ML111990563
| ML111990563 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/02/2011 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-348/11-301, 50-364/11-301 | |
| Download: ML111990563 (200) | |
Text
FNPHLT34JPM Pagelof8 SIMULATOR JPM A.
CRO-033A TITLE: Perform The Corrective Actions Required For Recovery Of A Misaligned Rod EVALUATION LOCATION: I SIMULATOR D CONTROL ROOM E CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-218 I1 ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
- 2. Examinee will be provided a marked up copy of FNP-1-AOP-19.0 Attachment 1 (attached). The markup shall be as follows:
- a. STEP 1 and STEP 2 will be signed off with appropriate place keeping per plant standards.
- b. The conditional steps which do not apply will be pre-marked as not applicable (N/A) as expected per plant standards.
- 3. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise.
- 4. A complete copy of AOP-19.0 will be provided, for use during the 1PM.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
. Correctly complete the applicable actions of FNP-l-AOP-19.0.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Howard Fitzwater I Date: 4/25/20 11 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 SIMULATOR JPM A. Page 2 of (Guide pages = 7)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-218 for 1PM A Put OPS group on MCB CRT Acknowledge computer alarms Provide a clean copy of AOP-19.O, v27.O Verify CONTROL ROD Disconnect switch box is unobstructed.
Verify RODS updated.
Run / Freeze Simulator Acknowledge annunciators Turn Horns ON UPON COMPLETION REMOVE any printouts on SIM1 simulator after each iteration of this 1PM.
REPLACE/CLEAN AOP-19.O upon completion of the 1PM Setup IC218*
RST IC-121 (JPM CRO-033A) contain the
- following necessary malfunctions/triggers:
Expert cmd:
Trgset 1 MCRFNS(45) < 201 IMF MAL-R0D545 (1)
IMF MAL-ROD547 (1)
Prevent an Automatic Rx trip insert
- CMFmaIf/cBKRXTRP_cc5/OPEN CMFmalf/cBKRXTRP_cc6/OPEN SNP 218
CONDITIONS When I tell you to begin, you are to PERFORM THE CORRECTIVE ACTIONS REQUIRED FOR RECOVERY OF A MISALIGNED ROD. The conditions under which this task is to be performed are:
- a. The plant was in MODE 1, ramping down from 100% when the ramp was stopped at 72%
power due to a Control Rod misalignment.
- b. DRPI indication for rod F6 indicates 204 steps.
- c. DRPI indication for all other Bank D rods indicates 186 steps.
- d. The cause of the misalignment was a blown fuse and it has been replaced.
- e. AOP-19.0, Malfunction of Rod Control System, is in progress.
- f. Maintenance personnel are not required to be notified prior to rod motion.
- g. You have been directed to complete ATTACHMENT 2 of AOP-19.0 beginning with step 3 while complying with the following realignment plan:
- 1. Restoration of Rod Alignment to be conducted between 70% and 80%.
- 2. The rate of control rod movement during recovery shall be conducted at 3 step increments, to achieve alignment within TS limits within the next 30 minutes.
- 3. Movement of other control rods to support recovery is NOT permitted.
INITIATING CUE, You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
- 1. Align lift coil disconnect switches. (BOP) Locate and Position the lifi coil S/U (Attachment 2 step 3) disconnect switches for ALL For rod re-alignment, align switches to Control Bank D rods EXCEPT DISCONNECT position for all non-affected rods rod F6 (7 total) to the up-in the affected bank. DISCONNECT position.
Bottom row of Switches.
HIGHLIGHTED indicates F6 position in that row.
T1 (Attachment 2 step 4) CHECKs the rod control bank S/U
- 2. Verify the ROD CONTROL BANK SELECTOR selector switch and SWITCH is selected to the affected bank. IDENTIFIES that it is selected to CONTROL BANK B.
FNP HLr-34 SIMULATOR JPM A. Page 4 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(Attachment 2 step 5) This step is Pre-marked as Not
- 3. IF required notify maintenance personnel when Applicable; initial conditions rod movement will begin, identify this NOT required.
CUE if notification attempted:
Maintenance personnel acknowledge.
NOTE:
- Performing element 4 (procedure step 6) will result in FF1, Rod Control Urgent Failure, to actuate; The UNAFFECTED group step counter will not actuate when rods are moved.
- Once ROD F6 inserted to a height of 201 steps, Control Rods F6 and Kl0 fall into the core.
If requested prior to rod motion CUE: Another operator will adjust Turbine load when required.
(Attachment 2 step 6) POSITIONS IN-HOLD-OUT S / U
- 4. Rod Alignment to the IN position For rod re-alignment, adjust misaligned rod to agree with associated group DRPI indication at a OBSERVES the GREEN rate determined in step 1.1. RODS IN light lit, CBD GP1 step counter counts down
- 5. IDENTIFIES symptoms of a dropped rod are INDENTIFIES dropped rod and S / U present and AOP-1 9 re-entered at step 1. Enters AOP-19 at step I OR INDICATIONS: UTILIZES ARP1.6, FE3 OR
- FE3, FE4, & FF1 in alarm FE4, step 2 response, which
- Rod Bottom LEDs are lit for rods F6 AND reads:
Kl0
- Reactor Power lowers 2% IF two or more rods drop in Mode
- Tavg lowers 2°F 1 or during reactor startup, THEN perform the following:
- Manually trip the reactor.
NOTE:
- AOP-19.0 steps 1 and 2 are IMMEDIATE OPERATOR actions.
- Elements 6 and 7 will not be completed IF ARP-1 .6, FE3 OR FE4 is implemented instead.
FNP HLI-34 SR4ULATOR JPM A. Page 5 of 8 (Guide pages 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(AOP-19.O step 1) S / U
- 6. Verify NO load change in progress. Checks DElI and/or Generator Load to determine No load change in progress.
(AOP-19.O step 2) S / U
- 7. IF unexplained rod motion occurring, THEN Evaluates and determines that stop rod motion. NO unexplained rod motion is
- a. IF rod control in AUTO, THEN place rod occurring. This step is Not control in MANUAL. Applicable.
- b. IF rod control in MANUAL, THEN place rod control in AUTO
- i. IF AUTO rod motion due to TAVG/TREF mismatch, THEN verify rod motion stops when TAVG is within 1 degree of TREF
- c. IF unexplained rod motion NOT stopped, THEN Trip the reactor (AOP-19.O step 3 Also FE3&FE4 step 2) S / U
- 8. Check that no dropped rod(s) exist(s) in Mode 1 IDENTIFIES two rods dropped OR during a reactor startup. and TRIPS THE REACTOR.
- a. IF MORE THAN ONE dropped rod exists, THEN perform the following:
- i. Trip the Reactor.
ii. Go to FNP-1-EEP-O, REACTOR TRIP OR SAFETY INJECTION.
NOTE:
- EEP-O steps 1 through 4 (elements 9-12) are IMMEDIATE OPERATOR actions.
(EEP-O step 1) S / U
- 9. Check reactor trip. IDENTIFIES THE REACTOR
- Reactor Trip and bypass breakers OPEN trip has occurred.
- Nuclear power FALLING IF DRPI available, THEN rod bottom lights -
LIT
FNP HLT-34 SIMULATOR JPM A. Page & of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(EEP-0 step 2) S / U
- 10. Check turbine trip. IDENTIFIES the turbine has
- TSLB 14-1 LIT tripped.
- TSLB 14-2 LIT
- TSLB 14-3 LIT
- TSLB 14-4 -LIT (EEP-0 step 3) S / U
- 11. Verify power to 41 60V ESF busses. IDENTIFIES BOTH TRAINS
- 1. 4160 V ESF busses AT LEAST ONE are powered by offsite power ENERGIZED
- a. iF 4160V bus power available light - iF bus power light LIT LIT OR - 1G bus power light LIT
- b. 1G 4160V bus power available light LIT - iF & 1KA train power
- 2. 4160 V ESF busses BOTH TRAINS available lights lit.
Energized - 1 G and 1 J B train power available lights lit.
- 3. [CA] Verify operating diesel generator(s) - NO diesels will be SUPPLIED FROM AT LEAST ONE SW operation therefore this step PUMP is N/A.
(EEP-0 step 4) S / U
- 1. Check any SI actuated. actuated and is NOT required.
o MLB-1 i-i and 11-1 lit o Byp & PERM light box status light RNO ACTIONS
- a. Ctmt Press and bistables
- b. RCS Press and bistables
- c. STM pressure and bistables STOP TIME Terminate when the Reactor is tripped and upon completion of the Immediate operator actions of EEP-O.0.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP HLT-34 SIMULATOR JPM A. Page 7 of 8 (Guide pages = 7)
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-AOP-19.0, V 27.0 FNP-1-ARP-1.6, V67.0
- 2. KJAs: 003AA1.02 RO-3.6 SRO-3.4 00 1A2. 11 RO-4.4 SRO-4.7 001A4.06 RO-2.9 SRO-3.2 GENERAL TOOLS AND EQUIPMENT:
Provide/Acciuire:
- 2. AOP-19.0 main body will be acquired from Simulator Critical ELEMENT justification:
STEP Evaluation
- 1. CRITICAL for completion of the assigned task
- Without proper alignment of the disconnect switches, either rod misalignment would be made worse, or the task could not be completed as directed.
- 2. Not critical since there is no action required (condition checked is as found)
- 3. Not critical since the initial conditions state that this is NOT required.
- 4. CRITICAL to accomplish the assigned TASKs objective
- This is the original objective (task) directed. IF this task is not completed within the 30 mm window, then the task could not be completed.
- 5. Not critical because the RX trip is identified as CRITICAL in element 8; Procedure selection is not important and a RX trip may be conducted from memory since the reactor is outside of design limits.
- 6. Not critical since there is NO action required.
- 7. Not critical since no action should be taken, and the only movable D bank rod has dropped.
- 8. CRITICAL for the operation within design limits.
9-12 Not critical since all actions will occur normally following the manual initiation of RX trip no operator action is required.
COMMENTS:
- 1. Task is intended to terminate when the RX is tripped; this provides a natural stopping point since a procedure transition would then be required. Completion of F-U immediate operator actions would be a secondary natural stopping point.
- 2. An automatic Rx trip set point would NOT be exceeded but a Manual RX trip is required. The Automatic RX trip is, however, disabled for this JPM to ensure the Manual RX trip remains critical in JJ possible cases.
- 3. EEP-0 lOAs added following prep week only for natural termination point.
FNP HLT-34 JPM SIMULATOR JPM A. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM THE CORRECTIVE ACTIONS REQUIRED FOR RECOVERY OF A MISALIGNED ROD. The conditions under which this task is to be performed are:
- a. The plant was in MODE 1, ramping down from 100% when the ramp was stopped at 72%
power due to a Control Rod misalignment.
- b. DRPI indication for rod F6 indicates 204 steps.
- c. DRPI indication for all other Bank D rods indicates 186 steps.
- d. The cause of the misalignment was a blown fuse and it has been replaced.
- e. AOP-19.0, Malfunction of Rod Control System, is in progress.
- f. Maintenance personnel are not required to be notified prior to rod motion.
- g. You have been directed to complete ATTACHMENT 2 of AOP-19.0 beginning with step 3 while complying with the following realignment plan:
- 1. Restoration of Rod Alignment to be conducted between 70% and 80%.
- 2. The rate of control rod movement during recovery shall be conducted at 3 step increments, to achieve alignment within TS limits within the next 30 minutes.
- 3. Movement of other control rods to support recovery is NOT permitted.
07j13/10 8:07:08 -
FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 27.0 ATTACHMENT 2 MISALIGNED ROD RECOVERY or MAINTENANCE TESTING For rods out of alignment by 12 steps or more, the recovery times of Attachment 4 shall apply.
- This attachment may be performed as many times as required for multiple misaligned rods, or as required by a maintenance testing plan.
Notify appropriate Plant Management and Engineering Support personnel prior to implementing any realignment plan.
g Any realignment plan should consider the following:
Determination of how long the rod has been misaligned._30 mrnutes Power level at which recovery will be performed. 70% to 80% RTP Rate of control rod movement during recovery. 3 step increments to be reahgned within 30 minutes Movement of other control rods to support recovery NOT Dermitted Record misaligned bank step counter indications in reactor operators log.
3 Align lift coil disconnect switches. (BOP) 3.1 For rod re-alignment, align switches to DISCONNECT position for all non-affected rods in the affected bank.
OR 1\J /i4i For maintenance testing align disconnect switches as required by the test plan.
Affected bank 1] Affected rods Special considerations:
4 Verify the ROD CONTROL BANK SELECTOR SWITCH is selected to the affected bank.
5 IF required notify maintenance personnel when rod movement will begin.
PaeQ)f 3
07/13/10 8:07:08 - -
FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 27.0 ATTACHMENT 2 MISALIGNED ROD RECOVERY or MAINTENANCE TESTING NOTE:
- Performing step 6 will cause the ROD CONT SYS URGENT FAILURE annunciator FF1 to actuate. This will lock out the non-affected group step counter.
- Performance of steps 6, 7 AND 8 should be a coordinated action.
6 Rod alignment 6.1 For rod re-alignment, adjust misaligned rod to agree with associated group DRPI indication at a rate determined in step 1.1.
/6 For maintenance testing align rods as specified by test plan Affected bank J Affected rods I Number of steps to move rod(s)___________
[1], Direction of rod motion W Special considerations:
7 Adjust turbine load to maintain RCS TAVG within 2°F of TREF.
8 [CAl WHEN the appropriate condition is met, THEN stop rod motion.
[] For rod realignment, When rod DRPI indicates that the affected rod is at the same position as non affected rods, OR When maintenance testing is complete.
9 Place all lift coil disconnect switches to CONNECTED. (BOP) 10 Reset rod control urgent failure alarm.
10.1 Depress ROD CONTROL URGENT FAILURE ALARM RESET pushbutton.
10.2 Verify ROD CONT SYS URGENT FAILURE annunciator FF1 NOT LIT. -
Page 2 of 3
07/13/10 8:07:08 -
FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 27.0 ATTACHMENT 2 MISALIGNED ROD RECOVERY or MAINTENANCE TESTING 11 Adjust affected bank group step counters.
11.1 Depress the recessed pushbutton switches on each step counter located to the right of the digital display.
[] The top switch raises the position value.
[] The middle switch lowers the position value.
{] The bottom switch resets the position value to zero.
11.2 Restore affect bank counter to position recorded in step 2.
12 IE misaligned rod is in a control bank, THEN adjust pulse to analog converter. (121 ft, CRDM SWGR room) 12.1 Unlock and open the rear of the DC HOLD cabinet.(CRDM Cab key) 12.2 Place the DISPLAY switch to affected bank.
12.3 Place the AUTOMATIC/MANUAL switch to MANUAL and hold in position.
12.4 Repeatedly depress the UP or DOWN pushbutton to adjust digital display to position recorded in reactor operators log.
12.5 Release the AUTOMATIC/MANUAL switch.
12.6 Place the DISPLAY switch to OFF.
13 Place ROD CONTROL BANK SELECTOR SWITCH to MANUAL.
14 Adjust RCS TAVG within 1°F of TREF.
15 Notify control room that ATTACHMENT 2, MISALIGNED ROD RECOVERY or 16 Return to procedure step in affect.
-END Page 3 of 3
- FNPHLT-34JPM Page1of1 SIMULATOR JPM B.
MODIFIED CRO-343C TITLE: Establish Letdown As Required Following a Spurious Letdown Isolation Signal and Stabilize Pressurizer Level EVALUATION LOCATION: 1 SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-219 IJ ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Establish excess letdown at the maximum allowed rate and stabilize PZR level using AOP-16.0.
Examinee:
Overall JPM Performance: Satisfactory tJ Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Howard Fitzwater I Date: 4/25/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP RLT34 SIMULATOR JPM B. Page 2 of 11 (Guide pages = 10)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into 10-219 for JPM B Put OPS group on MOB CRT Acknowledge computer alarms Run / Freeze Simulator Acknowledge annunciators Turn Horns ON Provide AOP-16.0, v17.0, with Steps 9.8 marked as in complete.
Ensure SOP 2.7 and ARP 1.4 (panel D) clean/replaced Setup IC_219*
RST IC-73
- Secure Letdown using MOB placard. LEAVE HV-8152 OPEN.
Place PK-145 in manual at 50%
demand.
Fill PZR to 53%
Increase seal injection flow to 8.5 gpm per pump (avoids nuisance alarm during task)
Insert PK145 output failure stuck at 5 amps.
CNH/PK145-B Demand Failure! 5 SN? 219
CONDITIONS When I tell you to begin, you are to ESTABLISH LETDOWN AS REQUIRED FOLLOWING A SPURIOUS LETDOWN ISOLATION SIGNAL AND STABILIZE PRESSURIZER LEVEL. The conditions under which this task is to be performed are:
- a. The Plant has experienced a Penetration Room High Pressure signal which isolated letdown.
- c. The malfunction has been corrected.
- d. HV-8175A & HV-8175B have been opened by the Radside System Operator.
- e. All required steps up to step 9.8 have been completed by another operator.
- f. You have been directed to establish letdown and stabilize pressurizer level using AOP-16.0, beginning at step 9.9.
INITIATING CUE, You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
(AOP-16.0 step 9.9) S/U
- a. LCV459 a. LCV459
- b. LCV46O b. LCV46O (AOP-16.0 step 9.10) S/U
- 2. Initiate minimum charging flow: Establishes Charging flowpath
- a. Verify CHG FLOW FK 122 in MAN - and minimum of 18 gpm.
- b. Establish minimum charging flow based on a. Checks FK- 122 in Manual orifices to be placed on service: b. OPENS FK-122 to establish
- i. 1ORIFICE-l8gpm a MINIMUM of 18 gpm on OR FI-122 ii. 2 ORIFICES 40 gpm
FNP HLT-34 SIMULATOR JPM B. Page 4 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCI NOTE:
- FI-150, Letdown Flow, would normally be expected to rise after a short time delay after completion of element 3. The indications driving the re-isolation of letdown may be delayed momentarily while the piping refills/pressurizes.
. A failure is inserted on PK-145 which prevents it from responding to the demand from PK 145 controller.
- Completing Element 3 will initiate DE3 & DE4 alarm.
NOTE:
- Listed below is the most likely procedural flowpath, but there are a variety of procedural flowpaths available to the candidate, such as:
- Implement AP-6, and isolate letdown and proceed to element 10 via step 9.11 RNO.
- Implement ARP- 1.4, DE3 or DE4 to isolate letdown.
- RE-enter AOP-16 step 1 and Re-perform AOP-16 step 7 and 8.
- Implement SOP-2.1 at step 9.15 of AOP-16 to isolate letdown.
(AOP-16.0 step 9.11) S / U
- 3. Establish approximately 60 gpm letdown flow by OPENS either HV8 149B OR OPENING: HV8149C.
OBSERVES the red light LIT a.HV8149B (IMPLEMENT ARP) IF the ARP OR is responded GO TO ELEMENT 4
- b. HV8149C 1O action: (IMPLEMENT RNO) IF determined that letdown flow IF no letdown flow can be established, THEN can NOT be established. GO proceed to [AOP-161 step 10. TO ELEMENT 9 (Remain in AOP-16 step 9) IF the failure is NOT recognized GO TO Element 5
FNP HLT34 SIMULATOR JPM B. Page 5 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ARP- 1.4, v5 1.0 location DE3 or DE4 response -NEXT PAGE)
- 4. ACTIONS will depend on WHICH ARP is implemented SEE BELOW: REGARDLESS of which ARP is used the following verifiable DE3 actions: action should take place
- 1) Monitor the LTDN ORIF ISO REL line to Checks indications, may attempt PRT Temperature (TI- 141) and LTDN HX to adjust PK-145 manually.
Outlet Press (P1- 145).
- 2) IF temperature continues to rise rapidly CLOSE HV8149B OR S/U indicating a lifted relief valve, THEN close HV8149C (whichever was LTDN ORIF ISO 45(60) GPM previously opened).
Q1E21HV8149A, B AND C. OBSERVES the green light LIT
- 3) If the high temperature is due to LP LTDN press PK-145 malfunctions, THEN place N/A valve controller in manual and adjust as required.
- 4) IF a ramp is in progress, THEN place turbine N/A load on HOLD.
- 5) Go to FNP-1-AOP-16.0, CVCS RETURN TO A OP-i 6 MALFUNCTION to address the loss of letdown flow. IF STEP 9.11 (RNO)or STEP lOGO TO ELEMENT 9 DE4 actions
- 1) Monitor LTDN HX Outlet Flow (Fl-iSO) and IF STEP 9.12 GO TO ELEMENTS LTDN HX Outlet Press (P1-145).
- 2) Ensure proper orifice isolation valve selection IF STEP 1 GO TO ELEMENT 11
- 3) IF the high pressure is due to LP LTDN PRESS PK-145 malfunction, THEN place valve controller in manual and attempt to reduce the pressure.
- 4) IF pressure can NOT be controlled manually with LP LTDN PK-145, THEN close LTDN ORIF ISO 45(60) GPM Q1E21HV8149A, B, and C.
- 5) If the high temperature is due to LP LTDN press PK- 145 malfunctions, THEN place valve controller in manual and adjust as required.
- 6) IF a ramp is in progress, THEN place turbine load on HOLD.
- 7) Go to FNP-l-AOP-16.O, CVCS MALFUNCTION to address the loss of letdown flow.
FNP HLT-34 SIMULATOR JPM B Page 6 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
NOTE: - IF AOP-16 step 19.11 is implemented WITHOUT Closing HV-8149A, B,C an RCS leak will exist and remain until NORMAL letdown in isolated. This procedural flowpath will rely on the SOP to Close HV-8149A,B,C which is a CRITICAL task.
- Element 5 may be entered with or without first isolating letdown. But the candidate must isolate NORMAL letdown to satisfy the critical task.
(AOP-16.0 step 9.12)
- 5. [CA] j all backup heaters energized due to Checks HA2 LIT and PRZR S/U pressurizer level deviation. THEN verify two sets level > 5% program and places of backup heaters in ON prior to level deviation two PZR backup heaters in the clearing. ON position prior to falling below 57%.
ACTION is conditional and may not be completed.
(AOP-16.0 step 9.13)
- 6. Adjust LP LTDN PRESS PK 145 to maintain Attempts to lower pressure by S / U desired letdown pressure BETWEEN 260-450 pushing the LOWER (OPEN)
PSIG. pushbutton on PK-145.
RNO action:
If necessary, THEN adjust LP LTDN PRESS PK P1-145 will be > 450 PSIG and 145 in MANUAL to stabilize Letdown Pressure at cycling on the Letdown Relief.
desired value.
(AOP-16.0 step 9.14)
- 7. Control LTDN HX OUTLET TEMP TK-144 to Identifies this action is NA due S / U maintain Letdown temp 90-115°F to failure of PK-145.
(AOP-16.0 step 9.15)
- 8. REFER to SOP-2.1 for further guidance on TDENTIFIES PK-145 is failed S / U LETDOWN System control. and this action is not appropriate. And goes to step 10 (GO TO element 9)
OR Goes to SOP-2. 1 and verifies Normal letdown isolated and directs SOP-2.7 (GO TO Element 14)
FNP HLT-34 SIMULATOR JPM . Page 7 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE (AOP-16.0 step 10)
- 9. Determine status of letdown flow PROCEEDS TO step 10 RNO S/U
- Normal Letdown established actions.
- Excess letdown flow (AOP-16.0 step 10.1 RNO)
- 10. Perform the following: PROCEEDS TO FNP-1-SOP-- S/U
- Continue monitoring levels: 2.7, CVCS Excess Letdown
- Pressurizer level OR GO TO ELEMENT 14
- VCT level IF REQUIRED BOOTH Cue:
- IF desired, THEN establish excess letdown SS directs placing Excess letdown using FNP-1--SOP-2.7. in service (AOP-16.0 steps 1 through 6 check status of Charging and are not listed here... the following steps address the Letdown malfunction)
(AOP-16.0 step 7 RNO) Identifies increasing temperature
(AOP-l6.0, step 7 RNO actions)
- 12. IF leakage to the PRT is excessive, Verify LTDN CLOSE HV8149B OR S/U ORIF ISO valves CLOSED HV8149C (whichever was previously opened).
7.1 Check PRT parameters STABLE
- OBSERVES the green light LIT
[j PRT PRESS P1472
[j PRT LVL LI-470
[]PRT TEMP TI-471 7.2 IF leakage to the PRT is excessive, THEN perform the following:
7.2.1 Verify LTDN ORIF ISO valves CLOSED-
[j Q2E21HV8149A
[]Q2E21HV8149B
{] Q2E21HV8149C
FNP HLT-34 SIMULATOR JPM B. Page 8 of 1 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(AOP-16 step 8 through 8.4)
- 13. IF desired due to plant conditions, THEN place Determines that Excess S / U excess letdown in service using FNP-1-SOP-2.7, letdown is required proceeds to CHECMIAL AND VOLUME CONTROL SOP-2.7 to place excess letdown SYSTEM EXCESS LETDOWN in service.
IF REQUIRED BOOTH Cue:
SS directs placing Excess letdown in service (SOP-2.7 step 4.1.1)
- 14. Verify the RCDT system in operation and on Directs RADSIDE SO to align S / U recirc per FNP-1-SOP-50.O, Liquid Waste RCDT per SOP-50.
Processing System Step 4.1.1.
(TIME COMPRESSION- may be necessary if candidate does not proceed until the following report is made)
BOOTH CUE: Radside SO Reports that the RCDT system is in operation and on recirc per SOP-50.0 step 4.1.1 (SOP-2.7 step 4.1 .2)
- 15. Notify the Radside System Operator to expect an Informs Radside SO that filling S / U increase in RCDT level prior to placing excess RCDT.
letdown on service.
BOOTH CUE: Radside SO acknowledges (SOP-2.7 step 4.1.3)
- 16. Verify HV3095 CCW TO EXC LTDN/RCDT Verifies HV3095 is open S / U HXS, Open. OBSERVES the red light LIT (SOP-2.7 step 4.1.4)
- 17. Verify CCW FROM EXC LTDN / RCDT HXS Verifies HV3443 is open S / U HV3443, Open OBSERVES the red light LIT (SOP-2.7 step 4.1.5)
- 18. Verify CCW FROM EXC LTDN / RCDT HXS Verifies HV3067 is open S / U HV3067, Open OBSERVES the red light LIT
FNP HLT34 SIMULATOR JRM B. Page 9 of ii (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(SOP-2.7 step 4.1.6)
(SOP-2.7 step 4.1.7)
- 20. Open HV8153, EXC LTDN ISO. OPEN HCV8 153 S / U OBSERVES the red light LIT (SOP-2.7 step 4.1.8)
- 21. Open HV8154, EXC LTDN ISO. OPEN HV8154 S / U OBSERVES the red light LIT (SOP-2.7 step 4.1.9)
- 22. Place HV8 143, EXC LTDN DIVERT VLV, Places HV8 143 in the RCDT S / U control switch in the RCDT position. position.
(SOP-2.7 step 4.1.10)
- 23. Slowly throttle open HCV137, EXC LTDN HX Throttles open HCV137 to S I U DISCH, to establish excess letdown flow not to establish excess letdown flow exceed 165° F excess letdown heat exchanger and not exceed 165°F.
outlet temperature.
STOP TIME Terminate when excess letdown flow is established and the operator has control of the trend.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP HLT-34 SIMULATOR JPM B. Page 10 of 11 (Guide pages = 10)
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-AOP-16.O, V 17.0 FNP-1-ARP-1.4, V51.0 FNP-1-SOP- 2.7, V 10.0
- 2. KJAs: 004A2.07 RO-3.4 SRO-3.7 004A4.05 RO-3.6 SRO-3.1 GENERAL TOOLS AND EOUIPMENT:
FNP-1-AOP-16.0, V 17.0 marked complete through but not including step 9.9.
Critical ELEMENT justification:
STEP Evaluation
- 1. CRITICAL to accomplish the assigned TASKs objective
- This is the original objective (task) directed. IF not performed, the original task could not be achieved and the decision to implement the alternative path would not be made for a legitimate reason.
- 2. Not critical since this course of action will not be successful, the establishment of normal charging has no critical impact on this task.
- 3. CRITICAL to accomplish the assigned TASKs objective
- This is the original objective (task) directed. IF not performed, the original task could not be achieved.
- 4. or CRITICAL since isolation of letdown is required to terminate an RCS leak.
12
- 5. - Not critical since this action is optional and has no impact on task..
11 13 Not critical, a decision is not critical, and the actions will be evaluated with other critical elements.
14 Not critical failure to complete this action will not prevent successful completion of establishing excess letdown, although there would be some long term equipment consequences.
15 Not critical this is a notification step that has no impact on successful completion.
16 Not critical since this valve is normally open on the MCB.
17 Not critical since this valve is normally open on the MCB.
18 Not critical since this valve is normally open on the MCB.
19 Not critical since this component is already properly aligned, failure to complete this step will have no impact on successful completion of the task.
20 CRITICAL since the task objective of controlling PZR level cannot be achieved without opening this valve.
21 CRITICAL since the task objective of controlling PZR level cannot be achieved without opening this valve.
22 Not critical since objective of controlling PZR level CAN be achieved without repositioning this valve.
23 CRITICAL since the task objective of controlling PZR level cannot be achieved without opening this valve. It is also critical to NOT exceed 165°F on excess letdown heat exchanger.
COMMENTS:
If PZR level is permitted to rise to 92%, an Automatic RX trip will be initiated.
If PZR level is permitted to rise > 63.5%, LCO 3.4.9 is not met.
FNP HLT-34 JPM SIMULATOR JPM s. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to ESTABLISH LETDOWN AS REQUIRED FOLLOWING A SPURIOUS LETDOWN ISOLATION SIGNAL AND STABILIZE PRESSURIZER LEVEL. The conditions under which this task is to be performed are:
- a. The Plant has experienced a Penetration Room High Pressure signal which isolated letdown.
- c. The malfunction has been corrected.
- d. HV-8175A & HV-8175B have been opened by the Radside System Operator.
- e. All required steps up to step 9.8 have been completed by another operator.
- f. You have been directed to establish letdown and stabilize pressurizer level using AOP-16.O, beginning at step 9.9.
12/01/10 14:11:55 FNP-lARPd.4 LOCATION DE3 SETPO1NT: 165 +/- 2°F E3 I LTDN ORIF ISO VLV REL ORIGiN: Temperature Bistable TB-141 from Temperature LINE TEMP Element (N1E21TE141-N) HI PROBABLE CAUSE
- 1. LTDN ORIF OUTLET REL VLV, Qi E2 1 V255, leaking or lifted.
- 2. LP LTDN PRESS PK-145 malfunction.
AUTOMATIC ACTION NONE OPERATOR ACTION Ii CAUTION: If actual VCT level is low, refer to annunciator DF3. (SOER 97-1) iJ
- 1. Monitor the LTDN ORIF ISO REL line to PRT Temperature (TI-141) and LTDN HX Outlet Press (P1- 145).
- 2. IF temperature continues to rise rapidly indicating a lifted relief valve, THEN close LTDN ORIF ISO 45 (60) GPM Q1E2IHV8149A, B AND C.
- 3. If the high temperature is due to LP LTDN press PK-145 malfunctions, THEN place valve controller in manual and adjust as required.
NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured.
- 4. IF a ramp is in progress, THEN place turbine load on HOLD.
- 5. Go to FNP-l-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.
References:
A-177100, Sh. 203; D-175039, Sh. 1; U-176024; PLS Document Page 1 of 1 Version 51.0
12101/10 14:11:55 FNP-l-ARP-l.4 LOCATION DE4 SETPOINT: 462 PSIG E4 I LTDN HX OUTLET ORIGIN: Pressure Bistable PB-145 from PRESS Pressure Transmitter (Q1E21PT145) HI PROBABLE CAUSE I. LP LTDN PRESS PK-145 malflmction.
- 2. All three Letdown Orifice Isolation Valves open.
AUTOMATIC ACTION NONE OPERATOR ACTION jI CAUTION: If actual VCT level is low, refer to annunciator DF3. (SOER 97-1) i
- 2. Ensure proper orifice isolation valve selection.
- 3. IF the high pressure is due to LP LTDN PRESS PK-145 malfunction, THEN place valve controller in manual and attempt to reduce the pressure.
- 4. IF pressure can NOT be controlled manually with LP LTDN PK-145, THEN close LTDN ORIF ISO 45 (60) GPM Q1E21HV8149A, B, and C.
NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured.
- 5. IF a ramp is in progress, THEN place turbine load on HOLD.
- 6. Go to FNP-l-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.
References:
A-177100, Sh. 204; D-175039, Sh. l&2; U-176018; PLS Document Page 1 of 1 Version 51.0
FrIey NUclér piant Procedure Number Ver UNIT i FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21:24 Letdown 1 of 7 S
A F
E T
Y Chemical and Volume Control System Excess Letdown R
E L
A T
E D
PROCEDURE USAGE REQUIREMENTS SECTIONS Procedure must be open and readily available at the Continuous Use: work location. Follow procedure step by step unless ALL otherwise directed by the procedure.
Procedure or applicable section(s) available at the Reference Use: work location for ready reference by person performing_steps.
Information Use: Available on site for reference as needed.
Approved By: Wade Warren (for) Date Approved: February 25, 2010 Operations Manager
UNIT I Farley Nuclear PIt A Procedure Number Ver FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21:24 Letdown 2 of 7 Procedure Version Description Version Number Version Description 10.0 Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions
Farley Nucleat piant Procedure Number Ver UNIT I FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21 :24 Letdown 3 of 7 Table of Contents Page 1.0 Purpose 4 2.0 Initial Conditions 4 3.0 Precautions and Limitations 4 4.0 Instructions 6 4.1 Placing Excess Letdown In Service 6 4.2 Removing Excess Letdown From Service 7 5.0 References 7
UNIT I Farley Nuclear Plant A P-rooeclure Number Ver FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21:24 Letdown of 7 10 Purpose This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for operation of excess letdown.
2.0 Initial Conditions 2.1 CVCS is aligned for normal operation per FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup and Operation.
2.2 The component cooling water system is supplying cooling water to the excess letdown heat exchanger per FNP-1-SOP-23.0, Component Cooling Water System.
2.3 The component cooling water system is supplying cooling water to the seal water heat exchanger per FNP-1-SOP-23.0, Component Cooling Water System, if excess letdown is to be lined up to the VCT.
2.4 The waste processing system is capable of receiving the excess letdown flow per FNP-1-SOP-50.0, Liquid Waste Processing System, if excess letdown is to be lined up to the RCDT.
3.0 Precautions and Limitations 3.1 Do not exceed 165°F excess letdown heat exchanger outlet temperature.
3.2 Aligning the excess letdown system to the VCT will raise the backpressure on the RCP seals, thus reducing RCP seal leakoff flow rates. While in this alignment, it must be verified that each reactor coolant pump No. I seal leakoff flow rate is maintained at I to 3 gpm.
3.3 Pressurizer and VCT levels should be monitored more frequently when excess letdown is in operation.
3.4 If plant operation is to continue for an extended period of time with excess letdown in service and normal letdown isolated, RCS oxygen and hydrogen concentrations should be monitored more frequently. SEAL WATER RETURN TO THE VCT ISOLATION 1-CVC-V-8482 (Q1E21V196) is to remain locked closed in modes 1-4.
3.5 Operating the plant with normal letdown isolated for extended periods can have a significant effect on RCS activity and chemistry control since RCP seal return flow/excess letdown flow cannot be lined up through the CVCS demineralizers. Also, the ability to borate or dilute the RCS is significantly affected due to the reduced charging flow rate.
UNIT I Farley Nuclear Plant A Procedure Number Wi FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21:24 Letdown 5 of 7 3.6 When placing excess letdown on service, always align to the RCDT first in order to flush the existing line volume. This will equalize the boron concentration with the existing RCS concentration, and clear the line of any trapped gases that may have accumulated.
3.7 Monitor RCDT pressure while excess letdown is aligned, and if necessary control pressure in accordance with FNP-1-SOP-50.0, Liquid Waste Processing System.
Relief valves setting for RCDT is set at 25 psig.
3.8 Placing Excess Letdown in service will cause calculated reactor thermal power to read lower than actual power due to the IPC computing no heat loss due to letdown while there is actual heat loss due to Excess Letdown.
UNIT I Farley Nuclear Plant A Procedure Number Ver FNP-1-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21 :24 Letdown 6 of 7 4.0 Instructions CAUTION Do not exceed 165° F excess letdown heat exchanger outlet temperature.
NOTES The volume of the reactor coolant drain tank is approximately 350 gallons.
Excess letdown flow will be limited to approximately 10-15 gpm.
4.1 Placing Excess Letdown In Service 4.1.1 Verify the RCDT system in operation and on recirc per FNP-1-SOP-50.0, Liquid Waste Processing System Step 4.1.1. LI 4.1.2 Notify the radside system operator to expect an increase in RCDT level prior to placing excess letdown on service. LI 4.1.3 Verify Q1P17HV3095, CCW TO EXC LTDN/RCDT HXS, OPEN. El 4.1.4 Verify Q1P17HV3443, CCW FROM EXC LTDN/RCDT HXS, OPEN. LI 4.1.5 Verify Q1P17HV3067, CCW FROM EXC LTDN/RCDT HXS, OPEN. LI 4.1.6 Verify Q1E21HCV137, EXC LTDN HX DISCH, CLOSED. LI 4.1.7 Open Q1E21HV8153, EXC LTDN ISO. LI 4.1.8 Open Q1E21HV8154, EXC LTDN ISO. LI 4.1.9 Place Q1E21HV8143, EXC LTDN DIVERT VLV, control switch in the RCDT position. LI 4.1.10 Slowly throttle open Q1E2IHCV137, EXC LTDN HX DISCH, to establish excess letdown flow not to exceed 165° F excess letdown heat exchanger outlet temperature. LI
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1.-SOP-2.7 10.0 10/8/2010 Chemical and Volume Control System Excess Page Number 10:21 :24 Letdown of 7 CAUTIONS A small portion of excess letdown piping can not be flushed to the RCDT (calculated to be approximately one gallon) and there are uncertainties associated with achieving a complete flush. Therefore, the reactivity affects associated with directing excess letdown to the VCT/Charging pump suction must be considered and contingencies established for mitigating the consequences.
Industry CE suggests alignment of normally off service systems to the charging pump suction may result in accumulation of gasses.
4.1.11 H desired to align excess letdown flow to the VCT/Charging pump suction, THEN perform the following:
4.1.11.1 Maintain flow to the RCDT for a sufficient time period to flush at least 300 gallons to the RCDT. LI 4.1.11.2 Throttle closed Q1E2IHCV137, EXC LTDN HX DISCH.
4.1.11.3 Place Q1E21HV8143, EXC LTDN DIVERT VLV, control switch in the VCT position. LI 4.1.11.4 Slowly throttle open Q1E21HCV137, EXC LTDN HX DISCH, to establish excess letdown flow not to exceed 165° F excess letdown heat exchanger outlet temperature.
4.1.11.5 Initiate action to ensure the idle charging pump suction lines are vented in accordance with FNP-1-SOP-2.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.2 Removing Excess Letdown From Service 4.2.1 Close QIE2IHCVI37, EXC LTDN HX DISCH. El 4.2.2 Place QI E21 HV8143, EXC LTDN DIVERT VLV, in the VCT position.
4.2.3 Close Q1E21HV8153, EXC LTDN ISO. El 4.2.4 Close Q1E21HV8154, EXC LTDN ISO. LI 5.0 References 5.1 Drawings P&lD - 175039 (Sh. I and 2) Chemical and Volume Control System.
5.2 FSAR Section 9.3.4.
5.3 FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup and Operation 5.4 FNP-1-SOP-23.0, Component Cooling Water System 5.5 FNP-1-SOP-50.0, Liquid Waste Processing System
4/27/2011 15:59 FNP-1-AOP-16.0 11-04-2010 Revision 17 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-16 .0 CVCS MALFUNCTION S
A F
PROCEDURE USAGE REQUIREMENTS-per FNP-O-AP-6 SECTIONS E T
Continuous Use ALL Y Reference Use R E
Inforniation Use L A
T E
0 Approved David L Reed (for)
Operations Manager Date Issued: 11/04/10
4/27/2011 15:59 - - - -
FNP-1-A0P16.O CVCS MALFUNCTION Revision 17 Table of Contents Procedure Contains Number of Pages Body 23 Attachment 1 1 Page 1 of 1
4/27/201115:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 A. Purpose This procedure provides actions for response to malfunctions of the Charging and Letdown portions of the Chemical Volume and Control System. If Letdown is manually secured or isolates due to system parameters the normal system operating procedure may be used for restoration.
B. Symptoms or Entry Conditions 1 Procedure is entered when a loss or malfunction of normal Letdown or Charging sysems is experienced. This may be indicated by the following:
1.1 Pressurizer level deviation due to the loss or malfunction of normal Letdown or Charging sysems.
1.2 One or more of the following annunciators in alarm:
[1 DEl RECEN HX LTDN FLOW DISCH TEMP HI
[] DE3 LTDN ORIF ISO VLV REL LINE TEMP HI annunciator in alarm (FNP-l--ARP-l .4)
[1 DE4 LTDN HX OUTLET PRESS HI annunciator in alarm. (FNP-1-ARP-l.4)
[1 DF3 VCT LVL HI-LO
[1 EA2 CHG HDR FLOW HI-LO(FNP-l-ARP-l.5)
[1 EB1 CHG PUMP OVERLOAD TRIP
[1 11A2 PRZR LVL DEV HI B/U HRS ON annunciator in alarm.
(FNP-1-ARP-l .8)
[1 HB1 PRZR LVL HI (FNP-l-ARP-l.8)
[] HB2 PRZR LVL DEV LO 1.3 Operating team observes a loss or malfunction of the normal Letdown or Charging systems.
C. Automatic Actions 1 Letdown isolation valves Q1E21V367(LCV46O)and Q1E21V368(LCV459) isolate when pressurizer level decreases to 15%.
2 Letdown orifice isolation valves close when either LT459 or LT460 sense pressurizer level of 15%.
3 LTDN LINE PENE RN ISO valves Q1E21V565A(11V8175A)and Q1E21V565B(RV8175B)isolate on hi energy line break sensor actuation.
4 T Signal - closes LTDN LINE CTMT ISO 01E2111V8152 and all Orifice Isolation valves.
5 If the operating charging pump trips on an overload condition, the associated swing or dedicated pump in the same train will automatically start.
Page 1 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- If all seal cooling is lost, it can be necessary to trip the RCP(s) within two minutes, depending on seal leakoff flow, to ensure that the RCP(s) stop rotating prior to actuation of the shutdown seal.
- Excess letdown may be placed on service anytime it is desired during the performance of this procedure in accordance with FNP-1-SOP-2.7, CHEMICAL AND VOLUME CONTROL SYSTEM EXCESS LETDOWN.
- Placing Excess Letdown in service will cause indicated reactor thermal power to read higher than actual power due to the IPC computing no heat loss due to letdown while there is actual heat loss due to Excess Letdown.
Verify ORG flow adequate to 1 Isolate Normal Letdown as cool letdown follows:
CHG FLOW 1.1 Verify closed all LTDN ORIF
[1 FI-l22A ISOs:
LTDN HX OUTLET FLOW El Q1E21HV8149A
[1 FI-150 El Q1E21HV8149B El 01E21HV8149C REGEN HX OUTLET TEMP El TI-l40 2 Stop any load change in progress NOTE: IF VCT level indication is lost due to a low level, OR IF it is suspected that the lower level tap has been uncovered, THEN the VCT level transmitters will need to be vented for reliable level indication. (2006203596}
3 Monitor VCT level to ensure proper level is maintained Page 2 of 23
4/27/2011 15:59 FNP-1-AOP-l6.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Oscillating flow indications and/or ammeter indications could be indicative of air or gas intrusion into the charging pump suction.
IE such indications are present, THEN consideration should be given to securing both letdown and any running charging pump AND ensuring the charging pump suction piping is adequately vented per FNP-1-SOP-2.1 prior to return to service. (Ref. SOER 97-1, CL 2008-01) 4 [CA] Observe CHG HDR PRESS and 4 IF VCT level reduces to 5%,
MOTOR AMPS to ensure proper THEN perform the following:
charging pump operation. (SOER 97-1) 4.1 Open RWST TO CEG PUMP valves
[1 P1-121 [1 Q1E21LCV115B
[1 AMMETER FOR RUNNING CHC PUMP [1 Q1E21LCV115D 4.2 Close VCT OUTLET ISO valves
[1 Q1E21LCV115C
[] Q1E21LCV115E 5 Check charging pump - RUNNING. 5 Start an available charging pump as follows:
- On service train charging pump running 5.1 Check VCT level and pressure adequate.
OR 5.2 Verify charging suction
- Off service train charging flowpath aligned:
pump running
[1 Q1E21LCV115C - OPEN
[1 Q1E21LCV115E - OPEN OR
- RWST TO CHG PUMP valves
[] Q1E21LCV115B - OPEN
[] Q1E21LCV115D - OPEN 5.3 Check auxiliary oil pump running for charging pump to be started as indicated by white light illuminated on MCB.
Step 5 continued on next page.
Page 3 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained 5.4 Check open miniflow isolation for charging pump to be started:
- 1A CHC PUMP MINIFLOW ISO, Q1E21MOV81O9A
- lB CHG PUMP MINIFLOW ISO, Q1E21MOV81O9B
5.6 Verify the following are closed:
[1 CRC FLOW FK 122
[1 SEAL WTR INJECTION HIK 186 5.7 Verify a CCW pump is running in same train aligned to supply charging pump to be started.
5.8 Start selected charging pump.
5.9 Observe CHG HDR PRESS indicator P1 121 and motor ammeter to check proper pump operation.
5.10 WHEN charging pump comes up to speed, THEN check auxiliary oil pump stops as indicated by white light Q[ being illuminated on MCB.
5.11 Adjust SEAL WTR INJECTION HIK 186 to maintain 6-13 gpm seal injection flow to each RCP.
5.12 IF all seal cooling lost to any RCP, THEN go to FNP-1-AOP-4.l, ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE.
Page 4 of 23
4/27/2011 15:59 -
FNP1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I 1 I 6 Check Charging flow FK-122 6 JE required, controlling in AUTO with flow THEN take manual control of indicated charging flow:
6.1 Place FK-122 in manual and adjust as required to maintain pressurizer level at program level.
6.2 Adjust SEAL WTR INJECTION HIK-186 as required to maintain RCP seal injection flow 6-13 gpm.
6.3 JE manual control of charging not accomplished, THEN refer to ATTACHMENT 1, MANUAL CONTROL OF CHARGING FLOW.
7 Check the following 7 Perform the following:
annunciator - CLEAR 7.1 Check PRT parameters - STABLE
[1 DE3 LTDN ORIF ISO VLV REL LINE TEMP HI [1 PRT PRESS P1 472
[1 PRT LVL LI-47O
[1 PRT TEMP TI-471 7.2 IF leakage to the PRT is excessive, THEN perform the following:
7.2.1 Verify LTDN ORIF ISO valves
- CLOSED
[1 Q2E21HV8149A
[] Q2E21HV8149B
[] Q2E21HV8149C 7.2.2 IF BTRS is in operation, THEN remove BTRS from service using FNP-1-SOP-3.O, BORON THERMAL REGENERATION SYSTEM.
Page 5 of 23
4/27/2011 15:59 FNP-l-AOP-l6.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I
8 Determine Status of Normal Letdown:
8.1 Check normal CVCS letdown - 8.1 IF normal CVCS letdown is on AFFECTED BY MALFUNCTION service, THEN proceed to Step 18.
- LTDN HX OUTLET FLOW. FI-150
- NO FLOW INDICATED 8.2 Minimize RCS makeup:
8.2.1 Manually close charging flow control:
CRC FLOW El FK-l22 8.2.2 Minimize seal injection between 6-13 gpm 8.2.3 Direct Chemistry to shutdown the zinc addtion system (ZAS) 8.3 Dispatch personnel to investigate cause of the Letdown malfunction 8.4 IF desired due to plant conditions, THEN place excess letdown in service using FNP-l-SOP-2.7, CHECMIAL AND VOLUME CONTROL SYSTEM EXCESS LETDOWN.
Page 6 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I CAUTION: To prevent heat exchanger damage, do not attempt restoration of letdown unless the CCW miscellaneous header is aligned to an operating CCW loop.
9 Determine if normal letdown should be re-established:
9.1 Check normal letdown 9.1 Continue actions to restore malfunction(s) CORRECTED normal letdown, and proceed to step 10.
9.2 Verify all letdown orifice isolation valves - CLOSED LTDN ORIF ISO 45 GPM
[] Q1E21HV8149A LTDN ORIF ISO 60 GPM
[] Q1E21HV8149B 1 Q1E21HV8149C 9.3 Place LP LTDN PRESS PK 145 on service:
[1 Place controller in MANUAL
[1 Adjust demand signal to 50% or less 9.4 Place LTDN HX OUTLET TEMP TK 144 on service:
[] Place controller in AUTO
[] Set to maintain temperature 90 to 115°F 9.5 Verify VCT HI LVL DIVERT VLV LCV-115A alignment:
[] Position indicator VCT light -
LIT
[1 Handswitch in - AUTO Step 9 continued on next page.
Page 7 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I
9.6 Verify LTDN HI TEMP DIVERT VLV Q1E21TCV143:
[1 DEMIN light - LIT
[] Handswitch in - AUTO 9.7 IF necessary, THEN OPEN both LTDN LINE PENE RN ISOs from the Penetration Room Isolation Panel.
[1 Q1E21HV8175A
[] Q1E21HV8175B 9.8 Verify LTDN LINE CTMT ISO Q1E21HV8152 - OPEN 9.9 Verify LTDN LINE ISO valves -
OPEN
[1 Q1E21LCV459
[] Q1E21LCV46O 9.10 Initiate minimum charging flow:
9.10.1 Verify CHG FLOW FK 122 in
- MAN 9.10.2 Establish minimum charging flow based on orifices to be placed on service:
- 1 Orifice - 18 gpm OR
- 2 Orifices - 40 gpm 9.11 Establish approximately 9.11 no letdown flow can be 60 gpm letdown flow by established, OPENING: THEN proceed to Step 10.
[1 Q1E21HV8149B OR
[1 Q1E21HV8149C Step 9 continued on next page.
Page 8 of 23
4/27/2011 15:59 FNP-1-AOP-16.0 CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained
- I I 9.12 [CA] j all backup heaters energized due to pressurizer level deviation, THEN verify two sets of backup heaters in ON prior to level deviation clearing.
9.13 Adjust LP LTDN PRESS PK 145 9.13 IE necessary.
to maintain desired letdown THEN adjust LP LTDN PRESS PK pressure -
145 in MANUAL to stabilize BETWEEN 260-450 PSIC Letdown Pressure at desired value.
9.13.1 Set controller between 4.3 and 7.5 9.13.2 Check letdown flow -
S TABLE 9.13.3 Place PK 145 in AUTO 9.13.4 Control Letdown pressure as desired 9.14 Control LTDN HX OUTLET TEMP TK 144 to maintain Letdown temperature 90 to 115°F.
[1 TI-116 VCT TEMP
[] TI-143 DIVERT LTDN HX TEMP
[] TI-144 CCW LTDN HX TEMP 9.15 Refer to FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION, for further guidance on Letdown system control Page 9 of 23
4/27/2011 15:59 - -
FNP-1-AOP-16.0 CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 10 Determine status of letdown flow:
10.1 Check letdown flow - 10.1 Perform the following:
ESTABLI SHED 10.1.1 Continue monitoring levels:
- Normal letdown flow
- Pressurizer level OR
- VCT level
- Excess letdown flow 10.1.2 IF desired, THEN establish excess letdown using FNP-l-SOP-2.7, CHEMICAL AND VOLUME CONTROL SYSTEM EXCESS LETDOWN.
10.1.3 Continue efforts to determine cause of letdown malfunction.
10.1.3.1 WHEN cause of letdown malfunction has been corrected, THEN return to step 8.0.
OR 10.1.3.2 IF adequate letdown flow cannot be restored, THEN proceed to step 11.0.
10.2 Co to procedure and step in effect Page 10 of 23
4/27/2011 15:59 - -
FNP-1-AOP-16.O CVCS MALFU1CTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- The intent of the following steps is to borate through the RCP seals and reduce reactor power. The power reduction and cooldown will lower TAVG and will either reduce the rate of pressurizer level increase or stop the pressurizer level increase through RCS shrinkage, and afford time to restore a letdown path.
- Maximum ramp rates specified in FNP-1-UOP-3.1 are not applicable.
Pressurizer level, response to boration through the RCP seals, and time required to restore a letdown path will dictate the maximum ramp rate. Depending on pressurizer level a reactor trip may be required.
__1l Verify CHG FLOW FK-122 -
MANUALLY CLOSED
_12 Check Reactor - CRITICAL 12 Proceed to step 16.0.
NOTE:
- Tech Spec. 3.4.9 actions apply when pressurizer level exceeds 63.5%.
- The requirement for a reactor trip at 75% prior to reaching the automatic trip setpoint at 92% allows more time to establish a cooldown before the pressurizer fills solid.
- If a reactor trip is required, the remainder of this procedure should be performed in conjunction with FNP-1-ESP-0.1, REACTOR TRIP RESPONSE.
13 [CA] Check PRZR level - LESS 13 Trip the reactor and go to THAN 75% FNP-1-EEP-O, REACTOR TRIP OR SAFETY INJECTION.
14 [CA] Maintain PRZR level -
20-60%.
14.1 Reduce reactor power/TAVG as necessary using FNP-1-UOP-3.1, POWER OPERATION Page 11 of 23
4/27/2011 15:59 - -
FNP-1-AOP-l6.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I NOTE: Boron addition rate to the RCS will be limited by the RCP seals.
Boration response using the normal boration path may be limited (and therefore limit the ramp rate) due to its relationship to the VCT outlet check valve and seal return. A boration path to the A Train charging pumps suctions via the manual emergency borate valve may be established to improve response by eliminating these effects. Once the valve lineup has been established, the MKUP MODE CONT SWITCH and MKUP MODE SEL SWITCH can be operated normally to initiate and secure a boration.
15 Check normal boration flow path 15 Align a boration flow path ADEQUATE FOR DESIRED RAMP RATE directly to the charging pump suction:
15.1 Close MKUP TO VCT Q1E21FCV114A.
15.2 Close MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B.
15.3 Verify BORIC ACID TO BLENDER Q1E21FCV113A in AUTO and closed.
15.4 Open MAN EMERG BORATE VLV Q1E21V185. (100 ft. AUX BLDG rad side chemical mixing tank area)
Step 15 continued on next page.
Page 12 of 23
4/27/2011 15:59 -
FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 15.5 [CA] WHEN boration required, THEN perform the following:
15.5.1 Adjust BORIC ACID MKUP FLOW FK 113 to deliver the desired number of gallons.
15.5.2 Position MKUP MODE CONT SWITCH to STOP.
15.5.3 Position MKUP MODE SEL SWITCH to BORATE.
15.5.4 Position MKUP MODE CONT SWITCH to START.
15.5.5 Verify a boric acid pump running.
15.5.6 Verify boric acid flow.
MAKEUP FLOW TO CHGIVCT
[1 BA Fl 113 Page 13 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 16 [CA] Maintain PRZR Level -
20- 60%
16.1 Maintain seal injection flow to each RCP 6-13 gpm 16.2 Maintain VCT level - 20-60%
16.2.1 Position Q1E21V198, VCT DRN TO RHT No. 1, as necessary to control VCT level.
(121 ft AUX BLDG. VCT valve room) 16.3 Check reactor - NOT CRITICAL 16.3 IF reactor is critical, THEN return to Step 13.
16.4 Cooldown as necessary to maintain PRZR level using FNP-l-UOP-2.2, SHUTDOWN OF UNIT FROM HOT STANDBY TO COLD SHUTDOWN.
16.5 Check PRZR level rise - 16.5 Direct Chemistry to open as ACCEPTABLE many RCS sample paths as the sample cooling unit will allow.
16.6 Check any letdown path - 16.6 Evaluate a CTMT entry to RESTORED restore letdown, excess letdown, or low pressure letdown when conditions permit.
17 [CA] Monitor letdown flow paths:
17.1 Check letdown paths - ANY 17.1 Return to Step 16.
ESTABLI SHED
- Normal letdown flow OR
- Excess letdown flow 17.2 Evaluate plant conditions to determine next course of action Page 14 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 1 CAUTION: Decreasing CHG flow significantly will increase LTDN temperature.
Maintain sufficient CHG flow to prevent LTDN temperature at the LTDN heat exchanger outlet from exceeding 135°F.
NOTE: With FK-122 M/A station in AUTO flow controller FK-l22 limits high flow to 130 gpm and low flow to 18 gpm.
18 Determine Charging Status:
18.1 Check charging - AFFECTED BY 18.1 IF charging is normal, MALFUNCTION THEN go to procedure and step in effect.
- CHG FLOW, FI-122A - ABNORMAL FLOW INDICATED 18.2 Check Charging flow - 18.2 Dispatch personnel to initiate CONTROLLED manually bypass of FCV-122 per ATTACHMENT 1, MANUAL CONTROL
[] FK-122 in AUTO OF CHARGING FLOW.
[] FK-122 in MANUAL 19 Check VCT outlet isolation 19 Verify open RWST TO CHG PUMP valves - OPEN suction valves:
[1 Q1E21LCV115C [1 Q1E21LCV115B El Q1E21LCV115E [1 Q1E21LCV115D 20 Verify charging pump suction header aligned:
[1 Q1E21MOV813OA open
[1 Q1E21MOV813OB open El Q1E21MOV8131A open E] Q1E21MOV8131B open Page 15 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 21 Verify charging pump discharge flow path-ALIGNED CHG PUMP DISCH HDR ISO
[1 Q1E21MOV8132A open
[] Q1E21MOV8132B open
[1 Q1E21MOV8133A open
[I Q1E21MOV8133B open CHG PUMPS TO REGENERATIVE HX El Q1E21MOV81O7 open El Q1E21MOV81O8 open 22 [CA] Maintain pressurizer level between 20-60%:
22.1 Check pressurizer level - 22.1 IF pressurizer level is STABLE increasing stable, perform the following:
22.1.1 Adjust letdown flow as necessary:
- Raise letdown flow to 120 gpm Step 22 continued on next page.
Page 16 of 23
4/27/2011 15:59 FNP-1-AOP-16.0 CVCS MALFUNCTION *Revision 17 Step Action/Expected Response Response NOT Obtained I I I 22.1.2 IF additional control is necessary to reduce pressurizer level, THEN Isolate the RCS as follows:
22.1.2.1 Place LP LTDN PRESS PK 145 in MANUAL and verify demand signal is approximately 50%.
22.1.2.2 Close LTDN ORIF ISOs:
Ii 01E21HV8149A
[1 Q1E21HV8149B
[1 Q1E21HV8149C 22.1.2.3 IF desired, THEN close both LTDN LINE ISOs:
[] Q1E21LCV459
[1 Q1E21LCV46O 22.1.2.4 Isolate charging flow by closing one of the CHG PUMP TO REGENRATIVE HX MOVs:
[1 Q1E21MOV81O7 OR
[1 Q1E21MOV81O8 22.2 Alternately cycle open and closed one of the following MOVs for charging control as required:
CHO PUMPS TO REGENERATIVE fiX
[1 Q1E21MOV81O7
[1 Q1E21MOV81O8 22.3 Adjust SEAL WTR INJECTION HIK-186 as required to maintain RCP seal injection flow 6-13 gpm Step 22 continued on next page.
Page 17 of 23
4/27/2011 15:59 FNP1AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 22.4 Check pressurizer level - 22.4 Place excess letdown in STABLE or DECREASING service using FNP-l-SOP-2.7, CHEMICAL AND VOLUME CONTROL SYSTEM EXCESS LETDOWN.
23 Check charging flow - 23 Perform the following:
ESTABLISHED 23.1 Continue maintaining pressurizer level with excess letdown flow and seal injection.
23.2 Continue efforts to correct the charging malfunction.
23.3 WHEN affected component(s)are restored, THEN establish normal charging:
23.3.1 Open charging flow regulator outlet valve Q1E21V134A.
23.3.2 Verify CHG FLOW FK-122 has a demanded output that indicates closed.
23.3.3 Open charging flow regulator inlet valve QlE2lVl34B.
23.3.4 IF previously isolated, THEN open the following valves as required to establish charging flow:
CHG PUMP TO REGENRATIVE HX MOVs:
[1 Q1E21MOV81O7
[1 Q1E21MOV81O8 Step 23 continued on next page.
Page 18 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I 23.3.5 Restore flow through FCV 122:
23.3.5.1 IF FCV-122 is bypassed, THEN:
a) Slowly throttle closed charging flow regulator bypass valve:
- 01E21V135 OR
- Q1E21V581 b) Verify FK122 in MANUAL.
c) Adjust charging flow to control pressurizer level.
23.3.5.2 IF FK-122 is in MANUAL, THEN establish minimum charging flow for one orifice on service.
(18 gpm) 23.3.6 Verify charging flow regulator bypass valves -
- Q1E21V581
- Q1E21V135 Page 19 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I I I CAUTION: To prevent heat exchanger damage, do not attempt restoration of letdown unless the CCW miscellaneous header is aligned to an operating CCW loop.
24 Determine normal letdown established:
24.1 Check letdown flow - 24.1 Re-establish normal letdown:
ESTABLISHED 24.1.1 Verify all letdown orifice
- Excess letdown flow [3 Q1E21HV8149A LTDN CRlF ISO 60 GPM
[1 Q1E21HV8149B
[1 Q1E21HV8149C 24.1.2 Place LP LTDN PRESS PK 145 on service:
[1 Place controller in AUTO
[1 Adjust demand signal to 50%
or less 24.1.3 Place LTDN HX OUTLET TEMP TK 144 on service:
[3 Place controller in AUTO
[3 Set to maintain temperature 90 to 115°F 24.1.4 Verify VCT HI LVL DIVERT VLV LCV115A:
[1 Position indicator VCT light - LIT
[1 Handswitch in - AUTO Step 24 continued on next page.
Page 20 of 23
4/27/2011 15:59 - -
FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained 24.1.5 Verify LTDN HI TEMP DIVERT VLV Q1E21TCV143:
[1 DEMIN light - LIT
[1 Handswitch in - AUTO 24.1.6 IF necessary, THEN OPEN both LTDN LINE PENE RN ISOs from the Penetration Room Isolation Panel.
[1 Q1E21HV8175A
[1 Q1E21HV8175B 24.1.7 Verify LTDN LINE CTMT ISO 01E21HV8152 - OPEN 24.1.8 Verify LTDN LINE ISO valves
- OPEN
[1 Q1E21LCV459
[1 Q1E21LCV46O 24.1.9 Initiate minimum charging flow:
24.1.9.1 Verify CHG FLOW FK 122 in - MAN 24.1.9.2 Establish minimum charging flow based on orifices to be placed on service:
- 1 Orifice - 18 gpm OR
- 2 Orifices - 40 gpm 24.1.10 Establish 60 gpm letdown flow by OPENING:
- Q1E21HV8149B OR
- 01E21HV8149C Step 24 continued on next page.
Page 21 of 23
4/27/2011 15:59 ENP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained 24.1.11 Adjust LP LTDN PRESS PK 145 to maintain desired letdown pressure -
BETWEEN 260-450 PSIG 24.1.11.1 Set controller between 4.3 and 7.5 24.1.11.2 Check letdown - STABLE 24.1.11.3 Place LP LTDN PRESS PK 145 in AUTO 24.1.11.4 IF necessary, THEN adjust LP LTDN PRESS PK 145 in MANUAL to stabilize Letdown Pressure at desired value.
24.1.11.5 Verify Letdown pressure is maintained at the desired value.
24.1.12 Verify that LTDN HX OUTLET TEMP TK 144 is maintaining Letdown temperature 90 to 115°F
[1 TI-116 VCT TEMP
[1 TI-143 DIVERT LTDN HX TEMP
[1 TI-l44 CCW LTDN HX TEMP 24.1.13 Refer to FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION, for further guidance on Letdown system control 24.1.14 IF letdown flow was lost with auxiliary spray in service, THEN refer to TRM 13.4.2.
24.1.15 IF normal letdown cannot be established, THEN return to step 8.
Page 22 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 Step Action/Expected Response Response NOT Obtained I
_25 IF excess letdown is in operation. M no longer desired, TREN remove excess letdown from operation using FNPl-SOP-2.7.
CHEMICAL AND VOLIIME CONTROL SYSTEM EXCESS LETDOWN.
26 Go to procedure and step in effect.
-END Page 23 of 23
4/27/2011 15:59 FNP-1-AOP-16.O CVCS MALFUNCTION Revision 17 ATTACHMENT 1 MANUAL CONTROL OF CHARGING FLOW 1 Establish continuous communications between control room and CIIG FLOW FCV 122.
2 Open charging flow regulator bypass valve 01E21V135.
3 Open charging flow regulator bypass valve Q1E21V581.
4 Close charging flow regulator inlet valve Q1E21V134B.
5 previously isolated, THEN have the control room operator open the following valves as required to establish charging flow.
CHG PUMP TO REGENERATIVE HX NOVs
[1 Q1E21MOV81O7 El Q1E21MOV81O8 NOTE: Q1E21V135 is a designed throttle valve and should be used for throttling first. IF it is not effective, THEN Q1E21V581 may be used as a throttle valve.
6 Throttle charging flow regulator bypass valve Q1E21V135 , Q1E21V581 to maintain pressurizer level programmed level.
7 Close charging flow regulator outlet valve Q1E21V134A.
-END Page 1 of 1
FNPHLT34JPM Pagelofli SIMULATOR JPM C.
CRO-333-MOIMFIED TITLE: Perform The Required Actions For Cold Leg Recirculation EVALUATION LOCATION: J SIMULATOR El CONTROL ROOM El CLASSROOM PROJECTED TIME: 14 MIN SIMULATOR IC NUMBER: IC-220 Ii ALTERNATE PATH El TIME CRITICAL El PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
TASK STANDARD: Upon successful completion of this 1PM, the examinee will:
Correctly complete the alignment to place ECCS for cold leg recirculation JAW ESP-l 3.
Examinee:
Overall JPM Performance: Satisfactory I1 Unsatisfactory EJ Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Howard Fitzwater Date: 4/25/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP FfLT-34 SIMULATOR JPM C. Pe 2 Of 11 (Guide pages = 10)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-220 for 1PM C Put OPS group on MCB CRT Acknowledge computer alarms NOTE: MINIMIZE the time the simulator is run before the student is ready to take the shift. RWST inventory should be as close to 12.5 ft as possible when started.
Run / Freeze Simulator Acknowledge annunciators Turn Horns ON (REPLACEMENT PAGES 5-14 OF 19)
Markup ESP-l.3, v22 as completed through Step 7.5. (STEP 7.4 is not performed; bypassed by 7.3)
STA screen on MCB display Setup IC22O*
RSTIC-151
- Contains the following; MAL-RCS2A / TRUE IMF cRH87O6A_cc3 Closed
- SNP 220
- FNP HLT-34 SIMULATORJPM C. Page 3 of 11 (Guide pages = 10)
CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR COLD LEG RECIRCULATION. The conditions under which this task is to be performed are:
- a. A safety injection is in progress following a LOCA.
- b. ESP-l .3 has been entered and all steps through Step 7.5 have been completed.
- c. lB Charging pump is aligned to A Train.
NITIATING CUE, You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
(ESP-1.3 step 7.6) S / U
Observes the green light LIT and pump amps decrease to 0 (ESP-l.3 step 7.7) 5 / U
- 2. Close RWST TO IA RHR PUMP MOV-8809A. CLOSES MOV-8809A Observes the green light LIT (ESP-l.3 step 7.8) 5 / U
M0V881 IA MOV-881 1A MOV8812A M0V8812A Observes the red lights LIT (ESP-l.3step7.9) S / U
- 4. Close RHR to RCS HOT LEGS XCON. CLOSES MOV-8887A MOV8887A Observes the green light LIT (ESP-l.3 step 7.10) S / U
[]RHR pump 1A amps > 0 checks amps.
Observes the red light LIT and amps rising.
NOTE: amp check is NOT critical
FNP I-tLT-34 SIMULATOR JPM C. Page 4 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ESP-1.3 step 7.11)
- 6. Verify A Train LHSI flow - CHECKS FI-605A S I U STABLE.
[j FI-605A (ESP-1.3 step 7.12)
- 7. Close RWST TO lB RHR PUMP MOV-8809B. CLOSES MOV-8809B S I U Observes the green light LIT (ESP-1.3 step 7.13)
- 8. Align CTMT sump to lB RHR PUMP. OPENs the following: S / U MOV881 lB MOV-881 lB MOV8812B MOV8812B Observes the red lights LIT (ESP-1.3 step 7.14)
- 9. Close RHR to RCS HOT LEGS XCON. CLOSES MOV-8887B S / U MOV8887B Observes the green light LIT (ESP-1.3 step 7.15)
[]RHR pump lB amps >0 checks amps.
Observes the red light LIT and amps rising.
NOTE: amp check is NOT critical (ESP-1.3 step 7.16)
[]FI-605B (ESP-1.3 step 7.17)
- 12. Verify at least one train of RHR in operation CHECKS FI-605A and B flow S / U providing recirculation flow stable
FNP HLT SIMULATOR JPM C. Page 5 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ESP- 1.3 step 7.18)
- 13. Verify CHG pump miniflow valves-CLOSED CHECKS the following closed: S/U
- MOV-8109A - MOV-8109A
- MOV-8109B - MOV-8109B
- MOV-8109C - MOV-8l09C
- MOV-8106 - MOV-8106 Observes the green lights LIT (ESP-1.3 step 7.19)
- MOV-8 100 - MOV-8100
- MOV-8112 - MOV8112 Observes the green lights LIT (ESP-1.3 step 7.20)
- 15. IF 1A RHR PUMP started, THEN align charging Determines lB charging pump is S / U pump suction header isolation valves based on 1 B aligned to the A train and then:
charging pump status.
CHECKS the following OPEN lB charging pump status: Aligned to the A train - MOV-8130A
- MOV-8130A OPEN - MOV-8130B
- MOV-8130B OPEN Observes the red lights LIT
- MOV-8131A CLOSED
- MOV-8131B CLOSED CLOSES the following:
- MOV-8131A
- MOV-8l3lB Observes the green lights LIT Evaluator . A failure is in on MOV-8706A that seals in the CLOSE signal. The MOV will stroke OPEN, NOTE: but will IMMEDIATELY stroke closed.
FNP HLT-34 SIMULATOR JPM C. Page &Of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ESP-1.3 step 7.21)
- 16. Open RHR supply to A train charging pump Places handswitch for the S/U suction. following in the OPEN position.
1A RHR HX TO CHG PUMP SUCT - MOV-8706A
[ ]MOV-8706A Observes the BOTH red and green lights LIT, then green light is LIT.
If reported to the SS that MOV 8706A has failed to remain open, and that RNO actions will be initiated CUE: The SS acknowledges.
(ESP-1 .3 step 7.21 RNO)
- 17. Stop the running A train CHG PUMP. STOPS the 1A CHG pump S/U Observes the green light LIT
-go to step 7.25 (ESP-1.3 step 7.25)
- 18. IF lB RHR PUMP started, THEN align charging Determines lB charging pump is S/U pump suction header isolation valves based on lB aligned to the A train and then:
charging pump status.
CHECKS the following OPEN lB charging pump status: Aligned to the A train - MOV-8130A
- MOV-8130A OPEN - MOV-8130B
- MOV-8130B OPEN Observes the red lights LIT
- MOV-8131A CLOSED
- MOV-8131B CLOSED CHECKS the following ClOSED:
- MOV-8l3lA
- MOV-8131B Observes the green lights LIT (ESP-1.3 step 7.26)
- 19. Open RHR supply to B train charging pump OPENs MOV-8706B S/U suction. Observes the red light LIT lB RHR HX TO CHG PUMP SUCT
[ ]MOV-8706B
FNP HLT-34 SIMULATOR JPM C. Page 7f 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ESP-l.3 step 7.27)
- 20. Verify B Train charging pump running. CHECKS amps on 1C charging s/U pump (B train).
(ESP-l.3 step 7.28)
- 21. Verify VCT level GREATER THAN 5%.
- CHECKS LI-112 and/or LI-115 S / U indicate> 5%.
(ESP-l.3 step 7.29)
- 22. Close B train RWST to charging pump header CLOSES LCV-115D s/U valve. Observes the green light LIT RWST TO CHG PUMP
[]LCV115D (ESP-1.3 step 7.30)
- 23. Check one CHG PUMP in each train - Checks charging pump amp S/U STARTED. metersdetermines only B train
] A train (1A or 1B) amps >0 CHG pump is running.
[1 B train (1C) amps >0 Go to 7.30 RNO.
CAUTION Injecting through A train and B train flowpaths simultaneously with only one charging pump running could result in pump runout conditions. Therefore, in Step 7.30 RNO the HHSI valve should be closed without delay after M0V8885 is opened.
(ESP-l .3 step 7.30 RNO actions)
- 24. IF an A train CHG PUMP Started, THEN Determines A train Chg pump S/U proceed to step 7.29. IF NOT. Establish B train was NOT started continues with injection per the following. RNO step 7.30.1 (ESP-1.3 step 7.30.1 RNO actions)
- 25. Open charging pump recirculation to RCS cold OPENS MOV-8885 S/U legs valve. Observes the red light LIT CHG PUMP RECIRC TO RCS COLD LEGS
[1 M0V8885
FNP HLT-34 SIMULATOR JPM C. Pg 8 ofil (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ESP-l.3 step 7.30.2 RNO actions)
[1 M0V8803A Observes the green lights LIT
[1 M0V8803B 7.30.3 RNO action says to go to step 7.32 (ESP-l.3 step 7.32)
- 27. Align charging pump discharge header isolation Determines lB charging pump is S / U valves based on lB charging pump status. aligned to the A train and then:
lB charging pump status: Aligned to the A train CHECKS the following OPEN
- MOV-8132A OPEN - MOV-8132A
- MOV-8132B OPEN - MOV-8132B
- MOV-8133A CLOSED Observes the red lights LIT
- MOV-8133B CLOSED CLOSES the following
- MOV-8133A
- MOV-8133B Observes the green lights LIT (ESP-l.3 step 7.33)
- 28. Verify SI flow STABLE.
- CHECKS SI flow instruments S / U for stable flow.
A TRN HHSI FlOW A TRN HHSI FlOW
[1 Fl 943 [ ] Fl 943 NO flow on this Fl due to failed alignment B TRN HHSI FlOW
[1 Fl 940 B TRN HHSI FlOW
[1 Fl 940 1A (1B) RHR HDR FlOW
[ ] FT 605A 1A (1B) RHR HDR FlOW
[ ] FT 605A [1 FT 605A
[ ]F1605B STOP TIME:
TERMINATE 1PM when SI flow verified stable on FI-940 and 605A and B.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP HLT-34 SIMULATOR JPM C. Page 9 of 11 (Guide pages 10)
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-ESP--1.3, V 22.0
- 2. K/As: O1JEA1.11 RO-4.2 SRO-4.2 GENERAL TOOLS AND EOUIPMENT:
Provide/Acquire:
- 1. A pre-marked ESP-1.3 through step 7.5
FNP I-ILT-34 SIMULATOR JPM C. Page 10 & 11 (Guide pages = 10)
Critical ELEMENT justification:
STEP Evaluation
- 1. CRITICAL since ESF components would be damaged if this step is not performed-impacting the ability to provide Long Term Core Cooling.
- 2. CRITICAL since failure to complete this task could allow contaminated fluids to be transferred to the RWST from CTMT sump and allow for potential Air binding of ESF components, impacting Long Term Core Cooling.
- 3. CRITICAL since ESF components would be damaged if this step is not performed-impacting the ability to provide Long Term Core Cooling.
- 4. CRITICAL for the alignment of Core Cooling
- 5. CRITICAL establishment of Core Cooling
- 6. Not critical since this action is a check step. NO actions/decisions are initiated from this action.
- 7. CRITICAL since failure to complete this task could allow contaminated fluids to be transferred to the RWST from CTMT sump and allow for potential Air binding of ESF components, impacting Long Term Core Cooling.
- 8. CRITICAL since ESF components would be damaged if this step is not performed-impacting the ability to provide Long Term Core Cooling.
- 9. CRITICAL for the alignment of Core Cooling
- 10. CRITICAL establishment of Core Cooling (2 train)
- 11. Not critical since this action is a check step. NO actions/decisions are initiated from this action.
- 12. Not critical since this action is a check step. NO actions/decisions are initiated from this action.
- 13. Not critical since there is NO action required.
- 14. Not critical since there is NO action required.
- 15. Not critical since improper performance of this action has no impact on HHSI.
- 16. Not critical since a malfunction will prevent success.
- 17. CRITICAL to protect ESF equipment (CHG pump)
- 18. Not critical since improper performance of this action has no impact on HHSI.
- 19. CRITICAL for the alignment of HHSI injection
- 20. Not critical since this action is a check step. NO actions/decisions are initiated from this action.
- 21. Not critical since improper performance of this action has no impact on HHSI and VCT level will be >5%.
- 22. CRITICAL for the alignment of HHSI injection
- 23. Not critical this is a verification step and the charging pump is running.
- 24. Not critical this is a verification step.
- 26. CRITICAL for the protecting HHSI pump from runout conditions.
- 27. Not critical since improper performance of this action has no impact on HHSI.
- 28. Not critical since this is a verification/check step, no actions will be initiated based on this action. NATURAL termination point of actions.
COMMENTS:
FNP HLT-34 JPM SIMULATOR JPM A. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR COLD LEG RECIRCULATION. The conditions under which this task is to be performed are:
- a. A safety injection is in progress following a LOCA.
- b. ESP-1.3 has been entered and all steps through Step 7.5 have been completed.
- c. lB Charging pump is aligned to A train.
4/25/2011 09:10 FNP-1-ESP-1 .3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I CAUTION: Pump damage will occur if a charging pump or RHR pump is started in a train in which a flow path from the containment sump to the RCS cannot be established or maintained.
Align ECCS for cold leg recirculat ion.
Check large break LOCA has 7.1 Proceed to step 7.4.
occurred as indicated by accumulators discharged.
7 Check containment sump level - 7.2 j both containment sump level GREATER THAN 3.4 ft {3 .8 ft). indications less than 3.4 ft f3.8 ft},
CTMT SUMP THEN go to FNP-1-ECP-1.1, LOSS LVL OF EMERGENCY COOLANT LI 3594A RECIRCULATION.
POST ACCIDENT CTMT WTR LVL LR 3594B Proceed to step 7.5.
0 Check containment sump level GREATER THAN 2.5 ft 2.9 ft}.
- 7.4 IF both containment sump level indications less than 2.5 ft
{2.9 it),
CTMT SUMP THEN go to FNP1-ECP-l.l, LOSS LVL OF EMERGENCY COOLANT LI 3594A RECIRCULATION.
POST ACCIDENT TMT WTR LVL LR 3594B 0 Verify recirculation valve disconnects ATTACHMENT 1.
- CLOSED USING 7.6 Stop both RHR PUMPs.
Step 7 continued on next page.
Page 5 of 19
4/25/2011 09:10 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained 7.7 Close RWST TO 1A RHR PUMP 7.7 Perform the following.
Q1E11MOV88O9A.
7.7.1 Stop the running A train CHG PUMP.
7.7.2 Proceed to step 7.12.
7.8 Align CTMT sump to 1A RHR 7.8 Perform the following.
PUMP.
7.8.1 Stop the running A train CTMT SUMP CHG PUMP.
TO 1A RHR PUMP
[] Q1E11MOV8811A open 7.8.2 Proceed to step 7.12.
[] Q1E11MOV8812A open 7.9 Close RI-JR to RCS I-TOT LEGS XCON Q1E11MOV8887A.
7.10 Start 1A RHR PUMP. 7.10 Perform the following.
RHR PUMP 7.10.1 Stop the running A train
[1 1A amps > 0 CHG PUMP.
7.10.2 Proceed to step 7.12.
7.11 Verify A Train LHSI flow -
STABLE.
1A RHR I-fOR FLOW
[1 Fl 6O5A 7.12 Close RWST TO lB RHR PUMP 7.12 Perform the following.
OlEl 1MOV88O9B.
7.12.1 Stop the running B train CHG PUMP.
7.12.2 Proceed to step 7.17.
7.13 Align CTMT sump to lB RHR 7.13 Perform the following.
PUMP.
7.13.1 Stop the running B train CTMT SUMP CI-IG PUMP.
TO lB RI-JR PUMP
[1 Q1E11MOV8811B open 7.13.2 Proceed to step 7.17.
[] Q1E11MOV8812B open Step 7 continued on next page.
Page 6 of 19
4/25/201109:10 --
FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 1 7.14 Close RHR to RCS HOT LEGS XCON Q1E11MOV8887B.
7.15 Start lB RHR PUMP. 7.15 Perform the following.
RHR PUMP 7.15.1 Stop the running B train
[1 lB amps > 0 CHG PUMP.
7.15.2 Proceed to step 7.17.
7.16 Verify B Train LHSI flow -
STABLE.
[1 Fl 605B Step 7 continued on next page.
Page 7 of 19
4/25/2011 09:10 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained 7.17 Verify at least one train of 7.17 Perform the following:
RHR in operation providing recirculation flow. 7.17.1 Check A Train RHR available:
- 1A RHR Pump
- CCW TO 1A RHR HX Q1P17MOV3185A 7.17.2 IF A Train RER components available for recirculation flowpath, THEN start an A Train Charging Pump and return to step 7.8.
7.17.3 Check B Train RHR available:
- lB RHR Pump
- CCW TO lB RHR HX Q1P17MOV3185B 7.17.4 IF B train RHR components available for recirculation flowpath, THEN start a B Train Charging Pump and return to step 7.13.
7.17.5 IF no RHR train is available, THEN check RWST level greater than 4.5 ft start any available charging pump aligned to the RWST.
Step 7 continued on next page.
Page 8 of 19
4/25/2011 09:10 FNP-l-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 7.17.6 Go to FNP-l-ECP-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION.
CAUTION: The charging pumps should be stopped if RCS pressure rises to greater than their shutoff head.
CAUTION: The charging pump miniflows should NQI be reopened to satisfy miniflow criteria while the charging pump suctions are aligned to the RHR pumps.
7.18 Verify charging pump miniflow valves CLOSED.
lA(lBlC) CHG PUMP MINIFLOW ISO
[1 Q1E21MOV81O9A El Q1E21MOV81O9B
[1 O1E21MOV81O9C CHG PUMP MINIFLOW ISO
[1 Q1E21MOV81O6 7.19 Verify seal return flow valves - CLOSED.
[1 Q1E21MOV8100 closed
[] Q1E21MOV8112 closed Step 7 continued on next page.
Page 9 of 19
[
4/25/2011 09:10 ENP-1-ESP-1 .3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 7.20 IF 1A RHR PUMP started, 7.20 IF lA RHR PUMP NOT started, THEN align charging pump THEN perform the following.
suction header isolation valves based on lB charging 7.20.1 Verify the A train CHG pump status. PUMP stopped.
7.20.2 Proceed to step 7.25.
lB Charging Aligned As Aligned As Pump A Train B Train Not Status pump pump Available CHG PUMP SUCTION HDR ISO Q1E21MOV [1 813OA [1 8130A [1 813OA open closed closed
[1 813OB [] 813OB [1 813OB open closed closed
[1 813lA [j 8131A [1 8l31A closed open closed
[1 8l31B [1 8l31B [] 8131B closed open closed 7.21 Open RHR supply to A train 7.21 Perform the following.
charging pump suction.
7.21.1 Stop the running A train 1A RHR HX CHG PUMP.
TO CHG PUMP SUCT
[1 Q1E11MOV87O6A 7.21.2 Proceed to step 7.25.
7.22 Verify A train CHG PUMP -
started.
7.23 Verify VCT level GREATER THAN 5%.
7.24 Close A train RWST to 7.24 Perform the following.
charging pump header valve.
7.24.1 Stop the running A train RWST CHG PUMP.
TO CHG PUMP
{] O1E21LCV115B 7.24.2 Close RHR supply to A train charging pump suction.
[1 Q1E11MOV87O6A Step 7 continued on next page.
Page 10 of 19
4/25/2011 09:10 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I 7.25 IF lB RHR PUMP started, 7.25 IF lB RHR PUMP NOT started, THEN align charging pump THEN perform the following.
suction header isolation valves based on lB charging 7.25.1 Verify the B train CHG pump status. PUMP stopped.
7.25.2 Proceed to step 7.30.
lB Charging Aligned As Aligned As Pump A Train B Train Not Status pump pump Available CHG PUMP SUCTION HDR ISO Q1E21MOV [1 8130A [1 813OA [] 8l30A open closed closed
[] 8130B [1 8l30B [] 813OB open closed closed
[1 8l3lA [1 8131A [1 8l31A closed open closed LI 8l31B [1 8l31B [] 8131B closed open closed 7.26 Open RHR supply to B train 7.26 Perform the following.
charging pump suction.
7.26.1 Stop the running B train lB RHR FIX CHG PUMP.
TO CHG PUMP SUCT
[1 Q1E11MOV87O6B 7.26.2 Proceed to step 7.30.
7.27 Verify B train CHG PUMP started.
7.28 Verify VCT level - GREATER THAN 5%.
Step 7 continued on next page.
Page 11 of 19
4/25/2011 09:10 ENP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 7.29 Close B train RWST to 7.29 Perform the following.
charging pump header valve.
7.29.1 Stop the running B train RWST CHG PUMP.
TO CHG PUMP
[1 Q1E21LCV115D 7.29.2 Close RHR supply to B train charging pump suction.
[1 Q1E11MOV87O6B 7.29.3 Proceed to step 7.30.
CAUTION: Injecting through A train and B train flowpaths simultaneously with only one charging pump running could result in pump runout conditions. Therefore, in Step 7.30 RNO the HHSI valves should be closed without delay after MOV8885 is opened.
7.30 Check one CHG PUMP in each 7.30 IF an A train CHG PUMP train - STARTED. started, THEN proceed to step 7.32
[1 A train (1A or 1B) amps > 0 IF NOT, establish B train
[] B train (1C or 1B) amps > 0 injection per the following.
7.30.1 Open charging pump recirculation to RCS cold legs valve.
CHG PUMP RECIRC TO RCS COLD LEGS
[] 01E21MOV8885 7.30.2 Close HHSI isolation valves.
[1 Q1E21MOV88O3A
[] Q1E21MOV88O3B 7.30.3 Proceed to step 7.32.
Step 7 continued on next page.
Page 12 of 19
4/25/2011 09:10 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained 7.31 Open charging pump recirculation to RCS cold legs valve.
CHO PUMP RECIRC TO RCS COLD LEGS
[1 01E21MOV8885 7.32 Align charging pump discharge header isolation valves based on lB charging pump status.
lB Charging Pump Aligned As Aligned As Not Status A Train pump B Train pump Available CHG PUMP DISCH HDR ISO Q1E21MOV [1 8132A [1 8132A [1 8132A open closed closed El 8l32B [1 8132B [] 8l32B open closed closed El 8133A [I 8133A El 8133A closed open closed El 8133B [I 8133B El 8l33B closed open closed 7.33 Verify SI flow - STABLE. 7.33 IE at least one train of flow from the containment sump to A TRN the RCS can NOT be HHSI FLOW established or maintained, El Fl 943 THEN go to FNP-1-ECP-l.l, LOSS OF EMERGENCY COOLANT HHSI RECIRCULATION.
B TRN RECIRC FLOW El Fl 940 lA(1B)
[I Fl 605A El Fl 6O5B Page 13 of 19
4/25/2011 09:10 -
FNP-l-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Any charging pump with suction aligned to an RHR pump should be stopped prior to stopping the RHR pump.
CAUTION: Charging pump or spray pump damage will occur if suction is lost and the pump is not secured.
NOTE:
- Erratic pump parameters (flow, discharge pressure, amps, etc.) are indications of pump cavitation.
Step 8 is a continuous action step which applies any time ECCS pumps are aligned to the sump.
8 Verify EGGS pumps not affected 8 both trains are affected by sump blockage, such that at least one train of SI recirculation flow cannot be 8.1 [CA] Monitor ECCS pump suction maintained, conditions - NO INDICATION OF THEN go to FNP-l-ECP-1.3, LOSS CAVITATION. OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP CHG PUMP BLOCKAGE.
[] 1A
[] lB
[] 1C RHR PUMP
[1 lA
[1 lB CS PUMP
[] 1A
[] lB Page 14 of 19
FNPHLT34 JPM Page 1 of SIMULATOR JPM D CRO-043A--MODIFIED TITLE: Stop the RCP with a degraded seal per the guidance AOP-4. 1 and complete the necessary lOAs of AOP-4.0.
EVALUATION LOCATION: II SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 10 MINT SIMULATOR IC NUMBER: IC-221 Il ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
TASK STANDARD: Upon successful completion of this 1PM, the examinee will:
Stop the RCP with a degraded seal per the guidance AOP-4. 1 and complete the necessary actions of AOP-4.0.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
veloper Howard Fitzwater Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-30l-3
FNP HLT-34 SIMULATOR JPM D Page 2of 8 (Guide pages = 7)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC221 for JPM D Put OPS S/U group on MCB CRT Acknowledge computer alarms Run / Freeze Simulator Acknowledge annunciators Turn Horns ON Mark up AOP-4.l through step 9.1 (step 9.2 not completed)
Turn on Scaler timer xlOO setting When directed by the student:
Close disconnect for MOV-3350B.
cMFremote/IRF cAFO3 3 5Bcdl closed Setup IC_22l*
RST IC-il
- Increase Seal Injection flows (HK-186 adjustment too high) OPEN 8369A/B/C to 0.09% (sim view or LOA)
REMOTE/E21/IRF LOA-CHGOO4 0.09 REMOTE/E21/IRF LOA-CHGOO5 0.09 REMOTE/E2l/IRF LOA-CHGOO5 0.09 Manually Trip the Rx Failure on HV3227 IMF H1C3227B-B (0 :16) 0.66 10 Insert RCP seal malfunction IMF MAL-cvc27B 4.8%
SNP 220
CONDITIONS When I tell you to begin, you are to STOP THE RCP WITH A DEGRADED SEAL PER THE GUIDANCE AOP-4.1 AND COMPLETE THE NECESSARY IMMEDIATE OPERATOR ACTIONS OF AOP-4.O.
The conditions under which this task is to be performed are:
- a. The plant is in MODE 3
- b. The lB RCP has a degraded #1 seal.
- c. You have been directed to STOP the lB RCP using AOP-4.l step 9.2 and complete the required action(s) of AOP-4.O.
INITIATiNG CUE, You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
TIME (AOP-4. I step 9.2)
Observes amps and flow decreasing.
(AOP-4.l step 9.2.1)
- 2. Close the pressurizer spray valve for the lB RCP. PLACE PK-444D in MANUAL S / U
[j PK444D for lB RCP and VERIFY the CLOSE Pushbutton light is LIT with a Demand is 0%
NOTE Element 3, contains actions to MONITOR for RCP stopping. This action is NOT critical. The closure ofHV-8141B is Critical.
FNP HLT-34 SIMULATOR JPM 0 Page 4 of 8 (Guide pages = 7)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
(AOP-4.1 step 9.2.2)
- 3. WHEN the RCP has come to a complete stop as MONITORS lB RCS LOOP S/U indicated by minimum RCS flow in the affected flow on FI-424, 425, 426 for loop, THEN close the appropriate RCP SEAL indication to drop to near zero LEAKOFF VALVE. then rebound to -10%
MONITORS TI-422D AND/OR TR-4 10 AND/OR TR4 10 for indications of reverse flow.
[]Q1E2IHV8I41B CLOSES HV8141B Observes green light LIT (AOP-4.1 step 9.2.3)
- 4. WHEN affected RCP has been removed from REFERS to AOP-4.0 S / U service, THEN refer to FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW.
NOTE Element 5 & 6 may be performed without reference to AOP-4.0.
AOP-4.0 NOTE states the following:
Steps 1 through 2.1 are IMMEDIATE OPERATOR actions.
(AOP-4.0 step 1)
- 5. Check 1A and lB RCPs RUNNING.
- Implements RNO actions S / U (AOP-4.0 step 1 & RNO actions)
Manually close pressurizer spray valve for lB RCP. CHECKS PK-444D in
[] lB RCS loop spray valve PK-444D. MANUAL and VERIFY the CLOSE Pushbutton light is LIT with a Demand is 0%
NOTE Element 6 will not be successful and the RNO actions of AOP-4.0 step 2 will be implemented.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
(AOP-4.0 step 2) S I U
- 6. [CA] Maintain SG narrow range level stable at CHECK lB SG Narrow Range approximately 65% using: LEVEL instruments and notes
[]Main Feedwater Regulating Valves level> 65%.
[]Main Feedwater Bypass Regulating Valves.
[]Auxiliary Feedwater Control Valves. CHECK the following controllers are in Manual and Closed
[]FCV 489 & GREEN LIGHT LIT
[]FK488 & GREEN LIGHT LIT
[1 H1C3228BA at 0% Demand ATTEMPT to close FCV3227B
[1 H1C3227BA placed to 0%
Observes HV3227B red light LIT and FI3229B at 400 gpm.
(AOP-4.0 step 2.1 RNO)
- 7. IF SG level rise cannot be controlled, THEN IDENTIFIES that SG level is not S / U perform the following: controlled.
(AOP-4.0 step 2.1 RNO) CHECK main feedwater is NOT IF main feedwater in service, THEN [...J. in service; May evaluation per the initial conditions NOTE Element 8 will require field actions to close the supply breaker for M0V33 SOB. This action is directed by SOP-22.0 section 4.12; However the breaker is identified on the hand switch and could be directed without reference to the SOP.
CUE if necessary: SS acknowledges (AOP-4.0 step 2.2 RNO)
- 8. IF auxiliary feedwater in service, THEN close the Identifies the need to close S I U affected SG AFW Stop Valve(s). MOV-3350B.
[]1A SG Q1N23MOV335OA
[1 lB SG Q1N23MOV335OB
[1 1C SG Q1N23M0V3350C
FNP HLT-34 SIMULATORJPM D Page 6 of 8 (Guide pages = 7)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
NOTE ONLY ONE of the following flowpaths must be completed:
- BOTH Element 9 AND Element 10 must be completed, OR
- Element 11 must be completed. This is an alternative action that the candidate may initiate to satisfy the intent of the step until field actions can be implemented to comply with the AOP-4.0 actions.
O IF Element 11 is performed instead, the candidate should recognize that Flow would NOT be isolated from the TDAFW pump should it subsequently start.
(AOP-4.0 step 2.2 RNO);
Guidance contained within SOP-22, section SEE NOTE 4.12) DIRECTS a System Operator to S/U
- 9. The AFW stop valve (M0V3350B) is powered CLOSE BKR FUU5, MOV-3350B down AND with SS concurrence, THEN, supply breaker at the MCC-1U.
unlock and close the following breaker(s) as Observes white light LIT above required: (Master Z key.) M0V3350B Q1R17BKRFUU5 AFW TO lB SG STOP VLV M0V3350B If requested CUE: The SS concurs BOOTH OPERATOR: When directed Close BKR FUU5, M0V3350B supply breaker on MCC-1U and report action complete.
CMFremote/IRF cAFO335B cdl. closed SEE (AOP-4.0 step 2.2 RNO)
NOTE
- 10. Close MOV-3350B, lB SG STOP VLV CLOSES MOV-.3350B S/U Observes green light LIT SEE (partial performance of EEP-2 step 5 for NOTE
- MDAFW flow isolationALTERNATE S/U success path) CLOSES ONE or BOTH of
- 11. Close MDAFWP isolation valves to all faulted the following.
SGs.
MOV-3764D, lB SG ISO MOV, MOV-3764D MOV-3764B, lB SG ISO MOV and/or MOV-3764B Observes green light LIT STOP TIME
FNP HLr-34 SIMULATOR JPM D Page 7 of 8 (Guide pages = 7)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
Terminate when flow is secured to the lB SG. 7 CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. FNP-1-AOP-4.l, VER 6
- 2. FNP-l-AOP-4.0, VER 19.0
- 3. FNP-l-SOP-22.0, VER 65.0
- 1. NONE Critical ELEMENT justification:
STEP Evaluation
- 1. CRITICAL for completion of the assigned task. 1 B RCP will continue to run if this is not completed.
- 2. CRITICAL for completion of the assigned task; Failing to complete this action will result in disabling PZR Press Control system.
- 3. CRITICAL for completion of the assigned task; Failing to complete this task will result in RCS leakage from the degraded seal.
- 4. Not critical since there is no action required, procedural reference/transition S. Not critical This action is a repeat of element 1 and is merely a check step.
- 6. Not critical since there is no action required: a check step.
- 7. Not critical since there is no action required: a check step.
- 8. Not critical since there is no action capable until the valve is energized.
- 9. CRITICAL since this action is required to complete the required actions (TASK objective.
- 10. CRITICAL for achieving TASK objective; Failure to complete this action would result in SG overfill an eventual fill of MS lines.
COMMENTS:
FNP HLT-34 SIMULATOR JPM D. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to STOP THE RCP WITH A DEGRADED SEAL PER THE GUIDANCE AOP-4.1 AND COMPLETE THE NECESSARY IMMEDIATE OPERATOR ACTIONS OF AOP-4.O.
The conditions under which this task is to be performed are:
- a. The plant is in MODE 3
- b. The lB RCP has a degraded #1 seal.
- c. You have been directed to STOP the lB RCP using AOP-4. 1 step 9.2 and complete the required action(s) of AOP-4.O.
4/27/2011 16:00 FNP-1-AOP-4.l ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE Revision 6 Step Action/Expected Response Response NOT Obtained I I I 8.6 Go to procedure and step in effect.
NOTE: The intent of the following step is to have the Unit shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in order to secure the affected RCP(s) 9 [CA] Perform a controlled shutdown of the unit in accordance with the appropriate Unit Operating Procedures concurrent with the remainder of this procedure.
9.1 Maintain GREATER than 9 gpm seal injection flow to the affected RCP while the pump is running.
Step 9 continued on next page.
Page 10 of 26
4/27/2011 16:00 FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE Revision 6 Step Action/Expected Response Response NOT Obtained I
9.2 WHEN the reactor is shutdown, THEN STOP the affected RCP(s).
9.2.1 IF 1A OR lB RCP is secured, THEN close the pressurizer spray valve for the affected RCP.
[1 PK444C for 1A RCP
[1 PK444D for lB RCP 9.2.2 WHEN the RCP has come to a complete stop as indicated by minimum RCS flow in the affected loop, THEN close the appropriate RCP SEAL LEAKOFF VALVE.
[] Q1E21HV8141A
[] Q1E21HV8141B El O1E21HV8141C 9.2.3 WHEN affected RCP has been removed from service, THEN refer to FNP-1-AOP-4.O, LOSS OF REACTOR COOLANT FLOW.
9.2.4 Refer to Technical Specifications sections 3.4 and 3.5.
9.3 Go to procedure and step in effect.
Page 11 of 26
07/13/10 8:10:54 - FNP-l-AOP-4.Q February 23, 2010 Version 19.0 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1 -AOP-4.0 S
A F
E T
Y LOSS OF REACTOR COOLANT FLOW R
E L
A T
E D
PROCEDURE USAGE REQUIREMENTS PER FNP0-AP-6 SECTIONS Continuous Use Remainder of Procedure Reference Use Steps 1 - 2.1 Information Use Approved:
Wade Warren (for Operations Manager Date Issued: February 24, 2010
07/13/108:10:54 FNP-1-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES ody 11 Attachment 1 2 Page 1 of 1
- 07/13/10 S:10:4 FNP-1-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 A. Purpose This procedure provides actions for response to a loss of forced RCS flow in one or more ioops when a reactor trip is not required. In order to prevent a possible reactor power excursion, NO RCP should be restarted while the reactor is critical.
This procedure is applicable in Modes 1, 2, 3 and 4.
B. Symptoms or Entry Conditions I. This procedure is entered when forced RCS flow is lost in one or more loops and no reactor trip is required.
C Automatic Actions Loss of flow in one loop with reactor power greater than 30% will cause a reactor trip.
2 Loss of flow in two loops with reactor or turbine power greater than 10% will cause a reactor trip.
D Operational Concerns 1 SG level in any affected loop will tend to shrink.
2 Thermal shock to the spray nozzle will occur if auxiliary spray is initiated without normal letdown in service.
3 The PRT may rupture causing abnormal containment conditions while using PRZR PORVs for pressurizer pressure control.
4 To prevent heat exchanger damage, do not attempt restoration of letdown or excess letdown unless the CCW miscellaneous header is aligned to an operating ioop.
5 In order to prevent a possible reactor power excursion, NO RCP should be restarted while the reactor is critical.
6 j lB RCP is NQI running, THEN 1A & IC RCPs are required to provide adequate spray flow through the IA RCS loop spray valve.
Page 1 ofli
07/13/10 8:10:54 FNP-1-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 Step Action/Expected Response Response Not Obtained II I NOTE: Steps 1 through 2.1 are IMMEDIATE OPERATOR actions.
Check 1A and lB RCPs RUNNING.
- I Manually close pressurizer spray valve for affected RCP.
[] 1A RCS loop spray valve PK-444C
[] lB RCS loop spray valve PK-444D 2 [CA] Maintain SG narrow range level 2 IF SG level rise cannot be controlled, stable at approximately 65% using: THEN perform the following:
{] Main Feedwater Regulating Valves
[] Main Feedwater Bypass Regulating Valves. 2.1 IE main feedwater in service,
[1 Auxiliary Feedwater Control Valves. THEN close the affected SG Main Feedwater Stop Valve(s)
[] 1A SG Q1N21MOV3232A
[] lB SG Q1N21M0V3232B
[] 1CSGQIN21MOV3232C 2.2 IF auxiliary feedwater in service, THEN close the affected SG AFW Stop Valve(s)
[] 1A SG Q1N23M0V3350A
[] lB SO Q1N23MOV335OB
[] 1C SG Q1N23MOV335OC 3 [CA] Monitor Tavg for all three RCS 3 Perform the following..
loops 541°F. (TS 3.4.2) 3.1 IF the main generator is ON LINE, THEN trip the reactor and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 3.2 IF the main generator is OFF LINE, THEN raise Tavg 541°F within 30 minutes 3.2.1 Adjust steam dumps to reduce secondary power demand as necessary Step 3 continued on next page Page Completed Page 2 of 11
FNP HLT-34 JPM Page 1 of 8 SIMULATOR JPM E CR0-NEW TITLE: Isolate SW to the affected CTMT Cooler using SOP-I 2.1 section 4.6.
EVALUATION LOCATION: SIMULATOR Li CONTROL ROOM Li CLASSROOM PROJECTED TIME: 12 MIN SIMULATOR IC NUMBER: IC-222 Li ALTERNATE PATH Li TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
. Isolate SW to the affected CTMT Cooler using SOP-12.l section 4.6
. Start a Second A train CTMT Cooler.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
PNP HLT-34 SiMULATOR JPM E Page 2 of (Guide pages = 7)
EVENT DESCRIPTION ACTION DETAILS Reset into IC222 for JPM H Put STA group on MCB CRT Acknowledge computer alarms VERIFY 1A & 1C CNMT Coolers are selected (These switches ARE NOT switch checked).
Run / Freeze Simulator Acknowledge annunciators Turn Horns ON Setup IC_222*
RST IC73 Bat setuprevisited .txt imf MaI-RCS2A TRUE mf Mal-epsi I imf MAL-MsslA 2 imf cBK882OB_d_cp2 True simulates a SW break on IC Cnmt Cooler IMF F13014B 1000
>Temperature is elevated on ID outlet due to reduced SW flow through that cooler
>Temperature is elevated on 1 C outlet due to the backflow from ID cooler into the break (NO check valves)
IMF TE3025C 105 IMF TE3025D 105
>the following failures are inserted immediately but can be inserted over time if desired Imf LT3594A 8.2 imf LT3594B 8.2
FNP 1-fLT-34 SIMULATOR JPM E Page 3 of (Guide pages = 7)
>perform all Actions of E-0
>Control AFW to 395 gpm total Flow to B & C SGs
>use AFW FCVs to stop AFW flow to A SG from both TD and MD AFW pumps
>Foldout page criteria for Charging pump miniflows
>Attachment 2 of E-0 (condensate/HDP/ SGBD valves)
>Perform all Actions of E-2 for A SG Faulted
>Perform all actions of E-1 through step 16
> fill generators B&C to 61%
> Close ECCS disconnects
>Perform ESP-1.3
>A train CNMT spray only running RWST level 10 ft when alignment complete IMF cBkpOla_D_CCI trips the IA CS pump on OC.
>SET TRIGGERS:
>Trigger 1: When First valve closed (301 9C) then Fl-301 3B will lower to a higher value.
Trgset I F13013B==4500 Trg I imf F13013B (0 10) 3600 33
>Trigger 2-3: When MOV-3019C is closed and MOV3O19D remains open, SW flow will be diverted through the 1D Cnmt cooler into the 1 C CNMT cooler via reverse flow, Both Cnmt Cooler discharge temps lower to normal.
Trgset 2 RNC3OI9C < 0.99 && FT3OI3BB> 14.0 Trg 2 imf TE3025D 82 63 Trgset 3 RNC3OI9C < 0.99 && RNC3OI9D <0.97 && T13025D > 90 Trg 3 imfTE3O25C 100 23
>Trigger 4-5: WHEN FLOW TO BREAK IS ISOLATED RAMP INDICATION TO NORMAL SINGLE COOLER FLOW &
RETURN D COOLER OUTLET TEMP TO EXPECTED TEMPS.
Trgset 4 RNC3OI9C < 0.60 && RNC344IC < 0.99 && FT3OI3BB >12.0 Trg 4 imf FI3OI4B 3036 24 Trgset 5 RNC344IC < 0.50 && RNC3OI9D < 0.99 Trg 5 9MF TI3025C 100 93
>Trigger 6-8: Deletes all malfunctions inserted to restore NORMAL response for the ID Cnmt Cooler when 1 C Cnmt Cooler is isolated.
Trgset 6 RNC3OI9C <0.10 && RNC344IC <0.90 && FT3OI3BB> 12.0 Trg 6 IMF F13013B 3036 28 Trgset 7 RNC344ID <0.60 && RNC3OI9D <0.60 Trg 7 IMF F13014B 0 36 Trgset 8 RNC3OI9C < 0.40 && RNC3OI9D <0.80 && FT3OI4BB > 12.0 Trg 8 IMF FI3013B 0 32 When all flow is terminated, these triggers remove malfunctions on flow meters.
Trgset9 RNC3OI9C <0.1. && RNC3OI9D <0.1 Trg 9 DMF F13013B Trgset 10 RNC3441 D < 0.1. && RNC3441 C <0.1 Trg 10 DMF F13014B Trgset 11 RNC3OI9C <0.1. && RNC344ID <0.1 Trg 11 DMF F13013B
>If 1 C COOLER ISOLATED BEFORE 1 D IS ISOLATED, these triggers allow instruments to respond as modeled.
Trgset 12 RNC3OI9C < 0.1 && RNC344IC <0.1 && F13013B > 2800 && ft3Ol3bb> 10.0 Trg 12 DMF F13013B Trgset 13 RNC3OI9C < 0.1 && RNC344IC <0.1 && F13014B >2800 && ft3Ol3bb> 10.0 Trg 13 DMF F13014B SNP222
CONDITIONS When I tell you to begin, you are TO ISOLATE SW TO THE AFFECTED CTMT COOLER USING SOP-12.l SECTION 4.6 and VERIFY at least two OPERABLE Containment Coolers are running in SLOW speed.
The conditions under which this task is to be performed are:
- c. Both trains of Containment Spray are not available.
- d. FRP-Z.2, Response to Containment Flooding, has been implemented.
- f. ALL available Containment Fan Coolers are required due to a failure of both trains of Containment Spray.
- g. You have been directed to Isolate SW to B Train CTMT Coolers using SOP-12.1 section 4.6 and VERIFY at least two OPERABLE Containment Coolers are running in SLOW speed.
INITIATING CUE, You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME NOTE
- The procedure allows isolation of the coolers individually or together. The candidate may elect to isolate both coolers with one pass through the procedure or to isolate a single cooler and perform two passes through the procedure.
- The leak is located on the inlet piping of the 1 C containment Cooler, isolation of only the supply line (301 9C & D) will not terminate the leak from the discharge line (leaking check valve):
CRITICAL actions are to close:
o MOV3O19C & M0V3441C
- The indications will demonstrate that the leak is isolated if the following steps are completed on 1 C containment cooler first. IF the candidate reports this indication to the SS provide the following CUE: SS acknowledges, continue with task as directed.
(SOP-12.1 step 4.6.1)
- 1. For the affected CTMT cooler, close SW TO *CLOSE MOV-3019C & S / U CTMT CLR valve: CLOSE MOV-3019D SW TO 1C CTMT CLR Q1P16MOV3O19C Observes the green lights LIT SW TO 1D CTMT CLR Q1P16MOV3O19D
FNP HLT-34 SIMULATOR JPM E Page 5 of 8 (Guide pages = 7)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
(SOP-12.l step 4.6.2)
- 2. IF desired, THEN close SW FROM CTMT CLR on *CLOSE MOV-3441C & S / U the affected cooler: CLOSE MOV-344lD SW FROM IC CTMT CLR Q1P16MOV3441C Observes the green lights LIT SW FROM ID CTMT CLR Q1P16MOV3441D (SOP-12.1 step 4.6.3)
- 3. IF desired, THEN close, or verify closed, EMERG CLOSE MOV-3024C & S / U SW FROM CTMT CLR on the affected cooler. CLOSE MOV-3024D EMERG SW FROM 1C CTMT CLR Observes the green lights LIT Q1P16MOV3O24C EMERG SW FROM 1D CTMT CLR Q1P16MOV3O24D NOTE
- Element 4 & 5 are not required to be implemented for this task.
Containment cooler status is as it is due to:
- BOTH B train fans are running due to the OPERATORs completion of EEP-O attachment 2.
(SOP-12.1 step 4.6.4)
- 4. IF desired, THEN stop the affected CTMT cooler STOP 1C Containment Cooler S / U 1C containment cooler STOP 1D Containment Cooler 1D containment cooler Observes the green lights LIT (SOP-12.1 step 4.6.5)
- 5. IF stopped in the previous step, THEN check CHECK closed light LIT for S / U CTMT CLR DISCH CLOSED light illuminated: dampers:
CTMT CLR 1C DISCH 3186C 3186C CTMT CLR 1D DISCH 3186D 3186D Observes the green lights LIT NOTE Element 6 & 7 are not required to be implemented for this task, however the candidate may elect to do so as they are part of the procedure section.
(SOP-12.1 step 4.6.6)
- 6. IF required, THEN verify that an unaffected CTMT Not applicable, since Both B S / U cooler in that train is selected for auto-start: train CTMT Coolers have no lC containment cooler SW aligned and are not ID containment cooler operable.
FNP HLT-34 SIMULATOR JPM E Page 6 of 8 (Guide pages = 7)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
(SOP-12.1 step 4.6.7)
- 7. Refer to the following for operability requirements: Not applicable, since Both B S / U Technical Specifications SR 3.6.6.2 and SR 3.6.6.3 train CTMT Coolers have no FNP-1-STP-17.O, Containment Cooling System SW aligned and are not Train A(B) Operability Test operable. TS are not applicable during accident response.
CUE if required: Another operator will review these requirements NOTE
- Element 8 can be accomplished with or without SOP-12. If SOP-12 is used, the candidate may choose:
Partial Section 4.1 contains checking the SW valve status of the lB CTMT Cooler then starting the fan in SLOW speed at step 4.1.6, the remainder of this section is NOT completed.
Partial Section 4.7 in which only step 4.7.1.3 and 4.7.1.4 are completed.
- Element 8 will impact Diesel Generator Loading, and diesel MW loading should be checked prior to starting any additional loads on the diesel.
(SOP-12.1 step 4.7.1.3)
- 8. Start containment cooler fans in SLOW speed: START the lB containment S / U lB containment cooler fan cooler in SLOW speed.
Observes the red light LIT (SOP-12.1 step 4.7.1.4)
CTMT CLR lB DISCH 3186B Observes 31 86B red light LIT STOP TIME Terminate when lB ctmt cooler is running.
FNP HLT-34 SIMULATOR JPM E Page 7 of 8 (Guide pages = 7)
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. FNP-1-SOP-12.l, VER4O
- 2. KA: 022A2.05 RO 3.1 SRO 3.5 W/EO15EA1.1 RO 2.9 SRO 3.0 W/EO15EA2.2 RU 2.9 SRO 3.3 GENERAL TOOLS AND EOUIPMENT:
- 1. NONE Critical ELEMENT justification:
STEP Evaluation
- 1. CRITICAL for completion of the assigned task; Failing to close MOV-3019C will prevent isolation of the SW supply line leak into containment and result in continued FILL of Containment.
- 2. CRITICAL for completion of the assigned task; Failing to close MOV-3441C will prevent isolation of the SW leak into containment due to a leaking SW return line Check valve and result in continued FILL of Containment.
- 3. Not critical since this action will not isolate SW flow; this is a bypass valve to an MOV which is operated on the BOP.
- 4. Not critical since the fans are running and is not required to be secured for this condition.
- 5. Not critical since stopping the fans are not required in the previous step and is the fans are secured the dampers will close.
- 6. Not critical since Both B train coolers SW is isolated, this action is not required.
- 7. Not critical since this is an emergency response, this action is not yet required.
- 8. CRITICAL since this action is required to complete the required actions (TASK objective).
Failure to complete this action will leave only 1 CTMT cooler in operation with NO CTMT SPRAY pumps, under these conditions 2 CTMT coolers are required.
- 9. Not critical since there is no failure installed, this is a check step for normal operation.
COMMENTS:
FNP HLT-34 SIMULATOR JPM E. HANDOUT Pg 1 of I CONDITIONS en I tell you to begin, you are TO ISOLATE SW TO THE AFFECTED CTMT COOLER USING SOP-12.1 SECTION 4.6 and VERIFY at least two OPERABLE Containment Coolers are running in SLOW speed.
The conditions under which this task is to be performed are:
- c. Both trains of Containment Spray are not available.
- d. FRP-Z.2, Response to Containment Flooding, has been implemented.
- f. ALL available Containment Fan Coolers are required due to a failure of both trains of Containment Spray.
- g. You have been directed to Isolate SW to B Train CTMT Coolers using SOP-12.l section 4.6 and VERIFY at least two OPERABLE Containment Coolers are running in SLOW speed.
Prgcur Nimber Var U NIT I Farley Nuclear Plant FNP-1-SOP-22.0 65.0 Page Number 2/15/2011 15:30:17 AUXILIARY FEEDWATER SYSTEM 18 of 98 4.11.14 Close and lock lB MDAFWP RECIRC FCV BYPASS Q1N23VOO9B. LI 4.11.15 Independently Verify the following:
4.12 Operation of AFW Stop Valves CAUTION IF >10% RTP, then do not power up the AFW Stop Valves. (Reference SR 3.7.5.1.)
4.12.1 H the AFW stop valve(s) are powered down AND with SS concurrence, THEN, unlock and close the following breaker(s) as required: (Master Z key.)
- QIR17BKRFUU4 AFWTO 1ASG STOP VLV Qi N23MOV3350A
- Q1R17BKRFUU5 AFWTO1BSGSTOPVLV Qi N23M0V3350B
- QIRI7BKRFUI2 AFWTO IC SG STOP VLV Qi N23M0V3350C LI 4.12.2 Operate the following valves as necessary to support evolutions in progress:
- Q1N23MOV335OA, IASG STOP VLV
- QIN23MOV335OC, 10 SG STOP VLV CAUTION The AFW stop valves are required to be open with power removed when >10% RTP.
(Reference SR 3.7.5.1.)
4.12.3 When ready to return the AFW system to normal, verify open the following valves:
- QIN23MOV335OA, IASG STOP VLV
Procedure Number Farley Nuclear Plant FNP-1-SQP-12i 40.0 CONTAINMENT AIR COOLING SYSTEM Page Number 11of76 4.5 Refueling Water Surface Ventilation Operation NOTE The refueling water surface exhaust may be temporarily routed to a filtration system such as the containment pre-access filtration unit and/or portable filtration unit for ALARA purposes during refueling operations. However, the exhaust flow shall NOT be directed to the containment purge intake. (DCP 97-1 -9220) 4.5.1 Place refueling water surface ventilation in service as follows:
4.5.1.1 Start the refueling water surface exhaust fan 2. LI 4.5.1.2 Start the refueling water surface supply fan 1. LI 4.5.2 Remove the refueling water surface ventilation from service as follows:
4.5.2.1 Stop refueling water surface supply fan 1. LI 4.5.2.2 Stop refueling water surface exhaust fan 2. LI 4.6 Isolating and Restoring Service Water to Individual CTMT Coolers NOTES It is permissible to use both the inlet and outlet valves to isolate individual CTMT coolers.
Overpressure protection for the CTMT Coolers are provided by relief valves located inside CTMT.
See CR2009114121 Movats testing of CTMT CLR SW MOVs can be performed utilizing this section of the procedure AFTER the desired CTMT cooler has been isolated. This includes CTMT CLR MOVs 301 9A,B,C,D and MOVs 3023A,B,C,D.
4.6.1 For the affected CTMT cooler, close SW TO CTMT CLR valve:
4.6.1.1 SW TO IA CTMT CLR QIP16MOV3OI9A LI 4.6.1.2 SW TO IBCTMT CLR QIP16MOV3O19B LI 4.6.1.3 SW TO 1 C CTMT CLR Qi P1 6M0V301 9C LI 4.6.1.4 SW TO 1 D CTMT CLR Qi P1 6M0V301 9D LI 4.6.2 IF desired, THEN close SW FROM CTMT CLR on the affected cooler:
4.6.2.1 SW FROM 1A CTMT CLR QIP16MOV344IA 4.6.2.2 SW FROM lB CTMT CLR QIPI6MOV344IB 4.6.2.3 SW FROM 1C CTMT CLR QIPI6MOV3441C 4.6.2.4 SW FROM 1D CTMT CLR Q1PI6MOV3441D
Farley Nuclear Plant A Procedure Number Ver CONTAINMENT AIR COOLING SYSTEM Page Number 4.6.3 HZ desired, THEN close, or verify closed, EM ERG SW FROM CTMT CLR on the affected cooler.
4.6.3.1 EMERG SW FROM 1A CTMT CLR QIPI6MOV3O24A LI 4.6.3.2 EMERG SW FROM lB CTMT CLR Q1P16MOV3O24B LI 4.6.3.3 EMERG SW FROM ICCTMTCLRQ1P16MOV3O24C LI 4.6.3.4 EMERG SW FROM 1D CTMT CLR QIPI6MOV3O24D LI 4.6.4 HZ desired, THEN stop the affected CTMT cooler 4.6.4.1 1A containment cooler LI 4.6.4.2 1 B containment cooler LI 4.6.4.3 1C containment cooler LI 4.6.4.4 1 D containment cooler LI 4.6.5 jf stopped in the previous step, THEN check CTMT CLR DISCH CLOSED light illuminated:
4.6.5.1 CTMT CLR IA DISCH 3186A 4.6.5.2 CTMT CLR lB DISCH 3186B 4.6.5.3 CTMT CLR 1C DISCH 3186C 4.6.5.4 CTMT CLR 1D DISCH 3186D 4.6.6 required, THEN verify that an unaffected CTMT cooler in that train is selected for auto-start:
4.6.6.1 IA containment cooler 4.6.6.2 1 B containment cooler 4.6.6.3 1C containment cooler 4.6.6.4 1 D containment cooler 4.6.7 Refer to the following for operability requirements:
4.6.7.1 Technical Specifications SR 3.6.6.2 and SR 3.6.6.3 4.6.7.2 FNP-l-STP-17.O, Containment Cooling System Train A(B)
Operability Test LI
Farley Nuclear Plant CONTAINMENT AIR COOLING SYSTEM 4.6.8 WHEN it is desired to return the affected cooler to service, THEN perform the following:
4.6.8.1 Verify SW FROM CTMT CLR OPEN on the affected cooler:
4.6.8.1.1 SW FROM IA CTMT CLR QIPI6MOV344IA LI 4.6.8.1.2 SW FROM lB CTMT CLR QIP16MOV3441B LI 4.6.8.1.3 SW FROM IC CTMT CLR QIPI6MOV3441C LI 4.6.8.1.4 SW FROM ID CTMT CLR Q1P16MOV344ID LI 4.6.8.2 For the affected CTMT cooler, open SW TO CTMT CLR:
4.6.8.2.1 SW TO IA CTMT CLR QI PI6MOV3OI9A LI 4.6.8.2.2 SW TO I B CTMT CLR Qi P1 6MOV3OI 9B LI 4.6.8.2.3 SW TO 10 CTMT CLR QIP16MOV3O19C LI 4.6.8.2.4 SW TO 1 D CTMT CLR QI PI6MOV3O19D LI 4.6.8.3 HZ required, THEN start the affected CTMT cooler:
4.6.8.3.1 1A containment cooler LI 4.6.8.3.2 1 B containment cooler LI 4.6.8.3.3 10 containment cooler LI 4.6.8.3.4 1 D containment cooler LI 4.6.8.4 E started in the previous step, THEN check applicable CTMT CLR DISCH OPEN light illuminated:
4.6.8.4.1 CTMT CLR 1A DISCH 3186A 4.6.8.4.2 CTMT CLR lB DISCH 3186B 4.6.8.4.3 CTMT CLR IC DISCH 31860 4.6.8.4.4 CTMT CLR ID DISCH 3186D 4.7 Shifting Containment Cooling Fan Speeds 4.7.1 Containment Cooler Fans 4.7.1.1 Stop containment cooler fans as required:
4.7.1.1.1 1A containment cooler fan LI 4.7.1.1.2 lB containment cooler fan LI 4.7.1.1.3 10 containment cooler fan LI 4.7.1.1.4 ID containment cooler fan LI
Farley Nuclear Plant CONTAINMENT AIR COOLING SYSTEM 4.7.1.2 Check CTMT CLR DISCH CLOSED light illuminated for coolers shutdown:
4.7.1.2.1 CTMTCLR 1ADISCH 3186A LI 4.7.1.2.2 CTMT CLR lB DISCH 3186B LI 4.7.1.2.3 CTMT CLR IC DISCH 3186C LI 4.7.1.2.4 CTMT CLR 1D DISCH 3186D LI 4.7.1.3 Start containment cooler fans in SLOW (FAST) speed:
4.7.1.3.1 1A containment cooler fan 4.7.1.3.2 1 B containment cooler fan LI 4.7.1.3.3 1C containment cooler fan LI 4.7.1.3.4 1 D containment cooler fan 4.7.1.4 Check applicable CTMT CLR DISCH OPEN light illuminated:
4.7.1.4.1 CTMT CLR IA DISCH 3186A 4.7.1.4.2 CTMTCLR lB DISCH 3186B 4.7.1.4.3 CTMT CLR 1C DISCH 3186C 4.7.1.4.4 CTMT CLR 1D DISCH 3186D 4.7.2 Containment Dome Recirc Fans 4.7.2.1 Place CTMT DOME RECIRC FANS in HIGH (LOW) speed as necessary:
4.7.2.1.1 1A CTMT DOME RECIRC FAN 4.7.2.1.2 lB CTMT DOME RECIRC FAN 4.7.2.1.3 1C CTMT DOME RECIRC FAN 4.7.2.1.4 1D CTMT DOME RECIRC FAN
FNP HLT34 JPM Pagel ot7 SIMULATOR JPM F.
CRO-415A-modified TITLE: START THE 2C DIESEL GENERATOR EVALUATION LOCATION: l SIMULATOR El CONTROL ROOM El CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-223 El ALTERNATE PATH El TIME CRITICAL El PRA JPM DIRECTIONS:
- 1. The actions of this task will be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Conduct a Load Shed, start the 2C DG and start a minimum of one Service Water pump to provide cooling water to the 2C DG.
Examinee:
Overall JPM Performance: Satisfactory 1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Howard Fitzwater Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 SIMULATOR JPM F. Page 2af7 DESCRIPTION ACTION BUTTONS DETAILS Reset into IC 223 for JPM F Put OPS group on MCB CRT and acknowledge computer alarms Place Danger Tags on 2B DG MSS to mode 3
-DGO8-2 Run/ Freeze Simulator Acknowledge annunciators Turn Horns ON VERIFY CTMT COOLER selector aligned to A & C IC SETUP
- RST 187
- IC187 contains the
- following required malfunctions:
MAL-DSGOO7 cNCPswlEdcc 5 cNCPSW1Edcc6 cNCPSW1 Fdcc5 cNCPSW1Fdcc6 MAL-EPS1 MAL-RCS2A Place lB DG in MODE 3
- Modified setup Close the following to ensure the breakers to simulate a critical steps failure of the load shed are in fact sequencer: critical.
1A CCW pump 1D & 1E SW pumps lB RHR pump lB CS pump lB charging pump lB AEW pump
FNP HLT-34 SIMULATOR JPM F. Page 3 of 7 CONDITIONS When I tell you to begin, you are to START THE 2C DIESEL GENERATOR. The conditions under which this task is to be performed are:
- b. The lB Diesel Generator has experienced a start failure and could not be started.
- c. 2B DG is tagged out.
- d. You have been directed by the Shift Manager to restore power to the 1 G 41 60V emergency bus using AOP-5.1, starting at step 2.6.
- e. Plant conditions DO NOT permit a PRE-LUBE of 2C DG.
iNITIATING CUE, You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
- 1. (step 2.6) Only those items with a
- and S / U Verify load shed of major loads on 1G and 1J are BOLDED are critical and 4160V busses. handswitch required to be taken to off, reset or stop.
NOTE: Handswitches with OPEN indication will be taken to off, reset or stop.
The green light will need to be LIT for each of the components below.
As Found AS LEFT LIGHT LIT Light LIT
[] lB CCW PUMP B TRN BKR DGO5 OPEN green green
[1 1A CCW PUMP BKR DGO4 OPEN RED green
[] 1C SW PUMP B TRN BKR DLO5 OPEN green green
[1 1D SW PUMP BKR DL03 OPEN RED green
[1 1E SW PUMP BKR DLO4 OPEN RED green
[1 #4 RW PUMP BKR DJO3-1 OPEN green green
[] #5 RW PUMP BKR DJO4- 1 OPEN green green
[] 1A CRDM CLG FAN BKR EE13 OPEN green green
FNP HLT-34 SIMULATOR JPM P. P 4 Of 7 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
[1 lB Cs PUMP BKR DG11 OPEN RED green
[1 lB RHR PUMP BKR DGO9 OPEN RED green
[} lB CHG PUMP B TRN BKR DGO7 OPEN green green
[1 1C CHG PUMP BKR DGO6 OPEN RED green
[1 lB MDAFWP BKR DGIO OPEN RED green (step 2.7.1) If the SS asked,
- 2. Prelube of the DG is not required or expected Booth Cue: PRE-LUBE is not due to conditions provided, required.
(step 2.7.2) 2C DG MODE SELECTOR S I U
- 3. Verify 2C DG MODE SELECTOR SWITCH in SWITCH position CHECKED in MODE 1. MODE 1 position.
(step 2.7.3) 2C DG UNIT SELECTOR S / U
- 4. Place 2C DG UNIT SELECTOR SWITCH in SWITCH is PLACED in Unit 1 Unit 1. position.
- 5. (step 2.7.4) Calls Unit 2 or review initial S / U Verify open UNIT 2 SW TO/FROM DG BLDG conditions to check on status of
- B HDR Q2P16V518/536. Unit 2 MCB UNIT 2SW TO/FROM DG BLDG B HDR Q2P16V518/536 checked.
IF required, Booth CUE:
Q2P16V518/536 were open pre event, No indication available for these valves on Unit 2.
(step 2.7.5) V520/528 CHECKED OPEN, red S I U
- 6. Verify open 2C DIESEL GENERATOR SW light is LIT.
SUPP TO/FROM UNIT 2 Q1P16V520/528 (step 2.7.6) 2C DG DIESEL START S I U
- 7. When load shed completed, depress 2C DG pushbutton depressed.
DIESEL START pushbutton
FNP HLT-34 SIMULATOR JPM F. Pg 5 Of 7 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 2.7.7) Indications for verification that 2C S / U
(step 2.7.8) Indication for Unit 1 2C DG S / U
- 9. Verify Unit 1 2C DG OUTPUT BKR DJO6 OUTPUT BKR DJO6 CHECKED closes, and the red light is LIT.
(step 2.7.9) Indication for BKR DG13 S I U
- 10. Verify 1J 4160V bus tie to 1G 4160V bus BKR CHECKED and the red light is DGI3 closed. LIT.
(step 2.8) Indication for BKR DGO2 S / U
- 11. Verify 1 G 41 60V bus tie to 1 L 41 60V bus BKR CHECKED and the red light is DGO2 closed LIT.
Note: Only one SW pump is required to SATISFY THE CRITICAL PORTION of the below task to prevent DG overheating.
(step 2.9) *SEE NOTE ABOVE: S / U
1D 1E 1C And CHECK the red light is LIT, SW header pressure will rise.
(step 2.10) Indication for Q1P16V5 18/536 5 / U
Q1P16V518/536.
(step 2.11) Indications for Q1P16V5211529 S / U
- 14. Verify open 2C DIESEL GENERATOR SW checked and the red light is LIT.
SUPP TO/FROM UNIT 1 Q1P15V5211529.
TIME Terminate when at least one SW pump is running or candidate says the 2C DG is ready for loading.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP HLT-34 SIMULATOR PM F. Page 6 of 7 GENERAL
REFERENCES:
- 1. FNP-1-AOP-5.1, Version 9.0
- 2. KJAs: 064A4.06 RO-3.9 SRO-3.9 055EA1.02 RO-4.3 SRO-4.4 GENERAL TOOLS AND EOUIPMENT:
Critical ELEMENT justification:
ELEMENT Evaluation 1 Critical: Task completion: The
- steps are critical since these breakers are closed and this would result in a DG overload condition and possible damage if the DG was started with the breakers closed.
2-3 NOT Critical: The prelube is covered in the conditions as not required to be done and the MSS is already in Mode 1.
4 Critical: Task completion: to load the 2C DG on Unit 1 this has to be completed.
5-6 NOT Critical: These valves are in the proper position and if not checked result in no problem with the completion of the task.
7 Critical: Task completion: If the DG start PB was not depressed then the DG would not start and the task could not be completed.
8-11 NOT Critical: Completion of these steps is not critical since if not checked the task would be completed successfiully without them.
12 Critical: Task completion: Since there are no SW pumps running, the DG would eventually sustain damage if at least one SW pump was not started.
13-14 NOT Critical: These valves are in the proper position and if not checked result in no problem with the completion of the task.
COMMENTS:
FNPHLT-34 HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to START THE 2C DIESEL GENERATOR. The conditions under which this task is to be performed are:
- b. The lB Diesel Generator has experienced a start failure and could not be started.
- c. 2B DG is tagged out.
- d. You have been directed by the Shift Manager to restore power to the 1 G 41 60V emergency bus using AOP-5.1, starting at step 2.6.
- e. Plant conditions DO NOT permit a PRE-LUBE of 2C DG.
07/13/10 8:11:09 FNP-1-AOP-5.1 CONTINGENCY ELECTRICAL ALIGNMENTS Version 9.0 Step Action/Expected Response Response Not Obtained II I CAUTION: This step may affect both units. Consideration must be given to providing adequate electrical power to each unit.
NOTE: The intent of this step is to energize B train safeguards busses from 2C DG when lB DG has failed or is unavailable.
2 Align 2C DG to 1G 4160 V bus.
2.1 Verify open Unit 2 2C DG OUTPUT BKRDJO6.
2.2 Verify open lB S/U XFMR to 1G 4160 V bus BKR DGI5.
2.3 Verify open 1A S/U XFMR to IG 4160 V bus BKR DGO1.
2.4 Verify open lB DG OUTPUT BKR DGO8.
2.5 Place lB DG MODE SELECTOR SWITCH in MODE 3.
Step 2 continued on next page Page Completed Page 6 of 15
07/13/108:11:09 -
FNP-1-AOP-5.1 CONTiNGENCY ELECTRICAL ALIGNMENTS Version 9.0 Step Action/Expected Response Response Not Obtained 2.6 Verify load shed of major loads on 1G and lJ4l6OVbusses.
{] lB CCW PUMP B TRN BKR DGO5 open
[] 1A CCW PUMP BKR DGO4 open
[j ICSWPUMPBTRNBKRDLO5open
[] 1D SW PUMP BKR DLO3 open
[] 1E SW PUMP BKR DLO4 open
[] #4 RW PUMP BKR DJO3l open
[] #5 RW PUMP BKR DJO4-l open
[1 1A CRDM CLG FAN BKR EEI3 open
[j 1BCSPUMPBKRDGI1open
[] 1BRHRPUMPBKRDGO9open
[1 lB CHG PUMP B TRN BKR DGO7 open
[] 1CCHGPUMPBKRDGO6open
[] lB MDAFWP BKR DG1O open 2.7 Perform 2C DG SBO start as follows.
2.7.1 IF plant conditions permit, THEN prelube 2C DG, 3 minutes maximum.
2.7.2 Verify 2C DG MODE SELECTOR SWITCH in MODE 1.
2.7.3 Place 2C DG UNIT SELECTOR SWITCH in Unit 1.
CAUTION: The following steps assume Unit 2 Service Water system is unaffected by the loss of Unit 1 electrical power. IF Unit 2 Service Water is unavailable, THEN steps 2.7.6 through 2.11 must be completed expeditiously to ensure adequate DG cooling.
2.7.4 Verify open Unit 2SW TO/FROM DG BLDG B HDR Q2P16V518/536.
(Unit 2 MCB) 2.7.5 Verify open 2C DIESEL GENERATOR SW SUPP TO/FROM UNIT 2 Q1P16V520/528.
Step 2 continued on next page Page Completed Page 7 of 15
07/13/10 8:11:09 FNP-1-AOP-5.1 CONTINGENCY ELECTRICAL ALIGNMENTS Version 9.0 Step Action/Expected Response Response Not Obtained 2.7.6 WHEN load shed verified, THEN depress 2C DG DIESEL START pushbutton.
2.7.7 Verify 2C DG starts.
NOTE: The LOSP sequencer should run when breaker closes, if a Safety Injection signal is NQI present.
2.7.8 Verify Unit 1 2C DG OUTPUT BKR DJO6 closes.
2.7.9 Verify 1J 4160 V bus tie to 1G 4160 V bus BKR DG 13 closed.
2.8 Verify 1G 4160 Vbus tie to 1L 4160 V bus BKR DGO2 closed.
2.9 Start two SW PUMPS (1D, 1E, IC).
2.10 Verify open SW TO/FROM DG BLDG -
B HDR Q1P16V518/536. (Unit 1 MCB) 2.11 Verify open 2C DIESEL GENERATOR SW SUPP TO/FROM UMT 1 Q1P16V521/529.
Step 2 continued on next page Page Completed Page 8 ofl5
07/13/108:11:09 -
FNP-1-AOP-5.l CONTINGENCY ELECTRICAL ALIGNMENTS Version 9.0 Step Action/Expected Response Response Not Obtained II I CAUTION: Plant conditions may dictate the need to load the emergency diesel generators above the continuous load rating limit (i.e. 2.85 MW for small DGs, 4.075 MW for large DGs). Under these circumstances, diesel generator loading may be raised not to exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load rating limit (i.e. 3,1 MW for small DGs, 4.353 MW for large DG5). Diesel loading should be reduced within the diesel generator continuous load rating limit as soon as plant conditions allow.
NOTE: The DG is now ready for loading as directed by the Shift Supervisor.
2.12 Go to procedure and step in effect.
CAUTION: This step should not be performed when lG 4160 V bus is aligned to lB S/U XFMR. Step 6 provides guidance for cross connecting A train and B train safeguards busses to lB S/U XFMR.
NOTE: The intent of this step is to energize A train safeguards busses from 1 B S/U XFMR when B train safeguards busses have failed, are unavailable or are powered from diesel generators, and A train DGs are unavailable or unreliable.
3 Align lB S/U XFMR to iF 4160 V bus.
3.1 Verify open Unit 11 -2A DG OUTPUT BKR DFO8.
3.2 Verify open Unit 1 1C DG OUTPUT BKR DHO7.
Step 3 continued on next page Page Completed Page 9 of 15
Page 1 oIT SIMULATOR JPM G.
CRO-328B TITLE: Restore Instrument Air To Containment EVALUATION LOCATION: F1 SIMULATOR D CONTROL ROOM D CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: 1PM IC-224 I1 ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
- 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise.
TASK STANDARD: Upon successful completion of this 1PM, the examinee will:
- Power up the 1H Load Center and then align the BOP air valves to containment.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater I Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 SIMULATOR JPM G. Page 2 of 7 (Guide pages 6)
Simulator setup/operation DESCRIPTION ACTION BUTTONS DETAILS Reset into IC 224 for JPM G Put STA group on MCB CRT and acknowledge computer alarms Run! Freeze Simulator Acknowledge annunciators Turn Horns ON Provide ESP-l.2 complete through step 1.10 When directed: ROVER reports the CR:
PLACE the TTOS switch to OFF The B1F sequencer is Remote / R43 / Ioa-dsqOO7 / off reset.
And RESET the BIF ESF sequencer Remote! R43 /LOA-DSQOO I /
TRUE IC SETUP RST 146 IMF Mal-AuxiC 20 RUN Simulator Allow instr air line break in containmtent at 20%
to depressurize header until HV 3611/3885/3825 all close automatically.
DMF MAL-AUX1C FREEZE Simulator SNAP IC 224
FNP RLT-34 SIMULATOR JPM G. Page 3 of 7 (Guide pages = 6)
CONDITIONS When I tell you to begin, you are to RESTORE INSTRUMENT AIR TO CONTAiNMENT. The conditions under which this task is to be performed are:
- a. A Loss of Off-site Power and a Small Break LOCA have occurred on Unit 1.
- b. 4160V busses 1D and 1E are de-energized.
- c. You are directed by the Unit 1 Shift Supervisor to restore instrument air to containment using ESP- 1.2, Attachment 1 starting at Step 1.11.
- d. A pre-job brief is not required.
INITIATiNG CUE, You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
TIME NOTE: The CAUTION before step 1.11 states the air compressor will consume 0.16 MW and the examinee should check the load on the 1 -2A DG prior to taking the actions to start any air compressor. In this scenario, as soon as DHOI is closed the 1A air compressor will start.
- 1. (step 1.11.1) CHECKS 1 C air compressor S / U Verify the 1 C air compressor handswitch in green indicating light is LIT.
AUTO after START/RUN.
ATTEMPTS to start 1 C air compressor; handswitch positioned in RUN/START then back to AUTO.
- 2. (step 1.11.2) The 1 C air compressor will not S / U Verify 1 C air compressor started. start and the green light will remain LIT.
RNO column
- 3. (step 1.11 a) POSITIONS the iCair S / U Verify 1 C air compressor handswitch in OFF. compressor handswitch in OFF position
- 4. (step 1.11 b) CHECKS MLB1 1-1 and 11-1 S / U Verify SI is reset. not LIT.
FNP HtLT-34 SIMULATOR JPM G. Page 4 of 7 (Guide pages 6)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 5. (step 1.11 c. 1 through 3 and d) Call ROVER to reset the S / U Direct resetting B1F sequencer. sequencer per step 1.11 c. and d.
Simulator operator press the buttons to the right to accomplish step 1 1 1 c. and d.
Remote I R43 I 1oa-dsqOO7 / off Report to the CR that the B iF sequencer is reset.
Remote! R43 /LOA-DSQOO1/ TRUE
- 6. (stepl.llf) POSITIONS DF-13 SYNC S/U Place Breaker DF-l 3 Sync Switch in manual. SWITCH in the MANUAL POSITION. (The red light under the A Train synch scopes will illuminate)
- *CLOSES Breaker DF13.
- 7. (step 1.llg) S / U Close Breaker DF-13 Checks the red light is LIT.
1H 4160 bus AC potential lights are illuminated.
- 8. (stepl.llh) places DF-13 SYNC SWITCH S / U Place SYNCH SWITCH to OFF. in the OFF position.
NOTE: Element 9 contains two actions and ONLY Closing DHO 1 is Critical
- 9. (step 1.11 i) *CLOSES DHO1 and observes S / U Close breaker DHO1 and Verify breaker EGO-i the red light LIT closed. and CHECKS Breaker EGO2-1 Observes red light is LIT.
- 10. (step i.llj) CHECKS 1 A air compressor S/U Verify start of 1 A air compressor. AUTO starts and the red light is LIT.
FNP BLT-34 SIMULATOR JPM G. Page 5 of 7 (Guide pages 6)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 11. (step 1.12) CHECKS INST AIR PI-4004B S I U Check IA pressure> 85 psig indication checked to verify TA pressure is rising.
TAKES <2 mins to recover >85 psi 12.(step 1.13) CHECKS MLB-3 1-2 and it is S I U Check instrument air to containment. LIT and KD 1 is in alarm.
- MLB-3 1-2 NOT lit
- Annunciator KD 1 clear.
RNO column
Handswitch must be held until the red light is LIT.
- 14. (step 1.13 RNO) OPENS HV-3885 S / U Open TA to PENE RM valve HV-3885.
Handswitch must be held until the red light is LIT.
Handswitch must be held until the red light is LIT.
- 16. Inform Shift Supervisor that instrument air Shift Supervisor acknowledges. S / U is aligned to containment TIME Terminate when SS informed.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. FNP-l-ESP-1.2, Version 24.0
- 2. KIA: 065AA1.03 RO-2.9 SRO-3.1 GENERAL TOOLS AND EQUIPMENT:
FNP HLT-34 SIMULATOR JPM G. Page 6 of 7 (Guide pages = 6)
None Critical ELEMENT justification:
ELEMENT Evaluation 1-3 NOT Critical: The 1 C Air Compressor will not start and placing the Handswitch to OFF is not critical since it has no effect on the final outcome.
4 NOT Critical: the SI is reset from previous steps in the procedure so this will not be done.
5 Critical: Task completion: if the B1F sequencer is not reset then the breaker will not close on the EPB.
6 NOT Critical: Completion of this step permits closing of DF-13, if not completed Element 7 could not be completed. Chief examiner determined this element NOT critical.
7 Critical: Task completion: these steps have to be accomplished correctly to close DF- 13 to supply power to the air compressor.
8 NOT Critical: returning the sync switch back to the OFF position has no impact on the successful completion of the task.
9 Critical: DHO1 must be closed to restore power to the 1A Air compressor.
However, EGO-i remains closed on the load shed and no action is required.
10-1 1 NOT Critical: The 1A air compressor will automatically start and IA pressure will rise to> 85 psig.
12 NOT Critical: The MLB light is not LIT and the annunciator is in alarm, but if the student did not accomplish these tasks correctly and still opened the BOP valves the task would be completed sat.
13-15 Critical: Task completion: These three valves are required to be opened to accomplish the given task.
16 NOT Critical: to call CR is not critical.
COMMENTS:
FNP HLT-34 JPM G HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to RESTORE iNSTRUMENT AIR TO CONTAINMENT. The conditions under which this task is to be performed are:
- a. A Loss of Off-site Power and a Small Break LOCA have occurred on Unit 1.
- b. 4160V busses 1D and 1E are de-energized.
- c. You are directed by the Unit 1 Shift Supervisor to restore instrument air to containment using ESP- 1.2, Attachment 1 starting at Step 1.11.
- d. A pre-job brief is not required.
4/27/2011 16:04 FNP-l-ESP-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION Revision 24 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 CAUTION: To ensure adequate supply voltage to all class 1E loads and to meet short circuit analysis constraints, only one air compressor, 1C (preferred) or 1A, should be powered from the diesel generator. One air compressor will consume 0.16 MW of diesel generator load.
1.11 Verify lC air compressor in 1.11 Align 1A air compressor for service, service as follows.
1.11.1 Verify 1C air compressor a) Verify 1C air compressor handswitch in AUTO after handswitch in OFF.
START/RUN.
b) Verify SI - RESET.
1.11.2 Verify 1C air compressor started. [1 MLB-1 1-1 not lit
[1 MLB-l 11-1 not lit c) IF LOSP has occurred, THEN place ElF Sequencer Test Trip Override Switch (TTOS)in OFF:
- 1) Obtain ElF Sequencer TTOS key from SSS office.
- 2) Insert key into B1F Sequencer Test Trip Override Switch.
- 3) Place ElF Sequencer Test Trip Override Switch in OFF Step 1 continued on next page.
Page 4 of 7
4/27/2011 16:04 FNP-1-ESP-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION Revision 24 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 1 CAUTION: LE offsite power is lost after sequencer is reset, THEN manual actions may be required to restart safeguards equipment.
d) Reset ElF sequencer by depressing the ESS STOP RESET pushbutton on the sequencer panel.
(139 ft. AUX BLDG A train SWGR room) e) WHEN directed by FNP-O-SOP-38 .O-1-2A, THEN verify the ElF Sequencer Test Trip Override Switch is in the ON position with the key removed.
f) Place BKR DF13 SYNCH SWITCH in MAN.
g) Close BKR DF13 (iF 4160 V bus tie to 1H 4160 V bus).
h) Place BKR DF13 SYNCH SWITCH in OFF.
i) IF 1H 4160 V bus energized.
THEN energize 1G 600 V LC from normal supply.
[] BKR DHO1 closed
[] BKR EGO2-1 closed j) Start 1A AIR COMPRESSOR.
Step 1 continued on next page.
Page 5 of 7
4/27/2011 16:04 FNP-1-ESP-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION Revision 24 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 1.12 Check INST AIR PRESS P1 4004B 1.12 Perform the following.
- GREATER THAN 85 psig.
NOTE: The intent of this step is to regain control of critical air operated components including PORVs and atmospherics. Based on plant conditions and availability of manpower, the applicability, priority and performance of the following actions is at the discretion of the Shift Supervisor.
1.12.1 Restore air pressure.
- Verify proper air compressor operation using FNP-1-SOP-31.O, COMPRESSED AIR SYSTEM.
- IF 2C air compressor available.
THEN align 2C air compressor to Unit 1 using FNP-1-SOP-31.O, COMPRESSED AIR SYSTEM.
1.12.2 IF instrument air NOT restored, THEN align nitrogen supply to PORVs using FNP-1-SOP-62.1, BACK-UP AIR OR NITROGEN SUPPLY TO THE PRESSURIZER POWER OPERATED RELIEF VALVES.
1.12.3 IF instrument air NOT restored.
THEN align emergency air supply to atmospheric relief valves and/or TDAFWP using FNP-1-SOP-62.O, EMERGENCY AIR SYSTEM.
Step 1 continued on next page.
Page 6 of 7
4/27/2011 16:04 FNP-1-ESP-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION Revision 24 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 1.12.4 IF instrument air NOT restored because 10 600 V LC is deenergized, THEN energize 10 600 V LC from iF 600 V LC using FNP-i-SOP-36.3, 600, 480 AND 208/120 VOLT AC ELECTRICAL DISTRIBUTION SYSTEM.
1.12.5 WHEN instrument air pressure restored, THEN perform step 1.13.
1.12.6 Proceed to PROCEDURE STEPS, step 7.
1.13 Check instrument air to 1.13 Align instrument air to containment, containment. (BOP)
[] MLB-3 1-2 NOT lit [1 N1P19HV3825 open
[1 N1P19HV3885 open IA TO PENE RM PRESS LO
[1 Annunciator KD1 clear IA TO CTMT
[] 01P19HV3611 open
- END -
Page 7 of 7
FNP HLT-34 - -
- Page I of 6 SIMULATOR JPM H.
CRO-395D TITLE: Display Individual CETC Values EVALUATION LOCATION: II SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 7 M1N SIMULATOR IC NUMBER: IC-225 LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee may be given an opportunity to preview the task prior to entering the Simulator to lower the required time to conduct the task.
- 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise.
- 3. The provided CUEs may be used to validate correct performance of each ELEMENT.
STANDARD:
Report the value of the specified CETC as indicated by SOP-68.O.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
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HLT34 SIMULATOR JPM FT. Page 3 of 6 (Guide pages =5)
CONDITIONS When I tell you to begin, you are to OBTAIN THE VALUE OF THERMOCOUPLE J12. The conditions under which this task is to be performed are:
- a. The Integrated Plant Computer (IPC) is NOT available.
- b. You have been directed to obtain the value of thermocouple J12 per FNP-l-SOP-68.O.
TNITIATING CUE, You may begin.
NOTE TO EXAMINER: J12 ADDRESS IS IN TABLE 7, AND J12 IS IN CHANNEL A; a common error is that B train is manipulated during this task.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 4.6.2.1) Table 7 used to identifi CE 14 as S / U Determine the two digit address for thermocouple address point and is an A train J12 CETC.
- 2. (step 4.6.1 provides the guidance to set initial S / U conditions required by 4.6.2.2 this action may or may not be conducted prior to step 4.6.2.2 requires it: With CET portion of the TMAX/CET pushbutton TMAX/CET push-button illuminated...) depressed. To select CET mode of Place A train in CET operation.
AS found: TMAX mode 1st button push: CET Mode 2 button push: return to TMAX mode May be repeated until desired mode achieved.
- 3. (step 4.6.2.2) SUBMODE S / U pushbutton depressed Select display to CE 1st / 2nd until CE displayed.
AS found: HI St 1
button push: CE 2 button push: ALL rd 3
button push: return to HI mode May be repeated until desired mode achieved
HLT-34 IM(JLATOR JPM H. Page 4 Of 6 (Guide pages =5)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4. (step 4.6.2.3 and 4.6.2.4) SUBMODE ACK S / U Select display to CEOO pushbutton ALARM ACK depressed until submode portion of AS found: HI.
1St button SUBMODE push: CE. the pushbutton is 2 button push: ALL. 1st / 2nd rd 3
button push: return to HI. mode illuminated and not flashing, May be repeated until desired mode achieved SUBMODE 1st portion of the lst/2nd pushbutton is flashing.
- 5. (step 4.4.2.5) SUBMODE S / U Align display to read CE 10 Depress pushbutton 1st / 2nd until 1 appears in the tens digit.
- 6. (step 4.6.2.6) SUBMODE ACK S / U Align to select ones digit Depress ALARM ACK pushbutton.
- 7. (step 4.6.2.7) SUBMODE S / U Align display to read CE 14 Depress pushbutton 1st / 2nd until 4 is displayed in the ones digit. 1 st/2nd pushbutton depressed until CE 14 in monitor window.
- 8. (step4.6.2.8) SUBMODEACK S / U Determine value of J12 pushbutton ALARM ACK depressed.
STOP TIME
HLT-34 - SIMULATOR 1PM H. Page 5 of 6 (Guide pages =5)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
Terminate when the value for thermocouple J 12 is displayed. I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. FNP SOP-68.0 Revision 8.0
- 2. KIAs: 017A4.01 RO-3.8 SRO-4.1 GENERAL TOOLS AND EOUIPMENT:
None Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical since finding the correct value in the Table will be revealed at element 7; affect on the final outcome of the task will be captured at a later element (#7).
- 2. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 3. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 4. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 5. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 6. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 7. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
- 8. CRITICAL to accomplish the assigned TASKs objective
- This button has to be in the correct alignment to get the correct value for the thermocouple.
COMMENTS:
FNP HLT-34 JPM H HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to OBTAIN THE VALUE OF THERMOCOUPLE J12. The conditions under which this task is to be performed are:
- a. The Integrated Plant Computer (IPC) is NOT available.
- b. You have been directed to obtain the value of thermocouple J12 per FNP-1-SOP-68.O.
10/08110 IQ:27;35 - FNP.4 -SOP.-6&O June 22, 2009 Version 8.0 PARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP- 1 -SOP-68 .0 S
A F
E T
Y INADEQUATE CORE COOLiNG MONITORING SYSTEM R
E L
A T
E D
PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
J. L. Hunter (for Operations Manager Date Issued June 23. 2009
10108110 10:27;35 - FNP-1-SOP-68.Q TABLE OF CONTENTS Procedure Contains Number of Pages Body 10 Tablel 2 Table2 I Table3 2 Table4 2 Table5 1 Table6 1 Table7 2 Table8 1 Table9 4 Table 10 4 Sign-Off List A 1 Page 1 of 1 Version 8.0
10,108110 1027:35 - - - - FNP-1-SOP-68.0-FARLEY NUCLEAR PLANT UNIT 1 SYSTEM OPERATING PROCEDURE SOP-68.0 INADEQUATE CORE COOLING MONITORING SYSTEM 1.0 Purpose This procedure provides the Initial Conditions, Precautions and Limitations, and Instructions for Operation of the Inadequate Core Cooling Monitoring System (ICCMS).
Instructions are included in the following sections:
4.1 System Startup.
4.2 Lamp Test.
4.3 Alarm and Error Code Determination.
4.4 Reactor Vessel Range Selection and HJTC Individual Value Display.
4.5 Subcooled Margin Monitor Mode Selection and Individual Value Display.
4.6 Core Exit Thermocouple Monitor Mode Selection.
4.7 Processor Cabinet Front Panel Display Error Code Determination.
4.8 System Shutdown.
2.0 Initial Conditions NOTE: Indicate completion of asterisked steps by initialing procedure sign-off list FNP-1-SOP-68.OA.
- 2.1 1 20V AC Instrumentation Distribution system is aligned so that power is available to the A Train and B Train ICCMS.
3.0 Precaution and Limitations 3.1 The SYSTEM RESET push-button should only be used to initialize the system when placed in service.
- 1 - Version 8.0
10108/10 1O:27;a5 - FNP-1-SOP-6g.o 3.2 The normal display mode for the SMM is the CETC mode. This displays the margin to saturation (°F) using the highest core exit thermocouple (excluding upperhead) and the lowest pressure. The RTD mode displays the margin to saturation (°F) using the hottest reactor coolant system (RCS) RTD (Th or T) and the lowest pressure. The pressure inputs are from PT-402 and 403 and from PT-455 for A-train and PT-457 for B-train. A subcooled margin to saturation is displayed as a positive number and superheat is displayed as a negative number.
3.3 j any digital display or a REACTOR VESSEL LEVEL mimic LED starts flashing, THEN determine the cause of the alarm per section 4.3.
3.4 Ensure that the Inadequate Core Cooling Monitoring System cabinet cooling fans are operating when the system is in operation.
4.0 Instructions 4.1 System Startup NOTE: Indicate completion of asterisked steps by initialing procedure sign-off list FNP-1-SOP-68.OA.
- 4.1.1 Verify Maintenance has completed FNP-1-STP-300.0, INADEQUATE CORE COOLiNG MONITORING SYSTEM CALIBRATION (TRAIN A) and FNP-l-STP-301.0, INADEQUATE CORE COOLING MONITORING SYSTEM CALIBRATION (TRAIN B).
- 4, 1.2 Verify all circuit breakers in back of cabinet are ON and the system has been powered up for at least one hour.
- 4 1,3 Verify that the Heated Junction Thermocouple power controllers are producing an output as indicated by the amber light of each controller ON.
- 4 1.4 Verify the RUN light on the cabinet front panel is ON.
NOTE: In the following step, when the SYSTEM RESET push-button is depressed, the data link is disrupted.
- 4,1.5 Depress the SYSTEM RESET push-button.
Version 8.0
10102/10 10;27:35 - FNP-.1-SOP-68.0-NOTE: Error codes E33, E34 and E25-E31 should be present until the Reactor Coolant System fill and vent is complete.
- 4* 1.6 SUBMODE AC}fl Depress the ACK push-button on the HEATED ALARM ACK)
JUNCTION THERMOCOUPLE MONITOR, SUB COOLED MARGIN MONITOR and CORE EXIT THERMOCOUPLE MONITOR panels and verify no unexplained error codes are displayed.
- 4 1.7 Perform a lamp test on the HEATED JUNCTION THERMOCOUPLE MONITOR, SUB COOLED MARGIN MONITOR, CORE EXIT THERMOCOUPLE MONITOR and the FRONT PANEL DISPLAY per section 4.2.
- 4 1.8 Verify that all LEDs on the REACTOR VESSEL LEVEL mimic are illuminated and NOT flashing or that the reason for any flashing LED is known.
- 4 1.9 Verify all CETC, HJTC and SMM DISABLE/READOUT switches are in the NORMAL position or the reason for any switch in the disconnect position is known.
4.1 .10 Verify proper operation of REACTOR VESSEL LEVEL display per FNP-l-UOP-4.3, MID LOOP OPERATIONS, Appendixi during Reactor Coolant System fill and vent.
- 4 1.11 Verify upper portion of the HEAD/PLENUM push-button is illuminated on the HEATED JUNCTION THERMOCOUPLE MONITOR and the decimal point after the second digit is illuminated on the digital display.
- 4.1.12 Verify at least one channel of the SUB COOLED MARGIN MONITOR is in the CETC mode as indicated by the upper portion of the CETC/RTD push-button illuminated and that the decimal point after the second digit is illuminated on the digital display.
4.2 Lamp Test 4.2.1 Depress the HEAD/PLENUM push-button on the HEATED JUNCTION THERMOCOUPLE MONITOR twice within a two-second time period.
4.2.2 Verify each of the four digits cycles to display numbers from 0 to 9 in sequence.
Version 8.0
l0!Q8Il010i2735 - . . - - FNP-1-SOP-68.0 4.2.3 Depress the HEAD/PLENUM push-button once.
4.2.4 WHEN the display indicates --, THEN depress the HEAD/PLENUM push-button to exit the test mode.
4.2.5 Depress the TEST push-button on the processor cabinet front panel display.
4.2.6 Verify that two zeros are displayed with the tens digit flashing.
4.2.7 Depress the ACK push-button twice.
4.2.8 Verify each of the four digits cycles to display numbers from 0 to in sequence.
4.2.9 Depress the TEST push-button to exit the test mode.
4.2.10 Starting with the CETC portion of the CETC/RTD push-button backlighted, depress the CETC/RTD push-button on the SUB COOLED MARGIN MONITOR twice within a two-second time period.
4.2.11 Verify each of the four digits cycles to display numbers from 0 to 9 in sequence.
4.2.12 Depress the CETC/RTD push-button once.
4.2.13 WHEN the display indicates --, THEN depress the CETC/RTD push-button to exit the test mode.
4.2.14 Depress the TMAX/CET push-button on the CORE EXIT THERMOCOUPLE MONITOR to illuminate the CET portion of the push-button.
SUBMODE .
4.2.15 Depress the push-button until the digital display 1 st/2nd indicates CE (SUBMODE ACK 4.2.16 Depress the push-button three times.
ALARM ACK Version 8.0
10/08/10 10:27:35 FNP-l-SQP-6&0 4.2.17 Verify each of the four digits cycles to display numbers from no to 9 in sequence.
4.2.18 Depress the TMAX/CET push-button to exit the test mode.
4.3 Alarm and Error Code Determination NOTE: IF errors exist within the system which have been acknowledged, THEN the ACK (ALARM ACK) button will be lighted. Existing errors may be reviewed at any time by depressing the ACK (ALARM ACK) button.
4.3.1 IF the digital display on any monitor is flashing, THEN depress the ACK (ALARM ACK) push-button to display the error code(s).
4.3.2 Determine the cause of the error(s) from Table 1, 2 or 3 as appropriate and submit a DR to have the cause of the error corrected.
NOTE: Placing a DISABLE/READOUT switch for a HJTC input in the DISCONNECT position will cause the associated LED on the REACTOR VESSEL LEVEL mimic to flash in alternating red and green colors.
4.3.3 IF desired, THEN disable any failed input as follows:
4.3.3.1 Refer to Technical Specifications prior to disabling any inputs.
4.3.3.2 Using Table 10 to aid in identifying to failed input, disable the failed input by placing the associated switch on the CETC, HJTC or SMM DISABLE/READOUT panel to the DISCONNECT position.
4.3.3.3 Verify the expected response has been received.
4.3.3.4 IF desired. THEN request a tagging order be written for the disabled input placed in DISCONNECT in step 4.3.3.2.
4.4 Reactor Vessel Level Range Selection and HJTC Individual Value Display 4.4.1 Depress the HEAD/PLENUM push-button on the HEATED JUNCTION THERMOCOUPLE MONITOR until the desired range for digital display is illuminated. This has no effect on mimic display.
4.4.2 To determine individual thermocouple temperatures, sensor AT values or heater power, perform the following:
Version 8.0
10108/10 10;27;35 FNP-1-SOP-68.O 4.4.2.1 Depress the HEAD/PLENUM push-button twice within a two-second time period to enter the lamp test mode.
4.4.2.2 Depress the HEAD/PLENUM push-button once more to enter the individual value display mode. Item numbers corresponding to individual sensor inputs or calculated values as listed in Table 4 will be displayed sequentially.
4.4.2.3 WHEN the item number corresponding to the desired input or calculated value from Table 4 is displayed, THEN depress the HEAD/PLENUM push-button again to display the value.
4.4.2.4 Depressing the HEAD/PLENUM push-button again will return to the sequential display of item numbers.
4.4.2.5 WHEN the digital display indicates --, THEN depress the HEAD/PLENUM push-button to exit the individual value display mode.
4.5 SUB COOLED MARGIN MONITOR Mode Selection and Individual Value Display.
NOTE:
- In the CETC mode, the SUB COOLED MARGIN MONITOR displays RCS subcooling calculated using core exit thermocouples excluding the upper head inputs. This is the mode required for use in the Emergency Response Procedures.
- Subcooling is displayed as positive (+) values and superheat is displayed as negative (-) values.
4.5.1 Depress the CETC/RTD push-button on the SUB COOLED MARGIN MONITOR until the desired mode of display is illuminated.
NOTE:
- An internal timer will automatically cause the system to exit the individual display mode after a period of three minutes in which no operator entries are made. The only exception to this is Item 16 which will display subcooling based upon the hottest core exit or upper head thermocouple until the operator returns to a normal display mode.
- The individual value display mode is indicated by the decimal point at the far right of the display flashing.
4.5.2 To detennine the value of individual inputs into the SUB COOLED MARGIN MONITOR or the results of calculations performed by system, perform the following.
Version 8.0
10/08110 10:27:35 - FNP-1-SOP-6g.0 4.5.2.1 Verify the CETC portion of the CETC/RTD push-button is illuminated.
4.5.2.2 Depress the CETC/RTD push-button twice within a two-second time period to enter the lamp test mode.
4.5.2.3 Depress the CETC/RTD push-button once more to enter the individual value display mode. Item numbers corresponding to individual sensor inputs or calculated values as listed in Table 5 will be displayed sequentially.
4.5.2.4 WHEN the item number corresponding to the desired input from Table 5 is displayed, THEN depress the CETC/RTD push-button to display the current value.
4.5.2.5 Depressing the CETC/RTD push-button again will return to the sequential display of item numbers for selection.
4.5.2.6 WHEN the digital display indicates i--, THEN depress the CETC/RTD push-button to exit the individual value display mode.
4.6 CORE EXIT THERMOCOUPLE MONITOR Mode Selection NOTE:
- The TMAX mode of operation continuously displays the maximum thermocouple temperature in the associated channel.
- The CET mode of operation allows selection of one of three submodes for display of individual core exit or upper head thermocouple temperatures.
4.6.1 To select mode of operation, depress the TMAX!CET push-button on the CORE EXIT THERMOCOUPLE MONITOR until the portion of the push-button corresponding to the desired mode is illuminated.
Version 8.0
1OJQ&lQ 10:27:35 - FNP-l-SOP-68.O 4.6.2 To display individual core exit thermocouple values, perform the following:
NOTE: The CET mode of operation has three submodes for display of core exit thermocouple data. An internal timer will automatically return the system to the TMAX mode after three minutes if no operator entries are made. The decimal point at the far right of the display will flash when in any CET submode.
The data displayed by each submode is as follows:
- - allows the operator to display the highest or next highest thermocouple temperature in a quadrant. Refer to Table 6 for display addresses.
- CE_ allows individual thermocouple temperatures to be displayed. Refer to Table 7 for input addresses corresponding to specific core locations.
- ALL_ Displays the highest and next highest thermocouple temperature per quadrant and the individual thermocouple temperatures sequentially. In this submode, the monitor will display an identifier from Table 6 or 7 for two seconds followed by the value for five seconds in sequence.
4.6.2.1 Find the two digit address for the desired parameter from Table 6 or 7 as appropriate.
4.6.2.2 With the CET portion of the TMAX/CET push-button SUBMODE illuminated, depress the push-button until the I st/2nd desired submode as described above is displayed.
4.6.2.3 WHEN the desired submode is displayed, THEN depress SUBMODEACK the push-button and verif the ALARM ACK SUBMODE SUBMODE portion of the push-button is 1 st/2nd illuminated and NOT flashing.
Version 8.0
10/08/10 1027:35 FNP-1-SOP--6&Q NOTE: In the ALL submode, the display will start to automatically sequence through SUBMODE ACK all quadrant and core exit temperature values as soon as the ALARM ACK push-button is depressed. Therefore steps 4.6.2.4 4.6.2.9 do not apply to this submode.
4.6.2.4 In the CE or HI submode, verify the 1st portion of the SUBMODE push-button is flashing.
1 st/2nd SUBMODE 4.6.2.5 Depress the push-button until the tens digit 1 st/2nd corresponds to the desired address.
SUBMODE ACK 4.6.2.6 Depress the push-button and verify the ALARM ACK SUBMODE 1st portion of the push-button is illuminated 1 st/2nd and NOT flashing and that the 2nd portion starts flashing.
SUBMODE 4.6.2.7 Depress the push-button until the ones digit 1 st/2nd corresponds to the desired address.
SUBMODE ACK 4.6.2.8 Depress the push-button and verify that ALARM ACK SUBMODE the 2nd portion of the push-button is I st/2nd illuminated and NOT flashing. The current value of the desired parameter is now displayed.
4.6.2.9 To select another parameter address depress the SUBMODE push-button and repeat steps 4.6.2.4 4.6.2.8.
1 st/2nd 4.6.2.10 To exit the CET mode, depress the TMAX/CET push button until the TMAX portion is illuminated.
4.7 Processor Cabinet Front Panel Display Error Code Determination Version 8.0
10108/10 1027:35 - - FNP-1-SOP-6g.0 4.7.1 Depress the TEST push-button on the front panel display. The display should display 00 with tens digit flashing.
4.7.2 Select test 01 to review hardware error codes or test 14 to review failed input errors as follows:
4.7.2.1 Depress the RTD!TMAX push-button to select the desired value for the tens digit.
4.7.2.2 Depress the ACK push-button. The tens digit will stop flashing and the ones digit will start to flash.
4.7.2.3 Depress the RTD/TMAX push-button to select the desired value for the ones digit.
4.7.2.4 Depress the ACK push-button to start the desired error code display.
4.7.3 Determine the cause of any errors by using Tables 8 and 9 for hardware and input errors respectively. IF no errors exist, THEN the display will indicate 0. IF errors do exist, THEN error codes will be displayed sequentially and will continue to cycle until the operator exits the test mode.
4.7.4 IF it is desired to change the selected test number, THEN depress the ACK push-button and select the new test number per step 4.7.2.
4.7.5 WHEN it is desired to exit the test mode, THEN depress the TEST push-button.
4.7.6 Initiate CRs as necessary to correct cause of alarms.
4.8 System Shutdown.
4.8.1 Turn off all circuit breakers in the back of the processor cabinet.
5.0 References 5.1 U-2 17312 Inadequate Core Cooling Monitoring System Users Guide.
5.2 U-263686 Inadequate Core Cooling Monitoring System Technical Manual Volume II, Electronics.
Version8.0
tO/0811D l02735 - - TABLE-I - FNP-1-SOP-68.0 HJTC DISPLAY ERROR CODES NOTE: IF an HJTC input is disconnected by the ICCMS monitoring panel, the signal is set to high out-of-range, THEN the error number will change from EXX to ELXX indicating that HJTC input XX has been eliminated and the associated LED on the Reactor Vessel Level mimic will flash in alternating red and green colors.
ERROR NUMBER DESCRIPTION E0 ICCMS Hardware Error El HJTC Input 1 (THI) Open or Shorted E2 HJTC Input 2 (T
) Open or Shorted 1
E3 HJTC Input 3 (TH2) Open or Shorted E4 HJTC Input 4 (T
) Open or Shorted 2
E5 HJTC Input 5 (TH3) Open or Shorted E6 HJTC Input 6 (T
) Open or Shorted 3
E7 HJTC Input 7 (TH4) Open or Shorted E8 HJTC Input 8 (T
) Open or Shorted 4
E9 HJTC Input 9 (Trn) Open or Shorted El 0 HJTC Input 10 (T
) Open or Shorted 5
Eli HJTC Input 11 (TH6) Open or Shorted El 2 HJTC Input 12 (T
) Open or Shorted 6
El 3 HJTC Input 13 (T
) Open or Shorted 117 E14 HJTC Input 14 (T
) Open or Shorted 7
El 5 HJTC Input 15 (TH8) Open or Shorted E16 HJTC Input 16 (T
) Open or Shorted 18 Page 1 of 2 Version 8.0
10108110 10:2735 - - 1ABLE-1 FNP-1-.SOP-6g.O HJTC DISPLAY ERROR CODES ERROR NUMBER DESCRIPTION E17 1 Low (<25°F)*
AT E18 2 Low (<25°F)*
AT E19 3 Low (<25°F)*
AT E20 4 Low (<25°F)*
AT E21 5 Low (<25°F)*
AT E22 6 Low (<25°F)*
AT E23 7 Low (<25°F)*
AT E24 8 Low (<25°F)*
AT E25 High AT 1 (200°F) or High T 1 (700°F)
E26 High AT 2 (200°F) or High T 2 (700°F)
E27 3 (200°F) or High T High AT 3 (700°F)
E28 High AT 4 (200°F) or High T 4 (700°F)
E29 High AT 5 (200°F) or High T 5 (700°F)
E30 High AT 6 (200°F) or High T 6 (700°F)
E3 1 7 (200°F) or High Tu High AT 7 (700°F)
E32 High AT 8 (200°F) or High T 8 (700°F)
E33 Head Level below 100%
E34 Plenum Level Below 100%
E35 2 Top HJTC Sensors Failed (No Head Level Indication)
Ii the AT calculation is failed due to an input failure, THEN the error numbers will change from El 7 thru E24 to EL 17 thru EL24.
Page 2 of 2 Version 8.0
10/08/10 10:27:35 - - TABLE-2 - FNP-1-SOP-68.0 SUB COOLED MARGIN MONITOR (SMM) DISPLAY ERROR CODES NOTE:
- IF a SMM Input is disconnected by the ICCMS Monitoring Panel or the signal is set up to high out-of-range, THEN the error number will change from EXX to ELXX indicating that SMM Input XX has been eliminated.
The highest of the RCS hot or cold leg temperatures are used for Saturation Margin Calculations in the RTD mode. j 2 of the 3 hot leg inputs are failed, THEN RTD saturation margin is failed (E14).
ERROR NUMBER DESCRIPTION E0 ICCMS Hardware Error El RCS Loop 1 Cold Leg low out of range E2 RCS Loop I Hot Leg low out of range E3 RCS Loop 2 Cold Leg low out of range E4 RCS Loop 2 Hot Leg low out of range E5 RCS Loop 3 Cold Leg low out of range E6 RCS Loop 3 Hot Leg low out of range E7 RCS Loop 1 Pressure PT-403 low out of range E8 RCS Loop 3 Pressure PT-402 low out of range E9 Pressurizer Pressure Train A(B) PT-455 (P1-457) low out of range ElO Spare SMM Input Eli Spare SMM Input E12 Spare SMM Input El 3 Less than 8 Valid CETC Temperatures (CETC Margin Failed)
E14 Only one Valid RCS Temperature (RID Margin Failed)
E15 CETC, UpperheadlCETC, or RTD Temperature margin Alaim
(<10°F subcooled RTD margin or> 10°F superheated CETC margin)
Page 1 of 1 Version 8.0
10108,110 10;27;3-5 - TABLE-3 - FNP-1--SOP--68.O CORE EXIT THERMOCOUPLE MONITOR (CETC) DISPLAY ERROR CODES NOTE:
- fl a CETC Input is disconnected by the ICCMS monitoring panel OR the signal is set to high out-of-range, THEN the error number will change from EXX to ELXX indicating that CETC input XX has been eliminated.
- A tag inside the door of the ICCMS cabinet gives the CETC tag number corresponding to the ICCMS Monitoring Panel identification. Table 7 also gives tag and core identification.
ERROR NUMBER DESCRIPTION E0 ICCMS Hardware Error El CETC Input 1 Shorted or Open E2 CETC Input 2 Shorted or Open E3 CETC Input 3 Shorted or Open E4 CETC Input 4 Shorted or Open E5 CETC Input 5 Shorted or Open E6 CETC Input 6 Shorted or Open E7 CETC Input 7 Shorted or Open E8 CETC Input 8 Shorted or Open E9 CETC Input 9 Shorted or Open El 0 CETC Input 10 Shorted or Open Eli CETC Input ii Shorted or Open El 2 CETC Input 12 Shorted or Open E13 CETC Input 13 Shorted or Open E14 CETC Input 14 Shorted or Open Page 1 of 2 Version 8.0
10/08/10 10:27:35 - - TALE-3 FNP-1-SOP-68.0 CORE EXIT THERMOCOUPLE MONITOR (CETC) DISPLAY ERROR CODES ERROR NUMBER DESCRIPTION El 5 CETC Input 15 Shorted or Open E16 CETC Input 16 Shorted or Open E17 CETC Input 17 Shorted or Open El 8 CETC Input 18 Shorted or Open E19 CETC Input 19 Shorted or Open E20 CETC Input 20 Shorted or Open E21 CETC Input 21 Shorted or Open E22 CETC Input 22 Shorted or Open E23 CETC Input 23 Shorted or Open E24 CETC Input 24 Shorted or Open E25 CETC Input 25 Shorted or Open E26 CETC Input 26 Shorted or Open (Spare on Channel B)
E27 CETC Input 27 Shorted or Open (Spare)
E28 CETC Input 28 Shorted or Open (Spare)
E29 CETC Input 29 Shorted or Open (Spare)
E30 CETC Input 30 Shorted or Open (Spare)
E3 1 CETC Input 31 Shorted or Open (Spare)
E32 CETC Input 32 Shorted or Open (Spare)
E33 One or more CETC Temperatures above 700°F E34 Less than 8 Valid CETCs (CETC margin and TMAX Failed)
Page 2 of 2 Version 8.0
1WO8!1O 10:27:35 - PABLE-4 - FNP-1-SOP-68.O HJTC INDIVIDUAL VALUE DISPLAYS NOTE: The HJTC display will automatically exit the individual value display mode aftel three (3) minutes if no further inputs are made by the operator. I ITEM NUMBER DESCRIPTION UNITS
-- Exits Lamp Test/Individual Value Display O Lamp Test °F 1 HJTC Input I - TH1 2 HJTC Input 2 Tu
- 1 3 HJTC Input 3 - TH2 °F 4 HJTC Input 4 Tu, 5 HJTC Input 5 - TH3 °F 6 HJTC Input 6 T
- 3 7 HJTC Input 7 - TH4 °F 8 HJTC Input 8 Tu
- 4 9 HJTC Input 9 - THS °F 10 HJTC Input 10 T- 5 11 HJTC Input 11- TH6 12 HJTC Input 12 Tu
- 6 13 HJTC Input 13 TH7 °F 14 HJTC Input 14 Tu
- 7 °F 15 HJTC Input 15 - TH8 °F 16 HJTC Input 16 Tu
- 8 °F 17 ) Differential Temperature 1 1
(T Page 1 of 2 Version 8.0
1W08110 IO:2735 - 3EABLE-4 - FNP-l-SOP-68.0 HJTC INDIVIDUAL VALUE DISPLAYS ITEM NUMBER DESCRIPTION UNITS 18 ) Differential Temperature 2 2
(AT °F 19 ) Differential Temperature 3 3
(AT °F 20 ) Differential Temperature 4 4
(AT 21 ) Differential Temperature 5 5
(AT °F 22 ) Differential Temperature 6 6
(AT °F 23 ) Differential Temperature 7 7
(AT 24 (ATS) Differential Temperature 8 °F 25 Heater Power 1 %
26 Heater Power 2 %
Page 2 of 2 Version 8.0
- 10/08/10 I027:35 - !fABLE5 - FNP-I-SOP-68.O SUB COOLED MARGIN MONITOR (SMM) DISPLAY INDIVIDUAL VALUE DISPLAY CHANNELS NOTE: The SMM channel will automatically exit the individual value display mode after three (3) minutes of inactivity with the exception of item 16. The individual value display mode is indicated by the decimal point at the far right of the digital display flashing.
ITEM NUMBER DESCRIPTION Units 0 Lamp Test 1 RCS Loop 1 Cold Leg °F 2 RCS Loop 1 Hot Leg °F 3 RCS Loop 2 Cold Leg °F 4 RCS Loop 2 Hot Leg 5 RCS Loop 3 Cold Leg °F 6 RCS Loop 3 Hot Leg °F 7 RCS Loop 1 Pressure PT-403 Psig 8 RCS Loop 3 Pressure PT-402 Psig 9 Pressurizer Pressure Train A(B) PT-455 (PT-457) Psig 10 Spare N/A 11 Spare N/A 12 Spare N/A 13 RCS Pressure Margin PSI 14 CETC Pressure Margin PSI 15 Upper Head/CETC Pressure Margin PSI 16 Upper Head/CETC Temperature Margin °F (uses hottest upper head or core exit temperature)
EXIT Test Mode Page 1 of 1 Version 8.0
IOiO8/1O 1Q:27-35 - fABLFi6 - FNP-l-SOP-68.O CORE EXIT THERMOCOUPLE MONITOR DISPLAY HI SUBMODE ADDRESS DESCRIPTION Hi 1 Highest CETC in Quadrant 1 H12 Next highest CETC in Quadrant 1 H21 Highest CETC in Quadrant 2 H22 Next highest CETC in Quadrant 2 H3 1 Highest CETC in Quadrant 3 H32 Next highest CETC in Quadrant 3 H41 Highest CETC in Quadrant 4 H42 Next highest CETC in Quadrant 4 Page 1 of 1 Version 8.0
10108/10 1027:35 - fABLE-7 - FNP-l-SOP-68.
CORE EXIT THERMOCOUPLE MONITOR DISPLAY CE SUBMODE FARLEY UNIT 1 NOTE:
- In the core location and tag number columns CHA and CHB mean Channel A and Channel B respectively. The last 2 digits of the instrument tag (computer point) number are shown in the tag number column. The remainder of the instrument tag (computer point) number information for both A and B channels is GOO--B; where are the numbers listed in the tag number column.
ADDRESS CORE LOCATION DESCRIPTION TAG NUMBER UNITS CHA CHB CHA CHB CEOO -- Lamp Test CEO1 A8 BlO CETC Input 1 01 03 °F CEO2 B5 E9* CETC Input 2 02 06 °F CEO3 E4 B12* CETC Input 3 04 07 CEO4 E9* Gi CETC Input 4 05 12 °F CEO5 F3 K3 CETC Input 5 08 19 °F CEO6 F5 G9* CETC Input 6 09 21 °F CEO7 E9* C8 CETC Input 7 10 27 °F CEO8 Fl 1 D3 CETC Input 8 11 29 °F CEO9 H7* D5 CETC Input 9 13 30 CE1O H8 E8 CETC Input 10 14 31 °F CEll H15 ElO CETCInputil 15 32 °F CE12 J2 L7* CETC Input 12 16 34 °F Page 1 of 2 Version 8.0
10/08/10 l0:2735 - FABLE-7 FNP=l=SOP68.0 CORE EXIT THERMOCOUPLE MONITOR DISPLAY CE SUBMODE ADDRESS CORE LOCATION DESCRIPTION TAG NUMBER UNITS CHA CHB CHA CHB CE13 J10 G8 CETC Input 13 17 35 °F CE14 J12 G15 CETCInputl4 18 36 CE15 L7* H3 CETC Input 15 20 37 CE16 E9* H5 CETC Input 16 22 38 CE17 L7* H9 CETC Input 17 23 39 °F CE18 N6 Hi 1 CETC Input 18 24 40 °F CE19 P8 H13 CETCInputl9 25 41 °F CE2O R7 L6 CETC Input 20 26 42 °F CE21 C12 L8 CETC Input 21 28 43 CE22 F13 L12 CETC Input 22 33 44 °F CE23 Ml 1 L14 CETC Input 23 47 45 °F CE24 L7* M3 CETC Input 24 48 46 °F CE25 N8 N10 CETC Input 25 49 50 °F CE26 M5 * -- CETC Input 26 51 °F CE27 -- Spare CETC Input 27 °F CE28 -- Spare CETC Input 28 °F CE29 -- Spare CETC Input 29 °F CE3O -- Spare CETC Input 30 °F CE3 1 -- Spare CETC Input 31 °F CE32 Spare CETC Input 32
- Upperhead Thermocouple Page 2 of 2 Version 8.0
10/08110 10:27:35 - FABLE-8 - FNP-l-SOP-68.0 PROCESSOR CABINET FRONT PANEL DISPLAY ICCMS HARDWARE ERROR CODES ERROR NUMBER DESCRIPTION E77 Card Cage Area of Chassis Overheating E78 Power Supply Area of Chassis Overheating E79 AID Converter #1 Failed E80 AID Converter #2 Failed E8 1 Loss of Heater Power E82 Data Link Out of Service E83 80/24 or 1 16A Board ROM Error E84 80/24 or 1 16A Board RAM Error E85 Top 2 sensors Failed (No Head Level Indication)
E86 All But One Valid RCS Temperature Failed (RCS Saturation Margin Failed)
E87 Less Than 8 Valid CETCs (CETC Saturation Margin, and TMAX Failed)
Page 1 of 1 Version 8.0
10/08/10 10:27:35 - FABLE-9 - FNP-l-SOP-68.O PROCESSOR CABINET FRONT PANEL DISPLAY FAILED INPUT ERROR CODES NOTE:
- jj an input is disconnected by the ICCMS monitoring panel OR high out of range, THEN the error number will change from EXX to ELXX indicating that input XX has been disconnected.
ERROR NUMBER DESCRIPTION El CETC-1 Shorted or Open E2 CETC-2 Shorted or Open E3 CETC-3 Shorted or Open E4 CETC-4 Shorted or Open E5 CETC-5 Shorted or Open E6 CETC-6 Shorted or Open E7 CETC-7 Shorted or Open E8 CETC-8 Shorted or Open E9 CETC-9 Shorted or Open ElO CETC-l0 Shorted or Open Eli CETC-l 1 Shorted or Open E12 CETC-12 Shorted or Open E13 CETC-13 Shorted or Open E14 CETC-14 Shorted or Open El 5 CETC-1 5 Shorted or Open E16 CETC-16 Shorted or Open E17 CETC-17 Shorted or Open Page 1 of 4 Version 8.0
10/08/10 1O:27:35 - FAHLE-9 - FNP-l-SOP-68.0 PROCESSOR CABiNET FRONT PANEL DISPLAY FAILED INPUT ERROR CODES ERROR NUMBER DESCRIPTION E18 CETC-18 Shorted or Open E19 CETC-19 Shorted or Open E20 CETC-20 Shorted or Open E21 CETC-21 Shorted or Open E22 CETC-22 Shorted or Open E23 CETC23 Shorted or Open E24 CETC-24 Shorted or Open E25 CETC-25 Shorted or Open E26 CETC-26 Shorted or Open (Spare in Channel B)
E27 CETC-27 Shorted or Open (Spare)
E28 CETC-28 Shorted or Open (Spare)
E29 CETC-29 Shorted or Open (Spare)
E30 CETC-30 Shorted or Open (Spare)
E3 1 CETC-3 1 Shorted or Open (Spare)
E32 CETC-32 Shorted or Open (Spare)
E33 HJTC-1 (THI) Shorted or Open E34 HJTC-2 (T
) Shorted or Open 1
E35 HJTC-3 (TH2) Shorted or Open E36 HJTC-4 (T
) Shorted or Open 2
E37 HJTC-5 (Tm) Shorted or Open E38 HJTC-6 (T
) Shorted or Open 3
Page 2 of 4 Version 8.0
IOIO8II&IO:2735 - fABLE-9 - FNP-I-S&P-68.O PROCESSOR CABiNET FRONT PANEL DISPLAY FAILED INPUT ERROR CODES ERROR NUMBER DESCRiPTION E39 HJTC-7 (TH4) Shorted or Open E40 HJTC-8 (Tu
) Shorted or Open 4
E41 HJTC-9 (TH5) Shorted or Open E42 HJTC- 10 (Tu
) Shorted or Open 5
E43 HJTC- 11 (T
) Shorted or Open 6
E44 HJTC- 12 (T
) Shorted or Open 6
E45 HJTC- 13 (T
) Shorted or Open 117 E46 HJTC- 14 (Tu
) Shorted or Open 7
E47 HJTC- 15 (TH8) Shorted or Open E48 HJTC- 16 (Tu
) Shorted or Open 8
E49 SMM-i Low Out of Range E50 SMM-2 Low Out of Range ES 1 SMM-3 Low Out of Range E52 SMM-4 Low Out of Range E53 SMM5 Low Out of Range E54 SMM-6 Low Out of Range E55 SMM-7 Low Out of Range E56 SMM-8 Low Out of Range E57 SMM-9 Low Out of Range E58 SMM-10 Low Out of Range (Spare)
E59 SMM- 11 Low Out of Range (Spare)
Page 3 of 4 Version 8.0
10108/10 1O2-7:35 - fABLE-9 - FNP-1-SQP-68.0 PROCESSOR CABINET FRONT PANEL DISPLAY FAILED INPUT ERROR CODES ERROR NUMBER DESCRIPTION E60 SMM- 12 Low Out of Range (Spare)
E61 Differential Temperature 1 (AT
) Low (<25°F) 1 E62 Differential Temperature 2 (AT
) Low (<25°F) 2 E63 Differential Temperature 3 (AT
) Low (<25°F) 3 E64 Differential Temperature 4 (AT
) Low (<25°F) 4 E65 Differential Temperature 5 (AT
) Low (<25°F) 5 E66 Differential Temperature 6 (AT
) Low (<25°F) 6 E67 Differential Temperature 7 (AT
) Low (<25°F) 7 E68 Differential Temperature 8 (AT
) Low (<25°F) 8 E69 1 High (200°F) or Tu AT 1 High (700°F)
E70 2 High (200°F) or Tu AT 2 High (700°F)
E71 3 High (200°F) or Tu AT 3 High (700°F)
E72 4 High (200°F) or T AT 4 High (700°F)
E73 5 High (200°F) or Tu AT 5 High (700°F)
E74 6 High (200°F) or Tu AT 6 High (700°F)
E75 7 High (200°F) or T AT 7 High (700°F)
E76 8 High (200°F) or T AT 8 High (700°F)
Page 4 of 4 Version 8.0
10/08/10 10:27:35 -
- -T-ABLE4G - FNPI =SOP68.0 A Train ICCMS Q1HI 1NGCCM2523A-A CETC DISABLE / READOUT ICCMS Instrument
- Signal Descnption Identification Tag Number CETC-l TE-2301 Core Exit Thermocouple A8 CETC-2 TE-2302 Core Exit Thermocouple B5 CETC-3 TE-2304 Core Exit Thermocouple E4 CETC-4 TE-2305 Core Exit Thermocouple E9 CETC-5 TE-2308 Core Exit Thermocouple F3 CETC-6 TE-2309 Core Exit Thermocouple F5 CETC-7 TE-23 10 Core Exit Thermocouple E9 CETC-8 TE-231 1 Core Exit Thermocouple Fl 1 CETC-9 TE-23 13 Core Exit Thermocouple H7 CETC-l0 TE-2314 Core Exit Thermocouple H8 CETC- 11 TE-23 15 Core Exit Thermocouple H 15 CETC-12 TE-2316 Core Exit Thermocouple J2 CETC-13 TE-2317 Core Exit Thermocouple Jl0 CETC-l4 TE-2318 Core Exit Thermocouple J12 CETC-15 TE-2320 Core Exit Thermocouple L7 CETC- 16 TE-2322 Core Exit Thermocouple E9
- CETC-17 TE-2323 Core Exit Thermocouple L7 CETC-l8 TE-2324 Core Exit Thermocouple N6 CETC-19 TE-2325 Core Exit Thermocouple P8 CETC-20 TE-2326 Core Exit Thermocouple R7 CETC-21 TE-2328 Core Exit Thermocouple C12 CETC-22 TE-2333 Core Exit Thermocouple Fl 3 CETC-23 TE-2347 Core Exit Thermocouple Ml 1
- CETC-24 TE-2348 Core Exit Thermocouple L7 CETC-25 TE.-2349 Core Exit Thermocouple N8
- CETC-26 TE-2351 Core Exit Thermocouple M5 CETC-27 SPARE Spare Core Exit Thermocouple CETC-28 SPARE Spare Core Exit Thermocouple CETC-29 SPARE Spare Core Exit Thermocouple CETC-30 SPARE Spare Core Exit Thermocouple CETC-31 SPARE Spare Core Exit Thermocouple CETC-32 SPARE Spare Core Exit Thermocouple Upper Head Page 1 of4 Version 8.0
1OJO&/1O1O:27:35 - - TABLE4O FNP-l-SOP-68.O A Train ICCMS Q1H1 1NGCCM2523A-A continued HJTC DISABLE / READOUT ICCMS Instrument
. Signal Descnption Identification Tag Number HJTC-1 TE-2352A Heated Thermocouple 1 HJTC-2 TE-2352A Unheated Thermocouple 1 HJTC-3 TE-2352B Heated Thermocouple 2 HJTC-4 TE-2352B Unheated Thermocouple2 HJTC-5 TE-2352C Heated Thermocouple 3 HJTC-6 TE-2352C Unheated Thennocouple3 HJTC-7 TE-2352D Heated Thermocouple 4 HJTC-8 TE-2352D Unheated Thermocouple4 HJTC-9 TE-2352E Heated Thermocouple 5 HJTC-l0 TE-2352E Unheated Thermocouple5 HJTC-1 1 TE-2352F Heated Thermocouple 6 HJTC-12 TE-2352F Unheated Thermocouple6 HJTC-13 TE-2352G Heated Thermocouple 7 HJTC-14 TE-2352G Unheated Thenuocouple7 HJTC- 15 TE-2352H Heated Thermocouple 8 HJTC-16 TE-2352H Unheated Thermocouple8 SMM DISABLE / READOUT ICCMS Instrument
- - Signal Description Identification Tag Number SMM-1 TE-410 RCS Loop 1 Cold Leg SMM-2 TE-413 RCS Loop 1 Hot Leg SMM-3 TE-420 RCS Loop 2 Cold Leg SMM-4 TE-423 RCS Loop 2 Hot Leg SMM-5 TE-430 RCS Loop 3 Cold Leg SMM-6 TE-433 RCS Loop 3 Hot Leg SMM-7 PT403 RCS Loop 1 Pressure SMM-8 PT-402 RCS Loop 3 Pressure SMM-9 PT-455 Pressurizer Pressure SMM- 10 SPARE Spare SMM Input SMM-1 1 SPARE Spare SMM Input SMM- 12 SPARE Spare SMM Input Page 2 of 4 Version 8.0
- 10/08/10 10:27:35 - TABLE4O FNP-1-SOP-68.O B Train ICCMS Q1H1 1NGCCM2523B-B CETC DISABLE / READOUT ICCMS Instrument
. Signal Description Identification Tag Number CETC-1 TE-2303 Core Exit Thermocouple B 10
- CETC-2 TE-2306 Core Exit Thermocouple E9 CETC-3 TE-2307 Core Exit Thermocouple B12 CETC-4 TE-2312 Core Exit Thermocouple Gi CETC-5 TE-23 19 Core Exit Thermocouple K3 CETC-6 TE-2321 Core Exit Thermocouple G9 CETC-7 TE-2327 Core Exit Thermocouple C8 CETC-8 TE-2329 Core Exit Thermocouple D3 CETC-9 TE-2330 Core Exit Thermocouple D5 CETC-1 0 TE-233 1 Core Exit Thermocouple E8 CETC-1 1 TE-2332 Core Exit Thermocouple ElO CETC-12 TE-2334 Core Exit Thermocouple L7 CETC-13 TE-2335 Core Exit Thermocouple G8 CETC-14 TE-2336 Core Exit Thermocouple G15 CETC-1 5 TE-2337 Core Exit Thermocouple H3 CETC-16 TE-2338 Core Exit Thermocouple H5 CETC-1 7 TE-2339 Core Exit Thermocouple H9 CETC-1 8 TE-2340 Core Exit Thermocouple Hi 1 CETC-19 TE-2341 Core Exit Thermocouple H13 CETC-20 TE-2342 Core Exit Thermocouple L6 CETC-21 TE-2343 Core Exit Thermocouple L8 CETC-22 TE-2344 Core Exit Thermocouple L12 CETC-23 TE-2345 Core Exit Thermocouple L14 CETC-24 TE-2346 Core Exit Thermocouple M3 CETC-25 TE-2350 Core Exit Thermocouple Nl 0 CETC-26 SPARE Spare Core Exit Thermocouple CETC-27 SPARE Spare Core Exit Thermocouple CETC-28 SPARE Spare Core Exit Thermocouple CETC-29 SPARE Spare Core Exit Thermocouple CETC-30 SPARE Spare Core Exit Thermocouple CETC-3 1 SPARE Spare Core Exit Thermocouple CETC-32 SPARE Spare Core Exit Thermocouple Upper Head Page 3 of4 Version 8.0
10/08/10 10:27:35 - FABLE10 FNP-1 -SOP-8.0 B Train ICCMS Q1H1 1NGCCM2523B-B, continued HJTC DISABLE / READOUT ICCMS Instrument
. Signal Description Identification Tag Number HJTC-1 TE-2353A Heated Thermocouple 1 HJTC-2 TE-2353A Unheated Thermocouplel HJTC-3 TE-2353B Heated Thermocouple 2 HJTC-4 TE-2353B Unheated Thermocouple2 HJTC-5 TE-2353C Heated Thermocouple 3 HJTC-6 TE-2353C Unheated Thermocouple3 HJTC-7 TE-2353D Heated Thermocouple 4 HJTC-8 TE-23 53D Unheated Thermocouple4 HJTC-9 TE-2353E Heated Thermocouple 5 HJTC-1O TE-2353E Unheated Thermocouple5 HJTC-1 1 TE-2353F Heated Thermocouple 6 HJTC-12 TE-2353F Unheated Thermocouple6 HJTC- 13 TE-2353G Heated Thermocouple 7 HJTC- 14 TE-2353G Unheated Thermocouple7 HJTC- 15 TE-2353H Heated Thermocouple 8 HJTC- 16 TE-2353H Unheated Thermocouple8 SMM DISABLE I READOUT ICCMS Instrument Signal Description Identification Tag Number SMM-1 TE-410 RCS Loop 1 Cold Leg SMM-2 TE-413 RCS Loop 1 Hot Leg SMM-3 TE-420 RCS Loop 2 Cold Leg SMM-4 TE-423 RCS Loop 2 Hot Leg SMM-5 TE-430 RCS Loop 3 Cold Leg SMM-6 TE-433 RCS Loop 3 Hot Leg SMM-7 PT-403 RCS Loop 1 Pressure SMM-8 PT-402 RCS Loop 3 Pressure SMM-9 PT-457 Pressurizer Pressure SMM-i 0 SPARE Spare SMM Input SMM- 1 1 SPARE Spare SMM Input SMM- 12 SPARE Spare SMM Input Page 4 of 4 Version 8.0
10J08110 1027235 FNP-1-SOP-68.0 SIGNOFF LIST INADEQUATE CORE COOLING MONITORING SYSTEM 1.0 The revision of this procedure has been verified to be the current revision.
(OR 1-98-498) 2.0 Initial Conditions Initials STEP 2.1 Initials Initials 4.0 Instructions (First Check) (Verification) 4.1 System Startup 4.1.1 N/A 4.1.2 4.1.3 N/A 4.1.4 N/A 4.1.5 N/A 4.1.6 N/A 4.1.7 N/A 4.1.8 N/A 4.1.9 4.1.11 4.1.12 Person Completing First Check (Signature) Date/Time Person Completing Verification (Signature) Date/Time Supervision Review (Signature) Date/Time Page 1 of 1 Version 8.0
FNIHLT-34 1PM Page 1 of 4 IN-PLANT JPM I.
SO-590 UNIT 2 TITLE: Place the SJAE Filtration Unit In Service EVALUATION LOCATION: D SIMULATOR D CONTROL ROOM PLANT PROJECTED TIME: 5 MIN. SIMULATOR IC NUMBER: N/A D ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:
- 1. This 1PM is written to be performed on UNIT 2-ONLY TASK STANDARD: Required for successful completion of this 1PM:
. To place the LCS in the FILTER position and close the manual bypass valve.
Examince:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMiNER:
Developer Howard Fitzwater Date: 4/25/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNEP HLT-34 1PM S1MtJLATO1 3PM I. Page 2 of 4 (Guide pages =3)
CONDITIONS When I tell you to begin, you are to PLACE THE SJAE FILTRATION UNIT IN SERVICE on UNIT 2.
The conditions under which this task is to be performed are:
- a. The Plant is in Mode 1.
- b. A small tube leak exists in A steam generator and AOP-2.O has been entered.
- c. You are directed by the control room to place the SJAE filtration unit in service using SOP-28.5.
- d. The SJAE discharge line drain trap has been routed to a poly-bottle with a filtered vent.
- e. A pre-job brief is not required.
INITIATING CUE, You may begin.
NOTE: THIS JPM MAY BE PERFORMED ON UNIT TWO [2] ONLY. I EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME NOTE: The SJAE discharge line drain trap drains to the Turbine Building Sump. fl the filtration unit is being placed in service due to a tube leak, THEN consideration should be given to EITHER isolating the drain trap routing the drainage to a poly bottle with a filtered vent.
- 1. (step4.3.1)
Place local control handswitch for the SJAE Describes how to position the S / U filtration unit suction valves in FILTER. Local control handswitch to FILTER.
CUE: The switch is positioned as you described.
- 2. (step4.3.l.1)
Verify open SJAE FILTER SUCT DMPR Describes how to CHECK OPEN S/U N2U41HV3677B Valve N2U41HV3677B CUE: Valve has positioned as you described.
- 3. (step 4.3.1.2)
Verify closed SJAE FILTER BYP DMPR Describes how to CHECK Closed S/U N2U41HV3677A Valve N2U41HV3677A.
CUE: Valve has positioned as you described..
FNP HLT-34 1PM SIMULATOR 3PM I. Page 3 of 4 (Guide pages 3)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4* (step 4.3.1.3)
Close SJAE FILTER BYP DMPR manual Describes how to CLOSE Valve S/U isolation N2U41V018 N2U41V018.
CUE: Valve is positioned as you described.
- 5. Inform control room that SJAE filtration Control room informed. S / U unit has been placed in service CUE: Control room acknowledges that the SJAE filtration unit is in service.
STOP TIME Terminate after the control room is notified that the SJAE filtration unit is in service.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element number.
GENERAL
REFERENCES:
- 1. FNP-2-SOP-28.5, Version 27.0
- 2. K As:
1 037AA1.02 RO-3.1 SRO-2.9 GENERAL TOOLS AND EQUIPMENT:
None Critical ELEMENT justification:
STEP Evaluation 1 Critical: Task completion: required to be placed in the FILTER position to align AOVs properly to allow flow through the filter.
2 NOT Critical: Verifying components which are already in the required position.
3 NOT Critical: Verifying components which are already in the required position.
4 Critical: Task completion: required to close valve to cause the steam and air flow to go through the filter and NOT bypass it.
5 NOT Critical:to call CR is not critical.
COMMENTS:
FNP HLT-34 JPM JPM i HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PLACE THE SJAE FILTRATION UNIT N SERVICE on UNIT 2.
The conditions under which this task is to be performed are:
- a. The Plant is in Mode 1.
- b. A small tube leak exists in A steam generator and AOP-2.O has been entered.
- c. You are directed by the control room to place the SJAE filtration unit in service using SOP-28.5.
- d. The SJAE discharge line drain trap has been routed to a poly-bottle with a filtered vent.
- e. A pre-job brief is not required.
1O/Od1O 10:42:44 -
FNP-2-SOP-28.5 4.3 Air Ejector Filter Operation.
NOTE: The SJAE discharge line drain trap drains to the Turbine Building Sump. IF the filtration unit is being placed in service due to a tube leak, THEN consideration should be given to EITHER isolating the drain trap OR routing the drainage to a poiy bottle with a filtered vent.
4.3.1 To place SJAE filter in operation, at LCS for SJAE FILTRATION N2U41G529-N, place local control handswitch for SJAE filtration unit valves in FILTER and perform the following:
4.3.1.1 Verify open SJAE FILTER SUCT DMPR, N2U4 1 HV3 677B.
4.3.1.2 Verify closed SJAE FILTER BYP DMPR, N2U4 1HV3677A.
4.3.1.3 Close SJAE FILTER BYP MAN ISO, N2U41V018.
4.3.2 To bypass SJAE filter, perform the following:
4.3.2.1 Verify open SJAE FILTER BYP MAN ISO, N2U41V018.
4.3.2.2 At LCS SJAE FILTRATION N2U41G529-N, place local control handswitch for SJAE filtration unit valves in BYPASS.
4.3.2.3 Verify open SJAE FILTER BYP DMPR, N2U4 1 HV3677A.
4.3.2.4 Verify closed SJAE FILTER SUCT DMPR, N2U4 1 HV3 677B.
Version 27.0
FNPHLT-34JPM Pagelof5 IN-PLANT JPM J.
SO-449-UNIT 2 TITLE: Supply Emergency Air To Steam Generator Atmospheric Relief Valves From Emergency Air Compressors EVALUATION LOCATION: LI SIMULATOR LI CONTROL ROOM I PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A El ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. This 1PM may be performed on UNIT 2-ONLY.
TASK STANDARD: Required for successful completion of this 1PM:
- Complete steps to align emergency air to the ARVs.
- Then reduce the pressure on the ARVs per the CUE to reduce the air pressure to the ARV which will close the ARV and reduce the cooldown rate.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Howard Fitzwater Date: 4/25/20 1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNPHLT-34WM IJNTT2 Page2of5 (Unit 2 Guide pages =4)
CONDITIONS When I tell you to begin, you are to SUPPLY EMERGENCY AIR TO THE 2B STEAM GENERATOR ATMOSPHERIC RELIEF VALVE FROM EMERGENCY AIR COMPRESSORS AND OPEN THE 2B ARV 25%. The conditions under which this task is to be performed are:
- a. Unit 2 has lost Instrument Air.
- b. NO POWER is available to MCB atmospheric relief valve controllers.
- c. You are directed by Shift Supervisor to perform SOP-62.O, Section 4.1, to align emergency air to 2B steam generator atmospheric relief valve and open the 2B ARV 25%.
- d. DC power is NOT available to the solenoid valves.
- e. A pre-job brief is NOT required.
INITIATIIJG CUE, You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
TIME
- 1. (step 4.1.1 or step 4.4.1)
Start A emergency air compressor. Describes how to place the S / U Start B emergency air compressor. Handswitches to ON and the candidate should identify the Air compressors will start.
CUE: Components respond and indications are as expected.
- 2. (step 4.4.2.1)
Verify closed emergency air header Describes how to Verify closed S / U isolation valve N2P 1 8V073B to 2B ARV. valve V073B by turning clockwise to verify closed.
CUE: Valve responds as you described.
- 3. (step 4.4.2.2)
Place the local handswitch Describes Placing the Local hand- S / U Q2N1 1HS3371BB to CLOSE switch H53371BB in the closed position.
NOTE: The Light Will Be Dark Due To No DC Power regardless of the position the switch is in.
CUE: You have positioned the switch as you described. The light(s) are NOT LIT.
FNP HLT-34 1PM UNIT 2 Page 3 of5 (Unit 2 Guide pages =4)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4 (step 4.4.2.2)
Close the manual isolation valve Describes how to Close Manual S/U Q2N1 1V921B for solenoid valve isolation valve v921B for (Q2N1 1SV3371BB) SV337 1BB.
CUE: The valve operates as described.
- 5 (step 4.4.2.2)
Open the manual bypass valve Describes how to OPEN Manual S/U Q2N1 1V914BB for solenoid valve bypass valve V914BB for (Q2N1 1SV3371BB) 5V337 1BB by turning counter Clockwise.
CUE: The valve operates as described NOTE: Atmospheric relief valves will start to open at 24 +/- 2 psig and will be full open at 45 psig.
- 6. (step 4.4.2.3)
Slowly throttle open emergency air header Describes how to partially open S/U iso valve N2P18VO73B while observing air N2P18V073B by turning supply pressure ON P12872BB for the 2B counterclockwise until ARV.
CUE: Valve operates as you described OBSERVES pressure rise on PT 2872BB CUE: P12872BB READS 44 PSIG
- 6. (step 4.4.2.4)
Open manual isolation valve Q2N1 1V921B Describes how to Open vent valve S / U to reduce pressure for 2B ARV. V92 lB by turning Counter clockwise.
CUE: P12872BB lowers to 30 psig.
- 7. Report to control room operator that 2B Control room operator notified. S/U
FNP 11LT14 1PM UNIT 2 Page 4 of 5 (Unit 2 Guide pages =4)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE) atmospheric relief valve is open and being supplied from the emergency air compressors.
CUE: CR0 acknowledges.
STOP TIME Terminate after control room operator is notified that 2B ARV is OPEN and being supplied from the emergency air compressors.
CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number.
GENERAL
REFERENCES:
- 1. FNP-2-SOP-62.0, Rev/Version 24.0
- 2. KAs: 065AA1.04 R0-3.5 SRO-3.4 GENERAL TOOLS AND EOUIPMENT:
None Critical ELEMENT justification:
STEP Evaluation 1 Critical: Task completion: required to start the EACs or there will be no pressure to open the ARV.
2 NOT Critical: Verifying components which are already in the required position.
3 NOT Critical: Placing the HS to close will not impact the successful completion of the task.
4 Critical: Task completion: required to close the manual valve to prevent venting off the air and allow the ARV to receive the air and open.
5 Critical: Task completion: required to open manual bypass to place air on the ARV to open the valve.
6 Critical: Task completion: required to reduce air pressure on the ARV to close the ARV to reduce the cooldown on the RCS on the ARV to open the valve.
7 NOT Critical:to call CR is not critical.
COMMENTS:
FNP HLT-34 JPM j HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to SUPPLY EMERGENCY AIR TO THE 2B STEAM GENERATOR ATMOSPHERIC RELIEF VALVE FROM EMERGENCY AIR COMPRESSORS AND OPEN THE 2B ARV 25%. The conditions under which this task is to be performed are:
- a. Unit 2 has lost Instrument Air.
- b. NO POWER is available to MCB atmospheric relief valve controllers.
- c. You are directed by Shift Supervisor to perform SOP-62.O, Section 4.1, to align emergency air to 2B steam generator atmospheric relief valve and open the 2B ARV 25%.
- d. DC power is NOT available to the solenoid valves.
- e. A pre-job brief is NOT required
10/08/10 10:41:38 - - - - FNP-2-SOP-62.0 4.0 Instructions CAUTION: Atmospheric reliefs will start to open at 24 +/-2 psig and will be full open at 45 psig. Observe local air supply pressure gauge N2P18P12872 AB (BB,CB).
IF the atmospheric relief is full open, THEN Tech Spec cooldown limits may be exceeded.
IN0TE: The compressors are rated at 41.6 Ft /min at 100 psig.
3 4.1 Placing the Emergency Air Compressors in Operation 4.1.1 Place emergency air compressor 2A hand switch in ON.
4.1.2 Place emergency air compressor 2B hand switch in ON.
4.1.3 With power available to the atmospheric relief valve, MCB controllers, proceed to step 4.3.
- 2A S/G atmospheric relief valve controller PC 3371A
- 2B S/G atmospheric relief valve controller PC 337 lB
- 2C S/G atmospheric relief valve controller PC 3371C 4.1.4 With no power available to the atmospheric relief valve, MCB controllers, proceed to step 4.4.
4.2 Removing the Emergency Air Compressors from Operation 4.2.1 Place emergency air compressor 2A hand switch in OFF.
4.2.2 Place emergency air compressor 2B hand switch in OFF.
Version 24.0
10/08/10 10:41:38 - FNP-2-OR-62.0 4.3 Manual-Electric Operation of Steam Generator Atmospheric Relief Valves 4.3.1 j not already performed, THEN place the emergency air compressors in operation.
- Place emergency air compressor 2A hand switch in ON.
- Place emergency air compressor 2B hand switch in ON.
4.3.2 Open emergency air header isolation valves for the affected atmospheric relief valve(s):
Atmospheric Relief Emergency Air Valve Header Iso Valve Q2N1 1PCV3371A N2P18V073A Q2N1 1PCV3371B N2P18V073B Q2N1 1PCV3371C N2P18V073C 4.3.3 Record the emergency air header pressure for the affected atmospheric relief valve(s):
Emergency Air Emergency Air Atmospheric Relief Header Pressure Header Pressure Valve Indicator Reading Q2N 1 1 PCV337 1A N2P 1 8P12872AB psig Q2N1 1PCV3371B N2P18P12872BB psig Q2N11PCV3371C N2P18PI2872CB psig 4.3.4 Open emergency air header to normal air header cross connect valve for the affected atmospheric relief valve(s):
Atmospheric Relief Cross Connect Valve Valve Q2N1 1PCV3371A N2P18V074A Q2N1 1PCV3371B N2P18VO74B Q2N1 1PCV3371C N2P18V074C Version 24.0
FO!O8/1Q-1O4h38 - - FNP=2=SOP62.O 4.3.5 Record the emergency air header pressure for the affected atmospheric relief valve(s):
Emergency Air Emergency Air Atmospheric Relief Header Pressure Header Pressure Valve Indicator Reading Q2N 1 1PCV337 1A N2P 1 8P12872AB psig Q2N1 1PCV3371B N2P18P12872BB psig Q2N1 1PCV3371C N2P18P12872CB psig NOTE: Failure of the check valve downstream of the Instrument Air Root Isolation wiiil allow Emergency Air Header Pressure to bleed into the IA System. I 4.3.6 the Emergency Air Header Pressure Reading recorded in step 4.3.5 is not within 5 psig of the pressure recorded in step 4.3.3 for a particular Atmospheric Relief Valve, THEN perform the following:
4.3.6.1 the MSVR is accessible, THEN isolate the instrument air supply to that affected Atmospheric Relief Valve (MSVR).
Atmospheric Relief Instrument Air Root Initial in this block if root Valve Isolation isolation was closed.
Q2N1 1PCV3371A No TPNS Q2N11PCV3371B No TPNS Q2N11PCV3371C No TPNS 4.3.6.2 IF the MSVR is not accessible, THEN close the valves opened in steps 4.3.2 and 4.3.4, AND proceed to section 4.4.
4.3.7 Notify the Control Room that the steam generator atmospheric reliefs may be operated using the main control board controllers Atmospheric Relief Controller Valve Q2N11PCV3371A PC 337lA Q2N11PCV3371B PC 337lB Q2N11PCV3371C PC 3371C Version 24.0
10/08110 10:41:38 - -
FNP-2-SOP-62.O 4.3.8 WHEN normal air supply available, THEN perform the following:
4.3.8.1 instrument air was isolated to an Atmospheric Relief Valve in step 4.3.6, THEN restore instrument air by opening the Instrument Air Root Isolation. Refer to the table below step 4.3.6 for configuration.
Atmospheric Relief Instrument Air Root Initial for opening the Valve Isolation root isolation.
Q2N1 1PCV337IA No TPNS Q2N11PCV337IB NoTPNS Q2N11PCV337IC No TPNS 4.3.9 With normal air supply available, remove the emergency air compressors from operation.
- Place emergency air compressor 2A hand switch in OFF.
- Place emergency air compressor 2B hand switch in OFF.
4.3.10 Close emergency air header isolation valves for the affected atmospheric relief valve(s):
Atmospheric Relief Emergency Air Valve Header Iso Valve Q2NI 1PCV3371A N2P18V073A Q2N1 1PCV3371B N2P18V073B Q2N1 1PCV3371C N2P18VO73C 4.3.11 Close emergency air header to normal air header cross connect valve for the affected atmospheric relief valve(s):
Atmospheric Relief Cross Connect Valve Valve Q2NI 1PCV3371A N2P18V074A Q2N1 1PCV3371B N2P18VO74B Q2N1 1PCV3371C N2P18V074C Version 24.0
10/08/10 10:41:38 FNP-2-SOP-62.0 4.4 Local Pneumatic Operation of Steam Generator Atmospheric Relief Valves NOTE: JJ. this section is entered from step 4.3.6, THEN step 4.4.1 may be satisfied.
4.4.1 Place the emergency air compressors in operation:
- Place emergency air compressor 2A hand switch in ON.
- Place emergency air compressor 2B hand switch in ON.
4.4.2 Opening Atmospheric Relief Valve 4.4.2.1 Verify emergency air header iso valve closed for the affected atmospheric relief valve(s):
Atmospheric Relief Emergency Air Valve Header Iso Valve Q2N1 1PCV3371A N2P18V073A Q2N1 1PCV3371B N2P18V073B Q2N1 1PCV3371C N2P18V073C 4.4.2.2 Perform the following for the affected atmospheric relief valve(s):
A. Place the local handswitch to CLOSE.
B. Close the MANUAL ISOLATION VALVE for SV337 lAB (BB, CB).
C. Open the MANUAL BYPASS VALVE for SV3371AB (BB, CB).
Atmospheric Manual Iso Manual Bypass Handswitch Solenoid Valve Relief Valve Valve Valve Q2N11PCV3371A Q2N11HS3371AB Q2N11V921A Q2N11V914AB Q2N11SV3371AB Q2N11PCV3371B Q2N11HS3371BB Q2N11V921B Q2N11V914BB Q2N11SV3371BB Q2N11PCV3371C Q2N11HS3371CB Q2N11V921C Q2N11V914CB Q2N11SV3371CB Version 24.0
10/08/10 1041:3S FNP-2-SOP-62.0 CAUTION: Atmospheric relief valves will start to open at 24 +/- 2 psig and will be full open at 45 psig. the atmospheric relief is full open, THEN Tech Spec cooldown limits may be exceeded.
4.4.2.3 Slowly throttle open emergency air header iso valve while observing air supply pressure for the affected atmospheric relief valve(s):
Atmospheric Relief Emergency Air Header Local Pressure Indicator Valve Iso Valve Q2N 1 1PCV337 1 A N2P I 8V073A N2P 1 8P12872AB Q2N1 1PCV3371B N2P18V073B N2P18P12872BB Q2N1 1PCV3371C N2P18V073C N2P18P12872CB 4.4.2.4 necessary to reduce air supply pressure, THEN open the manual isolation valve downstream of the solenoid valve for the affected atmospheric relief valve(s):
Atmospheric Relief Manual Iso Valve Local Pressure Indicator Valve Q2N1 1PCV337IA Q2N1 1V921A N2P18P12872AB Q2N11PCV3371B Q2N1 lV92lB N2P18PI2872BB Q2N1 1PCV3371C Q2N1 1V921C N2P18P12872CB Version 24.0
FNP HLT-34 JPM Page 1 of 4 IN-PLANT JPM J. (Alteriiate>
SO-448 UNIT 2 TITLE: Align Backup Air To PORVs From Nitrogen Bottles EVALUATION LOCATION: U SIMULATOR U CONTROL ROOM J PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A U ALTERNATE PATH U TIME CRITICAL U PRA JPM DIRECTIONS:
- 1. This JPM may be performed on UNIT 2-ONLY.
TASK STANDARD: Required for successful completion of this JPM:
. Complete steps to align nitrogen to the PORVs.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Name: Gary Ohmstede Date: 5/17/2011 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 JPM Page 1 of 4 CONDITIONS When I tell you to begin, you are to ALIGN BACKUP NITROGEN BOTTLES TO THE PORVs. The conditions under which this task is to be performed include the following:
- a. The Plant has lost Instrument Air to containment.
- b. Operation of the PORVs is required.
- c. You are directed by the control room operator to Align Backup Nitrogen to the PORVs per FNP-2-SOP-62. 1.
- d. A pre-job brief is not required.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
TIME NOTE: EXAMINEE MAY CHOOSE WHICH NITROGEN BOTTLE TO PLACE ON SERVICE. IF ASKED, NITROGEN BOTTLE PRESSURE IS 2000 psig FOR EACH BOTTLE.
- 1. (step 4.2.1) Turn the outlet valve counter S / U Place a nitrogen bottle on service clockwise on the nitrogen bottle to be placed on service.
CUE: Outlet valve is open.
- 2. (step 4.2.2) N2P19V244A(B) is turned S / U Open nitrogen isolation to back-up counterclockwise.
instrument air valve CUE: Valve is open.
CUE: P1-2228 indicates 0 psig when first looked at.
- 3 (step 4.2.3) Q2P19PCV2228A(B) is adjusted S / U Adjust instrument air control pressure to 100 psig as indicated on P1-2228.
CUE: P1-2228 indicates 100 psig.
- 4 (step 4.2.4) On the PRIP, Open Q2P19HV2228 S / U Open the PORV back-up air supply valve by taking the handswitch to the start position to open valve.
CUE: Valve position indicator RED LIGHT LIT and GREEN LIGHT NOT LIT.
(step 4.2.5 is N/A)
FNP HLT-34 JPM Page 2 of 4 EVALUATION CHECKLIST - -
RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 5. (step 4.2.6) Call the control room. S / U Inform the CR0 that backup air is aligned to PORVs from nitrogen bottles CUE: The CR0 acknowledges.
STOP TIME Terminate after CR0 acknowledges backup air is aligned to PORVs from the nitrogen bottles.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element number.
GENERAL
REFERENCES:
- 1. FNP-2-SOP-62.1, Version 17.0
- 2. KAs: 065AA2.07 R0-2.8 SRO-3.2 GENERAL TOOLS AND EOUIPMENT:
None Critical ELEMENT justification:
STEP Evaluation 1 Critical: Task completion: Placing the bottle on service is critical to get nitrogen to the PORVs.
2 Critical: Task completion: Placing the bottle on service is critical to get nitrogen to the PORVs.
3 Critical: Task completion: Ensuring there is enough nitrogen pressure is critical to operating the PORVs.
4 Critical: Task completion: required to open HV2228 to supply Nitrogen to the PORVs 5 NOT Critical:to call CR is not critical.
COMMENTS:
FNP HLT-34 JPM Page 3 of 4 CONDITIONS -
When I tell you to begin, you are to ALIGN BACKUP NITROGEN BOTTLES TO THE PORVs. The conditions under which this task is to be performed include the following:
- a. The Plant has lost Instrument Air to containment.
- b. Operation of the PORVs is required.
- c. You are directed by the control room operator to Align Backup Nitrogen to the PORVs per FNP-2-SOP-62. 1.
- d. A pre-job brief is not required.
10I08f10 10:41:40 FNP-2-SOP-62.l February 6, 2009 Version 17.0 FARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP-2-SOP-62. 1 S
A F
E T
Y BACK-UP AIR OR NITROGEN SUPPLY TO THE PRESSURIZER POWER OPERATED RELIEF VALVES R
E L
A T
E D
PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
Jim L. Hunter (for)
Operations Manager Date Issued 2-13-2009
10,108/10 10:414(} - -- - FNP-2-SOP-62.1 TABLE OF CONTENTS Procedure Contains Number of Pages Body 5 Page 1 of 1
10J08/ID I-O:4I4O FNP=2=SOP62.1 FARLEY NUCLEAR PLANT UNIT 2 SYSTEM OPERATING PROCEDURE SOP-62. 1 BACK-UP AIR OR NITROGEN SUPPLY TO THE PRESSURIZER POWER OPERATED RELIEF VALVES 1.0 Purpose This procedure provides the Initial Conditions, Precautions and Limitations, and Instructions for Operation of the Back-up Air or Nitrogen Supply to the Pressurizer Power Operated Relief Valves. Instructions are included in the following sections:
4.1 Operation of the PRZR PORVs Upon Loss of Instrument Air Using Alternate Instrument Air Supply 4.2 Operation of the PRZR PORVs Upon Loss of Instrument Air Using Nitrogen Supply 4.3 Shifting from One Nitrogen Bottle to the Other Nitrogen Bottle 4.4 Returning System to Normal Operation 4.5 Checking PRZR PORV Nitrogen Bottle Pressure 2.0 Initial Conditions 2.1 The back-up air or nitrogen supply to the pressurizer power operated relief valves system valves are aligned per system check list FNP-2-SOP-62.1A.
3.0 Precautions and Limitations 3.1 Any time the PRZR PORVs are operated monitor PRT parameters.
3.2 j at any time the PRZR PORVs dont reseat properly, THEN close the appropriate PRZR PORV ISO.
Version 17.0
10108110 10:41:40 FNP-2-SOP-62.l-4.0 Instructions 4.1 Operation of the PRZR PORVs Upon Loss of Instrument Air Using Alternate Instrument Air Supply 4.1.1 Establish backup air supply as follows:
A. Open back-up instrument air to PRZR PORVs valve N2P 1 9V242.
B. Open PORV BKUP AIR SUPPLY, Q2P19HV2228.
(PRIP)
C. IF Q2P19HV2228 will not open, THEN locally unlock and open, HV2228-B BY-PASS LIISIE ISO, Q2P19V1099.
(Master V key) 4.1.2 Verif proper operation of PRZR PORVs.
4.2 Operation of the PRZR PORVs Upon Loss of Normal Instrument Air Using Nitrogen Supply NOTE:
- Place in service only one nitrogen bottle at a time. WHEN the pressure decreases to approximately 150 psig to 200 psig, THEN place the other nitrogen bottle on service per step 4.3, and change out the used nitrogen bottle.
PORV BKUP air supply Q2P19HV2228 fails closed on a loss of B Train DC.
4.2.1 Open the nitrogen bottle outlet valve on the bottle to be placed in service.
4.2.2 Open nitrogen isolation to back-up instrument air valve N2P 1 9V244A(B).
4.2.3 Adjust N2P19PCV2228A(B) to indicate approximately 100 psig on P1 2228.
4.2.4 Open PORV BKUP AIR SUPPLY Q2P19HV2228. (PRIP) 4.2,5 IF Q2P19HV2228 will not open, THEN open Q2P19V1099, Q2P19HV2228-B BY-PASS LINE ISO (KEY V-35).
4.2.6 Verify proper operation of PRZR PORVs.
Version 17.0
10/08/10 1Q41:40 FNP-2-SOP-62.1-4.3 Shifting from One Nitrogen Bottle to the Other Nitrogen Bottle 4.3.1 Open the nitrogen bottle outlet valve on the fully charged bottle.
4.3.2 Open nitrogen isolation to back-up instrument air valve N2P 1 9V244A(B) on the fully charged nitrogen bottle.
4.3.3 Close nitrogen isolation to back-up instrument air valve N2P 1 9V244A(B) on the depleted nitrogen bottle.
4.3.4 Adjust N2P19PCV2228A(B) to indicate approximately 100 psig on P1 2228.
4.3.5 Close the nitrogen bottle outlet valve on the depleted bottle.
4.3.6 Replace the depleted nitrogen bottle with a fully charged nitrogen bottle.
4.3.7 Repeat steps 4.3.1 thru 4.3.6 as necessary to insure adequate nitrogen to PRZR PORVs.
Version 17.0
1-O!O8/1G 10:41:40- FNP2SOP62.l 4.4 Returning System to Normal Operation 4.4.1 IF the back-up instrument air to CTMT was used, THEN perform the following:
4.4.1.1 Verify IA TO PENE RM, N2P19HV3825 is NOT jacked open with the local handwheel. (100 NR Aux Bldg) 4.4.1.2 Verify IA TO PENE RM, N2P19HV3825 is open.
4.4.1.3 Verify IA TO PENE RM, N2P19HV3885 is NOT jacked open with the local handwheel. (100 NR Aux Bldg) 4.4.1.4 Verify IA TO PENE RM, N2PI 9HV3885 is open.
4.4.1.5 Verify IA TO CTMT, Q2P19HV361 1 is NOT jacked open with the local handwheel. (Room 2184) 4.4.1.6 Verify IA TO CTMT, Q2P19HV361 I is open.
4.4.1.7 Verify PORV BKUP AIR SUPPLY, Q2P19HV2228 is closed. (PRIP) 4.4.1.8 Verify Q2P19HV2228-B BY-PASS ISO, Q2P19V1099, is closed AND locked.
4.4.1.9 Verify BACKUP IA TO PORVS HDR, N2P19V242, is closed. (121 BTRS Chiller Room) 4.4.1.10 Verify valve position of the following valves by performing a partial FNP-2-STP-14.0, CTMT INTEGRITY VERIFICATION TEST.
- PORV BKUP AIR SUPPLY, Q2P19HV2228
10/08/10 1J:41:4 - FNP2-SOP-&21 4.4.2 the back-up nitrogen supply was used, THEN perform the following:
4.4.2.1 Close PORV BKUP AIR SUPPLY Q2P19HV2228. (PRIP) 4.4.2.2 IF Q2P19V1099, Q2P19HV2228-B BY-PASS ISO (KEY V-35), was opened, THEN close and lock Q2P19V1099.
4.4.2.3 Close nitrogen isolation to backup instrument air valve N2P 1 9V244A(B).
4.4.2.4 Close the nitrogen bottle outlet valve.
4.4.2.5 Verify valve position of the following valves by performing a partial FNP-2-STP-14.0, CTMT INTEGRITY VERIFICATION TEST.
- PORV BKUP AIR SUPPLY, Q2P19HV2228
- HV2228 BYP ISO VLV, Q2P19V1O99 4.5 Checking PORV Nitrogen Bottle Pressure 4.5.1 Verify N2P1 9V244A(B) closed.
4.5.2 Open compressed nitrogen bottle 2A(2B) outlet isolation valve and obtain reading on P1 2283A(B).
4.5.3 Close compressed nitrogen bottle 2A(2B) outlet isolation valve.
4.5.4 Nitrogen Pressure (REF lAS-S SA-003; Westinghouse letter APW-A-5299; PCN-80-643) 4.5.4.1 IF the total N 2 pressure between the two bottles is less than 2400 psig THEN, submit a CR to change out the lower pressure bottle.
4.5.4.2 The pressure of both N2 bottles added together must be greater than 2200 psig. j the sum of both N 2 bottle is less than 2200 psig. THEN inform the SS.
5.0 References 5.1 D-205034 sheet 4 Version 17.0
FNP HLT-34 JPM Page 1 of 5 IN-PLANT JPM K.
SO-095B-UNIT 2 TITLE: Align RHT To Drain To WHT EVALUATION LOCATION: LI SIMULATOR LI CONTROL ROOM l1 PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA 3PM DIRECTIONS:
- 1. This JPM may be perfomed on UNIT 2 ONLY.
TASK STANDARD: Required for successful completion of this JPM:
. Complete the valve line up to drain the RHT to the WHT.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
eveloper Name: Howard Fitzwater Date: 4/25/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 1PM UNIT 2 1PM K Page 2 of 5 (Unit 2 Guide pages =4)
CONDITIONS When I tell you to begin, you are to DRAIN 2A RECYCLE HOLDUP TANK (RET) TO THE WASTE HOLDUP TANK (WHT) on Unit 2. The conditions under which this task is to be performed are:
- a. 2A RHT is not on service and all initial conditions have been met for draining it to the WHT (i.e.,
tank has remained idle for several days for fission gas decay).
- b. You are directed by the Unit Operator to drain 2A RET to the WHT using the Preferred method using SOP-2.4.
- c. A pre-job brief is NOT required.
INITIATING CUE, You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step4.l0.l.1)
Verify 2A and 2B recycle evaporator feed DESCRIBES how to Verify 2A S/U pumps are in local and pulled to lock and 2B REV feed pumps are in local and pulled to lock verifying or placing in local and pull to lock.
CUE: Switches (and indications) ARE as/respond as you expected/described
- 2. (step 4.10.1.2)
Close 2A recycle evaporator feed pump DESCRIBES how to Close 2A S/U discharge Q2E21V295A(8567B) and 2B REV feed pump disch V295A recycle evaporator feed pump discharge (8567B) and 2B REV feed pump Q2E2 1V295B(8567A) disch V295B (8567A) by turning the handwheels clockwise.
CUE: The valve(s) respond(s) as you expected/described
- 3. (step 4.10.1.3)
Identify desired RHT to be drained: REFERS to Initial condition page 5 / U 2A RHT, 2B RET or 2C RHT and Checks the block on the procedure for 2A RHT
FNP HLT34 1PM UNIT 2 1PM K Page 3 of 5 (Unit 2 Guide pages =4)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4. (step4.1O.l.4)
Check desired RHT NOT on service while REVIEWS the Initial conditions S/U draining.
ALTERNATIVELY:
LOCATES and describes how to CHECK the following is CLOSED by turning clockwise:
2-CVC-V-8554A(V284A) 2A RHT MAN INLET ISO LOCATES and describes how to CHECK the following is LOCKED CLOSED by checking closed and lock installed:
2-CVC-V-8557A(V31 1A) 2A RHT EQUIPMENT DRAINS AND VLV LEAKOFF INLET ISO IF NEEDED CUE for 2-CVC-V-8554A(V284A): The valve(s) will not turn IF NEEDED CUE for 2-CVC-V-8557A(V311A): The valve(s) is locked and will not turn
- 5. (step 4.10.1.5)
Verify closed ALL RHT outlet isolations: DESCRIBES how to Close or S/U 2A RHT Q2E21V286A(8563A) verify closed RHT outlet isolation 2B RHT Q2E21V286B(8563B) valves by turning Clockwise:
2C RHT Q2E21V286C(8563C) 2A RHT V286A(8563A),
2B RHT V286B(8563B), and 2C RHT V286C (8563C).
CUE: The valve(s) respond(s) as you expected/described
- 6. (step 4.10.1.6)
Open recycle evaporator feed pump casing DESCRIBES how to Open REV S/U drain valves Q2E21V598A and feed pump casing drain valves Q2E21V598B V598A and V598B by turning handwheels counterclockwise.
CUE: The valve(s) respond(s) as you expected/described
FNP HLT-34 1PM UNIT 2 1PM K Page4cf5 (Unit 2 Guide pages =4)
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 7 (step 4.10.1.7)
Throttle open the 2A RHT outlet isolation to DESCRIBES how to Throttle open S / U establish the desired drain rate 2A RHT outlet isolation V286A 2A RHT Q2E21V286A(8563A) (8563A) to establish the desired drain rate, by turning handwheel counter-clockwise.
CUE: The valve(s) respond(s) as you expected/described and a drain rate is established as you described/expect STOP TIME Terminate when all elements of the task have been completed.
CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number.
GENERAL
REFERENCES:
- 1. FNP-2-SOP-2.4, Version 52.0
- 2. K/As: 068K1.07 RO-2.7 SRO-2.9 GENERAL TOOLS AND EQUIPMENT:
None Critical ELEMENT justification:
STEP Evaluation 1 NOT Critical: Verifying components which are already in the required position.
2 CRITICAL: Task completion: required to be closed to properly drain the RHT and not drain other parts of the system.
3-4 NOT Critical: clerical part of task ensuring proper RHT is drained 5 NOT Critical: Verifying components which are already in the required position.
6 CRITICAL: Task completion: required to open valve to drain RHT.
7 CRITICAL: Task completion: required to throttle open to start the draining of the RHT.
COMMENTS:
FNP HLT-34 - JPM K HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to DRAIN 2A RECYCLE HOLDUP TANK (RHT) TO THE WASTE HOLDUP TANK (WElT) on Unit 2. The conditions under which this task is to be perfonrLed are:
- a. 2A RHT is not on service and all initial conditions have been met for draining it to the WHT (i.e.,
tank has remained idle for several days for fission gas decay).
- b. You are directed by the Unit Operator to drain 2A RHT to the WHT using the preferred method using SOP-2.4.
- c. A pre-job brief is NOT required.
10/08/10 10:38:57 -
FNP-2-SOP-2.4 4.10 Draining Recycle Hold-Up Tanks (RHT):
NOTE: RHT should NOT be on service and should remain idle for several days if possible for fission gas decay unless the source of the water is NOT from the RCS.
4.10.1 desired to drain RHTs to WHT using Preferred method, THEN perform the following:
4.10.1.1 Verify 2A and 2B recycle evaporator feed pumps are in pulled to locku.
1ocal and t 4.10.1.2 Close the following valves:
- 2A REV FEED PUMP DISCH ISO, 2-CVC-V-8567B (Q2E2 1 V295A)
- 2B REV FEED PUMP DISCH ISO, 2-CVC-V-8567A (Q2E2 1 V295B).
4.10.1.3 Identify desired RHT to be drained:
2ARHT D, 2BRHT C, 2CRHT C, 4.10.1.4 Check desired RHT NOT on service while draining.
4.10.1.5 Check all RHT outlet isolations closed:
RRT VALVE REV FEED PUMP SUCT FROM #1 RHT, 2A Q2E2 1 V286A (#1 RHT 2-CVC-V-8563A)
REV FEED PUMP SUCT FROM #2 RHT, 7B Q2E21V286B (#2 RHT 2-CVC-V-8563B)
REV FEED PUMP SUCT FROM #3 RHT, 2C Q2E21V286C (#3 RHT 2-CVC-V-8563C)
(Step 4.10.1 continued on next page)
Version 52.0
10108110 10:38:57 _
FNP-2-SOP-2.4 4.10.1.6 Open the following valves:
- 2A REV FEED PUMP CASING DRN, Q2E21V598A
- 2B REV FEED PUMP CASING DRN, Q2E21V598B.
4.10.1.7 Slowly throttle open desired RHT outlet isolation to establish the desired drain rate:
RUT VALVE REV FEED PUMP SUCT FROM #1 RHT, 2A Q2E21V286A (#1 RHT 2-CVC-V-8563A)
REV FEED PUMP SUCT FROM #2 RHT, 2B Q2E21V286B (#2 RHT 2-CVC-V-8563B)
REV FEED PUMP SUCT FROM #3 RHT, 2C Q2E21V286C (#3 RHT 2-CVC-V-8563C) 4.10.1.8 WHEN RHT level 7% OR WHT at desired level THEN, close the following valves:
- 2A REV FEED PUMP CASING DRN, Q2E21V598A
- 2B REV FEED PUMP CASING DRN, Q2E21V598B 4.10.1.9 Close the RHT outlet isolation valve opened in Step 4.10.1.7.
4.10.1.10 Open the following valves:
- 2A REV FEED PUMP DISCH ISO, 2-CVC-V-8567B (Q2E2 1 V295A)
- 2B REV FEED PUMP DISCH ISO, 2-CVC-V-8567A (Q2E21V295B).
(Step 4.10 continued on next page)
Version 52.0