN PERFORM the following:
- 1) CLOSE FCV-74-3 Train A RHR suction valve to satisfy interlock.
- 2) WHEN FCV-74-3 is CLOSED, THEN ATTEMPT to OPEN FCV-63-72.
- 3) WHEN FCV-63-72 is OPEN, THEN ENSURE RHR Pump A-A RUNNING.
(Step continued on next page.)
7 of 24
I STEP] ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I
- 7. a. (Continued) IF Train B containment sump valve FCV-63-73 CANNOT be opened, THEN PERFORM the following:
- 1) CLOSE FCV-74-21 Train B RHR suction valve to satisfy interlock.
- 2) WHEN FCV-74-21 is CLOSED, THEN ATTEMPT to OPEN FCV-63-73.
- 3) WHEN FCV-63-73 is OPEN, THEN ENSURE RHR Pump B-B RUNNING.
IF NO containment sump recirculation path can be established, THEN PERFORM the following:
- 1) RESUME FRP implementation.
- b. ENSURE RWST to RHR suction b. IF containment sump valve valves FCV-74-3 and FCV-74-21 on affected train (FCV-63-72 or CLOSED. FCV-63-73) is OPEN, THEN PERFORM the following:
- WHEN power restored to FCV-63-1, THEN CLOSE FCV-63-1 WHILE monitoring RHR flow.
8 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 ISTEPI ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED CAUTION SI pump operation with miniflow isolated and RCS pressure above shutoff head will result in SI pump damage.
NOTE The following continuous action applies even after this procedure is exited.
valves:
FCV-63-3 CLOSED
- FCV-63-3
- FCV-63-4 OR
- FCV-63-175
- FCV-63-4 and FCV-63-175 CLOSED.
- 10. CLOSE RHR crosstie valves: ENSURE the following:
- FCV-74-33
- FCV-74-33 CLOSED
- FCV-74-35. OR
- FCV-74-35 CLOSED.
9 of 24
SQN TRANSFER TO RHR CONTAINMENT SUMP ES-1.3 Rev. 17 ISTEPI IACT1ONIEXPECTED RESPONSE I IRESPONSENOTOBTAINED
from RHR:
- FCV-63-7 OPEN
- FCV-63-7 OR
- FCV-63-6.
- FCV-63-6 OPEN.
FCV-63-8.
- Train B RHR pump RUNNING
- FCV-63-1 1 OPEN.
suction FCV-63-1 1.
- Train A RHR pump RUNNING
- FOV-63-8 OPEN.
- 13. VERIFY Steps 9 through 12 DO NOT CONTINUE this procedure COMPLETED. UNTIL Steps 9, 11, and 12 COMPLETED.
10 of 24
JPM Sim C Page 1 of 15 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIMC Isolate the Ruptured Steam Generator (With MSIV Failure to Close) c 4--
as q ss ??p pr g
JPM Sim C Page 2 of 15 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Isolate the Ruptured Steam Generator (With MSIV Failure to Close)
Task#: 0000380501 Task Standard: Steam Generator #1 is isolated with a failed #1 MSIV using E-3 Steam Generator Tube Rupture Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X K/A Reference/Ratings: EPE 038 EAI.32 (4.6/4. 7)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 11 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim C Page 3 of 15 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize simulator in IC #212.
a) Activate malfunction IMF THO5A f:8.5 to initiate S/G tube rupture in S1G #1.
b) Activate malfunction IMF MS14A f:100, to fail open SIG Loop 1 MSIV.
c) Actuate a MANUAL reactor trip and safety injection, take all actions up through Step 3 of E-3.
d) Complete the actions of E-0 thru step 12, which will transition the crews to E-3 e) Complete any required actions in ES-0.5. Including closing the TD AFW LCVs, but do not put handswitches in pull-to-lock.
f) Complete the first three steps in E-3.
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR.
- 7. Provide a copy of E-3 STEAM GENERATOR TUBE RUPTURE
- 8. PLACE SIMULATOR IN RUN SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
References:
[ Reference Title Rev No.
r 1. E-3 STEAM GENERATOR TUBE RUPTURE 18
JPM Sim C Page 4 of 15 Rev. 0 DIRECTIONS TO TRAiNEE: -
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Steam Generator Tube Rupture on Steam Generator #1.
- 2. A manual safety injection was initiated.
- 3. E-3, STEAM GENERATOR TUBE RUPTURE is in progress, steps 1 through 3 of E-3 have been completed INITIATING CUES:
- 1. You have been directed to continue with E-3, STEAM GENERATOR TUBE RUPTURE beginning at Step 4.
- 2. Inform the SRO when you have isolated the #1 Steam Generator.
JPM Sim C Page 5 of 15 Rev. 0 Start Time STEP 1 : ObtainacopyofE-3,STEAMGENERATORTUBERUPTURE SAT U N SAT Examinee obtains a copy of E-3, STEAM GENERATOR TUBE Standard: RUPTURE Cue Provide a marked up copy of E-3, STEAM GENERATOR TUBE RUPTURE completed through step 3.
Comment Procedure CAUTION If the TD AFW pump is the only source of feed flow, isolating both Caution: steam supplies will result in loss of secondary heat sink.
STEP 2 : ISOLATE flow from Ruptured S.IG(s): SAT
- a. ADJUST Ruptured SIG(s) H UNSAT
. atmospheric relief controller setpoint Critical Step to 87% in AUTO. (1Q40 psig)
Standard: Examinee adjusts automatic setpoint for PIG1-6A to 87%.
Comment Examiner This step is critical because it preempts opening the ruptured Steam Note Generator atmospheric relief valve.
JPM Sim C Page 6 of 15 Rev. 0 STEP 3 4. ISOLATE flow from Ruptured S/G(s):
- b. CHECK Ruptured SfG(s) UNSAT atmospheric relief hand switch in P-AUTO and valve(s) CLOSED.
Standard Examinee observes SIG #1 atmospheric relief handswitch, 1-HS-1-6, on 1-M-4 in P-AUTO.
Corn ment STEP 4 : 4. ISOLATE flow from Ruptured S/G(s): SAT c CHECK S/G #1 or 4 ruptured. UNSAT Standard Examinee observes steam generator #1 level rising with no feed or by referring to the initial conditions.
Comment STEP 5 : 4 ISOLATE flow from Ruptured SIG(s): SAT
- d. CLOSE TD AFW pump steam UNSAT supply from Ruptured S/G Critical Step FCV-i-15(S/G#1)or FCV-i-16(SJG#4).
Standard Examinee places 1-HS 15 TD AFW pump steam supply to SIG #1 to CLOSE Comment Examiner This step is critical because it isolates a flowpath from the ruptured Note steam generator to atmosphere.
JPM Sim C Page 7 of 15 Rev. 0 STEP 6 4. ISOLATE flow from Ruptured S/G(s); SAT
- e. VERIFY Ruptured S!G(s) blowdown UNSAT isolation valves CLOSED Standard: Examinee observes FCV-1-7 and FCV-1-181 CLOSED green indication lights above handswitch 1-HS-1-7/181 on 1-M-4 ON.
Comment STEP 7 4. ISOLATE flow from Ruptured S/G(s):
Examinee places 1-HS-1-4 SIG #1 MSIV to CLOSE. Recognizes Standard: MSIV FCV-1-4 failed to close, by the red light above 1-HS-1-4 ON, and goes to the RNO to isolate the SIG.
Comment Examiner S/G #1 MSIV will NOT close and the operator MUST go to the RNO Note column
JPM Sim C Page 8 of 15 Rev. 0 Alternate path STEP 8 : SAT
- 4 ISOLATE flow from Ruptured S/G(s):
UNSAT
. f. PERFORM the following: Critical Step I) CLOSE Intact SF0 MSIVs and MSIV bypass valves.
Critical) Examinee places handswitches for the intact SIG MSIVi1 HS-I I IA, I -HS-1 -22A, & I-HS-I -29A to CLOSE.
Standard:
(Not Critical) Examinee verifies MSIV bypasses closed by observing green lights ON above handswitch 1-HS-1-148, 1-HS-1-149, & 1-HS-1-150 MSIV bypass valves.
Comment Examiner This step is critical because it isolates the steam side flowpath from Note the all intact steam generators which isolates the ruptured steam generator from atmosphere.
STEP g : ISOLATE flow from Ruptured 5/0(s):
SAT t PERFORM the following: UNSAT
- 2) DISPATCH operator to perform EA i-I, Closing MSIVs Locally, for any MSIV or MSIV bypass valve which fails to close.
StandardS Examinee dispatches an operator to perform EA- 1-1, Closing MSIVs Locally, for #1 SIG MS IV.
Acknowledge the direction from the examinee.
Comment
JPM Sim C Page 9 of 15 Rev. 0 STEP 10 : 4. ISOLATE flow from Ruptured S/G(s):
{ PERFORM the following:
UNSAT
- 3) ISOLATE steam header: Critical Step
- PLACE condenser steam dumps in OFF. [M-4]
Standard Examinee places I -HS-1 -1 OSA and I -I-IS-I -I 03B Steam Dump Valves to Condenser to OFF.
Comment Examiner This step is critical because it isolates the steam side flowpath from Note the main steam lines which isolates the ruptured steam generator from atmosphere.
STEP 11 : 4 ISOLATE flow from Ruptured SIG(s):
- f. PERFORM the following:
UNSAT
- 3) ISOLATE steam header:
ENSURE steEirn dump valves CLOSED [M-4]
Standard Examinee verifies the steam dump valves are closed by observing green light indication on 1 -XX-55-4A for all steam dump valves are ON Comment
JPM Sim C Page 10 of 15 Rev. 0 STEP 12 : ISOLATE flow from Ruptured S1G(s):
SAT f PERFORM the following:
UNSAT
- 3) ISOLATE steam header: Critical Step CLOSE FCV-47-180, HP Steam Seal Supply Isolation. [M-2]
Standard Examinee places 1-I-IS-47-180, HP Steam Seal Supply lsolatioto CLOSE, Comment Examiner This step is critical because it isolates the steam side flowpath from Note the main steam lines which isolates the ruptured steam generator from atmosphere.
STEP 13 ISOLATE flow from Ruptured S/G(s):
- f. PERFORM the following:
UNSAT
- 3) ISOLATE steam header:
- ENSURE ECV-47-181 HP Steam Seal Supply Bypass CLOSED. [M-2J Examinee verifies FCV-47-181 HP Steam Seal Supply Bypass Standard: CLOSED by observing green light indication above the handswitch to ON.
Comment
JPM Sim C Page 11 of15 Rev. 0 STEP 14 : ISO LATE flow from Ruptured S/Gs): :
- f. PERFORM the following:
UNSAT
- isolation valves. [M-2}
Examinee places all handswitches MSR HP steam supply isolation and MSR HP steam supply bypass valves to the CLOSE position:
1-HS-1-141A 1-HS-1-135A 1-HS-1-241A 1-HS-1-235A Standard:
1-HS-1143A 1-HS-i137A :
1-HS1-243A 1-HS-1-237A 1-HS1145A 1-HS-1-139A 1HS1245A 1H51239A Comment Examiner This step is critical because it isolates the steam side flowpath from Note the main steam lines which isolates the ruptured steam generator from atmosphere.
JPM Sim C Page 12 of 15 Rev. 0 STEP 15 4. ISOLATE flow from Ruptured S/G(s):
- f. PERFORM the followincj:
UNSAT
- 3) ISOLATE steam header:
- DISPATCH operator to locally isolate steam header USING EA-i-4. Local Isolation of Steam Header in Turb Bldg.
Standard Examinee dispatches an operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.
Acknowledge the direction from the examinee.
Comment STEP 16 ISOLATE flow from Ruptured S/G(s):
SAT F PERFORM the following:
UNSAT
- 4) USE Intact S/G(s) atmospheric relief for steam dump Standard: Examinee addresses the procedure step.
Comment
JPM Sim C Page 13 of 15 Rev. 0 STEP 17 : MONITOR Ruptured SfG(s) level:
SAT UNSAT
- a. CHECK ruptured Sf0 narrow range level greater than 10% [25% ADVI.
Examinee verifies #1 S/G narrow range level greater than 10% by Standard: observing Ll-3-42, or Ll-3-39, or Ll-3-38 or other installed plant instrumentation.
Comment STEP 18 : 5. MONITOR Ruptured S/G(s) level: SAT
- b. ENSURE AEW isolated UNSAT to ruptured Sf0: : Critical Step
. i CLOSE AFW LCVs for ruptured 5/0.
Examinee depresses selector switch for LCV-3-164A Motor Driven Standard: AFW pump to SIG #1 to ACCIDENT RESET, and selects 1-HS 164A to MANUAL or BYPASS.
Comment Examiner This step is critical because it ensures feed to the ruptured steam Note generator remains isolated.
JPM Sim C Page 14 of 15 Rev. 0 STEP 19 : 5. MONITOR Ruptured S/C(s) level: SAT
- b. ENSURE AFW isolated UNSAT to ruptured S/C: Critical Step
- 2) PLACE Turbine Driven AFW LC\/ for ruptured S/C
- in CLOSE PULL TO LOCK.
Standard Examinee places 1-HS-3-174A Turbine Driven AFW LCV for #1 SIGto.
CLOSE and PTL.
Comment Cue Provide the following cue Another operator will perform the remaining steps of this procedure.
Examiner This step is critical because it isolates feed to the ruptured steam Note generator Terminating The task is complete when the Examinee isolates the #1 Steam ue. Generator Stop Time
JPM Sim C Page 15 of 15 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Steam Generator Tube Rupture on Steam Generator #1.
- 2. A manual safety injection was initiated.
- 3. E-3, STEAM GENERATOR TUBE RUPTURE is in progress, steps 1 through 3 of E-3 have been corn pleted INITIATING CUES:
- 1. You have been directed to continue with E-3, STEAM GENERATOR TUBE RUPTURE beginning at Step 4.
- 2. Inform the SRO when you have isolated the #1 Steam Generator.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOl PROGRAM MANUAL EMERGENCY PROCEDURE E-3 STEAM GENERATOR TUBE RUPTURE Revision 18 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 7/30/2010 REVISION DESCRIPTION: Revised Step 5 to incorporate contingency actions for inability to isolate AFW from MCR (PER 221800, PCR 10000217).
Converted Step 5 caution into substep (PCR 08001122).
Changed Step 17 to a continuous action (PCR 07001811).
Enhanced Substep 20.b RNO (PCR 08000692), Changed Step 25 to NOT be a continuous action and clarified RNO actions (PCR 10000183). Clarified substep 30.e (PCR 08001134).
incorporated various other enhancements (PCR 07001857 and 08000045).
This procedure contains a Foldout Page and a Handout Page (2 copies).
51h C
L SQN STEAM GENERATOR TUBE RUPTURE
[STEP 1 [ACTION/EXPECTED RESPONSE [SPONSE NOT OBTAINED I This procedure has a foldout page.
MONITOR at least one RCP RUNNING. IF all RCPs are STOPPED, THEN PERFORM the following:
- a. SUSPEND monitoring ruptured loop T-cold indication on PTS status tree.
- b. WHEN step 32 is completed OR E-3 is exited, THEN RESUME monitoring ruptured loop T-cold indication on PTS status tree.
MONITOR RCP trip criteria:
- a. CHECK the following: GO TO Step 3.
- RCS pressure less than 1250 psig AND
- b. STOP RCPs.
Page 4 of 44
SQN STEAM GENERATOR TUBE RUPTURE I STEf] ACTIONIEXPECTED RESPONSE j [iESPONSE NOT OBTAINED MONITOR indications of Ruptured SIG(s):
i
)
4 IDENTIFY Ruptured S/G(s) as a. WHEN Ruptured S1G(s) identified, f indicated by any of the foflowing: THEN PERFORM Steps 4 through 8.
Unexpected rise in any S/G narrow range level. GO TO Step 9.
OR J-1igh radiation from any S1G sam pie 7
OR (7) lines RADCON survey of main steam 7 and SIG blowdown lines.
OR High radiation on any main steamline radiation monitor.
Page 5of44
SQN STEAM GENERATOR TUBE RUPTURE Rev,18 L]ZEP [fCTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED ZTION If the TD AFW pump is the only source of feed flow, isolating both steam supplies will result in loss of secondary heat sink.
ISOLATE flow from Ruptured S/G(s):
- a. ADJUST Ruptured SIG(s) atmospheric relief controller setpoint to 87% in AUTO. (1040 psig)
- b. CHECK Ruptured S/G(s) b. WHEN Ruptured S/G(s) pressure atmospheric relief hand switch in less than 1040 psig, P-AUTO and valve(s) CLOSED. THEN PERFORM the following:
- 1) VERIFY atmospheric relief CLOSED.
- 2) IF atmospheric relief NOT closed, THEN CLOSE atmospheric relief.
IF Ruptured S/G(s) atmospheric relief CANNOT be closed, THEN DISPATCH personnel to close atmospheric relief USING EA-1-2, Local Control of SIG PORVs.
(Step continued on next page.>
Page 6 of 44
SQN STEAM GENERATOR TUBE RUPTURE 18 I STEP I I ACTION!EXPECTED RESPONSE I I RESPONSE NOT OBTAINED CAUTION If the TD AFW pump is the only source of feed flow, isolating both steam supplies will result in loss of secondary heat sink.
- 4. ISOLATE flow from Ruptured SIG(s):
- a. ADJUST Ruptured S/G(s) atmospheric relief controller setpoint to 87% in AUTO. (1040 psig)
- b. CHECK Ruptured SIG(s) b. WHEN Ruptured SIG(s) pressure atmospheric relief hand switch in less than 1040 psig, P-AUTO and valve(s) CLOSED. THEN PERFORM the following:
- 1) VERIFY atmospheric relief CLOSED.
- 2) IF atmospheric relief NOT closed, THEN CLOSE atmospheric relief.
IF Ruptured SIG(s) atmospheric relief CANNOT be closed, THEN DISPATCH personnel to close atmospheric relief USING EA-1-2, Local Control of S/G PORV5.
(Step continued on next page.)
Page 6 of 44
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.18 ISTEPI ACTIONIEXPECTED RESPONSE I IRESPONSE NOT OBTAINED 7
- 4. c. CHECK SIG #1 or #4 ruptured. c. GO TO Substep 4.e.
- d. CLOSE TD AFW pump steam d. IF at least one MD AFW pump running, supply from Ruptured SIG THEN FCV-1-15 (SIG #1) or ISOLATE steam to TD AFW pump FCV-1-16 (SIG #4). USING FCV-1-17 or FCV-1 -1 8.
IF TD AFW pump is still running, THEN DISPATCH operator to locally close steam supply from ruptured SIG FCV-1-15 or FCV-1-16.
[West Valve Vault Room]
- e. VERIFY Ruptured SIG(s) blowdown e. CLOSE valve(s).
isolation valves CLOSED.
(Step continued on next page.)
Page 7 of 44
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 18 STEP I I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED
- 4. f. CLOSE Ruptured S/G(s) MSIV f. PERFORM the following:
and MSIV bypass valve.
- 2) DISPATCH operator to perform EA 1-1, Closing MSIVs Locally, for MSIV or MSIV bypass valve which fails to close.
- 3) ISOLATE steam header:
- PLACE condenser steam dumps in OFF. [M-4]
- ENSURE steam dump valves CLOSED. [M-4]
- CLOSE FCV-47-180, HP Steam Seal Supply Isolation. [M-2}
- ENSURE FCV-47-181 HP Steam Seal Supply Bypass CLOSED. [M-2]
- DISPATCH operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.
- 4) USE Intact SIG(s) atmospheric relief for steam dump.
IF any Ruptured S/G CANNOT be isolated from at least one Intact SIG, THEN GO TO ECA-3.1, SGTR and LOCA -
Subcooled Recovery.
Page 8 of 44
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev. 18 ISTEPI ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED I
- 5. MONITOR Ruptured S/G(s) level:
- a. CHECK ruptured SIG narrow range a. PERFORM the following:
level greater than 10% [25% ADV].
- 1) IF rupturedS/Gisalsofaulted (SIG pressure dropping uncontrolled),
THEN ENSURE AFW isolated to ruptured SIG UNLESS needed for RCS cooldown.
- 2) IF ruptured SIG is NOT faulted OR is required for cooldown, THEN PERFORM the following:
a) MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10% [25% ADV].
b) WHEN ruptured SIG level is greater than 10% [25% ADV],
THEN PERFORM Substep 5.b.
c) GO TO Step 6.
- b. ENSURE AFW isolated b. IF any AFW valve for ruptured SIG to ruptured SIG: CANNOT be CLOSED AND affected AFW flowpath
LCV for ruptured SIG in CLOSE PULL TO LOCK.
Page 9 of 44
JPM Sim D Page 1 of 16 Rev. 0 SEQUOYAHNUCLEARPLANT JOB PERFORMANCE MEASURE SIMD Start a Reactor Coolant Pump C-b1
JPM Sim D Page 2 of 16 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Start a Reactor Coolant Pump Task#: 0030010101 Task Standard:
Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X KIA ReferencelRatings: APE 015/017 AA1.03 (3.7/3.8)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 18 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim D Page 3 of 16 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize to IC 7
- 3. Stop the #1 RCP.
- 4. Insert AN_OV_359 to OFF (Disables Loose Parts Alarm.)
- 7. Close the Loop 1 Pressurizer Spray valve
- 8. Place the Simulator in RUN when the operator assumes the task.
- 9. An extra operator will be required to acknowledge alarms.
- 10. ACKNOWLEDGE ALARMS
- 11. FREEZE SIMULATOR.
- 12. Provide a marked up procedure 1-SO-68-2, Reactor Coolant Pumps Section 5.1 completed through step 10.
- 13. PLACE SIMULATOR IN RUN
- 14. Booth operator standby to insert the SCN File RCPHEATUP.scn (from exams folder) during the JPM SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
References:
Reference Title Rev No.
- 1. 1-SO-68-2 Reactor Coolant Pumps 33
- 2. AOP- R.04 Reactor Coolant Pump Malfunctions 24 1-AR-M5-B CVCS Seal Water and RCP 39
JPMS1mD Page 4 of 16 Rev. 0 DLRECTLONS TO-TRAIFIEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Uniti isinMODE3
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-SO-68-2 Section 5.1, steps 1 through 10 are complete.
- 5. All other RCPs are in service INITIATING CUES:
- 1. You have been directed to start and monitor the RCP #1 using 1-SO-68-2, Reactor Coolant Pumps starting at step 5.1.11.
- 2. Notify the SRO when you are complete.
JPM Sim D Page 5 of 16 Rev. 0 Start Time STEP 1 Obtain a copy of 1S0682, Reactor Coolant Pumps Section 5.1 completed through step 10. SAT UNSAT Standard Examinee obtains a copy of 1-SO-68-2, Reactor Coolant Pumps Section 5.1.
Cue Provide a marked up copy of 1-S0-68-2, Reactor Coolant Pumps Section 5.1 completed through step 10.
Comment
[11] PLACE [i-HS-68-84A1 #1 RCP Lift Oil Pump in STEP 2 SAT
. the START position.
. .. UNSAT Critical Step Standard Examinee places handswitch 1-FfS-68-84A#1 RCP Lift Oil Pump to START.
Comment Exminer This step is critical to make up a start interlock for the #1 RCP.
Examiner REAC COOL PMPS OIL LIFT PRESS LOW annunciation will come in Note and clear during performance of the next step
JPM Sim D Page 6 of 16 Rev. 0 STEP [12] WHEN Lift Oil Pump for #1 RCP has run 3 .
SAT 2 minutes. THEN ANNOUNCE #1 RCP start on the P/A system. UNSAT Standard: Examinee makes an announcement over the PA system Comment STEP [13] IF no RCPs are running AND RCP #1 is the first 4 SAT
. RCP to be started, THEN MONITOR the SRMs during startup of the RCP. [C.3] UNSAT Standar& Examinee determines other 3 RCPs are running and marks this step as N/A.
Comment STEP 5 : [14] PLACE [1-HS-68-8A #1 RCP in the START position.
SAT P...
- UNSAT
. . . : . ,. : . Critical Step Standard: Examinee places 1-HS-68-8A#1 RCP to START.
Comment Examiner .
Note This step is critical because it starts the RCP.
JPM Sim D Page 7 of 16 Rev. 0 Procedure NOTE Motor and Pump Operating Parameters are listed in Note Appendix D. Appendix E provides vibration limits if pump is started after maintenance activities.
[15] ENSURE #1 RCP motor and pump are operating STEP 6 : SAT within the parameters listed in Appendix D.
UNSAT Standard: Examinee monitors #1 RCP motor and pump parameters using installed instrumentation.
Comment Examiner Note Direct the Booth Operator to insert File RCPHEATUP.scn.
The motor will start heating up and result in the REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH alarm on 1-M-5, Window E Examiner 1 on 1-XA-55-5B coming in during the performance of the next steps Note (JPM steps 6-7; procedure steps 15-17). When alarm comes in, the operator may not complete performing procedure step 15, 16 or 17.
N/A those steps if applicable and move on to JPM step 9 if the examinee transitions to alarm procedure.
[16] ENSURE [ITCV-67-861 RCP Motor Cooler 1A is STEP 7 : OPEN (1-HS-67-86 red light illuminated). SAT UNSAT Standard: Examinee verifies 1-TCV-67-86 is open on Panel M-27A by observing the red indicating light above handswitch ON.
Comment
JPM Sim D Page 8 of 16 Rev. 0
[17] WHEN Lift Oil Pump has run greater than 1 minute after STEP 8 SAT
. RCP start. THEN PLACE [1-HS-68-84A1 #1 RGP Lift Oil Pump UNSAT the STOP position.
Standard Examinee places 1-HS-68-84A #1 RCP Lift Oil Pump handswitch to STOP Comment STEP 9 : CVCSSEALWATERANDRCP SAT I -XA.-55-5B 29 (E-I) UNSAT REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH Standard Examinee acknowledges alarm and observes rise in RCP motor stator temperatures.
Comment If the actions contained in the Annunciator Response Procedure (ARP)
Examiner are implemented, JPM steps 11-24 cover the actions directed by the Note ARP and AOP to stop the RCP. If RCP is stopped without implementing the ARP, JPM 10 step will end the JPM.
JPM Sim D Page 9 of 16 Rev. 0 STEP 10 STOPLoop1 ROP
- UNSAT Critical Step Standard: Examinee places 1-HS-68-8A#1 RCP handswitch to STOP.
If the examinee stops the RCP now provide the following cue, Another operator will perform the remaining steps of this procedure.
Comment Examiner This step is critical because it prevents continued damage to the Note running RCP.
Examiner The following steps are from the Annunciator Response Procedure 1-Note AR-M5-B.
NOTE RCP 1-4 is known to have high winding temperature (up to Procedure approximat&y 3O3F when running with RCS temperature below Note 4000F. (EWR W-COM-068-057)) However, alarms on RCP 1-4 should NOT be dismissed as expected.
Corrective [11 DETERMINE which pump is in alarm by monitoring computer STEP 11 . Actions points. SAT Pump 1: Point T0409A, 41 IA or 412A (A,B. & C 0)
Pump 2: Point T0429A, 431A or 432A (A,B, & C 0) UNSAT Pump 3: Point T0449A. 4E1A or 452A (A.B. C 0)
Pump 4: Point T0469A, 471A or472A (A,B, &C 0)
Standard Examinee determines the #1 RCP in alarm by observing the ICS display.
Comment
JPM Sim D Page 10 of 16 Rev. 0 STEP 12 : [2] CONTACT Engineering to obtain engineering assistance detenmnng the validity of the alarm SAT UNSAT Standard Engineering is contacted to obtain engineering assistance in determining the validity of the alarm.
c Respond as Unit Supervisor Engineering has been contacted.
Comment (3] MONITOR the following parameters for increasing trends:
STEP 13 : SAT a Motor Current
- b. Bearing Temperatures UNSAT c PurnpiMotor Vibration
- d. Containment Air Temperatures Exarninee monitors or directs monitoring parameters by observing Standard: indications on installed instrumentation and determines indications normal.
Corn rnent
JPM Sim D Page 11 of 16 Rev. 0.
STEP 14 : [4] ENSURE ERCW aligned to pump cooler.
SAT UNSAT Standard: Examinee verifies ERCW aligned to pump cooler by observing red light above 1-HS-67-86 on 0-M-27A ON.
Comment Examiner Note May have been performed in JPM step 7.
STEP 15 : [5] VERIFY ERCW system temperature and pressure normaL SAT UNSAT Standard: Examinee verifies ERCW system temperature and pressure normal by observing indications 0-M-27A.
Comment STEP 16 : 161 VERIFY lower corn parment air temperature normal. SAT UNSAT Standard Examinee verifies lower compartment air temperature normal by observing indications on ICS and other installed plant instrumentation.
Comment
JPM Sim D Page 12 of 16 Rev. 0 STEP 17 : [11 REFER TO 1 -SO-68-2 for RCP operating 1imts SAT U N SAT Standard: Examinee refers to 1-SO-68-2 Appendix D for the operating limits.
Comment If the remaining actions contained in the Annunciator Response Examiner Procedure (ARP) are implemented, JPM steps 19-20 cover the actions Note directed by the ARP and AOP to stop the RCP. If RCP is stopped at this point, JPM 18 step will end the JPM.
STEP 18 : STOP Loop I RCP SAT s
UNSAT Critical Step Standard: Examinee places 1-HS-68-8A #1 RCP handswitch to STOP.
If the examinee stops the RCP now provide the following cue, Another operator will perform the remaining steps of this procedure.
Comment Examiner This step is critical because it prevents continued damage to the Note running RCP.
JPM Sim D Page 13 of 16 Rev. 0
[8J IF QpslEngineenng determines alarm is valid, THEN STEP 19 : SAT PERFORM the following:
Ia] CHECK pump motor amps. (normal 415 amps with 608 amps UNSAT maximum) fb] IF RCP motor amps approach 608 amps, THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunction&
StandardS Examinee verifies pump amps normal by observing El-68-8 less than 400 amps.
Comment 9] IF OpslEngineering determines alarm is valid and pump motor STEP 20 SAT
- stator temperature approaches 31 1°F (329°F for RCS temperature less than 540°F), THEN UNSAT GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
Standard Examinee observes the motor winding temperature is greater than 31 1°F using the ICS and goes to AOP-R.04.
Respond as Engineering Alarm is valid Comment STEP 21 : L DIAGNOSE the failure:
SAT Motor Stator Temperature High on ANY RCP 2.6 24 UNSAT Standard: Examinee goes to AOP-R.04 section 2.6 Corn ment
JPM Sim D Page 14 of 16 Rev.0 Procedure CAUTION: Operating the RCP with excess winding temperature will reduce the expected Caution life of the motor insulation.
NOTE: POP motor winding temperature limits are as follows:
Procedure Note
- 329°F if RCS temperature is less than 540°F.
- 311 °F if RCS temperature is greater than or equal to 540°F.
STEP 22 : Alternate Path SAT
- 1. MONITOR RCP Motor Stator temperature a. IF RCP Motor Stotor temperature less than applicable limit by monitoring reaches applicable limit UNSAT the following computer points: AND indication is verified valid.
. Pump 1:TO409A,4ilAor4l2A THEN PERFORM the foilownig:
. Pump 2: T0429A, 431A or 432A
- Pump 3: T0440A 451A or 452A 1) IF reactor power less than 20%,
. Pump 4: T0460A, 471A or 472A GO TO Section 21. ANY RCP Tripped or RCP Shutdown Required. [C1]
Examinee determines the motor winding temperature is greater than Standard: 31 1 °F by observing the ICS and goes to the RNO column and ultimately to Section 2.1.
Comment 2.1 ANY RCP Tripped or RCP Shutdown Required Procedure Caution CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is stopped.
CHECK unit in Mode 1 or 2. STOP affected RCP(s)
STEP 23 : SAT Time:
UNSAT GO TO Caution prior to Step 3.
Standard: Examinee determines the Unit is in MODE 3 and proceeds to RNO Comment
JPM Sim D Page 15 of 16 Rev. 0 CHECK unit in Mode 1 or 2. STOP affected RCP(s).
STEP 24 SAT Tirne UNSAT GO TO Caution prior to Step 3.
Critical Step Standard: Examinee places handswitch 1-HS-68-8A #1 RCP to STOP.
Comment Examiner This step is critical because it prevents continued damage to the Note running RCP.
Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPMSimD Page 16 of 16 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. UnitlisinMODE3
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-SO-68-2 Section 5.1, steps 1 through 10 are complete.
- 5. All other RCPs are in service INITIATING CUE:
- 1. You have been directed to start and monitor the RCP #1 using 1-SO-68-2, Reactor Coolant Pumps starting at step 5.1.11.
- 2. Notify the SRO when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
F I
- SQN REACTOR COOLANT PUMPS 1-SO68-2 Rev: 33 I Pagellof75 Date________
5O STARTUP STANDBY READINESS 5.1 #1 Reactor Coolant Pump Start RHR over pressurization restrictions prohibit starting a RCP, when RCS temperature is greater than or equal to 3OO°F AND no RCPs are running, AND RHR is aligned to the RCS for shutdown cooling.
IO 2 RCS pressure may increase when starting the first RCP.
CAUTION 3 Computer point 1P0499A, which inputs to OSlSXXO68127.Og should be monitored along with compliance instrumentation to ensure all pressure /temperature requirements are met.
If starting RCP for troubleshooting of vibration problems, after maintenance activities that affect pump vibration or for balance shot activities then refer to Appendix E for vibration monitoring requirements.
- p. /iii IF no RCPs are running AND fFCV-74-1] and [FCV-74-21 are OPEN, THEN
[a] RECORD RCS temperature. °F
[b] IF RCS temperature is >200°F and <300°F, THEN ENSURE pressurizer level is <60%.
WHEN 30 minutes have elapsed since last #1 RCP run/attempted start, THEN PROCEED to step 3.
IF access into containment is permitted, THEN PERFORM Appendix A RCP Local Inspection Check Sheet.
VERIFY [1-TR-7O4j] CCS Hx 1A1/1A2 Outlet Temperature 105°F.
ENSURE [1-HS-67-861 RCP Motor Cooler 1A is in the P-AUTO position.
SQN REACTOR COOLANT PUMPS 1-50-68-2
. Rev:33 i Pagel2of75 Date Th4 5.1 # I Reactor Coolant Pump Start (Continued)
IF RCS pressure is> 100 psig, THEN ENSURE [jFCV-62-91, RCP #1 Seal Leak-off and
[I-FCV-62-631, Seal Return Isolation are OPEN.
Appendix B should be used to diagnose RCP seal abnormalities.
2 Step [7] may be marked N/A if leakoff is less than 0.2 gpm and Step [8] will be performed.
DETERMINE #1 RCP seal No. 1 leakoff 0.2 gpm by using any of the following:
INSTRUMENT 1FR6223 (red pen scale range 0.0-1.0) Ei/
1FR--6224 (red pen scale range 0.010.0) lOS LI Ultrasonic (requires a SR to be installed) LI Differential Pressure (requires a SR to be installed) LI The Bucket Test is NO longer performed. Less than 0.2 gpm flow rate is acceptable for a short period of time after RCP seal maintenance has been performed, provided flow verification has been performed by ultrasonics or differential pressure.
[8] IF #1 ROP seal No. 1 leakoff is <0.2 gpm AND RCP seal maintenance has been performed, THEN
[a] ENSURE SR initiated to have either an ultrasonic or differential pressure instrument installed). LI
[b] DETERMINE #1 RCP seal No. 1 leakoff flow rate from the installed ultrasonic or differential pressure instrument.
[c] EVALUATE leak-off rate, continuation of RCP start-up, and duration of RCP run time.
Engineering
SQN REACTOR COOLANT PUMPS 1SO-68-2 Re.v33 Page 13of75 Date 1O4:47 51 #1 Reactor Coolant Pump Start (Continued)
VERIFY [1-PDI-62-8A] #1 RCP Seal No. 1 differential pressure greater than or equal to 220 psid.
P [10] IF Reactor Coolant Pump is being started after major maintenance, troubleshooting or for balance shot activities, THEN PERFORM Appendix E for modified RCP vibration monitoring requirements and limitations.
PLACE [1-HS-68-84A1 #1 RCP Lift Oil Pump in the START position.
[12] WHEN Lift Oil Pump for #1 RCP has run 2 minutes, THEN ANNOUNCE #1 RCP start on the P/A system.
[13] IF no RCPs are running AND RCP #1 is the first RCPto be started, THEN MONITOR the SRMs during startup of the RCP. [C3]
[14] PLACE f1-HS-68-8A1 #1 RCP in the START position.
NOTE Motor and Pump Operating Parameters are listed in Appendix D. Appendix E provides vibration limits if pump is started after maintenance activities.
[15] ENSURE #1 RCP motor and pump are operating within the parameters listed in Appendix D.
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rv:Sa Pagel4of75 Date 5.1 #1 Reactor Coolant Pump Start (Continued)
[16] ENSURE [1-TCV-67-86] RCP Motor Cooler 1A is OPEN (1-HS-67-86 red light illuminated).
[17] WHEN Lift Oil Pump has run greater than 1 minute after RCP start, THEN PLACE [1-HS-6884A] #1 RCP Lift Oil Pump in the STOP position. LI
[18] IF RHR is removed from service, THEN DETERMINE if both CCS pumps are needed inservice.
[19] IF the second running CCS pump is to be removed from service, THEN GO TO 1SO701 and STOP the second running CCS pump.
END OF TEXT
CVCS SEAL WATER AND RCP I XA-55-5B I 2 (3 I LS-81-1A 4 5 I 6 7 LS-62-6A FS-62-iO PdIS-62-96 LS-68-1OAIB FS-31A-28 PDIS-30-148/149 PRIM WATER REAC COOL PMP 1 REAC COOL PMPS SEAL WATER INJ REAC COOL PMP 1 ELEC BD RM HIGH PRESS IN STORAGE TANK STANDPIPE LVL A SEAL LEAKOFF FILTER 1 OIL RESERVOIR AIR COND SYS AUX BLDG LOW LEVEL HIGH-LOW LOW FLOW HIGH AP LEVEL HI-LOW A-A ABNORMAL A LS-81 -1 E LS-62-1 9A FS-62-1 1 PdIS-62-97 LS-68-34A1B FS-31 A-27 FS-31 A-8 PRIM WATER REAC COOL PMP 2 REAC COOL PMPS SEAL WATER INJ REAC COOL PMP 2 ELEC BD RM CB AIR CU STORAGE TANK STANDPIPE LVL SEAL LEAKOFF FILTER 2 OIL RESERVOIR AIR COND SYS FANS A-A, B-B HI LEVEL HIGH-LOW B HIGH FLOW HIGH AP LEVEL HI-LOW B-B ABNORMAL LO FLOW FAN ON B
PDIS-81-5B LS-62-32A FS-62-1 TS-62-58 LS-68-53A1B FS-31A-37 FS-31A-23 PRIM WATER REAC COOL PMP 3 REAC COOL PMPS EXCESS LETDOWN REAC COOL PMP 3 SPREADING RM MAIN CONTROL MAKEUP HDR STANDPIPE LVL SEAL WATER HX TEMP OIL RESERVOIR EXHAUST FANS ROOM c DIFF PRESS LOW HIGH-LOW FLOW LO HIGH LEVEL HI-LOW LOW FLOW FAN ON AIR COND SYS A-A ABNORMAL c PDIS-81 -9B LS-62-45A PdS-62-8 PS-68-9 LS-68-76A1B FS-31 A-i 4 FS-31 A-20 PRIM WATER REAC COOL PMP 4 REAC COOL PMPS REAC COOL PMPS REAC COOL PMP 4 CB PRESS MAIN CONTROL MAKEUP HDR STANDPIPE LVL SHAFT SEAL OIL LIFT PRESS OIL RESERVOIR FANS AB ROOM DIFF PRESS HI HIGH-LOW WATER AP LOW D LOW LEVEL HI-LOW LOW FLOW FAN AIR COND N D
ON B-B ABNORMAL REAC COOL PMPS TS-62-42 REACTOR TS-62-43 FIS-62-12 PS-77-251 FS-31A-108 MOTOR STATOR REAC COOL PMPS COOLANT REAC COOL PMPS RCP NO 1 SEAL CVCS HYDROGEN CB EMER PRESS TEMPERATURE LOWER BEARING PUMPS MOTOR SEAL WATER BYPASS FLOW SUPPLY PRESS FANS A-A, B-B HIGH TEMP HIGH THRUST BEARING TEMP HI E TEMP HIGH LOW LOW LO FLOW FAN ON E
I 2 3 I I I 4 5 6 I 7
29 (E-1)
Source Setpoint SER 404 Computer alarm at REAC COOL PMPS
- 1. TE-68-12D, G, J Pump 1 293°F MOTOR STATOR
- 2. TE-68-35E, F, H Pump 2 293°F TEMPERATURE
- 3. TE-68-54E, G, J Pump 3 293°F HIGH
- 4. TE-68-77E, G, J Pump 4 293°F Probable 1. Excessive load on pump motor.
Causes 2. Air restriction to pump motor coolers.
- 3. Insufficient ERCW to pump motor coolers.
- 4. Boron buildup on Reactor Coolant Pump Motor heat exchanger.
Corrective [1] DETERMINE which pump is in alarm by monitoring computer Actions points.
Pump 1: Point T0409A, 41 1A or 412A (A,B, & C 0)
Pump 2: Point T0429A, 431A or 432A (A,B, & C 0)
Pump 3: Point T0449A, 451A or 452A (A,B, & C 0)
Pump 4: Point T0469A, 471A or 472A (A,B, & C 0)
NOTE RCP 1-4 is known to have high winding temperature (up to approximately 303°F when running with RCS temperature below 400°F. (EWR 10-COM-068-057)) However, aarms on RCP 1-4 should NOT be dismissed as expected.
[2] CONTACT Engineering to obtain engineering assistance in determining the validity of the alarm.
[3] MONITOR the following parameters for increasing trends:
- a. Motor Current
- b. Bearing Temperatures
- c. Pump/Motor Vibration
- d. Containment Air Temperatures
[4] ENSURE ERCW aligned to pump cooler.
[5] VERIFY ERCW system temperature and pressure normal.
[6] VERIFY lower compartment air temperature normal.
[7] REFER TO 1-SO-68-2 for RCP operating limits.
[8] IF Ops/Engineering determines alarm is valid, THEN PERFORM the following:
[a] CHECK pump motor amps. (normal 415 amps with 608 amps maximum.)
[b] IF RCP motor amps approach 608 amps, THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
- CONTINUED ON NEXT PAGE*
SQN I -AR-M5-B Page 36 of 45 I Rev. 39
29 (E-1)
CORRECTIVE ACTIONS (CONTD)
REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH
[9] IF Ops/Engineering determines alarm is valid and pump motor stator temperature approaches 311°F (329°F for RCS temperature less than 540°F), THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
[1O]IF Ops/Engineering determines alarm is valid and other plant parameters indicate RCP motor problem, THEN REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions.
[11]IF Ops/Engineering determines alarm is valid and is due to boron buildup on Reactor Coolant Pump Motor Heat Exchanger, THEN OBTAIN Engineering recommendation to PERFORM 1SO682, Section 8.3 At Power RCP Motor Cooler ERCW Isolation NOTE Compensatory monitoring is required on all running RCPs since alarm does NOT reflash.
[12]IF RCP operation will continue with temperature above alarm setpoint, THEN INITIATE compensatory monitoring USING 1-SO-68-2, Reactor Coolant Pumps.
References 45B655-05B-0, 47A61 5-0, 47W61 0-67-2 SQN I -AR-M5-B Page 37 of 45 I Rev. 39
SQN - REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS CAUTION I RCP should NOT be tripped when reactor power is greater than 5% (FR-S.1) or when RCP operation is required by FR-C.I (Inadequate Core Cooling) or FR-C.2 (Degraded Core Cooling).
CAUTION 2 Exceeding any of the following limits requires tripping the affected RCP, except as described in Caution I:
- RCP #1 Seal Temperature greater than 225°F
- RCP Lower Bearing Temperature greater than 225°F
- RCP Upper Motor Bearing Temperature greater than 200°F
- RCP Lower Motor Bearing Temperature greater than 200°F
- RCP Motor Voltage less than 5940V or greater than 7260V
- RCP Motor Amps greater than 608 amps
- RCP Vibration greater than 20 mils on any axis (x andlor y) [C.3]
NOTE: RCP trip criteria is also located in Appendix B.
- 1. DIAGNOSE the failure:
IF... GOTO SECTION PAGE ANY RCP tripped or RCP shutdown required 2.1 4 NOTE During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time.
- 1 Seal Leakoff high flow (high flow Alarm) on ANY RCP 2.2 7
- 1 Seal Leakoff low flow (low flow Alarm) on ANY RCP 2.3 13
- 3 Seal Leakoff high flow (low RCP standpipe level) on ANY RCP 2.5 21 Motor Stator Temperature High on ANY RCP 2.6 24 Page 3 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-RG4 Rev. 24 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.6 RCP Motor Stator Temperature High CAUTION: Operating the RCP with excess winding temperature will reduce the expected life of the motor insulation.
NOTE: RCP motor winding temperature limits are as follows:
- 329°F if RCS temperature is less than 540°F.
- 311°F if RCS temperature is greater than or equal to 540°F.
MONITOR RCP Motor Stator temperature a. IF RCP Motor Stator temperature less than applicable limit by monitoring reaches applicable limit the following computer points: AND indication is verified valid,
- Pump 1: T0409A, 4llAor4l2A THEN PERFORM the following:
- Pump 2: T0429A, 431A or 432A
- Pump 3: T0449A, 451A or 452A 1) power less than 20%,
THEN
- 2) IF reactor power greater than 20%,
THEN INITIATE plant shutdown at 24%
per minute USING AOP-C.03, Rapid Shutdown or Load Reduction.
Page 24 of 34
STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I 2.1 ANY RCP Tripped or RCP Shutdown Required CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is stopped.
- 1. CHECK unit in Mode 1 or 2. STOP affected RCP(s).
Time:
GO TO Caution prior to Step 3.
CAUTION: If #1 seal leakoff flow is HIGH on any RCP, Step 3 requires closing seal return valve within 5 minutes after stopping affected RCP(s). Step 3 should be continued after E-O immediate actions. [C.2]
- 2. PERFORM the following:
- a. TRIP the reactor.
- b. WHEN reactor is tripped, THEN STOP affected RCP(s).
Time:
- c. GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing in this procedure.
Page 4 of 34
JPM Sim E Page 1 of 11 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIME Respond to ERCW Pump Trip
JPM Sim E Page 2 of 11 Rev.O ROISRO JOB PERFORMANCE MEASURE Task: Respond to ERCW Pump Trip Task#: 0000620501 Task Standard: STANDBY A TRAIN ERCW Pump has been started and the auto start selection switch is not selected to the Q-A ERCW Pump position.
Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA ReferencelRatings: 076 A2.01 (3.5/3.7)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name / Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 5 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim E Page 3of 11 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize to IC 14
- 3. Ensure Q-A pump is in service and the selector switch is selected for Q-A pump.
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR.
- 7. PLACE SIMULATOR IN RUN
- 8. When directed, activate MF #RWO1G (Trips Q-A ERCW Pump)
SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentIProcedures Needed:
References:
L Reference Title Rev No.
[1. O-AR-M27-A COMPONENT COOLING 11 1i AOP-M.O1 Loss of ERCW 23
- JPMSimE Page 4 of 11 Rev. 0
- DIRECTIONS TO TRAINE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 1, 75% power.
INITIATING CUES:
- 1. You have been directed to respond to plant conditions.
JPM Sim E Page 5 of 11 Rev. 0 Start Time STEP 1 : COMPONENT COOLING XA-5527B-A 1I SAT UN SAT ERCWICCS PUMP MOTOR TRIP Corrective (1] IF ERCW pump motor TRIPS, THEN Actions GO TO AOP-M.O1, Loss of Essential Raw Cooling Water.
Standard Examinee acknowledges alarm and transitions to AOP-M.01 LOSS OF ESSENTIAL RAW COOLING WATER Comment STEP 2 Obtain a copy of AOP-M.O1 LOSS OF ESSENTIAL RAW COOLING WATER. SAT UNSAT Standard:
Cue Examinee obtains a copy of AOP-M.01 LOSS OF ESSENTIAL RAW COOLING WATER.
Corn ment
JPM Sim E Page 6 of 11 Rev. 9 DjAGNOSEfhefiihjre.
STEP 3 : SAT IF... GO TO SECTION PAGE ERCW Pump(s) tripped or f&!ed 2! ERCW pump failure 5 UNSAT Standard Examinee observes a green light indication for ERCW pump Q-A and goes to Section 2.1 ERCW Pump Failure Comment STEP 4 . 1 IDENTIFY and LOCK OUT tailed ERCW
. pump. SAT UNSAT Standard: Examinee places O-HS-67-460A ERCW pump Q-A in Pull-to-Lock.
Comment Examiner The indicating lights for ERCW pump Q-A will go out when the Note: handswitch is placed in PTL.
STEP 5 : 2 START additional ERCVV pumps as required to maintain supply header - SAT pressure between 78 psig and 124 psig.
UNSAT
- Critical Step Examinee places O-HS-67-432A for the OR O-HS-67-436A1or Standar& the uKAn ERCW pump to START as required to maintain Supply headerpressures [between 78 psig and 124 psigjas indicated oni.
Pl-87-493A or 2-Pl-67-493A.
Comment Examiner This step is critical to maintain continued LRCW flow to critical plant Note: equipment.
JPM Sim E Page 7 of 11 Rev. 0 STEP 6 : CHECK tWO Trafl A ERCW Pumps AVAILABLE. SAT UNSAT Standard Examinee verifies two A Train powered ERCW Pumps available by observing indicating light indication above the A Train handswitches.
Comment STEP 7 4. CHECK 1A and 2A ERCW Supply
. header pressures and flows NORMAL: SAT
[between 78 psig and 124 psig]:
. I -Pl-67-493A
- 2-Pi-67-493A
- h. Supply header flows
[expected valuej:
. 1-Fl-67-61
. 2-FI-67-6i Examinee observes 1A and 2A ERCW supply header pressures at Standard: 110 psig and Unit 1A supply header flow approx. 2700 gpm and Unit 2A supply header flow approx. 13,500 gpm.
Comment
JPM Sim E Page 8 of 11 Rev. 0 STEP 8 CHECK lB and 2B ERCVV supply header pressures and flows NORMAL SAT
- a. Supply header pressures [between UNSAT 78 psig and 124 psig]:
- i-Pl-67-488A
- 2-Pl-67-488A
- b. Supply header flows [expected valuel;
- i-Fl-67-62
- 2-F 1-67-62 Examinee observes 1 B and 2B ERCW supply header pressures at Standard: 120 psig and Unit I B supply header flow approx. 1500 gpm and Unit 2B supply header flow approx. 1 1,500 gpm.
Corn ment
- 6. DISPATCH personnel to inspect cTEID
- s. I r SAT
. failed pump(s) and determine cause for failure.
UNSAT Standard: Examinee dispatches an AUO to locally inspect the Q-A ERCW pump.
Cue Respond as AUO Acknowledge inspect the Q-A ERCW pump.
Comment
JPM Sim E Page 9of 11 Rev. 0
- 7. NOTIFY STA to evaluate Tech Spec STEP 10 LCO 3.7.4, ERCW System, for both units. SAT UNSAT Standard: Exam inee notifies STA to evaluate Tech Specs.
Comment Respond as STA Acknowledge evaluate Tech Spec LCO 3.7.4, ERCW System, for both units.
8 CHECK ERCW pump loading amps STEP 11 . NORMAL. SAT UNSAT Standard: Examinee observes the running ERCW pump amps less than 60 amps Comment
. 9. TRANSFER emergency power seiector STEP 12 -
SAT switch away from failed pump. -, -
UNSAT Critical Step Standard: Examinee places the O-XS-67-285 ERCW Pumps J-A & Q-A DIG Power Select to J-A Comment Examiner This step is critical to maintain a continued source of EDG back up Note: power to the running ERCW pumps.
JPM Sim E Page 10 of 11 Rev. 0 Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPM Sim E Page 11 of 11 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODEl, 75% power.
INITIATING CUE:
- 1. You have been directed to respond to plant conditions.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
COMPONENT COOLING XA-55-27B-A 1 12 I 3 4 I 5 I 6) 7 CCS REAC BLDG SPARE SPARE SPARE SPARE SIS PUMP A-A SIS PUMP B-B SUPPLY HEADER MECH SEAL HX MECH SEAL HX FLOW LOW OUTLET FLOW A OUTLET FLOW A
LOW LOW RC PUMPS RC PUMP 1 RC PUMP 2 RC PUMP 3 RC PUMP 4 CENT CHG CENT CHG THRM BARRIER THRM BARRIER THRM BARRIER THRM BARRIER THRM BARRIER PUMP A-A PUMP B-B RETURN HEADER OUTLET FLOW OUTLET FLOW OUTLET FLOW OUTLET FLOW MECH SEAL HX MECH SEAL HX FLOW LOW LOW LOW LOW LOW OUTLET FLOW OUTLET FLOW B LOW LOW B RCPUMPS SPARE SPARE SPARE SPARE CNTMT SPRAY CNTMT SPRAY THRM BARRIER PUMP A-A PUMP B-B RETURN TEMP MECH SEAL HX MECH SEAL HX C HIGH OUTLET FLOW LOW OUTLET FLOW LOW c RC PUMPS RC PUMP 1 RC PUMP 2 RC PUMP 3 RC PUMP 4 RHR PUMP A-A RHR PUMP B-B OIL CLR RETURN OIL COOLERS OIL COOLERS OIL COOLERS OIL COOLERS MECH SEAL HX MECH SEAL HX TEMPERATURE OUTLET FLOW OUTLET FLOW OUTLET FLOW OUTLET FLOW OUTLET FLOW OUTLET FLOW HIGH LOW LOW LOW LOW LOW LOW D D SPARE SPARE ERCW PUMP ERCW/CCS PUMP EXCESS LETDOWN RHR HX A RHR HX B MOTOR MOTOR HX OUTLET OUTLET OUTLET OVERLOAD TRIP TEMPERATURE TEMPERATURE TEMPERATURE HIGH HIGH HIGH E E 1 I 2 T 3 I 4 I 5 I 6 r_____
SQN O-AR-M27-B-A Page 2 of 40 0,1 Rev.11
32 (E-4)
Source Setpoint ERCW/CCS PUMP SER 1117(Unit 1 annunciator system)
MOTOR 30A4 CCS pumps lA-A or C-S Various motor breakers TRIP ERCW pumps J-A or Q-A open when control switch is 30B4 CCS pump lB-B closed or after close, (relay ERCW pumps L-B or N-B 30X) 30A5 CCS pump 2A-A ERCW pumps K-A or R-A 30B5 CCS pumps 2A-A or C-S ERCW pumps M-B or P-B Retransmitted to U-2 SER 2123 (Unit 2 annunciator system)
Probable 1. Overload or fault condition.
Causes 2. Safe stop locally or breaker not racked in.
Corrective [1] IF ERCW pump motor TRIPS, THEN Actions GO TO AOP-M.O1, Loss of Essential Raw Cooling Water.
[2] IF CCS motor trip, THEN GO TO AOP-M.03, Loss of Component Cooling Water.
[3] DETERMINE which motor tripped.
[4] TURN control switch to OFF position to reset alarm.
[5] DISPATCH operator to investigate cause of alarm.
[6] EVALUATE LCO 3.7.3 (CCS) or 3.7.4 (ERCW).
References 45B655-27BA-O, 45N657-2 1 SQN 0-AR-M27-B-A Page 34 of 40 0,1 Rev.11
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOl PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-MMI LOSS OF ESSENTIAL RAW COOLING WATER Revision 23 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J. K. WILKES EFFECTIVE DATE: 10/2/2010 REVISION DESCRIPTION Revised Section 2.1 to address PER action 229972-001.
Revised Appendix F.6 to correct error. Also, made other editorial changes.
INTENT CHANGES TO SECTION 2.12 OF THIS PROCEDURE MUST BE APPROVED BY PORC.
SQN LOSSO ESSENTIAL RAW 000LINGWATER AQP-MQ1 Rev.23 1.0 PURPOSE This procedure provides the actions necessary to mitigate the effects of an ERCW pump trip or piping leak/rupture.
Sections 2.0 through 2.11 may be performed by a single unit.
Section 2.12 (Loss of All ERCW) should be performed on BOTH units.
Page 2 of 188
SQN LOSS OF ESSENTIAL RAW COOLING WATER AQP-MOI Rev. 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS CAUTION: ERCW header rupture in Aux Bldg could fill passive sump in 15 minutes.
Prompt action may be needed to isolate rupture using this AOP.
- 1. DIAGNOSE the failure:
IF... GO TO SECTION PAGE ERCW Pump(s) tripped or failed 2.1 ERCW pump failure 5 Controllable ERCW leak: 2.2 Controllable ERCW 10 e Rapid isolation of leak is NOT required based on leak safety or equipment damage concerns AND
. Adequate flow to ERCW components available.
High flow ERCW Supply Header 1A 2.3 Supply Hdr 1A Rupture 17 in Aux Bldg High flow ERCW Supply Header lB 2.4 Supply Hdr lB Rupture 22 in Aux Bldg High flow ERCW Supply Header 2A 2.5 Supply Hdr 2A Rupture 26 in Aux Bldg High flow ERCW Supply Header 2B 2.6 Supply Hdr 2B Rupture 35 in Aux_Bldg Indications of an ERCW Return Header Rupture 2.7 Return Hdr Rupture 42 (must be diagnosed locally). in Aux Bldg NOTE: If alarms listed in remainder of this table are NOT lit, ERCW pressure/flow indications and reports from personnel outside MCR should be used to determine appropriate section.
Low flow ERCW Supply Header 1A and 2A, AND 2.8 Supply Header 1A/2A 58 STRAINER DIFF PRESS HIGH alarm LIT Rupture in Yard Area
[M-27A, C-3 and/or D-2]
Low flow ERCW Supply Header 1 B and 2B, 2.9 Supply Header 1 B/2B 74 AND Rupture in Yard Area STRAINER DIFF PRESS HIGH alarm LIT
[M-27A, C-6 and/or D-5]
(step continued on next page)
Page 3 of 188
SQN LOSS OF ESSENTIAL RAW COOLING WATER Rev. 23 STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS (Continued)
- 1. (Continued)
IF... GO TO SECTION PAGE Low flow ERCW supply headers 1A and 2A, AND STRAINER DIFF PRESS alarms DARK
[M-27A, C-3 and D.-2],
AND at least one of the following alarms LIT:
. ERCW DECK SUMP LEVEL HI alarm LIT 2.10 Supply Header A 88
[1-M-15B, A-3] Rupture Upstream of OR Strainer Inlet Valves OR Loss of Train A
. ERCWDECKSUMPPMPRUNNING ERCW
[1-M-15B, D-2 or D-4]
- MECH EQUIP SUMP LVL HI alarm LIT
[1-M-15A, B-61 Low flow ERCW supply headers 1 B and 2B, AND STRAINER DIFF PRESS alarms DARK
[M-27A, C-6 and D-5],
AND at least one of the following alarms LIT:
. ERCW DECK SUMP LEVEL HI alarm LIT 2.11 Supply Header B 94
[1-M-15B, A-3] Rupture Upstream of OR Strainer Inlet Valves OR Loss of Train B
. ERCW DECK SUMP PMP RUNNING ERCW
[1-M-15B, D-2 or D-41 OR a MECH EQUIP SUMP LVL HI alarm LIT
[1-M-15A, B-6}
Loss of flow on ALL ERCW supply headers in modes 14. 2.12 Loss of all ERCW flow 99 END OF SECTION Page 4 of 188
I STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.1 ERCW Pump Failure
- 1. IDENTIFY and LOCK OUT failed ERCW pump.
- 2. START additional ERCW pumps as required to maintain supply header pressure between 78 psig and 124 psig.
- 3. CHECK two Train A ERCW Pumps IF NO Train A ERCW pump is available, AVAILABLE. THEN GO TO Section 2.10, Loss of Train A ERCW.
I IF only one Train A ERCW Pump available, THEN EVALUATE isolation of non-essential Train A CCS heat loads USING Appendix E, CCS Heat Load Reduction [C.1]
Page 5 of 188
SQN LOSS OFESSENTIAL RAW COOLING WATER AOP-M.O1 Rev. 23 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 ERCW Pump Failure (contd)
- 4. CHECK 1A and 2A ERCW supply IF header leak or rupture is indicated, header pressures and flows NORMAL: THEN RETURN TO Section 2.0 for diagnosis.
- a. Supply header pressures
[between 78 psig and 124 psig]:
- 1-PI-67-493A
- 2-Pl-67-493A IF pressure is low due to only one pump
- b. Supply header flows available,
[expected value]: THEN
- 1-FI-67-61 EVALUATE isolation of non-essential ERCW loads.
- 2-FI-67-61
- 5. CHECK lB and 2B ERCW supply header IF header leak or rupture is indicated, pressures and flows NORMAL: THEN RETURN TO Section 2.0 for diagnosis.
- a. Supply header pressures [between 78 psig and 124 psig]:
- 1-PI-67-488A IF NO Train B EROW pump is available,
- 2-Pl-67-488A THEN GO TO Section 2.11, Loss of Train B ERCW.
- b. Supply header flows [expected value]:
I
- 1-FI-67-62
- 2-FI-67-62 IF pressure is low due to only one pump available, THEN EVALUATE isolation of non-essential ERCW loads.
Page 6 of 188
SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP-M.O1 Rev. 23 I STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 ERCW Pump Failure (contd)
- 6. DISPATCH personnel to inspect failed pump(s) and determine cause for failure.
- 8. CHECK ERCW pump loading amps INVESTIGATE abnormal amp readings.
NORMAL.
- 9. TRANSFER emergency power selector switch away from failed pump.
Page 7 of 188
JPM Sim F Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIMF Transfer lA-A 6.9 KV SD Bd from Alternate to Normal Supply
JPM Sim F Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Transfer lA-A 6.9 KV SD Bd from Alternate to Normal Supply Task#: 0620520201 Task Standard: lA-A 6.9 kv Shutdown Board is energized by manually starting the lA-A EDG.
Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X K/A Reference/Ratings: 064 A4.01 (4.0/4.3)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name! Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim F Page 3 of 10 Rev. 0 -
SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize to IC 14
- 3. Transfer lA-A 6.9 Ky Shutdown Board to the alternate feeder.
- 4. Insert IMF EG08A DIG lA-A Fails to Auto Start.
- 5. Insert Override ZDIHS5744ATrip 6.9KV SD Bd lA-A Alt. Fdr. Bkr. 1716.
- 6. An extra operator will be required to acknowledge alarms.
- 7. ACKNOWLEDGE ALARMS
- 8. FREEZE SIMULATOR.
- 9. Provide a copy of 0-SO-202-4, 6900V Shutdown Boards completed through 8.1.4 step 2.
- 10. PLACE SIMULATOR IN RUN SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
Tools/EquipmentlProcedures Needed:
References:
L 1. f Reference Title Rev No.
I 0-SO-202-.4 6900V Shutdown Boards 30
JPMSimF Page 4 of 10 Rev. 0 DLRECTtONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Units 1 and 2 are in MODE 1.
- 2. Relay testing has been completed on normal feeder to lA-A 6.9 Ky Shutdown Board.
INITIATING CUES:
- 1. You have been directed to transfer lA-A 6.9kV Shutdown Board to Normal Feeder at 1-M-1 using 0-SO-202-4, 6900V Shutdown Boards, Section 8.1.4, starting at step 3.
- 2. 0-S0-202-4, 6900V Shutdown Boards, Section 8.1 has been completed.
- 3. Another operator has been assigned and will provide concurrent verification.
- 4. Inform the SRO when complete.
JPM Sim F Page 5 of 10 Rev. 0 Start Time STEP 1 . Obtain a copy of 0-SO-202-4 6900V Shutdown Boards, Section 8.1.4 SAT UNSAT Standard: Examinee obtains a copy of 0-SO-202-4 6900V Shutdown Boards, Section 8.1.4 c* Provide a marked up copy of 0SO-202-4 6900V Shutdown Boards, Section 8.1.4 completed through step 2 Corn m ent Procedure NOTE Steps [3] through [9] are performed from the Unit 1 main control board panel 1-M-1 arid are to be reviewed immediately prior to Note performance.
STEP [3] ENSURE fl-XS-57-39], 6.9kV Shutdown Board 2 SAT lA-A voltmeter selector switch is in Sd Sd. 1A position.
U NSAT Standard: Examinee observes 1-XS-57-39 6.9kV Shutdown Board lA-A voltmeter selector switch in the SDBD 1A position.
Comment
JPM Sim F Page 6 of 10 Rev. 0 STEP 3 : [4] PLACE [iHS57-44Ai control switch for [17181, in SAT CLOSE position, AND HOLD.
UNSAT Critical Step Standard: Examinee places 1-HS-57-44A control switch for [1718J to CLOSE.
Comment Cue Respond to the examinee when asked to provide a concurrent verification, Operator concurs.
Examiner This step is critical since breaker transfer will only occur if the Note handswitch is placed and held in the CLOSE position.
STEP 4 : [5] PLACE [1-HS-57-41A], control switch for [1716] in TRIP SAT position MOMENTARILY.
UNSAT
- ; Critical Step Standard: Examinee places 1-HS-57-41 A control. switch for 117.16] to TRIP.
Comment Cue Respond to the examinee when asked to provide a concurrent verification, Operator concurs.
Examiner This step is critical since breaker transfer will only occur if the Note handswitch is placed and held in the TRIP position.
JPM Sim F Page 7 of 10 Rev. 0 NOTE: NOTE Steps [63 & [73 may be N/Ad if breaker does not close.
STEP 5 : [6] VERIFY breaker [1716] OPEN and breaker [1718] SAT CLOSED.
UNSAT Standard: Exarninee observes ACB 1718 fails to close and loss of 6.9 Ky SD Bd.
Comment Examiner ACB 1718 fails to close resulting in a loss of 6.9 KV SD Bd. lA-A Note followed by failure of DIGs to auto start and re-energize SD Bd. IA-A.
STEP 6 : [7] VERIFY [iEI-57-391. IA-A 69kV Shutdown Board SAT Bus voltmeter INDICATES normal voltage (6560-7260). UNSAT Standar& Examinee observes no bus voltage indicated on 6.9 kv SD Bus lA-A voltmeter 1 -EI-57-39.
Corn rnent STEP 7 : [8] RELEASE [1-HS-57-44A] to MID position.
SAT U N SAT Standard: Examinee releases 1-HS-57-44A control switch for [1718] to MID position Comment
JPM Sim F Page 8 of 10 Rev. 0 IF transfer does NOT occur, THEN STEP 8 : SAT PERFORM the following:
[a] ENSURE aN four diesel Generators have started UNSAT Standar& Examinee observes diesel generators did not start, recognizes DG RUN green light ON. [M-1j Corn rnent Alternate Path .
STEP 9 : SAT
. [9] IF transfer does NOT occur. THEN UNSAT PERFORM the following:
Critical Step
. [a] ENSURE all four desel Generators have started Examinee places 1-HS-82-15, DIG EMERG START IA-A, 2A-A, IS-B, 1 B-B to EMERG START position Standard: OR Examinee places O-HS-82-16A, DG IA-A Emergency Start, to EMERG START position. . . . . . .
Comment Exarniner This step is critical because the lA-A EDG will not start until one of the Note handswitches is placed in the START position due to a previously inserted malfunction.
JPM Sim F Page 9 of 10 Rev. 0 ti&if does NOT occur, THEN STEP 10 : SAT PERFORM the folowing:
Eb] ENSURE DG emergency breaker closes UNSAT on the blacked out shutdown board.
Examinee verifies DG emergency breaker 1912 closed, by observing red Standard: light above 1-HS-57-46A ON [M-261 or Breaker 1912 indicating light ON
[M-1]
Comment Cue Respond to the examinee when asked to provide a concurrent verification, Operator concurs.
1 Termin p rovid ating e the following cue Another operator will perform the Cue: STOP
[ remaining steps of this procedure.
Stop Time
JPM Sim F Page 10 of 10 Rev. 0 JPM BRIEFING SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. Units I and 2 are in MODE 1.
- 2. Relay testing has been completed on normal feeder to lA-A 6.9 Ky Shutdown Board.
INITIATING CUE:
- 1. You have been directed to transfer lA-A 6.9kV Shutdown Board to Normal Feeder at 1-M-1 using 0-SO-202-4, 6900V Shutdown Boards, Section 8.1.4, starting at step 3.
- 2. 0-SO-202-4, 6900V Shutdown Boards, Section 8.1 has been completed.
- 3. Another operator has been assigned and will provide concurrent verification.
- 4. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
W S W SQN 6900V SHUTDOWN BOARDS 0-SO-202-4 Rev: 30 0 Page 103 of 19 8.0 INFREQUENT OPERATION Transferring Power Supplies on 6.9kV Shutdown Board IA-A
ç43ii3bN During transfer of IA-A 6.9kV Shutdown Board control power to A Auxiliary Boiler will be momentarily lost.
This will result in tripping A Auxiliary boiler if it is running. [C.2]
When Unit 1 is in the Start Bus Outage alignment, the requirements of 15E500 sheet 3. Table 3 Start Bus Outage Alignment (Mode 5, 6, or de fueled) are applicable and Notes 2 & 3 below DO NOT apply for Unit 1.
NJ2 6.9 kV Shutdown Board alignments resulting in 2 shutdown boards fed from a single CSST winding will require coordination with the Transmission Operator (SELD) to maintain Off-site Power Source operability.
3 In addition to the requirements of Appendix A, the following requirements must be met: Two offsite power sources are available when the unit with both Shutdown Boards on a qualified single CSST winding meets either of the following conditions:
- a. alternate supply for the Shutdown Board NOT transferred is available.
- b. normal supply for the board that is transferred is maintained available.
Otherwise, LCO 3.8.1.1 action a applies. [C.3]
4 If LCO 3.8.1.1 action a must be entered due to shutdown board alignment, this action may be exited when both boards are transferred to their alternate feeders or both boards are transferred to their normal feeders. If D/Gs are operable, then the Shutdown boards may be considered operable by the provisions of LCO 3.0.5. [C.3]
5 Opening 6.9kV Unit Board breakers that feed 6.9kV shutdown boards will require configuration control in accordance with SPP-i0.1. [C.1]
ENSURE both unit ROs NOTIFIED of transfer operation. [C.2]
ENSURE Prerequisites, Section 4.0 has been PERFORMED.
ENSURE Auxiliary Boilers are SHUTDOWN.
ENSURE U-i Turbine Valve Testing NOT in progress.
ENSURE radwaste releases NOT in progress.
2 PPk,ucs
[ SQN 6900V SHUTDOWN BOARDS 0-SO..202-4 Rev: 30 0 PagelO4of 199 Unit I Date T4f 8.1 Transferring Power Supplies on 6.9kV Shutdown Board 1AA (Continued) 2 ENSURE Inverter 1-I in service (0-SO-250-2), OR Inverter 0-I in service supplying VIPB 1-I, OR VERIFY 120V ac Vital Instrument Bd. 1-I is deenergized.
ENSURE Inverter 2-I in service (0-SO-250-2), OR Inverter 0-I in service supplying VIPB 2-I, OR VERIFY 120V ac Vital Instrument Bd. 2-I is deenergized.
ENSURE preferred lnverter No 1 in service in accordance with 0-SO-250-4.
J) ENSURE 1-M-7 Power Racks A and B aligned from normal I supplies in accordance with 0-SO-250-3.
NOTIFY Nuclear Security that Access Control Power T Supply normal fdr will be momentarily interrupted.
- k) 1 ij ENSURE CCW cooling tower operational changes are I- NOT in progress.
ENSURE spent resin loading operations are NOT in progress in AB railroad bay.
$J3 NOTIFY Unit 1 Main Control Room that EHC and Turbine Lube Oil pump motor overload alarms will come in.
(XA-55-2A, windows C-4 (18) and C-6 (20).
ENSURE Power Checklist 0-202-4.01 has been completed.
ti IF Core Alterations are in progress, THEN NOTIFY Refueling SRO that power to the Manipulator Crane will be interrupted during board transfer.
[I SQN 6900V SHUTDOWN BOARDS O-SO-202-4 Rv;3Q L PagelO5ofl99 Unit I Date T4j 81 Transferring Power Supplies on 6.9kV Shutdown Board IA-A (Continued)
IF in Modes 1 through 4, THEN EVALUATE LCO 3.8.2.1 for 6.9kV Shutdown Board operability.
UISRO U2SRO EVALUATE LCO 3.8.1.1 due to the inoperability of offsite AC source. [C.3]
UISRO U2SRO IF in Mode 5 or 6, THEN EVALUATE LCO 3.8.1.2 and 3.8.2.2 forTS compliance. [C.3]
Ui SRO U2 SRO IF lA-A 6.9kV Shutdown Board is to be transferred from normal to alternate from l-M-1 control panel, THEN GO TO Section 8.1.1 of this Instruction, p IF lA-A 6.9kV Shutdown Board is to be transferred from normal to alternate from O-M-26 control panel, THEN GO TO Section 8.1.2 of this Instruction.
IF iA-A 6.9kV shutdown Board is to be transferred from normal to alternate locally from shutdown board, THEN GO TO Section 8.1.3 of this Instruction.
SQN 6900V SHUTDOWN BOARDS 0-SO-202-4 Rev: 30 0 PagelO6of 199 Unit 1 DateflOAr1 4j3Transferring Power Supplies on 6.9kV Shutdown Board IA-A (Continued) iF lA-A 6.9kV shutdown board is to be transferred from alternate to normal from 1-M-1 control panel, THEN GO TO Section 8.1.4 of this Instruction.
IF lA-A 6.9kV shutdown board is to be transferred from alternate to normal from O-M-26 control panel, THEN GO TO Section 8.1.5 of this Instruction.
)p. S.
3 IF IA-A 6.9kV shutdown board is to be transferred from alternate to normal locally from the shutdown board, THEN GO TO Section 8.1.6 of this instruction.
END OF TEXT
J,ww I SQN 6900V SHUTDOWN BOARDS 0-50-2024 0 . Rev;30 Page 118 of 199 Unit 1 Date_________
Transferring IA-A 6.9kV Shutdown Board From Alternate to Normal from 1-NI-I Control Panel OT I When transferring 6.9 kV Shutdown Board power supplies and transfer does NOT occur, allow Diesel Generator emergency breaker to close and loads to be applied as required by sequential timers.
Be aware of toads feeding from board prior to transfer.
If in service prior to transfer, the AA MCR Air Conditioning Compressor should automatically restart following board transfer.
ti] ENSURE Section 8.1 of this Instruction has been PERFORMED.
NOTE Step [2] is a final verification that the breaker is physically ready to close.
[2] PERFORM the following at 6.9KV Shutdown Board, lA-A, compartment 11, for Ii -BCTA-202-CMII I -A], 6,9KV Shutdown Board lA-A Normal Supply Breaker [17181:
[a] ENSURE spring charging motor toggle switch in ON position.
[b] VERIFY spring charged based on SPRINGS CHARGED CAUTION label at the bottom of front panel.
[C] ENSURE normal 3 phase voltage AVAILABLE on NORMAL supply breaker [1718]
compartment 11, via local voltmeter and selector switch on door. [C.I]
SQN 6900V SHUTDOWN BOARDS 0-50-202-4 I Rev:30 L_._o Pagell9of 199 Unit I Date_______
8.1.4 Transferring IA-A 6.9kV Shutdown Board From Alternate to Normal from l-M-l Control Panel (Continued)
NOTE Steps [3] through [9] are performed from the Unit 1 main control board panel 1-M-i and are to be reviewed immediately prior to performance.
[3] ENSURE [I-XS-57-39], 6.9kV Shutdown Board 1A4\ voltmeter selector switch is in Sd Bd. 1A position.
---......,,BEGINNING OF CRITICAL STEPS
[4] PLACE [I-HS-57-44A1, control switch for [1718], in CLOSE position, AND HOLD.
1st CV
[5] PLACE [I-HS-57-41A1, control switch for [17j61 in TRIP position MOMENTARILY, 1st cv NOTE Steps [6] & [7] may be N/Ad if breaker does not close.
[6] VERiFY breaker [17161 OPEN and breaker [1718]
CLOSED.
1st CV
[7] VERIFY 11-EI-57-391, lA-A 6.9kV Shutdown Board Bus voltmeter INDICATES normal voltage (6560-7260).
[8] RELEASE [1-HS-57-44A] to MID position.
END OF CRiTICAL STEPS
[9] IF transfer does NOT occur, THEN PERFORM the following:
[a] ENSURE all four diesel Generators have started.
[b] ENSURE DG emergency breaker closes on the blacked out shutdown board. /
1 s t
[ci GO TO SO-82 series for recovery
[ SQN 6900V SHUTDOWN BOARDS 0-50-202-4
.Rev:30.
0 Pagel2Oofl99 Unit 1 Date_______
8.1.4 Transferring IA-A 6.9kV Shutdown Board From Alternate to Normal from 1-M-1 Control Panel (Continued)
NOTE The 6.9kV Shutdown Board Room Chiller Package A will automatically restart when room temperature reaches the turn on setpoint for the associated Chill Water Pump with no Operator action.
[10] IF restart of the 6.9kV Shutdown Board Room Chiller Package A without room temperature excursion is desired, THEN START the A Chill Water Circ Pump USING
[O-HS-31 3-303B-A].
NOTE Spreading Room Ventilation may NOT restart following board transfer.
[I I] VERIFY all loads previously in service remain in service.
[12] ENSURE any annunciators illuminated due to transfer are DARK (located panel I -XA-55-1 B or O-XA-55-26A).
[13] IF only one shutdown board is on each CSST winding, AND all shutdown board transfers are complete, THEN NOTIFY Transmission Operator that MV Shutdown Boards are in a normal alignment.
END OF TEXT
JPM Sim G Page 1 of 13 Rev. 0 SEQUOYAK NUCLEAR PLANT JOB PERFORMANCE MEASURE SIMG Respond to a Failure of PRM N-44
JPM Sim G Page 2 of 13 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Respond to a Failure of PRM N-44 Task#: 3210140401 Task Standard: Recognize failure of Power Range Monitor, N-44, defeat its control functions, and prepare for removal from service.
Alternate Path: YES: NO: X Time Critical Task: YES: NO: X K/A Reference/Ratings: 015 A3.02 (3.7/3.9)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 8 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim G Page 3 of 13 Rev. 0 SPECIAL INSTRUCTIONS:
- 1. Ensure Simulator Operator Checklist is complete
- 2. Initialize IC #14 (75%, BOL).
- 3. Select N45 to one PR channel and A I channel
- 4. An extra operator will be required to acknowledge alarms.
- 5. ACKNOWLEDGE ALARMS
- 6. FREEZE SIMULATOR.
- 7. PLACE SIMULATOR IN RUN
- 8. When directed, approximately 1 minute after operator assumes shift, insert MF NIO7D
@ 0%.
SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
References:
L Reference Title Rev No.
L 1. AOP-l.O1 Nuclear Instrument Malfunction 10 I2 1-AR-M6-A Reactor Protection and Safeguards 15
JPM Sim G Page 4 of 13 Rev. 0 DIRECTIONS TOTRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
- 1. Unit 1 is operating at 75% reactor power.
INITIATING CUES:
- 1. Respond to plant conditions.
JPM Sim G Page 5 of 13 Rev.0 -
Start Time STEP I r I SAFEGUARDS SAT
[ 1-XA-558A UNSAT 8 (B-I)
NC4I UINC4I K NS POWER RANGE HIGH NEUTRON FLUX RATE Standard: Examinee acknowledges alarm and transitions to 1-AR-M6-A.
Comment Examiner Note Direct the facility operator to insert ME NIO7D @ 0%.
Correctlve [1] iF reactor tnps, THEN STEP 2 SAT Actions GO TO E-O, Reactor Tflp or Safe injection.
UNSAT Examinee observes the Reactor NOT tripped by observing power level Standard: indications, rod position indications and 1-)(X-55-5 trip status panel with only Hi Pwr Rate N44 bistable tripped.
Comment
JPM Sim G Page 6 of 13 Rev. 0 STEP 3 12] fl° rGCtQr trip, THEN SAT Ia] PLACE 1HS45-S1 10, Rod Contro Mode Selector Switch in
- the MANUALposition.
UNSAT Critical Step Standard: Examinee places 1-HS-85-51 10, Rod Control Mode Selector Switch in MANUAL.
Comment Examiner This step is critical because it prevents inadvertent rod movement Note while a malfunction is in progress.
bj CHECK for any rod bottom lights and/or RPI indicating STEP 4 SAT
. dropped rod(s).
UNSAT Standard: Examinee verifies no dropped rods by observing NO dropped rod lights and Rod Position indicating normal rod configuration.
Comment STEP 5 : CHECK 1-XX-55-S trip status panel for any bstab3es that may be tripped, SAT UNSAT Standard: Examinee observes 1-XX-55-5 trip status panel and observes only N44 bistable(s) tripped.
Comment
JPM Sim G Page 7 of 13 Rev. 0 STEP 6 tdl EVALUATE reactor trip CfltC with SRQ.
SAT U N SAT Standard: Examinee addresses reactor trip criteria with the Unit Supervisor c!1 Respond as Unit Supervisor concur with your assessment Comment STEP 7 t3l IF power range Ch3flfli fald ThEN GO TO AOPL01, Nu!ear Instnjment Malfunction. SAT U N SAT Standard: Examinee goes to AOP-I.01 Nuclear Instrument Malfunction.
Comment DIAGNOSE the failure:
STEP 8 :
SAT IF... GO TO SECTION PAGE UNSAT Power Range Failure 2.3 14 Standard Examinee goes to AOP-I.01 Nuclear Instrument Malfunction section 2.3.
Comment
JPM Sim G Page 8 of 13 Rev. 0 STEP 9 : 2.3 Power Range Failure SAT UNSAT I PLACE rod control in MAFL Standard: Examinee verifies 1-HS-85-5110, Rod Control Mode Selector Switch MANUAL.
Comment Examiner Note May have been performed in JPM step 3.
STEP 10 2. IF power increase is in progress, SAT THEN STABILIZE reactor power at current leveL UNSAT Standard: Examinee determines a power increase was NOT in progress and goes to step 3.
Comment
JPM Sim G Page 9 of 13 Rev.O STEP 11 3 EVALUATE the following Tech Specs SAT for applicability:
U N SAT 3.3.1 1 (3.3.1). Reactor Trip System Instrumentation
- 33.35, Remote Shutdown I nstru in en (alion
- 3.3.31, Accident Monitoring Instrumentation
- 4.2.4.2, QPTR with one PR Channel Inoperable Standard: Examinee addresses Tech Specs for applicability.
Cue Respond as Unit Supervisor I will EVALUATE Tech Specs for applicability.
Comment STEP 12 : 4. CHECK THREE power range channels SAT OPERABLE UNSAT Standard Examinee verifies three power range channels OPERABLE by observing channels N-41, N-42, and N-43 indicating normally.
Corn ment
JPM Sim G Page 10 of 13 Rev. 0 STEP 13 :
5 PLACE tOHowflg switches located on Detector Current Comparator drawer SAT
[M-13, N50J in position correspondinci to UNSAT failed Power Range Channel: Critical Step
. Upper Section Standard Examinee places DetectOr Current comparator T Upper Section* switch in the PRN-44 position.
Cue If directed, acknowledge Examinee is leaving the At the Controls Area.
Comment Examiner This step is critical because it allows for the removal of the control Note functions of the failed Nuclear Instrument.
STEP 14 : 5. PLACE folowing switches located on Detector Current Comparator drawer SAT
[M-13, N50] in position corresponding to UNSAT failed Power Range Channel: Critical Step a Lower Section Standard Exarnineç places Detector Current comparator BLower Section switch In the PRN44 position.
Comment Examiner This step is critical because it allows for the removal of the control Note functions of the failed Nuclear Instrument.
JPM Sim G Page 11 of 13 Rev. 0 STEP 15 5. PLACE following switches located
- SAT Detector Current Comparator drawer
[M-13, N50] in position corresponding to UNSAT failed Power Range Channel: Critical Step S
- Appropriate Rod Stop Bypass switch Standard Examinee places Rod Stop Bypass switch in the Bypass PRN-44 position.
Comment Examiner This step is critical because it allows for the removal of the control Note functions of the failed Nuclear Instrument.
STEP 16 : 5. PLACE following switches located on Detector Current Comparator drawer SAT
. [M-13, N501 in position corresponding to UNSAT
- failed Power Range Channel: Critical Step
- Appropriate Power Mismatch Bypass switch Standard: Examin places Power Mismatch Bypass switch in the Bypass PRN 44 position.
Comment Examiner This step is critical because it allows for the removal of the control Note functions of the failed Nuclear Instrument.
JPM Sim G Page 12 of 13 Rev. 0 STEP 17
. 6 DEFEAT failed Power Range channel
. USiNG Comparator Channel Defeat switch: SAT UNSAT
- Comparator and Rate Drawer Critical Step
[M-13, N37j Standar& Examinee places Comparator Channel Defeat switch in the N-44 position.
Corn ment Examiner This step is critical because it allows for the removal of the control Note functions of the failed Nuclear Instrurnent.
Terminating Provide the following cue Another operator will perform the ue. remaining steps of this procedure.
Stop Time
JPM Sim G Page 13 of 13 Rev.O JPM BRIEFiNG SHEET The examiner 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.
INITIAL CONDITIONS:
- 1. Unit 1 is operating at 75% reactor power.
INITIATING CUES:
- 1. Respond to plant conditions.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
8 (B-I)
Source Setpoint NC-41 UINC-41 K SER N1S POWER RANGE SER HIGH NEUTRON SER FLUX RATE SER 458 Positive/Negative +5%, -5% with a 2.2 High Flux Rate Bistable, second time constant NC4IU, NC41K NC42U, NC42K NC43U, NC43K NC44U ,NC44K 1/4 for alarm 2/4 for trip Probable 1. One or more rods dropped (negative rate).
Causes 2. Rod ejection (positive rate).
- 3. Loss of detector voltage.
- 4. Channel in test.
Corrective [1] IF reactor trips, THEN Actions GO TO E-O, Reactor Trip or Safety Injection.
[2] IF no reactor trip, THEN
[a] PLACE 1-HS-85-5110, Rod Control Mode Selector Switch in the MANUALposition.
[b] CHECK for any rod bottom lights and/or RPI indicating dropped rod(s).
[c] CHECK 1-XX-55-S trip status panel for any bistables that may be tripped.
[d] EVALUATE reactor trip criteria with SRO.
[3] IF power range channel failed, THEN GO TO AOP-l.O1, Nuclear Instrument Malfunction.
[4] IF more than one dropped rod occurs, THEN
[a] TRIP the reactor, AND
[b] GO TO Reactor Trip or Safety injection.
[5] IF one rod has dropped, THEN GO TO AOP-C.O1, Rod Control System Malfunctions.
(step continued on next page)
SQN l-AR-M6-A Page 11 of4O I Rev. 15
8 (B-I)
CONTINUED NC-41 UINC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE Corrective
[6] IF alarm is due to channel being tested, Actions THEN (Continued) ENSURE the rate mode switch, on the control power drawer, is placed in the RESET position and that the RATE TRIP bistable light goes out prior to test completion.
[T] EVALUATE Technical Specifications.
References 45B655-06A-O, 47W611-99 SQN 1-AR-MG-A Page 12 of 40 I Rev. 15
SQN NUCLEARINSTRUMEtT MALFUNCTION 1001 Rev. 10
( STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 7 2.0 OPERATOR ACTIONS
- 1. DIAGNOSE the failure:
IF... GOTO SECTION PAGE Source Range Failure 2.1 4 Intermediate Range Failure 2.2 9 Power Range Failure 2.3 14 Page 3 of 49
SQN NUCLEAR INSTRUMENT MALFUNCTION Rev. 10 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 Power Range Failure
- 1. PLACE rod control in MAN.
- 2. IF power increase is in progress, THEN STABILIZE reactor power at current level.
- 3. EVALUATE the following Tech Specs for applicability:
- 3.3.1.1 (3.3.1), ReactorTrip System Instrumentation
- 3.3.3.5, Remote Shutdown Instrumentation
- 3.3.3.7, Accident Monitoring Instrumentation
- 4.2.4.2, QPTR with one PR Channel Inoperable Page 14 of 49
SQN - NUCLEAR INSTRUMENT MALFUNCTION AQP-IIO1 Rev. 10 I STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 2.3 Power Range Failure
- 4. CHECK THREE power range channels IF less than two channels are operable, OPERABLE. THEN EVALUATE the need to trip reactor based upon potential loss of auto reactor trip function.
IF only two channels are operable, THEN PERFORM the following:
- a. REFER TO Tech Spec LCO 3.0.3.
- b. IF at least three channels CANNOT be made operable, THEN PERFORM plant shutdown USING one of the following:
- 0-GO-5, Normal Power Operation OR
- 0-GO-6, Power Reduction from 30%
Power to Hot Standby.
- c. DO NOT CONTINUE UNTIL at least three power range channels are OPERABLE.
Page 15of49
. SQN NUCLEAR INSTRUMNT MALFUNCTION AOP-IO1 Rev. 10 STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 2.3 Power Range Failure (contd)
- 5. PLACE following switches located on Detector Current Comparator drawer
[M-1 3, N50] in position corresponding to failed Power Range Channel:
- Upper Section
- Lower Section o Appropriate Rod Stop Bypass switch
- Appropriate Power Mismatch Bypass switch
- 6. DEFEAT failed Power Range channel USING Comparator Channel Defeat switch:
- Comparator and Rate Drawer
[M-13, N37J Page 16 of 49
JPM Plant H Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE INPLANT H (RO/SRO)
Boron Flowpath Alignment (O-Sl-OPS-062-064.O)
JPM Plant H Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Boron Flowpath Alignment (0-SI-OPS-062-064.0)
Task#: 40020204 Task Standard: The examinee completes the required portions of 1-SI-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D Checklist 3 Alternate Path: YES: NO: X Time Critical Task: YES: NO: X K/A Reference/Ratings: 004 A2.25 (3. 8/4. 3)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name! Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Plant H Page 3 of 10 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
1 Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
SPECIAL INSTRUCTIONS TO EVALUATOR:
ToolslEquipmentlProcedures Needed:
- 1. 1-SI-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D
References:
Reference Title Rev No.
- 1. 1-Sl-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION 16 VERIFICATION
- 2. GOI-6 APPARATUS OPERATIONS 140 READ TO OPERATOR HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 5.
INITIATING CUES:
- 1. You have been directed to proceed to the Unit 1 Auxiliary Bldg and perform the initial valve positioning of 1-SI-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D Checklist 3.
- 2. ALL prerequisites are complete.
- 3. Inform the SRO when complete.
JPM Plant H Page 4 of 10 Rev. 0 Start Time STEP Obtain a copy of 1-SI-OPS-062-064.0 BORIC ACID FLOW PATHS 1 SAT VALVE POSITION VERIFICATION Appendix D Checklist 3.
U N SAT Examinee obtains a marked up copy of 1 -SI-OPS-062-064.0 BORIC Standard: ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D Checklist 3.
Cue Provide a copy of 1-SI-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D Checklist 3.
Comment STEP 2 Check 1-FCV-62-140 Boric Acid to Blender FCV OPERABLE
- SAT U N SAT Examinee verifies 1-FCV-62-140 Boric Acid to Blender FCV OPERABLE Standard by observing control air properly lined up to its controller, air regulator, positioner and operator and is assembled and has no physical barriers or obstructions to its operation.
Provide the following cue: valve has control air properly lined up to its controller, air regulator, positioner and operator and is assembled and has no physical barriers or obstructions to its operation.
Comment From GOI-6 Examiner 1.7 Air-Operated Diaphragm Valves Note A. For a pneumabcally operated FCV to be aligned and!or operable it must have control air properly lined up to its controller, air regulator, positioner and operator. It must appear properly assembled and have no physical bamers or obstructions to its operation Examiner Note Valve is located 690 AB, Penetration Room, by Blender
JPM Plant H Page 5 of 10 Rev. 0 STEP Oheck 1-62-929, Manual Emergency Borate valve CLOSED.
3 SAT U N SAT Standard Examinee locates and verifies 1-62-929, Manual Emergency Borate valve closed by simulating clockwise direction on the valve handwheel.
When the examinee locates the valve provide the following cue, The Cue valve stem follower is down.
Provide the following cue the examinee simulates positioning the Cue valve, HW did not turn in the clockwise direction and is snugS Comment Examiner .
Note Valve is located AB, 690 Penetration Room, Left of Blender, 1 off Floor.
JPM Plant H Page 6 of 10 Rev. 0 STEP 4 : OPEN 1-62927, FCV-62-140 Isolation.
SAT UNSAT Critical step Standard Examinee locates and simulates opening 1-62-927, FCV-62-140 Isolation by simulating counter clockwise direction on the valve handwheel.
When the examinee locates the valve provide the following cue, The Cue valve stem follower is down.
Provide the following cue the examinee simulates positioning the Cue valve, HW turned several times in the counter clockwise direction and is now snug and the valve stem follower is up.
Comment Examiner This step is critical because it restores the normal flowpath to FCV Note 140.
Examer Valve is located AB, 690 Penetration Room, By Blender
JPM Plant H Page 7 of 10 Rev. 0 STEP Check 1-62-936 Blender to RWST Isolation CLOSED 5 : SAT UNSAT Standard Examinee locates and simulates closing 1-62-936 Blender to RWST Isolation by simulating clockwise direction on the valve handwheel.
When the examinee locates the valve provide the following cue, The valve stem follower is down.
Provide the following cue the examinee simulates positioning the valve, c e u-- HW did not turn in the clockwise direction and is snug.
Comment Examiner .
Note Valve is located AB, 690 Penetration Room, By Blender
JPM Plant H Page 8 of 10 Rev. 0 STEP Check 1-FCV-62-144 Blender to CCP Suction OPERABLE 6 : SAT U NSAT Examinee verifies 1-FCV-62-144 Blender to CCP Suction OPERABLE by Standard observing control air properly lined up to its controller, air regulator, positioner and operator and is assembled and has no physical barriers or obstructions to its operation.
Provide the following cue: valve has control air properly lined up to its Cue controller, air regulator, positioner and operator and is assembled and has no physical barriers or obstructions to its operation.
Comment From GOI-6 Examiner Ai!Opted Diaphragm Valves Note A. For a pneumatically operated FCV to be aligned and/or operable it must have control air properly lined up to its controller, air regulator. positioner and operator. It must appear properly assembled and have no physical barriers or obstructions to its operation.
Examiner Note Valve is located 690 AB, Penetration Room, by Blender
JPM Plant H Page 9 of 10 Rev. 0 STEP 7 : Open 1-62-696, Blender to VCT Isol SAT UNSAT Critical step Standard Examine locates and simulates opening 1-62-696, Blender to VCT Isol by simulating counter clockwise direction on the valve handwheel.
When the examinee locates the valve provide the following cue, The valve stem follower is down.
Provide the following cue the examinee simulates positioning the Cue valve, HW turned several times in the counter clockwise direction and is now snug and the valve stem follower is up.
Comment Examiner This step is critical because it restores the normal flowpath from the Note blender to the VCT.
Exmn,er AB, 690 Penetration Room, in VCT Room Hallway Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPM Plant H Page 10 of 10 Rev.0 JPM BRtEFI SHEET DIRECTIONS TO EXAMINEE:
All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 5.
INITIATING CUE:
- 1. You have been directed to proceed to the Unit 1 Auxiliary Bldg and perform the initial valve positioning of 1-Sl-OPS-062-064.0 BORIC ACID FLOW PATHS VALVE POSITION VERIFICATION Appendix D Checklist 3.
- 2. ALL prerequisites are complete.
- 3. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
4 J. rd I SQN BORIC ACiD FLOW PATHS VALVE 1-SI-OPS-062-064.0 Unit I POSITION VERIFICATION Rev. 0016 I Page 31 of 37 Appendix D (Page 8 of 8) 4M PERFORMANCE OF BORATION FLOW PATH VIA VCT (MODES 4-6)
CHECKLIST 3 Page 1 of 1 NOTE Special performances shall be independently verified. Periodic scheduled performances may be single verified with the IV signoff marked N/A.
REQUIRED DESCRIPTION VALVE NO. POSITION INITIALS Boric Acid to Blender FCV 1-FCV-62-140 OPERABLE 1st IV Manual Emergency Borate Valve 1-62-929 CLOSED 1st IV FCV-62-140 Isolation 1-62-927 OPEN 1st IV Blender to RWST Isolation 1-62-936 CLOSED 1st IV Blender to CCP Suction 1-FCV-62-144 OPERABLE 1st IV Blender to VCT Isol 1-62-696 OPEN 1st IV OPEN!
VCT Outlet MOV 1-LCV-62-133 OPERABLE 1st IV OPEN!
VCT Outlet MOV 1-LCV-62-132 OPERABLE 1st IV
JPM Plant I Page 1 of 8 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE IN PLANT I (ROISRO)
Reset the TO AFW Pump Locally
JPM Plant I Page 2 of 8 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Reset the TD AFW Pump Locally Task#: 0610080104 Task Standard: Locally shift control power and reset the Unit 1 TDAFW Pump.
Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X K/A Reference/Ratings: 061 A2.04 (3.4/3.8)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 11 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Plant I Page 3 of 8 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
- 1. EA-3-7, LOCAL OPERATION OF TD AFW PUMP
References:
Reference Title Rev No.
- 1. EA-3-7 LOCAL OPERATION OF TD AFW PUMP 6 READ TO OPERATOR HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
DIRECTIONS TO EXAM1NEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM.
WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 3
- 2. ECA-0.0 is in progress at step 7b
- 3. The Turbine Driven Auxiliary Feed Pump has tripped.
- 4. The Control Room has indications that DC power has been lost to the Turbine Driven Auxiliary Feed pump due to a loss of 125VDC Vital Battery Board Ill.
- 5. Unit 1 Alternate DC power supply from I 25V Vital Batt Bd IV is available.
INITIATING CUES:
- 1. You have been directed to proceed to the Auxiliary Feed pump room and locally start the Turbine Driven Auxiliary Feed pump using EA-3-7, LOCAL OPERATION OF TD AFW PUMP, starting at step 9.
- 2. Inform the SRO when complete.
JPM Plant I Page 4 of 8 Rev. 0 Start Time NOTE 1 The TD AFW pump governor valve IFCV.1-521 fails open on Procedure Of DC control power to ID AFW pump speed controller.
Note NOTE 2 Unit 1 Alternate DC power supply is from I 25V Vital Ball Bd IV.
Unit 2 Alternate DC power supply is from I 25V Vital Batt Bd IL Obtain a copy of EA-3-7, LOCAL OPERATION OF TD AFW PUMP STEP 1 : SAT UNSAT StandardS Examinee obtains a copy of EA-3-7, LOCAL OPERATION OF TD AFW PUMP Cue Provide a marked up copy of a copy of EA-3-7, LOCAL OPERATION OF TD AFW PUMP completed through step 8.
Comment
JPM Plant I Page 5 of 8 Rev. 0 STEP 2 : 9. IF alternate DC control power supply is AVAILABLE (determined by MCR),
SAT THEN
. PERFORM the following:
UNSAT
- a. TRANSFER affected unit to alternate DC control power supply ..
at TO AFW PUMP RM DC CONTROL PWR TRANSFER SWITCH: ritica. tep Unit 1 on wall outside numo room behind CCS seal drain tank.
- 1) PLACE NORMAL breaker in OFF. U
- 2) PLACE ALT breaker in ON position. U Standard Examinee simulates placing NORMAL DC Control Power Supply breaker. in OFF and the ALT breaker in ON position.
Cue If asked, provide the following cue Vital Battery Board IV is available.
Cue When the examinee finds the DC Control Power Supply breakers, provide the following cue Breakers are in the as-found position.
After the examinee simulates operating the DC Control Power Supply cid breakers, provide the following cue NORMAL DC Control Power Supply breaker is in OFF and the ALT breaker is in ON.
Comment Examiner This step is critical because it aligns a source of control power to the Note Turbine Driven Auxiliary Feed pump.
JPM Plant I Page 6 of 8 Rev. 0 STEP 3 : Alternate path . .
- b. ENSURE TD AFW pump trip and throttle valve [F.V-1-ii LATCHED and mechanical overspeed mechanism RESET. UNSAT (Refer to placard on TO AFW pump room wall]
. Critical Step
- TRIP and THROTTLE VALVE:
1 .ENSU RE Trip and Throttie Valve Operator run CLOSED.
Standard Examinee simulates closing the Trip and Throttle Valve Operatr by depressingOLOSE on pushbutton 1-HS-51B. .
When the examinee finds the Trip and Throttle valve provide the Cue following cue. The manual trip lever is down, the emergency connecting rod is to the right, and the Trip and Throttle valve latchup lever down and not engaged with the trip hook.
After the examinee simulates depressing the CLOSE on pushbutton 1-HS-51 B provide the following cue, You have depressed CLOSE on pushbutton 1-HS-51B for 10 seconds.
After the examinee simulates closing the Trip and Throttle Valve Operator by depressing CLOSE on pushbutton 1-HS-51B, provide the following cue. The Trip and Throttle valve latchup lever is up.
Comment Examiner The guidance for this action comes from the placard on the TD AFW Note pump room wall.
Examiner At the examiners discretion refer the examinee to the handout AFW Note Local Indication instead of the first cue of this JPM step.
Examiner This step is critical because it resets the Turbine Driven Auxiliary Feed Note pump trip throttle valve.
JPM Plant I Page 7 of 8 Rev. 0 STEP 4 Alternate path SAT
- b. ENSURE TD AFW pump trip and throtUe valve [EcV-1-51]
LATCHED and mechanical overspeed mechanism RESET. UNSAT
- [Refer to placard on ID AFW pump room waUl Critical Step Examinee resets the AFW turbine overspeed trip mechanism by simulating the following.
- 1. PULL connecting linkage left and HOLD.
Standard: 2. RAISE manual trip lever to horizontal position and HOLD.
- 3. RELEASE connecting linkage.
- 4. RELEASE manual trip lever
- 5. VERIFY trip lever remains in horizontal position.
Provide the following cue after the examinee simulates resetting the AFW turbine overspeed trip mechanism. Manual trip lever is horizontal, and the trip hook engaged with the latch-up lever.
Comment Examiner Only items one and two of this standard are critical, all other items are Note NOT critical.
Examiner The guidance for this action comes from the placard on the TD AFW Note pump room wall.
Examiner This step is critical because it resets the Turbine Driven Auxiliary Feed Note pump trip throttle valve.
Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPM Plant I Page 8 of 8 Rev. 0 JPM BRIEFING SHEET DIRECTIONS TO EXAM INEE:
All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 isinMODE3
- 2. ECA-0.0 is in progress at step 7b
- 3. The Turbine Driven Auxiliary Feed Pump has tripped.
- 4. The Control Room has indications that DC power has been lost to the Turbine Driven Auxiliary Feed pump due to a loss of 125VDC Vital Battery Board Ill.
- 5. Unit 1 Alternate DC power supply from 125V Vital Batt Bd IV is available.
INITIATING CUE:
- 1. You have been directed to proceed to the Auxiliary Feed pump room and locally start the Turbine Driven Auxiliary Feed pump using EA-3-7, LOCAL OPERATION OF TD AFW PUMP, starting at step 9.
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-3-7 LOCAL OPERATION OF TD AFW PUMP Revision 6 QUALITY RELATED PREPARED/PROOFREAD BY: E. A. ELAM RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 12/20/2007 REVISION DESCRIPTION: Revised to include entry from EDMG-1 Loss of Main/Auxiliary Control Room Function Initial Response and reference to the Operations Incident Manager (QIM). Added optional TDAFW Pump flow adjustment using FIC-46-57 to Section 4.2. Added Site Security as alternate key source in Section 4.2 Step 3. Enhanced Section 4.2 Note 3 before Step 13 to provide guidance if 30 minutes is exceeded before TDAFW Pump injects. Added clarifying note to Appendix C.
Enhanced several steps in Sections 4.1 and 4.2 to provide better direction to operator. Added note to Appendix C to provide guidance on control of S/G Injection Flow. Added Source Note page and B.5.b Phase 2 and 3 license condition commitment.
A copy of this procedure is stored outside the TDAFWP room in the EA-3-7 Storage Box Il I 1IJfAbDkRE
SQN EA-3-7
- CAL OPERATION OF TD AFW. RUMP 1,2 Page2of23 1.0 PURPOSE To provide instructions for locally operating the TD AFW pump following loss of AC and/or DC control power OR other events which could impact the ability of the MCR to monitor and control TD AFW flow. [C.1]
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. ECA-O.O, Loss of All AC Power.
B, AOP..T.O1, Security Events.
C. EDMG-1, Loss of MCR/ACR Function Initial Response 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. If the accountability siren sounds the operator should continue performing this procedure. The SM should be aware of procedure performance and personnel locations.
B. The ID AFW pump electronic overspeed trip at 4300 rpm will be disabled on loss of power. The mechanical overspeed trip at 4900 rpm will be available for overspeed protection.
SQN EA4-7 LOCAL OPERATION OF TD AFW PUMP Revs 6 1,2 Page3of23 4O PERFORMANCE
- 1. RECORD approximate time of unit trip.
- 2. CONSULT the MCR (if communications available) or the Operations Incident Manager (OlM) to determine applicable section of this procedure:
IF the following conditions met: THEN GO TO This procedure entered due to aircraft threat (AOP-T.O1) or loss of main and auxiliary control room functions (EDMG-1)
Section 42, Local Control OR of TDAFW Pump Flow with Temporary DIP Gage Temporary gage for locally monitoring TDAFWP flow is needed due to loss of instrumentation or electrical power This procedure entered from (Loss of all AC Power) or FR-Hi (Loss.6f Secondary Heat Sink)
Section 4.1, Local Actions AND to Restore TDAFW Pump Flow.
Temporary gage for locally monitoring TDAFWP flow is NOT needed
T .
SQN LOCAL OPERATLON OF TO AFW PUMP 1,2 Page4of23 4.1 Local Actions to Restore TD AFW Pump Flow IDENTIFY applicable unit:
Unit 1 Unit2 LI OBTAIN the following items:
radio gloves OBTAIN the following keys: [glass-faced box in SM office]
Vital Area key Protected Area key. EV GO TO Panel L-381 for applicable unit.
[AS el. 669, Outside TDAFW Pump Room]
Equipment Storage boxes are located in vicinity of TDAFWP rooms (Unit 1: across from TDAFWP room, near lA-A CCP Room door),
(Unit 2: behind lighting board, AB el. 669 south wall).
f&) IF SCBA is needed, L/ THEN REFER TO App. B, Use of Permanent Air Bottle in TDAFWP Room. El MONITOR communications available with MCR:
- IF communication with MCR is lost and CANNOT be restored OR MCR has lost the ability to monitor TDAFW pump flow due to loss of vital AC power, THEN GO TO Section 4.2, Local Control of TDAFW Pump Flow with Temporary DIP Gage. LI
r SQN
. LOCAL OPERATION OFTD AFW PUMP Rev. 6 1,2 Page5of23 4.1 Local Actions to Restore TD AFW Pump Flow (Continued)
IF TD AFW pump is NOT running, THEN GO TO Ste6)
NOTE Loss of AC control power with DC control power still available will result in TD AFW pump operating at minimum speed. Removal of DC control power will cause governor valve to fail open and will allow manual control of TDAFWP speed using FCV-1-51 handwheel.
- 8. IF TDAFW pump is RUNNING THEN PERFORM the following:
- a. MONITOR [FIC-46-571 to determine if AC control power has been lost. [inside panel L-381, outside TDAFWP Room] LI
- b. IF FlC-4657 is energized, THEN PERFORM the following:
- 1) PLACE FXS-46-571 in AUX position.
[Unit I on wall outside pump room behind CCS seal drain tank.
Unit 2 on wall opposite TD AFW pump room.] LI
- 2) PLACE [FIC-46-571 TDAFWP flow controller in MANUAL
[Inside Panel L-381]
AND REMAIN on station until further direction from MCR.
T SON LOCAL OPERATION OF TD AFW PUMP.
1,2 Page6of23 4.1 Local Actions to Restore TD AFW Pump Flow (Continued)
- 8. (Continued)
- c. IF FIC-46-57 is de-energized OR required TDAFW pump flow CANNOT be establlshed using FIC-46-57, THEN PERFORM the following:
- 1) ENSURE TDAFW pump TRIPPED USING trip lever at east end of shaft.
- 2) ENSURE NORMAL and ALTERNATE breakers on DC control power transfer switch in OFF position.
[Unit 1 on wall outside pump room behind CCS seal drain tank.
Unit 2 on wall opposite TD AFW pump room Li
- 3) GOTOSteplO. LI
4.1 Local Actions to Restore TD AFW Pump Flow (Continued)
OTE The TD AFW pump governor valve [FCV-1 -521 fails open on loss of DC control power to TD AFW pump speed controller.
rrji Unit 1 Alternate DC power supply is from 125V Vital Batt Bd IV.
Unit 2 Alternate DC power supply is from 125V Vital Batt Bd II.
alternate DC control power supply is AVAILABLE (determined by MCR),
THEN PERFORM the following:
- a. TRANSFER affected unit to alternate DC control power supply at TD AFW PUMP RM DC CONTROL PWR TRANSFER SWITCH:
Unit 1 on wall outside pump room behind CCS seal drain tank.
Unit 2 on wall opposite TD AFW pump room.]
- b. ENSURE TD AFW pump trip and throttle valve IfCV-1 -511 LATCHED and mechanical overspeed mechanism RESET.
[Refer to placard on TD AFW pump room wall]
- LATCH IFCV-1-5j] and RESET mechanical overspeed mechanism.
a I
- - a i an t0 i
.1:
t.rI rn t
a
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JPM Plant J Page 1 of 9 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE INPLANT J (ROISRO)
Respond to Decreasing RCS Pressure and Level From the Aux. Control Room
JPM Plant J Page 2 of 9 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Respond to Decreasing RCS Pressure and Level From the Aux.
Control Room Task#: 0000680501 Task Standard: Examinee terminates the pressure and level reduction in the RCS (PZR) using AOP-C.04 Appendix C.
Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA ReferencelRatings: APE 068 AA1.12 (4.4/4.4)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 16 mm Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Plant J Page 3 of 9 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR: -
- 1. SM approval will be required to enter the Trip Hazard Zone in backup control room.
- 2. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 3. Any UNSAT requires comments.
ToolslEquipmentlProcedures Needed:
1 AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix C
References:
Reference Title Rev No.
- 1. AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL 25 ROOM READ TO OPERATOR HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
DIRECTIONS TO EXAMINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM.
WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Units 1 and 2 are in MODE 3
- 2. AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM is in progress
- 3. Unit 1 RCS Pressure is 2000 psig and DROPPING uncontrollably
- 4. Unit 1 Pressurizer Level is 20% and DROPPING uncontrollably
- 5. Unit 1 RCS Cold Leg Temperature is 540° and stable.
INITIATING CUES:
- 1. You have been directed to proceed to the Auxiliary Control Room and perform AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix C
- 2. Inform the SRO when complete.
JPM Plant J Page 4 of 9 Rev. 0 Start Time STEP I
. Obtain a copy of AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM SAT UNSAT Standard: Examinee obtains a copy of AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix C Provide a copy of AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix C Comment STEP 2 I=niLL RCS pressure &OPpH uncontrolled, THEN SAT PERFORM the following:
- a. ENSURE the following transfer switches in AUX position:
U N SAT Critical Step F SWITCH EQUIPMENT NAME LOCATION AUX POSITION 1-XS-68-340C PressudzerPORV 1-L-I1A Standard: Examinee simulates placing aux transfer switch 1-XS-68-340C on panel 1-L-1 lAto the AUX position.
CU Point to Aux transfer switch 1-XS-68-340C on panel 1-L-1 1A to indicate the switch is in the AUX position.
Comment Examiner This step is critical to prevent inadvertent opening of the Pressurizer Note PORV.
JPM Plant J Page 5 of 9 Rev. 0 1 IF Unit 1 RCS pressure dropping uncontrolled STEP 3 : THEN SAT PERFORM the following:
- UNSAT
- a. ENSURE the followng transfer switches n AUX poshon:
SWITCH
[ EQUIPMENT NAME LOCATION AUX POSITION Critical Step 1-XS-68-334C PressurizerPORY i-L-i1B Standard Examinee simulates placing aux transfer switch 1-XS-68-334Con panel I -L-I 18 to the AUX position.
Cue Point to Aux transfer switch I -XS-68-334C on panel 1 -L-1 1 B to indicate the switch is in the AUX position.
Comment Examiner This step is critical to prevent inadvertent opening of the Pressurizer Note PORV.
b ENSURE pressurizer PORVs CLOSED {1-L-1O1:
STEP 4 : SAT
. i-PCV-68-334 El
. i-PCV-68-340 El UNSAT Examinee locates switches 1-HS-68-334C Pressurizer PORV and 1-Standard: HS-68-340AC Pressurizer PORV on Panel 1-L-10 and verifies green lamps ON.
Cue Point above switches 1-HS-68-334C and 1-HS-68-340AC on Panel 1-L-10, state Green Light ON.
Cue If the examinee observes RCS Pressure, provide the following cue RCS Pressure is dropping.
Comment
JPM Plant J Page 6 of 9 Rev. 0
- 2. RCS T-cold is less than 54OF AND dropping uncontrolled.
STEP THEN SAT PERFORM the foflowing:
- a. ENSURE transfer switches for MSP/s and S!G atmospheric reliefs UNSAT (on Checklist 1> have been placed in AUX position. [1-L-i IA and 118] El
- b. ENSURE jLI SIG atmospheric relief valves CLOSED. [i-L-1O] El
- c. IF cooldown is continuing, THEN ENSURE Urntl MSIV bypass valve fuses removed USING Appendix E. El Standard Examinee marks step as N/A based on the Initial Conditions and proceeds to step 3.
Comment STEP 6 3. IF Unit 1 pressurizer level is dropping uncontrolled, SAT PERFORM the following to isolate letdown paths:
UNSAT
- a. ENSURE transfer switches for normal and excess letdown valves (on Checklist 1) have been placed in AUX position, [1 -L-1 1A and 118]
Examinee verifies transfer switches for normal and excess letdown Standard: valves (on Checklist 1) have been placed in AUX position on Panel 1-L-1IA and I1B Cue Provide the following cue, Another operator has completed Checklist 1.
Comment
JPM Plant J Page 7 of 9 Rev. 0 STEP 7 : 3. IF Unit I pressurizer level is dropping uncontrolled.
SAT PERFORM the following to isolate letdown paths:
UNSAT
- b. ENSURE normal and excess letdown isolated: [1 -L-1 0]
. i-FCV-62-72 CLOSED Standard Examinee locates switch for 1-FCV-62-72 on Panel 1-L-10 and observes green lamp ON.
Cue Point above switch 1-FCV-62-72 on Panel 1-L-10, state Green Light ON.
Comment STEP 8 : 3. IF Unit 1 pressurizer level is dropping uncontrolled.
SAT PERFORM the following to isolate letdown paths:
UNSAT
- b. ENSURE normal and excess letdown isolated: [i-L-10] Critical Step
. l-ECV-62-13 CLOSED Standard: Examinee simulates placing handswitch for 1-FCV-62-73 to CLOSE Before examinee addresses this step, point to handswitch for 1-FCV-cJL 62-73 on panel 1-L-10, indicate the switch is in the OPEN position and state Red Light ON.
After examinee simulates placing handswitch for 1-FCV-62-73 to cJd CLOSE, point to handswitch for 1-FCV-62-73 on panel 1-L-10, indicate the switch is in CLOSE position and state Green Light ON.
Comment Examiner . . .. .
Note This step is critical because it isolates the Normal Letdown flowpath.
JPM Plant J Page 8 of 9 Rev. 0 Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time
JPM Plant J Page 9 of 9 Rev. 0 JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:
All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Units 1 and 2 are in MODE 3
- 2. AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM is in progress
- 3. Unit 1 RCS Pressure is 2000 psig and DROPPING uncontrollably
- 4. Unit 1 Pressurizer Level is 20% and DROPPING uncontrollably
- 5. Unit 1 RCS Cold Leg Temperature is 540° and stable.
INITIATING CUE:
- 1. You have been directed to proceed to the Auxiliary Control Room and perform AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix C
- 2. Inform the SRO when complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
j Jrr f SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-QM4 Rev. 25 Page 1 of 2 APPENDIX C STABILIZING UNIT I RCS PARAMETERS IF Unit 1 RCS pressure dropping uncontrolled, THEN PERFORM the following:
- a. ENSURE the following transfer switches in AUX position:
SWITCH EQUIPMENT NAME LOCATION AUX POSITION 1-XS-68-340C Pressurizer PORV 1-L-1 IA El 1-XS-68-334C Pressurizer PORV 1-L-1 18 El
- b. ENSURE pressurizer PORVs CLOSED [1-L-10]:
- 1 -PCV-68-334
- 1 -PCV-68-340
- 2. IF Unit 1 RCS T-cold is less than 540°F AND dropping uncontrolled, THEN PERFORM the following:
- a. ENSURE transfer switches for MSIVs and SIG atmospheric reliefs (on Checklist 1) have been placed in AUX position. [1 -L-1 1A and 11 B]
- b. ENSURE Unit 1 SIG atmospheric relief valves CLOSED. [1L-10] El
- c. IF cooldown is continuing, THEN ENSURE Unit 1 MSIV bypass valve fuses removed USING Appendix E.
I? 3 ii-IRo4PES Page 126 of 193
SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-C.04
- Rev.25 Page 2 of 2 APPENDIX C
- 3. IF Unit I pressurizer level is dropping uncontrolled, THEN PERFORM the following to isolate letdown paths:
- a. ENSURE transfer switches for normal and excess letdown valves (on Checklist 1) have been placed in AUX position. [1 -L-1 1A and 1 1 B] El
- b. ENSURE normal and excess letdown isolated: [1-L-1O]
. 1-FCV-62-72 CLOSED El
. 1-FCV-62-73 CLOSED El
. 1-.FCV-62-74 CLOSED El
. 1-FCV-62-54 CLOSED El
. 1-FCV-62-55 CLOSED El
. 1-FCV-62-56 CLOSED (1-HIC-62-56C) El
- c. ENSURE the following fuses for Unit 1 head vent valves REMOVED:
VALVES FUSE LOCATION FUSE ID REMOVED 125V Vital Battery Board I, Ckt B14 O-FU2-250-KEB14-D 1 -FSV68-395 1-FSV-68-396 125V Vital Battery Board II, Ckt A30 O-FU2-250-KFA3O-E END OF TEXT Page 127 of 193