ML12214A347
| ML12214A347 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/23/2012 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| Shared Package | |
| ML12214A278 | List: |
| References | |
| Download: ML12214A347 (320) | |
Text
FNP ILT-35 JPM Page 1 of 13 SIMULATOR JPM A.
CRO-033(NEW)
TITLE: Perform step 4.2 of STP-5.0, Full Length Control Rod Operability Test.
EVALUATION LOCATION: 1 SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-217 ISI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee will be provided a marked up copy of STP-5.0. All other references of the simulator will be available at the examinees discretion.
- a. STP-5.0 will be marked as follows:
- i. All of section 3.0 is complete, except 3.3 which is NA.
ii. All of section 4.1, 4.3 through 4.8 are marked NA.
- 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the coffectness of system response to his/her actions and respond to any abnormal conditions which may arise.
- 3. All events are TRIGGERED, and NO Cues are required by the examiner, however the trigger may be initiated upon the Examiners request.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Inserted Shutdown Bank A in BANK control> 10 but <15 steps per step 4.2 of STP-5.0;
- Initiate an Rx trip following a DROP of 2 or more rods per the guidance of FNP-1-AOP-19.0.
o (safety sinifIcance) Operating outside of designed assumptions for accident analysis;> 1 dropped rod may result in exceeding power peaking factors (Hot Channel) under some accident conditions if the Rx is not tripped manually.
Examinee:
Overall JPM Performance: Satisfactory 1J Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 2/1/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM SIMULATOR JPM A. Page 2 of 13 (Guide pages = 12)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-2 17 for JPM A Ensure rods are in Manual Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Manually insert fului es IF i equia ed When TRUE (1) then triggers l&2 should fire.
VERIFY Simulator PRINTER and 1) REMOVE any printouts on BOTH procedures are cleaned. PRINTERS after each JPM.
- 2) REPLACE/CLEAN marked up procedures and Operator aids.
Setup
- Withdraw CB D to 184 steps, allow temp to stabilize when temp is +0.5°F Freeze the simulator.
Run quick setup BAT file 201 2nrcexamjpma.txt
- BAT file contains fol1owin required presets:
- CMFmalf/ cbkrxtrpcc2l closed CMFmalf/ cbkrxtrpcc22 closed PREVENTS RX TRIP BREAKER AUTO or Manual operation.
FNP ILT-35 JPM SIMULATOR JPM A. Page 3 of 13 (Guide pages = 12)
TRIGGER SETUP:
Trigger 1 &2: monitors for outward rod motion manual(SB A) or Auto ACTION: inserts Stationary Gripper malfunction on G3 and N7 Rods trgset 1 jpcsout trg 1 imfmal-rod5Ol trgset 2 jpcsout t
trg 2 Nmfmal-rod5O4 SNP 217 [tm]
CONDITIONS When I tell you to begin, you are to perform step 4.2 of STP-5.O, Full Length Control Rod Operability Test.
The conditions under which this task is to be performed are:
- a. The Plant is at 72% power.
- b. Previous STP-5.0 performance was UNSAT due to Shutdown Bank A testing.
- c. Maintenance is complete and a partial performance of STP-5 .0 is required for Post Maintenance Acceptance Testing.
- d. You have been directed to perform step 4.2 of STP-5.0.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE:
- The Failure is TRIGGERED to occur on OUTWARD ROD MOTION ONLY. This event may be manually initiated.
- NMP-OS-001 section 6.1.2.2 states that the OATC is required to obtain concurrence prior to performing planned reactivity manipulations. ALSO, section 6.1.2.3 REQUIRES that these manipulations are PEER CHECKED.
If requested prior to rod motion CUE: The SS concurs with your Reactivity manipulation.
A PEER CHECK request is acknowledged (STP-5.0 step 4.2.1)
- 1. RECORD the STEP COUNTER reading for D RECORD 227 steps for both S / U Shutdown Bank A Groups 1 and 2. Shutdown Bank A:
o Group 1 o Group 2.
(STP-5.0 step 4.2.2)
- 2. Place the ROD CONTROL BANK SELECTOR Li POSITION the ROD BANK S / U SWITCH in the SB A position SELECTOR SWITCH COUNTER CLOCKWISE-to the SBA position
FNP ILT-35 JPM SIMULATOR JPM A. Page 5 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(STP-5.0 step 4.2.3)
- 3. Verify indicated control rod speed is Z LOCATE SI-408 and CHECK S / U approximately 62 steps per mm on SI-408. approximately 62 steps per mill indicated.
NOTE:
- The actions of the following element will cause FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, alarm. This is an expectcd alam per P&L
. If a candidate were to direct or initiate the ARP actions, then CUE (as required): A second Operator will perform those actions. The Shift Supervisor directs you to continue with the STP.
(STP-5.0 step 4.2.4.1)
- 4. Using the CONTROL ROD MOTION switch, Position CONTROL ROD S / U drive Shutdown Bank A 10 steps into the core MOTION switch UP to the and observe RODS IN light. RODS IN position (STP-5.0 P&L 2.5) CHECK RODS IN light -LIT
[...] Any single bank may be inserted as far as 15 steps from the ARO position for this test. STOPS rod motion at >10 steps, BUT< 15 steps (STP-5.0 step 4.2.4.2)
- 5. Verify individual rod movement by observing U CHECK DRPI system S / U DRPI system indicators, indicators for SB A
FNP ILT-35 JPM SIMULATOR JPM A. Page 6 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(STP-5.0 step 4.2.4.3)
- 6. Using the CONTROL ROD MOTION switch, POSITIONS CONTROL ROD S / U return Shutdown Bank A to the original position MOTION switches DOWN to recorded in Step 4.2.1 and observe RODS OUT the RODS OUT position.
light.
IDENTIFY 2 dropped RODS (AOP-19 entry conditions)
NOTE: The following alarms/conditions will be observable:
o FB4,FB5,FC5,FF5 o PR NI flux tilt o RCS pressure lowers 1950 psig.
o RCStemp<541°F (AOP- 19 step 1-immediate operator action step)
- 7. Verify NO load change in progress CHECKs that NO load change S / U is occulTing using any of the following:
PT-4461PT-447- Stable DEH Console/CRT MW -
stable OTHER El DETERMINES NO load change is in progress.
NOTE:
- IF AUTO is selected, CB D will step out due to temperature mismatch, creating a larger flux tilt, this is NOT acceptable.
IF MAN is selected there is NO consequence AND, although NOT required per AOP-19.0, is NOT appropriate per P&L 2.10 of SOP-41.0 which states: [. . .For.. .1 Dropped or misaligned rods [...] the ROD CONTROL BANK SELECTOR SWITCH should be placed in MANUAL and rods shall be held without movement until the issue is resolved.
FNP ILT-35 JPM SIMULATOR JPM A. Page 7 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(AOP-l 9 step 2-immediate operator action step)) SD A will be selected. It is
- 8. CHECK ROD MOTION is unexplained acceptable to leave the ROD S/U CONTROL BANK SELECTOR (AOP-19 step 2.1) SWITCH in the SBA position.
- a. IF rod control In AUTO, THEN place rod control in MANUAL. Z THIS STEP IS N/A; however MAN position may be selected (AOP-19 RNO step 2.1) per NOTE above.
- b. IF rod control in MANUAL THEN place rod control in AUTO Z CHECKs that RODS are moving properly and DOES NOT reposition ROD BANK SELECTOR SWITCH; this step is NOT APPLICABLE.
- IF repositioned, it is critical that the final position is NOTAUTO (MANUAL is acceptable)
PROCEED TO ELEMENT 10 if PROPERLY performed.
NOTE:
- ELEMENT 9 IS N/A- it has been provided ONLY for the Evaluator to follow actions IF incorrect manipulation of step 2.1.
(AOP- 19 RNO step 2.1.1 -immediate operator action step)
- 9. IF AUTO rod motion due to TAVG/TREF mismatch, IF placed in AUTO then Rods OUT is the S I U THEN verify rod motion stops when TAVG is within 1 PROPER operation of CB D.
degree of TREF E CHECKs that RODS are moving (AOP-19 step 2.2) properly IF unexplained ROD motion NOT stopped, THEN perform IDENTIFIES RODS moving the following: OUT E TR-408/TI-408 show NEGATIVE (AOP-19 step 2.2.1) VALUE < (-)5°F TRIP the Reactor DETERMINES ROD MOTION IS EXPLAINED NOTE: If determined UNEXPLAINED a RX trip will be initiated under the following guidance--- proceed to element 11.
FNP ILT-35 JPM SIMULATOR JPM A. Page 8 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(AOP- 19 step 3 & RNO actions)
- 10. Check that no dropped rod(s) exist(s) in Mode 1 CHECKs that two (2) Rods S/U OR during a reactor startup. have dropped:
Li Rod G3 rod bottom light-LIT (AOP-19 RNO step 3.1) Li Rod N7 rod bottom light-LIT IF MORE THAN ONE dropped rod exists, Li PR Nis- MISMATCHED THEN perform the following: Li RCS pressure and Temp
- Trip the Reactor LOWERED
- Go to FNP- 1 -EEP-0, Reactor Trip or Safety Injection. Li OPERATES EITHER the RX TRIP switch(s) in the COUNTER CLOCKWISE DIRECTION.
CENTER section switch Z LEFT-SIDE switch (EEP-0.0 Step 1)
- 11. Check reactor trip. Li CHECKs that the RX has S / U Reactor trip and bypass breakers OPEN tripped.
Nuclear power FALLING Li Reactor trip and bypass IF DRPI available THEN rod bottom lights breakers CLOSED LIT Li Nuclear power STABLE or RISING (except as response to previous dropped rods)
Li IF DRPI available THEN rod bottom lights ONLY 2 LIT.
(EEP-0.0 RNO step 1.1)
Manually trip reactor. Li OPERATES the RX TRIP switch(s) in the COUNTER CLOCKWISE DIRECTION.
Li CENTER section switch Li LEFT-SIDE switch NOTE: BOTH switches are expected to be operated at least once between the two elements 10 and 11.
FNP ILT-35 JPM SIMULATOR JPM A. Page 9 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(EEP-O.O RNO 1.1)
- 12. IF reactor can NOT be tripped, THEN trip both *POSITION5 the MG set S / U MG set supply breakers. supply breaker hand switches El N1CI IEOO5A in the CLOCKWISE
[]NIC11EOO5B DIRECTION.
NlCllEOO5A OBSERVES the RX TRIP is Successful N1CI1EOO5A- GREEN LIGHT LIT N1C1IEOO5B-GREEN LIGHT LIT LI Rod bottom lights ALL LIT Li JR NI Flux Lowering NOTE: BOTH MG set supply breakers MUST BE OPERATED to be successful.
(EEP-O.O Step 2)
- 13. Check turbine Trip. LI OBSERVES TSLB2 S / U
[] TSLB2 14-1 LIT
[] TSLB2 14-2 LIT LI Positions MAIN TURB
[] TSLB2 14-3 LIT EMERG TRIP switch the
[] TSLB2 14-4 LIT COUNTER-CLOCKWISE direction E OBSERVES RED LIGHT-NOT LIT TSLB2 lights COL 14- ALL LIT LI HOLDS for 5 secs.
NOTE: AN Automatic Turbine Trip MAY occur IF an SI actuates prior to manually Tripping the Main Turbine.
FNP ILT-35 JPM SIMULATOR JPM A. Page 10 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(EEP-0.0 step 3)
- 14. Verify power to 4160 V ESF busses. CHECKS the following: S/U (EEP-0.O step 3.1) iF 41 60V bus power available 4160 V ESF busses AT LEAST TRAIN light LIT ONE ENERGIZED 1K 4160V bus power
- iF 4160V bus power available light LIT available light LIT
- 1 G 41 60V bus power available light LIT lG4l60Vbuspower available light LIT (EEP-0.0 step 3.2) IL 4160V bus power available 4160 V ESF busses BOTH TRAINS light LIT ENERGIZED
- A Train (iF & 1K) power available lights lit 1-2A, 1B, 1C DIESELS for
- B Train (1G & IL) power available lights lit operation using any means:
MLB-4 (pump status)
(EEP-0.0 step 3.3)
SEQ Status lights
[CAJ Verifi operating diesel generator(s) -
SUPPLIED FROM AT LEAST ONE SW DG output bkrs PUMP D DG speed IF DG running: then IA OR lB SW pump brkr
-RED light LIT IC or 1D SW pump brkr RED light LIT 1 SW header pressure in both A & B trains> 60 psig
FNPILT-35JPM SIMULATORJPMA. Page 11 of 13 (Guide pages = 12)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(EEP-0.0 step 4)
(EEP-0.0 step 4.1)
Check any SI actuated indication BOTH MLB1 1-1 & 11-1 -
BYP & PERM Panel SI actuated LIT -
LIT MLBI 1-1-LIT MLB 111-ILIT IF SI has NOT actuated, (EEP-0 RNO step 4.1) CHECKS the following If any setpoint and coincidence shown in the PT-950 through PT-954 <4 table below has been reached or exceeded psig.
THEN SI is required. TSLB-1 for 2/3 col 1 NOT LIT (EEPO RNO STEP 4.1.2) TSLB-2 for 2/3 col 17-NOT IF SI is required, Actuate SI. LIT PT-402/403 OR PT (EEP-0.0 step 4.2) 455/456/457> 1850 psig.
Verify BOTH TRAINS of SI -ACTUATED E SG pressures > 585 psig TSLB 4 NO coincidence met.
STOP TIME Terminate when the Immediate Operator Actions have been completed AND when ESP-0. I transition is made or STEP 5 of EEP-0 started.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-AOP-19.0, V 29.0 FNP-1-EEP-0.0, Rev 43
- 2. K/As: 001A4.03 RO-4.0 SRO-3.7 001A2.l1 RO-4.4 SRO-4.7 003AA2.03 RO-3.6 SRO-3.8 007EA2.02 RO-4.3 SRO-4.6 GENERAL TOOLS AND EQUIPMENT:
FNP ILT-35 JPM SIMULATOR JPM A. Page 12 of 13 (Guide pages = 12)
Provide/Acquire:
I. A marked up copy of FNP-1-STP-5.O; mark up as described in INSTRUCTIONS.
- 2. AOP-19.0, EEP-0.O will be acquired from Simulator (IOA pages will require cleaning/replacements)
Critical ELEMENT justification:
STEP Evaluation 1 Not critical this is a logging step only 2 CRITICAL- Required for task completion, movement of PROPER rod bank.
3 Not critical check step only 4 CRITICAL- Required for task completion.
5 Not critical check step only 6 CRITICAL- Required for task completion, and will initiate the ALTERNATE path.
7 Not critical step is a check step.
8 Not critical This step is N/A, no rod motion occurring, it is not expected the candidate touch the ROD CONTROL BANK SELECTOR SWITCH.
9 Not critical step is provided as contingency upon failure to perform element 8 propei ly If yet another improper evaluation is made, then the task will advance to element 11.
10 Not critical this step is a diagnostic step and if improper diagnosis is performed element 12 will NOT be performed.
11 Not critical this step will be unsuccessful due to the snap blocking RTBs from opening 12 CRITICAL Since NO automatic RX trip setpoints will be exceeded, no automatic RPS will occur. (safety sijinificance) Operating outside of designed assumptions for accident analysis;> 1 dropped rod may result in exceeding power peaking factors (Hot Channel) under some accident conditions if the Rx is not tripped manually.
Additionally, since the RPS system (Manual switches) failed to cause a RX trip, the FSAR safety significance of an ATWT is encountered.
- 13. Not critical- The Main Turbine will not automatically trip due to MG ste breakers being opened vs. RTBs, but a Turbine Trip will occur if an SI occurs, which is probable since there is only one operator, and this will provide the necessary CORE and GENERATOR protection.
14 -15 Not critical Actions will occur properly and no operator action is required.
COMMENTS:
FNP ILT-35 JPM JPM SIMULATOR JPM A. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to perform step 4.2 of STP-5.O, Full Length Control Rod Operability Test.
The conditions under which this task is to be performed are:
- a. The Plant is at 72% power.
- b. Previous STP-5.O performance was UNSAT due to Shutdown Bank A testing.
- c. Maintenance is complete and a partial performance of STP-5.O is required for Post Maintenance Acceptance Testing.
- d. You have been directed to perform step 4.2 of STP-5.O.
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-l-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 1 of 22 S
A F
E T
Y FULL LENGTH CONTROL ROD OPERABILITY TEST 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: David L. Reed (for) Date Approved: April 20. 2011 Operations Manager
U N IT I Farley Nuclear Plant Procedure Number Ver FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 153243
. TEST 2of22 SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-1-STP-5.O SR 3.1.4.2 TITLE M 0 DE S RE UIRING TEST FULL LENGTH CONTROL ROD OPERABILITY 2
TEST TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY: I DATE\TIME (Print) (Signature)
COMPONENT OR TRAIN TESTED (IF APPLICABLE)
[ } ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT
[] PARTIAL STP PERFORMED [] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL:
TEST COMPLETED: [ j SATISFACTORY [] UNSATISFACTORY
[] THE FOLLOWING DEFICIENCIES OCCURRED:
[] CORRECTIVE ACTION TAKEN OR INITIATED SHIFT SUPERVISOR I SHIFT SUPPORT SUPERVISOR REVIEW
[] PROCEDURE PROPERLY COMPLETED AND SATISFACTORY PER STEP 9.1 OF FNP-O-AP-5
[ j COMMENTS:
REVIEWED BY I DATE (Print) (Signature)
- Reviewer must be AP-31 Level II certified & cannot be the Performing Individual ENGINEERING SUPPORT SCREENED BY______________________ DATE GROUP SCREENING (IF APPLICABLE)
{ ] COMMENTS:
Procedure Number Ver U N IT I Farley Nuclear Plant FNR-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 3of22 Procedure Version Description Version Number Version Description 25.0 Updated procedure to requirements of NMP-OS-008001, Operations Procedure Writing Instructions Added step 4.15.
26.0 Applied procedure formatting per NMPAP-002.
Removed guidance for cycling rod groups to displace crud buildup.
(Al 2011201184)
Procedure Number Ver U N IT I Farley Nuclear Plant EN P-i -STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 4of22 Table of Contents Page 1.0 PURPOSE 5 2.0 PRECAUTIONS AND LIMITATIONS 5 3.0 INITIAL CONDITIONS 6 4.0 INSTRUCTIONS 7 4.2 SHUTDOWN BANKA 8 4.3 SHUTDOWN BANK B 10 4.4 CONTROL BANKA 12 4.5 CONTROL BANK B 14 4.6 CONTROLBANKC 16 4.7 CONTROL BANKD 18
5.0 REFERENCES
20 APPENDIX I BANK D ROD MOVEMENT FOR TROUBLESHOOTING 21 TABLE 1 22
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 5of22 1.0 PURPOSE 1.1 To demonstrate the operability of the full length control rods.
1.2 ACCEPTANCE CRITERIA 1.2.1 Each full length control rod not fully inserted responds correctly to control signals, and is moved at least 10 steps in either direction.
1.2.2 Asterisked steps (*) are those associated with Acceptance Criteria.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Variations in turbine load and boron concentration should be avoided during this test.
2.2 Carefully monitor reactor conditions during all rod manipulations. Correct any abnormal conditions by repositioning the control bank being used for control.
2.3 Ensure that all parameters return to their original values after a tested control bank has been returned to its original position, before testing the next control bank.
2.4 Before transferring to automatic reactor control, manually adjust TAVG to within +/- 1°F of the reference temperature to avoid a transient following the transfer.
2.5 With rods being operated in MAN or AUTO, ensure that rods are above the low-low insertion limit by a minimum of 10 steps (unless being performed during reactor startup) Concerning Control banks A,B,C and Shutdown banks A and B being operated in Individual Bank Select mode, the rod insertion limits provided on Curve 2 do not apply. Any single bank may be inserted as far as 15 steps from the ARO position for this test. (Ref. Core Analysis procedure NF-CAP-200, Attachment 1 Step 14) (CR 2009100757) 2.6 If any rod in a bank is determined to be INOPERABLE, then return the rod to operable status before testing the next rod bank.
2.7 Only the steps for the applicable shutdown bank or control bank being tested need to be signed off. The other steps can be marked N/A with Shift Supervisors review and approval as designated by his initial next to the steps that are marked N/A.
2.8 Shutdown bank and control bank testing may be performed in any sequence.
2.9 The following alarm is expected during this test:
- FF5 COMP ALARM ROD SEQ/DEV OR PR FLUX TILT 2.10 The following alarms may be expected during this test, depending on initial rod height and rod full out position:
- FE1 - CONT ROD BANK POSITION LO
- FD5 - BANK D FULL ROD WTHDRL AUTO ROD STOP (220 steps)
Procedure Number Ver U N IT I Farley Nuclear Plant FNR1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 6of22 2.11 Generate a condition report when any alarm function is suspected to be inoperable.
2.12 For any control rod anomaly promptly contact and discuss the event with management. Due to the potential for a dropped rod and a resultant reactor trip.
(CR2005105949) 2.13 Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, REACTIVITY MANAGEMENT PROGRAM.
2.14 The SM/SS shall be notified if any acceptance criteria are N.QI satisfied.
3.0 INITIAL CONDITIONS 3.1 Check that the current copy of this procedure is the correct version.(OR 1-98-498) 7.
Initial 3.2 Check that the current copy of this procedure is correct for the unit.
(OR 1-98-498) 7, Initial 3.3 If in Mode 3, then verify the requirements are met for enabling rod control per FNP-1-STP-351C, ENABLING ROD CONTROL SYSTEM SURVEILLANCE CHECKLIST. (IR 2-96-025)
Initial 3.4 Check that the Rod control system is aligned per FNP-1 -SOP-41 .0, Control Rod Drive and Position Indication System.
Initial 3.5 Check that the reactor trip breakers are shut.
Initial
Procedure Number Ver U N IT I Farley Nuclear Plant A FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 7of22 4.0 INSTRUCTIONS If this procedure is only being used to test/troubleshoot the rod control circuit using Control Bank D, then mark the remainder of Section 4.0 N/A and perform Appendix 1.
4.1 *IF either of the following conditions applies: N/A Initial
- A Rx startup is in progress
- FNP-0-ETP-3643, Verification Of Rod Control System Operability THEN perform the following:
4.1.1 Complete Table 1 as each bank is withdrawn at least 10 steps for complete credit for this STP. N/A Initial 4.1.2 N/A steps 4.2 through 4.7. N/A Initial 4.1.3 PerformStep4.8. N/A Initial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant A FNP-1-STP-5.o 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 8of22 SHUTDOWN BANKA 4.2.1 Record the STEP COUNTER reading for Shutdown Bank A Groups 1 and 2.
Initial
- Shutdown Bank A Group 1
- Shutdown Bank A Group 2 4.2.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the SB A position.
Initial 4.2.3 Verify indicated control rod speed is approximately 62 steps per mm. on Sl-408.
Initial 4.2.4
- Shutdown Bank A withdrawn, THEN perform the following steps:
4.2.4.1 Using the CONTROL ROD MOTION switch, drive Shutdown Bank A 10 steps into the core and observe RODS IN light.
Initial 4.2.4.2 Verify individual rod movement by observing DRPI system indicators.
Initial 4.2.4.3 Using the CONTROL ROD MOTION switch, return Shutdown Bank A to the original position recorded in Step 4.2.1 and observe RODS OUT light.
Initial 4.2.4.4 Verify individual rod movement by observing DRPI system indicators.
Initial 4.2.4.5 Verify satisfactory or unsatisfactory movement of each Shutdown Bank A rod and record results in Table 1.
Initial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 9of22 4.2.5
- Shutdown Bank A inserted, THEN perform the following steps:
4.2.5.1 Using the CONTROL ROD MOTION switch, pull Shutdown Bank A 10 steps out of the core and observe RODS OUT light.
Initial 4.2.5.2 Verify individual rod movement by observing DRPI system indicators.
Initial 4.2.5.3 Using the CONTROL ROD MOTION switch, return Shutdown Bank A to the original position recorded in Step 4.2.1 and observe RODS IN light.
Initial 4.2.5.4 Verify individual rod movement by observing DRPI system indicators.
Initial 4.2.5.5 Verify satisfactory or unsatisfactory movement of each Shutdown Bank A rod and record results in Table 1.
Initial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.2.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to re-establish stable reactor conditions.
Initial 4.2.7 Verify proper indicated control rod speed:
Initial
- 48 steps per mm. on Sl-408 if in MAN
- 8 steps per mm. on Sl-408 if in AUTO
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 100f22 4.3 SHUTDOWN BANK B 4.3.1 Record the STEP COUNTER readings for Shutdown Bank B P . Step N/Ad due to Initial
- Partial performance
- Shutdown Bank B Group 1 on Shutdown Bank A ONLY. MM/DDIYY
- Shutdown Bank B Group 2 mm/dd/
4.3.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the SB B position.
Intial 4.3.3 Verify indicated control rod speed is approximately 62 steps per mm. on Sl-408.
In tial 4.3.4 F Shutdown Bank B withdrawn, THEN perform the following steps:
4.3.4.1 Using the CONTROL ROD MOTION switch, drive Shutdown Bank B 10 steps into the core and observe RODS IN light.
In :ial 4.3.4.2 Verify individual rod movement by observing DRPI system indicators.
In ial 4.3.4.3 Using the CONTROL ROD MOTION switch, return Shutdown Bank B to the original position recorded in Step 4.3.1 and observe RODS OUT light.
In ial 4.3.4.4 Verify individual rod movement by observing DRPI system indicators.
In ial 4.3.4.5 Verify satisfactory or unsatisfactory movement of each Shutdown Bank B rod and record results in Table 1 Initial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 11of22
- E 435 Shutdown Bank B inserted, THEN perform the following steps:
4.3.5.1 Using the CONTROL ROD MOTION switch, pull Shutdown Bank B 10 steps out of the core and observe RODS OUT light. step N/Ad due to N/A Partial performance Initial on Shutdown Bank A 4.3.5.2 Verify individual rod movement by observing DRPI ONLY. MM/DD/YY system indicators.
)zmfd4/q4/ In tial 4.3.5.3 Using the CONTROL ROD MOTION switch, return Shutdown Bank B to the original position recorded in Step 4.3.1 and observe RODS IN light.
lntial 4.3.5.4 Verify individual rod movement by observing DRPI system indicators.
Intial 4.3.5.5 Verify satisfactory or unsatisfactory movement of each Shutdown Bank B rod and record results in Table 1.
Intial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.3.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to re-establish stable reactor conditions.
Intial 4.3.7 Verify proper indicated control rod speed:
Intial
- 48 steps per mm, on SI-408 if in MAN
- 8 steps per mm. on S 1-408 if in AUTO
U N IT I Farley Nuclear Plant Procedure Number Ver FNP-1-STP-5.o 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 12 of 22 4.4 CONTROL BANKA 4.4.1 Record the STEP COUNTER reading for Control Bank A Groups 1 and 2. Step N/Ad due to 7 N/A Partial performance Initial on Shutdown Bank A
- Control Bank A Group 1 ONLY. MM/DD/YY
- Control Bank A Group 2 nun, 4.4.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the CB A position.
mi ial 4.4.3 Verify indicated control rod speed is approximately 48 steps per mm. on Sl-408.
Ini ial 4.4.4 lF at power, THEN perform the following steps:
4.4.4.1 Using the CONTROL ROD MOTION switch, drive Control Bank A 10 steps into the core and observe RODS IN light.
Ini ial 4.4.4.2 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.4.4.3 Using the CONTROL ROD MOTION switch, return Control Bank A to the original position recorded in Step 4.4.1 and observe RODS OUT light.
ni ial 4.4.4.4 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.4.4.5 Verify satisfactory or unsatisfactory movement of each Control Bank A rod and record results in Table 1.
Initial r ACCEPTANCE CRITERIA I Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 13of22 445 prior to startup, THEN perform the following steps:
4.4.5.1 Using the CONTROL ROD MOTION switch, pull Control Bank A 10 steps out of the core and observe RODS.
OUT light step N/Ad due to Partial performance Initial on Shutdown Bank A 4.4.5.2 Verify individual rod movement by observing DRPI ONLY. MM/DDIYY system indicators.
iiun/dd/qçt Ini ial 4.4.5.3 Using the CONTROL ROD MOTION switch, return Control Bank A to the original position recorded in Step 4.4.1 and observe RODS IN light.
Ini ial 4.4.5.4 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.4.5.5 Verify satisfactory or unsatisfactory movement of each Control Bank A rod and record results in Table 1.
Ini ial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.4.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to reestabIish stable reactor conditions.
Ini al 4.4.7 Verify proper indicated control rod speed:
Ini al
- 48 steps per mm. on SI-408 if in MAN
- 8 steps per mm. on Sl-408 if in AUTO
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY Page Number TEST 14 of 22 4.5 CONTROL BANK B 4.5.1 Record the STEP COUNTER reading for Control Bank Groups I and 2. otep N/Ad due to Partial performance Initial on Shutdown Bank A
- Control Bank B Group 1 ONLY. MM/DD/YY
- Control Bank B Group 2 mm/cLd/t 4.5.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the CB B position.
Inial 4.5.3 Verify indicated control rod speed is approximately 48 steps per mm. on SI-408.
In ial 4.5.4 9F at power, THEN perform the following steps:
4.5.4.1 Using the CONTROL ROD MOTION switch, drive Control Bank B 10 steps into the core and observe RODS IN light.
Ini ial 4.5.4.2 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.5.4.3 Using the CONTROL ROD MOTION switch, return Control Bank B to the original position recorded in Step 4.5.1 and observe RODS OUT light.
Ini ial 4.5.4.4 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.5.4.5 Verify satisfactory or unsatisfactory movement of each Control Bank B rod and record results in Table 1.
Ini ial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant A FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 15of22 455 prior to startup, THEN perform the following steps:
4.5.5.1 Using the CONTROL ROD MOTION switch, pull Bank B 10 steps out of the core and observe ROD P9j/Ad due to IartiaI performance N/A OUT light.
on Shutdown Bank A Initial ONLY. MM/DD/YY 4.5.5.2 Verify individual rod movement by observing DRPI system indicators. Icicf 4
fjLId mit al 4.5.5.3 Using the CONTROL ROD MOTION switch, return Control Bank B to the original position recorded in Step 4.5.1 and observe RODS IN light.
lnital 4.5.5.4 Verify individual rod movement by observing DRPI system indicators.
Inital 4.5.5.5 Verify satisfactory or unsatisfactory movement of each Control Bank B rod and record results in Table 1.
htal ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.5.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to re-establish stable reactor conditions.
Inital 4.5.7 Verify proper indicated control rod speed:
Inital
- 48 steps per mm. on S 1-408 if in MAN
- 8 steps per mm. on S 1-408 if in AUTO
U N IT I Farley Nuclear Plant Procedure Number Ver FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 16of22 4.6 CONTROL BANK C 4.6.1 Record the STEP COUNTER reading for Control BankC ,
Groups 1 and 2. iep N/Ad due to N/A Partial performance Initial on Shutdown Bank A
- Control Bank C Group 1 ONLY. MM/DD/YY
- Control Bank C Group 2 ,
m 0 m/d41q41 4.6.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the CB C position.
Ini ial 4.6.3 Verify indicated control rod speed is approximately 48 steps per mm. on Sl-408.
lni ial 4.6.4 at power, THEN perform the following steps:
4.6.4.1 Using the CONTROL ROD MOTION switch, drive Control Bank C 10 steps into the core and observe RODS IN light.
Ini al 4.6.4.2 Verify individual rod movement by observing DRPI system indicators.
Ini al 4.6.4.3 Using the CONTROL ROD MOTION switch, return Control Bank C to the original position recorded in Step 4.6.1 and observe RODS OUT light.
Ini al 4.6.4.4 Verify individual rod movement by observing DRPI system indicators.
Ini al 4.6.4.5 Verify satisfactory or unsatisfactory movement of each Control Bank C rod and record results in Table 1.
Init,al ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY Page Number TEST 17of22 4.6.5
- prior to startup, THEN perform the following steps:
4.6.5.1 Using the CONTROL ROD MOTION switch, pull Control Bank C 10 steps out of the core and observe RODS St N/Ad due to N/A OUT light.
Partial performance Initial on Shutdown Bank A 4.6.5.2 Verify individual rod movement by observing DRPI ONLY. MM/DD/YY system indicators.
lni ial 4.6.5.3 Using the CONTROL ROD MOTION switch, return Control Bank to the original position recorded in Step 4.6.1 and observe RODS IN light.
lni ial 4.6.5.4 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.6.5.5 Verify satisfactory or unsatisfactory movement of each Control Bank C rod and record results in Table 1.
Ini ial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.6.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to re-establish stable reactor conditions.
Ini ial 4.6.7 Verify proper indicated control rod speed:
Ini ial
- 48 steps per mm. on Sl-408 if in MAN 8 steps per mm. on 5 1-408 if in AUTO
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 FULL LENGTH CONTROL ROD OPERABILITY Page Number 6/1/2011 15:32:43 TEST 18of22 4.7 CONTROL BANKD I 4.7.1 Record the STEP COUNTER reading for Control Bank D Step N/Ad due to Groups 1 and 2. N/A Partial performance lnital on Shutdown Bank A
- Control Bank D Group 1 ONLY. MM/DD/YY
- Control Bank D Group 2 ,fjtIddIqy; 4.7.2 Place the ROD CONTROL BANK SELECTOR SWITCH in the CB D position.
mi ial 4.7.3 Verify indicated control rod speed is approximately 48 steps per mm. on Sl408.
ni ial 4.7.4 9f at power, THEN perform the following steps:
4.7.4.1 Using the CONTROL ROD MOTION switch, drive Control Bank D 10 steps into the core and observe RODS IN light.
lni ial 4.7.4.2 Verify individual rod movement by observing DRPI system indicators.
Ini ial 4.7.4.3 Using the CONTROL ROD MOTION switch, return Control Bank D to the original position recorded in Step 4.7.1 and observe RODS OUT light.
Ini al 4.7.4.4 Verify individual rod movement by observing DRPI system indicators.
mi ial 4.7.4.5 Verify satisfactory or unsatisfactory movement of each Control Bank D rod and record results in Table 1.
ni ial ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
U N IT I Farley Nuclear Plant A Procedure Number Ver FNP-1-STP-5.0 26.0 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY Page Number TEST 19of22 475 prior to startup, THEN perform the following steps:
4.7.5.1 Using the CONTROL ROD MOTION switch, pull Control Bank D 10 steps out of the core and observe RODS Step N/Ad due to OUT light. Partial performance N/A on Shutdown Bank A Initial 4.7.5.2 Verify individual rod movement by observing DRPI ONLY. MM/DDIYY system indicators.
mi aI 4.7.5.3 Using the CONTROL ROD MOTION switch, return Control Bank D to the original position recorded in Step 4.7.1 and observe RODS IN light.
Ini al 4.7.5.4 Verify individual rod movement by observing DRPI system indicators.
lni al 4.7.5.5 Verify satisfactory or unsatisfactory movement of each Control Bank D rod and record results in Table 1.
Inital ACCEPTANCE CRITERIA Rods move greater than or equal to 10 steps.
4.7.6 Return ROD CONTROL BANK SELECTOR SWITCH to the MAN or AUTO position, as required, to re-establish stable reactor conditions.
Inital 4.7.7 Verify proper indicated control rod speed:
Inital
- 48 steps per mm. on 5 1-408 if in MAN
- 8 steps per mm. on S1-408 if in AUTO
Procedure Number Ver U N IT I Farley Nuclear Plant FNP-1-STP-5.0 26.0 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY Page Number TEST 20 of 22 4.8 Verify P to A Converter agrees with current plant conditions as follows.
4.8.1 In cabinet N1C11LOO7-N, at the P-A Converter, select eachStep N/Ad due to 7
Control Bank indicated below and record the BANK Partial performance POSITION DISPLAY in the space provided, on Shutdown Bank A N/A Initial ONLY. MM/DDIYY Control Bank Bank Position Display A
B C
D 4.8.2 Return the P-A Converter display switch to OFF.
mi ial 4.8.3 Compare each bank position display obtained in Step 4.8.1 to actual rod position and notify the Shift Supervisor of any differences.
Ini ial
5.0 REFERENCES
5.1 U-266647, Precautions, Limitations and Setpoints for Nuclear Steam Supply Systems.
5.2 NEL-98-0266 letter dated 7/16/98, from MJ Ajluni, to JR Johnson, titled Generic Evaluation Regarding 15 Step Rod Operability Test.
U N IT I Farley Nuclear Plant Procedure Number Ver FNP-1-STP-5.0 26.0 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY Page Number TEST 21 of 22 APPENDIX 1 BANK D ROD MOVEMENT FOR TROUBLESHOOTING NOTE The following sequence may be repeated as necessary for troubleshooting. However, subsequent performance should be delayed long enough to determine the affect on axial offset.
N/A 1.0 Record the STEP COUNTER reading for Control Bank D Groups 1 and 2.
Step N/Ad due to Ini a1 Partial performance
- Control Bank D Group 1 on Shutdown Bank A
- Control Bank D Group 2 ONLY. MM/DD/YY 2.0 Place the ROD CONTROL BANK SELECTOR SWITCH in the MAN position.
Ini al 3.0 Verify indicated control rod speed is approximately 48 steps per mm. on S 1-408.
lnital 4.0 Using the CONTROL ROD MOTION switch, drive Control Bank D 10 to 15 steps into the core and observe RODS IN light.
Inital 5.0 Using the CONTROL ROD MOTION switch, return Control Bank D to the original position recorded in Step 1.0 and observe RODS OUT light.
Inital 6.0 WHEN desired, return ROD CONTROL BANK SELECTOR SWITCH to the AUTO position.
Inital 7.0 Verify indicated control rod speed is approximately 8 steps per mm. on Sl-408.
Inital
Procedure Number Ver I U N IT I I Farley Nuclear Plant FNP-1-STP-5.0 26.01 Page Number I 6/1/2011 15:32:43 FULL LENGTH CONTROL ROD OPERABILITY TEST 22of22 I TABLE 1 NOTE I If any Rod in a Bank is determined inoperable, then return Rod to operable status before testing next Rod Bank.
I SHUTDOWN SHUTDOWN CONTROL CONTROL CONTROL CONTROL BANKA BANK B BANKA BANK B BANK C BANKD Rod G3 I Rod E5 / /
Rod C9 I Rod Eli I Rod Bi Rod B8 I Rod J13 Rod LII I Rod Ki4 Ki 2 / Hi4 I Rod N7 I Rod L5 I Rod P6 Rod P8 Rod J3 Rod G7 I Rod K2 I F6 Rod C7 I Rod G9 I Rod B6 Rod D6 I Rod FiO Rod G13 I Rod J9 I Rod N9
/ Rod J7 Rod MiO /
00 cI) clCD D CD
02/15/12 6 03 35 FNP-1-AOP-19 0 December 22, 2011 Version 29.0 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP- 1 -AOP- 19.0 S
A F
E T
Y MALFUNCTION OF ROD CONTROL SYSTEM R
B L
A T
E D
PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: Remainder of Procedure
Reference:
Steps 1 - 2 Information: NONE Approved by: David L Reed (for) Effective Date: December 31, 2011 Operations Manager
02/15/12 6:03:35 FNP-1-AOP-19.O MALFUNCTION OF ROD CONTROL SYSTEM Version 29.0 Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 9 Attachment 1 3 Attachment 2 3 Attachment 3 1 Attachment 4 1 Page 1 of 1
02/15/12 6:03:35 FNP-l-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 29.0 A. Purpose This procedure provides actions for response to a malfunction of the rod control system.
This procedure is applicable when the rod control system is capable of rod withdrawal.
B. Symptoms or Entry Conditions I. This procedure is entered when a malfunction of the rod control system is indicated by any of the following:
- a. Significant reactivity insertion due to unexplained rod motion
- b. Failure of a control bank to move when required NOTE:
- A rod is considered dropped if it has fallen completely to the bottom of the core. A rod is considered misaligned if its DRPI indication disagrees with the group step counter demand position.
- Technical Specifications requires that all individual indicated rod positions be within 12 steps of their group step counter demand position.
- In general the rod group step counters and the DRPI rod position indications should agree within +/- four steps.
- c. One or more dropped rods in Mode 1 OR during reactor startup.
- d. One or more rods misaligned in Mode I OR during reactor startup.
- e. Complete loss of position indication for one or more rods.
Page 1 of9
02/15/12 6:03:35 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 29.0 Step Action/Expected Response Response Not Obtained NOTE: Steps I and 2 are IMMEDIATE OPERATOR actions.
I Verify NO load change in progress. 1 Check for cause of load change.
1.1 IF load rejection in progress or has occurred, THEN go to FNP-1-AOP-17.0, RAPID LOAD REDUCTION.
1.2 IF secondary leakage is indicated, THEN go to FNP-l-AOP-14.0, SECONDARY SYSTEM LEAKAGE.
2 IF unexplained rod motion occurring, THEN stop rod motion.
2.1 IF rod control in AUTO, 2.1 IF rod control in MANUAL, THEN place rod control in MANUAL. THEN place rod control in AUTO NOTE: In AUTO rod control, rods will step OUT if TAVG less than TREF by at least 1.5 degrees, and Rods will step IN if TAVG greater than TREF by at least 1.5 degrees.
2.1.1 IF AUTO rod motion due to TAVG/TREF mismatch, THEN verify rod motion stops when TAVG is within I degree of TREF 2.2 IF unexplained rod motion NOT stopped, THEN perform the following.
2.2.1 Trip the reactor 2.2.2 Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION Page Completed Page 2 of 9
02/15/12 6:03:35 FNP-l-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 29.0 Step Action/Expected Response Response Not Obtained I I NOTE:
- Dropped rod guidance is only applicable in Mode 1 QE during a reactor startup.
- At low power levels, RCS temperature may be reduced less than Minimum Temperature for Criticality (T.S. 3.42) and actions must be taken within 30 minutes.
3 Check that no dropped rod(s) exist(s) in 3 Determine number of dropped rods.:
Mode 1 during a reactor startup.
3.1 MORE THAN ONE dropped rod exists, THEN perform the following:.
3.1.1 Trip the Reactor.
3.1.2 Go to FNP- 1 -EEP-0, REACTOR TRIP OR SAFETY INJECTION.
3.2 j only ONE dropped rod exists, THEN perform the following:
3.2.1 Verify rod control in manual.
3.2.2 Restore RCS TAVG to programmed value
- Adjust turbine load.
- Adjust RCS boron concentration 3.3 Consult Technical Specifications 3.1.4, 3.1.5, 3.1.6 and 3.2.4.
3.4 Proceed to step 6.
Page Completed Page 3 of 9
FNP-1-EEP-O REACTOR TRIP OR SAFETY INJECTION Revision 43 Step Action/Expected Response Response NOT Obtained NOTE:
- Steps 1 through 4 are IMMEDIATE ACTION steps.
- FOLDOUT PAGE should be monitored continuously.
Check reactor trip. 1 Perform the following.
[1 Reactor trip and bypass 1.1 Manually trip reactor.
breakers - OPEN
[1 Nuclear power - FALLING 1.2 IF reactor can NQI be tripped,
[1 IF DRPI available, TEEN trip both MG set supply THEN rod bottom lights - LIT breakers.
[1 N1C11EOOSA H N1C11EOO5B 1.3 j reactor will trip, THEN go to FNP-1-FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWT.
2 Check turbine trip. 2 Perform the following.
[1 TSLB2 14-1 - LIT 2.1 Place main turbine emergency
[1 TSLB2 14-2 - LIT trip switch to TRIP for at
[1 TSLB2 14-3 - LIT least 5 seconds.
[1 TSLB2 14-4 - LIT 2.2 IF turbine can NQT. be tripped, THEN reduce GV position demand signal to zero from DEH panel.
[] TURBINE MANUAL depressed
[1 GV CLOSE depressed
[] FAST ACTION depressed 2.3 IF steam flow to main turbine is NOT secured, THEN close all main steam line isolation and bypass valves.
Page 5 of 35
FNP-l-EEP-0 REACTOR TRIP OR SAFETY INJECTION Revision 43 Step Action/Expected Response Response NOT Obtained I I I 3 Verify power to 4160 V ESF busses.
3.1 4160 V ESF busses - AT LEAST 3.1 Perform the following:
ONE ENERGIZED 3.1.1 Secure any diesel generator
. iF 4160V bus power available running without SW cooling light - LIT per ATTACHMENT 1, SHUTDOWN OF A DIESEL GENERATOR.
OR 3.1.2 Go to FNP-1-ECP-0.0, LOSS
. 1G 4160V bus power available OF ALL AC POWER.
light - LIT 3.2 4160 V ESF busses - BOTH 3.2 [CA] Try to restore power to TRAINS ENERGIZED deenergized 4160 V ESF bus using FNP-1-AOP-5.0, LOSS OF A
[1 A Train (iF & 1K) power OR B TRAIN ELECTRICAL POWER, available lights lit as time permits while
[1 B Train (1G & 1L) power continuing with this available lights lit procedure.
3.3 [CA] Verify operating diesel 3.3 IF service water flow can NOT generator(s) - SUPPLIED FROM be readily restored to a AT LEAST ONE SW PUMP running diesel generator, THEN secure the diesel generator using ATTACHMENT 1, SHUTDOWN OF A DIESEL GENERATOR.
Page 6 of 35
FNP-l -EEP-0 REACTOR TRIP OR SAFETY INJECTION Revision 43 Step Action/Expected Response Response NOT Obtained I I 4 Check SI Status.
4.1 Check any SI actuated 4.1 Check SI required.
indication.
4.1.1 any setpoint and BYP & PERMISSIVE coincidence shown in the SAFETY Table below has been INJECTION reached or exceeded,
[] ACTUATED status light lit THEN SI is required.
[] MLB-1 1-1 lit
[] MLB-1 11-1 lit Signal Setpoint Coincidence TSLB PRZR 1850 psig 2/3 TSLB2 PRESS LO 17-1 (If not 17-2 blocked) 17-3 STEAM LINE 100 psid 1 steam line TSLB4 DIFFERENTIAL 100 psig less 10-2, 10-3, 10-4, PRESSURE than other 11-2, 11-3, 11-4, two on 2/3 12-2, 12-3, 12-4, protection 13-2, 13-3, 13-4, sets 14-2, 14-3, 14-4.
15-2, 15-3, 15-4, LOW STEAM 585 psig 2/3 TSLB4 LINE PRESS. (rate 19-2 (If not compensated) 19-3 blocked) 19-4 CONTAINMENT 4 psig 2/3 TSLB1 PRESSURE 1-2 HIGH 1-3 1-4 4.1.2 SI is required, THEN actuate SI.
4.1.3 IF SI required, THEN go to FNP-l-ESP-O.l, REACTOR TRIP RESPONSE.
4.2 Verify both trains of SI- 4.2 Manually actuate SI.
ACTUATED.
[1 MLB1 1-1 AND MLB1 11-1 lit Page 7 of 35
FNP ILT-35 JPM Page 1 of 7 SIMULATOR JPM B.
CRO-(NEW 1)
TITLE: Re-establish HHSI flow due to a SGTR per Attachment 3 of ESP-1.1, SI Termination.
EVALUATION LOCATION: 1 SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-218 LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Exarninee will be provided a marked up copy of ESP- 1.1, Attachment 3. All other references of the simulator will be available at the examinees discretion.
- 2. The actions of this task are intended to be perfonried 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 High Head Safety injection flow in at least One train.
Examinee:
Overall JPM Performance: Satisfactory 1J Unsatisfactory LI Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 2/1/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM SIMULATOR JPM B. Page 2 of 7 (Guide pages = 6)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-2 18 for JPM B Put STA group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
Setup
- Run quick setup BAT file 201 2nrcexamjpmb.txt
- BAT file contains fol1owin reiuired presets:
- malf/MAL-RCS4A 400 Inserts malfunction to prevent auto-swap on Low VCT level cmFmalf/Imf MAL-cCV 11 5Bdcc25 cmFmalf/ imf MAL-cCV1 1 5D_d_cc25 ALLOW PRZR lvi to fall to 15% Then, OPEN HV-8152 ESTABLISH l20 gprn Charging flow on FK-l22 (--42.2% demand)
Align Chg suctions to VCT Verify VCT level is >20%
FREEZE The simulator when PRZR level is 13%.
SNP 218 [tm]
CONDITIONS When I tell you to begin, you are to Re-establish HHSI flow due to a SGTR per Attachment 3 of ESP-L1, SI Termination.
The conditions under which this task is to be performed are:
- b. Normal Charging has been aligned.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE:
- SEQUENCE IS CRITICAL in Element 1: IF RWST suctions AND VCT suctions are closed simultaneously with a running Chg pump, operability will be challenged.
(step 1)
I. Align charging pump suction to OPENS BOTH by turning S / U RWST. Hand switch CLOCKWISE
[]Lcvll5B- RED LIGHT LIT
[]LCV1 15D RED LIGHT LIT Li CHECKS OPEN All of the following: CHG PUMP SUCTION HDR ISO
[]MOV813OA- RED LIGHT LIT
[]M0V8130B- RED LIGHT LIT
[]MOV8131A RED LIGHT LIT
[]MOV8131B- RED LIGHT LIT NOTE: Must be done after LCV115B or D OPENED.
(partial stroke is acceptable).
CLOSES BOTH by turning Hand switch COUNTER-CLOCKWISE
[]Q1E21LCV1 15C closed
[]Q1E21LCV1 15E closed
FNP ILT-35 JPM SIMULATOR JPM B. Page 4 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
Booth operator ____ imfccvp0lcdco2 If CHG pump suctions are not aligned to a suction source in 4 mm and 45 sec., THEN trip 1C CHG pump.
(step 2)
- 2. Verify charging pump mini flow valves OPEN. - CHECKS the following: S/U 1A(1B,IC)CHGPUMP MINIFLOW ISO
[]MOV8IO9A-RED light LIT
[]MOV81O9B-RED light LIT
[]MOV8IO9C-RED light LIT CHG PUMP MINIFLOW ISO
[]MOV8 106-RED light LIT (Step 3.1)
- 3. Isolate Letdown CHECKS the following S/U CLOSED:
LTDN ORIF ISO 45 GPM
[]HV8149A-GRN light LIT LTDN ORIF ISO 60 GPM
[]HV8149B-GRN light LIT
[jHV8149C-GRN light LIT Z POSITIONS the following in the COUNTER-CLOCKWISE direction:
[]HV8152-GRN light LIT NOTE:
- ANY one of the following closed satisfies the CRITICAL ASPECT of element 4 -
M0V8107, M0V8108, or FK-122.
(step 3.2)
- 4. Manually close charging flow control valve. Z
- POSITION the following in S / U the COUNTER-ClOCKWISE (Step 3.3) direction:
Verify Charging pump discharge flow path- o FK-122, Ivlanual, Zero (0%)
Aligned. o M0V8107-GRN light LIT o M0V8108-GRN light LIT Z CHECK OPEN the following:
[jMOV8I32A-RED light LIT
[]MOV8132B-RED light LIT
[jMOV8I 33A-RED light LIT
[]M0V8133B-RED light LIT
FNP ILT-35 JPM SIMULATOR JPM B. Page 5 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 4)
- 5. OPEN HHSI isolation valves POSITION the following in S / U the ClOCKWISE direction to OPEN:
[]M0V8803A-RED light LIT
[]M0V8803B-RED light LIT (step 5)
- 6. Start additional CHG PUMPS as required CHECKS RCS parameters S I U o RCS pressure LOWERING/STABLE o PRZRLvI LOWERING/STABLE STARTS the 1A CHG pump by turning in CLOCKWISE direction.
(step 6)
- 7. Monitor charging pump mini-flow criteira CHECKs RCS Pressure S / U L >l300psig DETERMINES NO operation needed.
(Step 7)
- 8. Return to step in effect. IDENTIFIES the required S / U transition to EEP-1.
STOP TIME Terminate when ATTACHMENT 3 is reported complete, Element 8 may be satisfied via questioning.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP ILT-35 JPM SIMULATOR JPM B. Page 6 of 7 (Guide pages = 6)
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-l-ESP-1.1, V 25.0
- 2. K/As: 006A4.01 RO-4.l SRO-3.9 006A4.02 RO-4.0 SRO-3.8 006A4.07 RO-4.4 SRO-4.4 GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire:
- 1. An unmarked up copy of FNP- 1 -ESP- 1.1; will be provided via nonally available Simulator procedures.
- 2. Attachment 3 will be replaced after each JPM.
Critical ELEMENT justification:
STEP Evaluation I CRITICAL
- 1) Sequencing the VCT and RWST suction valve operations could lead to disabling the running Charging pump and air binding the NON-Running pump.
- 2) Failure to align to the RWST would result in LOSS of suction (Automatic transfer is disabled) IF VCT level were to fall to 0% and no other suction source aligned within 5 mins the Chg pumps will fail.
2 Not cntical check step only 3 Not cntical HV 8152 isolation is ONLY 1 of 2 CNMT isolations others Shut Automatically on Low PZR LVL.
4 CRITICAL- PREVENT HHSI pump RUNOUT by aligning only 1 discharge path at a time. ONLY one of the three (3) valves is required to satisfy the critical aspect of this element.
5 CRITICAL- Task objective, establishes HHSI flow.
6 Not cntical RCS pressure/PZR level stabilizes with only ONE Chg pump, starting a second is NOT REQUIRED for core protection, IT is expected however that the pump be started since SI REDUCTION Criteria of ESP- 1.2 is NOT satisfied.
7 Not cntical step is a check step 8 Not critical Natural termination point of assigned task.
COMMENTS:
FNP ILT-35 JPM JPM SIMULATOR JPM B. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to Re-establish illS! flow due to a SGTR per Attachment 3 of ESP-1.1, SI Termination.
The conditions under which this task is to be perfonried are:
- a. ESP- 1.1, SI Termination, is in progress.
- b. Normal Charging has been aligned.
12/01/10 14:12:32 FNP-1-UOP-1.2 5.74 WHEN reactor power is 20-25%, THEN verify instrument air isolation test in Appendix 3 completed for the Main Feed Regulating Valves.
5.75 IF a main power transformer (MPT) has been replaced and it is desired to obtain third harmonic voltage readings during the initial power ascension following MPT replacement, THEN perform the following WHEN load at 200 MWs:
- Hold power ascension at 200 MWs
- Adjust MVARs as directed by the applicable work order.
- Contact the ES Manager to gather the required data.
5.76 Start transferring feed water control from the Main Feed Regulating Bypass Valves to the Main Feed Regulating Valves as follows:
5.76.1 Maintain each SG level at approximately the programmed level.
NOTE: The following steps should be done very slowly and in small increments.
The main feed regulating valve should be opened only a few percent, while verifying the main feed regulating bypass valve starts to close and allowing stabilization time for the automatic circuitry time constants involved. Then open up on the main feed regulating valve a few more percent and allow stabilization time. This should be a slow evolution, allowing parameters to stabilize after each adjustment.
5.76.2 Open the Main Feed Regulating Valves as follows:
Slowly open Main Feed Regulating Valves to approximately 10%
using the following:
[1 FK478 1A SG FW FLOW controller.
[j FK488 lB SG FW FLOW controller.
[1 FK498 1C SG FW FLOW controller.
OR Slowly open Main Feed Regulating Valves until the Main Feed Regulating Bypass Valves have automatically closed to a reliable controlling position. (approximately 15-50%)
[] FK479 1A SG FW BYP FLOW controller
[] FK489 lB SG FW BYP FLOW controller
[] FK499 1C SG FW BYP FLOW controller Version 101.0
12/01/10 14:12:32 FNP-l-UOP-1.2 5.76.3 Monitor the operation of the automatic feedwater control system.
[] Steam generator levels
[j Feed flows
[J Steam flows
[] SGFP speed
[] Feed regulating or Bypass valve oscillations 5.76.4 Continue opening main feed regulating valves as power increases while keeping main feed regulating bypass valves in AUTO and at a reliable controlling position. This will continue until approximately 35% power. Control will then be shifted to the main feed regulating valves per FNP-l-UOP-3.1, POWER OPERATION.
NOTE: The preferred supply for 1A, lB and 1C 4160V busses is from the unit auxiliary transformers. At the Shift Supervisors direction, the busses may remain aligned to the startup transformers.
5.77 IF desired, THEN transfer 4160V buses 1A, lB and 1C to the unit auxiliary
/ transformers per FNP-1-SOP-36.2, 4160V AC ELECTRICAL DISTRIBUTION SYSTEM.
NOTE: Heaters will automatically de-energize and energize as the cooling tower fans are started and stopped if the heater breakers are closed per FNP-l-SOP-26.OA.
- 5.78 At the lA cooling tower local control station/panel, perform the following:
5.78.1 Start the non-running fans on 600V LC 1U.
5.78.2 Start the non-running fans on 600V LC 1V.
5.78.3 Start the non-running fans on LC # 11.
5.79 Notify ACC that the generator is ready for additional load.
5.80 Go to FNP-l-UOP-3.1, POWER OPERATION, for increasing reactor power greater than 25%.
- 5.8 1 Shift Support Supervisor completes Data Sheet 1.
Shift Supervisor Review Version 101.0
FNP-1-ESP-l .1 8-11-2010 Revision 25 FARLEY NUCLEAR PLANT EVENT SPECIFIC PROCEDURE FNP-1-ESP-1 .1 SI TERMINATION S
A F
PROCEDURE USAGE REQUIREMENTS-per FNP-O-AP-6 SECTIONS E T
Continuous Use ALL Y Reference Use R E
Information Use L A
T E
D Approved Operations Manager Date Issued:
FNP-l-ESP-1.l SI TERMINATION Revision 25 Table of Contents Procedure Contains Number of Pages Body 43 Figure 1 1 Figure 2 1 Attachment 1 7 Attachment 2 1 Attachment 3 3 Foldout Page 1 Page 1 of 1
FNP-l-ESP-l.l SI TERMINATION Revision 25 A. Puryose This procedure provides the necessary instructions to terminate safety injection and stablize plant conditions.
B. Symptoms or Entry Conditions I. This procedure is entered from the following:
- a. FNP-1-EEP-O, REACTOR TRIP OR SAFETY INJECTION, step 22; FNPl-EEP-l, LOSS OF REACTOR OR SECONDARY COOLANT, step 7, and FNP-l-EEP-2, FAULTED STEAM GENERATOR ISOLATION, step 8 when specified termination criteria are satisfied.
- b. FNP-1FRP-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 36, after secondary heat sink has ben established and SI has been terminated.
Page 1 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Automatic reinitiation of SI will not occur since reactor trip breakers are not reset.
NOTE: FOLDOUT PAGE should be monitored continuously.
1 Verify SI reset. 1 Perform the following:
[1 MLB-1 1-1 not lit (A TRN) 1.1 any train will reset
[1 MLB-1 11-1 not lit (B TRN) using the MCB SI RESET pushbuttons.
THEN place the affected train S821 RESET switch to RESET.
(SSPS TEST CAB.)
1.2 IF a failure exists in SSPS such that SI cannot be reset, THEN reset SI using FNP-1-SOP-40.O, RESPONSE TO INADVERTENT SI AND INABILITY TO RESET OR BLOCK SI, Appendix 2.
2 Stop all but one CHG PUMP.
3 Verify RCS pressure - STABLE OR 3 Go to FNP-1--ESP-1.2, POST LOCA RISING. COOLDOWN AND DEPRESSURIZATION.
[1 P1 402A
[1 P1 403A Page 2 of 43
FNP-l-ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 4 Isolate HIISI flow.
4.1 Check CHG PUMP - SUCTION 4.1 IE CHG pump suction aligned to ALIGNED TO RWST discharge of RHR Pumps [via Q1E11MOV87O6A(B)] in the RWST recirculation mode.
TO CHG PMP THEN perform the following.
[1 Q1E21LCV115B open 4.1.1 Manually close charging
[] Q1E21LCV115D open flow control valve.
CHG FLOW
[] FK 122 4.1.2 IF train A charging pump running, THEN perform the following.
IF NOT, THEN proceed to RNO Step 4.1.3.
4.1.2.1 Close charging pump recirculation to RCS cold legs valve.
CHG PUMP RECIRC TO RCS COLD LEGS LI Q1E21M0V8885 4.1.2.2 Verify charging pump discharge flow path -
ALIGNED.
[] Q1E21MOV8132A open LI Q1E21MOV8132B open LI Q1E21MOV8133A open
[] Q1E21MOV8133B open CHG PUMPS TO REGENERATIVE HX
[] Q1E21MOVB1O7 open
[] 01E21M0V8108 open Step 4 continued on next page.
Page 3 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 4.1.2.3 Verify only one charging line valve - OPEN.
RCS NORMAL CHG LINE
[] Q1E21HV8146 RCS ALT CHG LINE
[1 01E21HV8147 4.1.2.4 Open charging flow control valve FK-l22 as necessary to obtain 60 gpm gpm.
CHG BlOW
[] FK 122 manually adjusted 4.1.2.5 Close HHSI isolation valves.
[] Q1E21MOV88O3A
[] Q1E21MOV88O3B 4.1.2.6 Verify charging flow greater than 60 gpm.
4.1.2.7 Proceed to Step 6.
Step 4 continued on next page.
Page 4 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 4.1.3 IE train B charging pump running, THEN perform the following.
4.1.3.1 Close HHSI isolation valves.
[1 Q1E21MOV88O3A
[1 Q1E21MOV88O3B 4.1.3.2 Verify charging pump discharge flow path -
ALIGNED.
[1 Q1E21MOV8132A open
[] 01E21M0V8132B open
[1 Q1E21MOV8133A open
{J Q1E21MOV8133B open CHG PUMPS TO REGENERATIVE HX
[1 Q1E21MOV81O7 open
[] Q1E21MOV81O8 open 4.1.3.3 Verify only one charging line valve - OPEN.
RCS NORMAL CHG LINE
[1 Q1E21HV8146 RCS ALT CHG LINE
[] Q1E21HV8147 4.1.3.4 Open charging flow control valve FK-122 as necessary to obtain 60 gpm.
CHG FLOW
[] FK 122 manually adjusted Step 4 continued on next page.
Page 5 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 4.1.3.5 Close charging pump recirculation to RCS cold legs valve.
CHG PUMP RECIRC TO RCS COLD LEGS H Q1E21MOV8885 4.1.3.6 Verify charging flow greater than 60 gpm 4.1.3.7 Proceed to Step 6.
4.2 Verify charging pump miniflow valves OPEN.
1A(1B,1C) CHG PUMP MINIFLOW ISO
[1 Q1E21MOV81O9A
[1 Q1E21MOV81O9B
[1 Q1E21MOV81O9C CHG PUMP MINIFLOW ISO
[] Q1E21MOV81O6 4.3 Close HHSI isolation valves.
[] Q1E21MOV88O3A H Q1E21MOV88O3B Page 6 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
5 Establish normal charging.
5.1 Manually close charging flow control valve.
CHG FLOW
[1 FK 122 5.2 Verify charging flow path aligned.
5.2.1 Verify charging pump discharge flow path -
ALIGNED.
[1 01E21M0V8132A open
[1 Q1E21MOV8132B open
[1 Q1E21MOV8133A open
[1 Q1E21MOV8133B open CHG PUMPS TO REGENERATIVE HX
[1 Q1E21MOV81O7 open
[1 01E21M0V8108 open 5.2.2 Verify only one charging line valve - OPEN.
RCS NORMAL CHG LINE
[1 Q1E21HV8146 RCS ALT CHG LINE
[1 Q1E21HV8147 5.2.3 Control charging flow.
CHG FLOW
[1 FK 122 adjusted Page 7 of 43
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I NOTE: The RCS may be approaching solid plant conditions. In the event the RCS must be operated water solid, charging flow should be adjusted to maintain subcooling instead of pressurizer level.
6 Adjust charging flow to raise 6 If pressurizer level falling, pressurizer level - GREATER Then perform the following.
THAN 25%{50%}.
a) If depressurization of a faulted SC in progress, THEN do proceed until depressurization complete or pressurizer level stable or rising.
b) j depressurization of a faulted SC QI in progress, THEN reinitiate SI.
- Go to FNP-1-ESP-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
6.1 [CAl Maintain pressurizer 6.1 solid plant operation level 25%-50%{50%-60%}. required, THEN control charging flow to maintain subcooling greater than 16°F{45°F}.
CHG FLOW
[I FK 122 adjusted Page 8 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 7 Secure LHSI system.
7.1 RHR pumps - ANY RUNNING WITH 7.1 Proceed to step 8.
SUCTION ALIGNED TO RWST.
7.2 Stop any RHR Pumps running with suction aligned to the RWST.
7.3 Check on service train RHR 7.3 Proceed to step 8 pump - STOPPED.
7.4 Isolate CCW to the on service train RHR heat exchanger.
[1 Q1P17MOV3185A closed OR
[1 Q1P17MOV3185B closed 8 Verify SI flow not required.
8.1 Check SUB COOLED MARGIN 8.1 Perform the following.
MONITOR indication - GREATER THAN 16°Ft45°F} SUECOOLED IN 8.1.1 Establish HHSI flow using CETC MODE. ATTACHMENT 3, RE-ESTABLISHING HHSI FLOW 8.1.2 Go to FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
8.2 Check pressurizer level - 8.2 Perform the following.
GREATER THAN 13%{43°n}.
8.2.1 Establish HHSI flow using ATTACHMENT 3, RE-ESTABLISHING HHSI FLOW 8.2.2 Go to FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
9 Verify PHASE A CTMT ISO reset.
[1 MLB-2 1-1 not lit
[1 MLB-2 11-1 not lit Page 9 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I 10 Check PHASE B CTMT ISO - RESET. 10 Perform the following.
[] MLB-3 1-1 not lit 10.1 Reset PHASE B CTMT ISO.
[1 MLB-3 6-1 not lit 10.2 Verify proper PRF system operation using FNP-l-SOP-60.0, PENETRATION ROOM FILTRATION SYSTEM.
11 IF instrument air available, THEN establish instrument air to containment.
11.1 Verify at least one air compressor - STARTED.
AIR COMPRESSOR
[1 lA
[1 lB
[1 1C 11.2 Verify INST AIR PRESS P1 4004B
- GREATER THAN 85 psig.
11.3 Check the following:
[1 MLB-3 1-2 NOT lit IA TO PENE RM PRESS LO
[1 Annunciator KD1 clear OR Verify instrument air aligned to containment. (BOP)
[1 N1P19HV3825 open
[] N1P19HV3885 open IA TO CTMT
[1 Q1P19HV3611 open
[CA] Verify 4160 V busses energized.
12.1 Perform ATTACHMENT 1, VERIFYING 4160 V BUSSES ENERGIZED.
Page 10 of 43
FNP-l-ESP-1.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I
__13 [CA] Maintain RCS hot leg temperature - STABLE AT EXISTING VALUE.
NOTE:
- The steam dumps will be interlocked closed when RCS TAVG reaches P-12 (543°F). This interlock may be bypassed for A and E steam dumps with the STM DUMP INTERLOCK switches.
- Excessive opening of steam dumps can cause a high steam flow LO-LO TAVG main steam line isolation signal.
13.1 IF condenser available, 13.1 Dump steam to atmosphere.
THEN dump steam to condenser from intact SOs. 13.1.1 Direct counting room to perform FNP-O-CCP-645, MAIN BYP & PERMISSIVE STEAM ABNORMAL COND AVAIL ENVIRONMENTAL RELEASE.
[1 C-9 light lit 13.1.2 IF normal air available, STM DUMP THEN control atmospheric
[1 MODE SEL A-B TRN in STM PRESS relief valves to dump steam from intact SGs, STM DUMP IF NOT dump steam using INTERLOCK FNP-1-SOP-62.O, EMERGENCY
[] A TRN in ON AIR SYSTEM.
[] B TRN in ON 1A(1B,1C) MS ATMOS STM HDR REL VLV PRESS [1 PC 3371A adjusted
[1 PK 464 adjusted [1 PC 3371B adjusted
[1 PC 3371C adjusted Page 11 of 43
FNP-1-ESP1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I CAUTION: To prevent heat exchanger damage, do not attempt restoration of letdown or excess letdown unless the CCW miscellaneous header is aligned to an operating CCW loop.
14 [CA] WHEN pressurizer level greater than 25%5O%} CCW cooling established, THEN establish letdown.
14.1 Establish normal letdown. 14.1 Establish excess letdown.
14.1.1 Open letdown isolation a) Align CCW to excess valves, letdown heat exchanger.
LTDN LINE CCW TO EXC PENE RM ISO LTDN/RCDT HXS
[] 01E21HV8175A (PRIP) [1 Q1P17HV3095 open
[1 Q1E21HV8175B (PRIP)
CCW FROM EXC LTDN LINE LTDN/RCDT HXS CTMT ISO [] Q1P17HV3067 open
[1 Q1E21HV8152 [] Q1P17HV3443 open LTDN LINE b) Adjust EXC LTDN HX DISCH ISO HIK 137 closed.
[1 01E21LCV459
[1 Q1E21LCV46O c) Align excess letdown to VCT.
14.1.2 Open charging flow control valve FK-l22 as necessary EXC LTDN to obtain minimum charging ISO flow for letdown cooling. [] Q1E21HV8153 open H Q1E21HV8154 open CHG FLOW
[] FK 122 manually adjusted EXC LTDN DIVERT VLV 14.1.3 Manually adjust LP LTDN [] Q1E21HV8143 to VCT PRESS PK 145 to 50% open.
Step 14 continued on next page.
Page 12 of 43
FNPl-ESP-i.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I d) Establish excess letdown 14.1.4 Open letdown orifice flow.
isolation valve(s)
EXC LTDN LTDN ORIF ISO HX DISCH 45 GPM {] HIK 137 adjusted
[1 Q1E21HV8149A e) Maintain excess letdown heat exchanger outlet temperature less than LTDN ORIF ISO 165°F.
60 GPM
{] Q1E21HV8149B EXC LTDN HX OUTLET TEMP
[1 Q1E21HV8149C [1 TI 139 14.1.5 Manually adjust letdown pressure to 260-450 psig.
LP LTDN PRESS
[] PK 145 adjusted 14.1.6 Place LP LTDN PRESS PK 145 in AUTO.
Page 13 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 1 I NOTE: The RCS may be approaching solid plant conditions. The purpose of the following step is to establish an adequate pressurizer steam bubble if one does not already exist.
15 Check pressurizer level - LESS 15 Establish a bubble in the THAN 92%. pressurizer.
15.1 Verify normal pressurizer spray valves CLOSED.
[1 PK 444C
[i PK 444D 15.2 Verify RCS PRZR AUX SPRAY Q1E21HV8145 - CLOSED.
15.3 Energize pressurizer heaters.
PRZR HTR GROUP VARIABLE
[] 1C PRZR HTR GROUP BACKUP
[1 1A
[1 lB
[1 1D
[1 1E 15.4 Control charging and letdown to maintain pressurizer pressure at existing value.
Step 15 continued on next page.
Page 14 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 15.5 WHEN pressurizer temperature at saturation temperature for existing pressurizer pressure, THEN perform the following.
15.5.1 Adjust charging flow to minimum.
CHG FLOW
[1 FK 122 adjusted 15.5.2 Maintain seal injection to each RCP - 6-13 gpm.
15.5.3 Verify adequate letdown flow.
- Verify 45 GPM letdown orifice - IN SERVICE.
LTDN ORIF ISO 45 GPM
[1 Q1E21HV8149A open
- Verify one 60 GPM letdown orifice - IN SERVICE.
LTDN ORIF ISO 60 GPM
[1 Q1E21HV8149B open
{] Q1EZ1HV8149C open 15.5.4 WHEN pressurizer level reaches less than 50%{60%),
THEN control charging and letdown to maintain pressurizer level 25%-50%{50%-60%}
Page 15 of 43
FNP-1-ESP-i.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 16 Align reactor makeup system.
16.1 Adjust BORIC ACID MKUP FLOW FK 113 to deliver maximum boron concentration.
16.2 Verify reactor makeup system -
IN AUTOMATIC MODE.
MKUP MODE SEL SWITCH
[1 N1E21HS2100Q in AUTO MKUP MODE CONT SWITCH
[1 N1E21HS2100P TO START 16.3 Direct Chemistry to sample RCS for boron concentration using FNP-1-CCP-651, SAMPLING THE REACTOR COOLkNT SYSTEM.
16.4 WHEN sample results obtained, THEN adjust BORIC ACID MKUP FLOW FK 113 to deliver greater than existing RCS boron concentration.
Page 16 of 43
FNP-l-ESP-i.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
17 Align charging pump suction to VCT.
[1 Q1E21MOV813OA open
[1 Q1E21MOV813OB open
[1 Q1E21MOV8131A open
[1 Q1E21MOV8131B open VCT OUTLET ISO
[1 Q1E21LCV115C open
[1 Q1E21LCV115E open RWST TO CHG PUMP
[1 Q1E21LCV115B closed
[1 Q1E21LCV115D closed lA(1B) RHR HX TO CHG PUMP SUCT
[1 Q1E11MOV87O6A closed
[1 Q1E11MOV87O6B closed 18 [CA] Check containment spray System.
18.1 Check any CS PUMP - STARTED. 18.1 Proceed to step 19.
18.2 Reset containment spray signals.
CS RESET
[1 A TRN
[1 B TRN 18.3 [CA] WHEN containment spray recirculation flow has been aligned for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, MP containment pressure is less than 16 psig, THEN stop both CS PUMPs.
Page 17 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 19 Check intact SG levels.
19.1 Check any intact SC narrow 19.1 Verify total AFW flow greater range level - GREATER THAN than 395 gpm.
3l%{48%}.
AFW FLOW TO 1A(1B,lC) SC
[1 Fl 3229A
[1 Fl 3229B
[1 Fl 3229C AFW TOTAL FLOW
[] Fl 3229 19.2 [CA] WHEN intact SG narrow 19.2 j any SC narrow range level range level greater than continues to rise, 3l%t48%}, THEN stop AFW flow to that SC.
THEN maintain intact SC narrow range level 31%-65%{48%-65%}.
19.2.1 Control MDAFWP flow.
[1 A TRN reset
[1 B TRN reset MDAFWP TO lA/lB/iC SG B TRN LI FCV 3227 in MOD Intact SG 1A lB lC MDAFWP TO lA(lB,1C) SG Q1N23HV []3227A []3227B []3227C in MOD in MOD in MOD MDAFWP TO 1A(1B,1C) SG FLOW CONT HIC []3227AA []3227BA []3227CA adjusted adjusted adjusted Step 19 continued on next page.
Page 18 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 19.2.2 Control TDAFWP flow.
TDAFWP FCV 3228
[1 RESET reset TDAFWP SPEED CONT
[] SIC 3405 adjusted Intact SG 1A lB 1C TDAFWP TO 1A(lB,1C) SG Q1N23HV []3228A []3228B []3228C in MOD in MOD in MOD TDAFWP TO 1A(1B,1C) SG FLOW CONT HIC []3228AA []3228BA E]3228CA adjusted adjusted adjusted CAUTION: If RCP seal cooling had previously been lost, the affected RCP should not be started prior to a status evaluation.
20 Check RCP support conditions.
20.1 Verify No. 1 seal support conditions established.
20.1.1 Verify miscellaneous header 20.1.1 Verify all RCPs - STOPPED.
aligned.
CCW TO SECONDARY HXS Ii Q1P17MOV3O47 open 20.1.2 Verify flow indicated in 20.1.2 Verify all RCPs - STOPPED.
the On-Service train.
HX 1A(1B.1C)
CCW FLOW
[1 Fl 3043AA
[1 Fl 3043BA
[1 Fl 3043CA Step 20 continued on next page.
Page 19 of 43
FNP-1-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I 1 I 20.1.3 [CA] Maintain seal 20.1.3 Verify affected RCP(s) -
injection flow - GREATER STOPPED.
THAN 6 gpm.
20.1.4 Verify No. 1 seal leakoff 20.1.4 Verify affected RCP(s) -
flow - WITHIN FIGURE 1 STOPPED.
LIMITS.
20.1.5 Verify No. 1 seal 20.1.5 Verify affected RCP(s) -
differential pressure - STOPPED.
GREATER THAN 200 psid.
- 1 SEAL PRESS
[1 1A RCP - P1 l56A
[1 lB RCP - P1 155A
[1 lC RCP - P1 154A Step 20 continued on next page Page 20 of 43
PNP-l-ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I CAUTION: To prevent heat exchanger damage, do not attempt restoration of RCP seal return flow unless the CCW miscellaneous header is aligned to an operating CCW loop.
20.2 Check if seal return flow should be restored.
20.2.1 Check at least one RCP has 20.2.1 Proceed to step 20.3.
seal injection flow-GREATER THAN 6 gpm.
20.2.2 Check VCT pressure - 20.2.2 Establish VCT pressure GREATER THAN RCDT pressure. GREATER THAN RCDT pressure by raising VCT pressure VCT PRESS using FNP-l-SOP-2.5 RCS P1 CHEMICAL ADDITION, VCT GAS 117 CONTROL AN) DEMINERALIZER RCDT PRESS IND (Liquid OPERATION or venting the Waste Processing Panel 100 RCDT using FNP-l-SOP-51.0, Aux Bldg Rad Side) WASTE GAS SYSTEM prior to
[1 N1G21PI1004 restoring seal return flow, proceed to step 20.3.
20.2.3 Restore seal return flow.
[1 Q1E21MOV8100 open
[1 01E21M0V8112 open Step 20 continued on next page.
Page 21 of 43
FNP-1-ESP-1.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 20.3 RCP thermal barrier CCW alignment.
20.3.1 Verify RCP CCW thermal barrier - ALIGNED.
[1 Q1P17HV3045 open
[] Q1P17HV3184 open 20.3.2 Check RCP thermal barrier - 20.3.2 +Verify CCW flow isolated.
INTACT.
CCW FROM RCP RCP THRM BARR THRM BARR [1 Q1P17HV3045 closed CCW FLOW [1 Q1P17HV3184 closed HI
[] Annunciator DD2 clear 20.4 Check CCW to RCP oil coolers - 20.4 Perform the following.
SUFFICIENT.
20.4.1 Verify CCW ALIGNED.
CCW FLOW FROM RCP CCW TO RCP CLRS OIL CLRS [] Q1P17MOV3O52 open LO
[1 Annunciator DD3 clear CCW FROM RCP OIL CLRS
[1 Q1P17MOV3046 open
[] Q1P17MOV3182 open 20.4.2 IF annunciator DD3 clear, THEN proceed to step 20.5.
20.4.3 Verify all RCPs - STOPPED.
20.5 Check oil level for RCP(s) 20.5 Verify affected RCP(s) needed to support pressurizer STOPPED.
spray- SUFFICIENT.
RCP 1B(1A AND 1C) BRG UPPER/LOWER OIL RES LO LVL
[1 Annunciator HH1 clear
[1 Annunciator HH2 clear
[1 Annunciator HH3 clear Step 20 continued on next page.
Page 22 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 20.6 Check RCS - WITHIN FIGURE 2 20.6 Verify all RCPs STOPPED.
LIMITS.
20.7 Verify 4160 V busses for 20.7 Proceed to step 21.4.
RCP(s) needed to support pressurizer spray - ENERGIZED
[1 1A 4160 V bus
[1 lB 4160 V bus
[1 lC 4160 V bus 21 [CA] Check if RCP(s) should be reconfigured to optimize RCS flow and pressurizer spray performance.
21.1 Check RCP lB - STOPPED. 21.1 Proceed to step 22. OBSERVE NOTE PRIOR TO STEP 22.
[1 lB 21.2 Check any RCP - STARTED. 21.2 IF REACTOR VESSEL LEVEL indication LESS THAN 100%
UPPER HEAD, THEN establish conditions to accomodate void collapse prior to initial RCP start.
21.2.1 Raise pressurizer level to greater than 67%{90%} using charging and letdown.
- Raise charging flow.
CHG FLOW
[1 FK 122 adjusted
- Reduce letdown flow.
21.2.2 IF SUB COOLED MARGIN MONITOR indication less than 400F{690F} subcooled in CETC mode, THEN dump steam at faster rate to establish subcooling.
Step 21 continued on next page Page 23 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I 21.2.3 Use PRZR heaters, as necessary to saturate the pressurizer water.
PRZR HTR GROUP VARIABLE
[1 ic PRZR HTR GROUP BACKUP
[1 1A
[] lB
[1 1D
[1 1E Step 21 continued on next page.
Page 24 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- To ensure pressurizer spray, the priority for operating RCPs is first lB then both 1A AND 1C.
21.3 Establish RCP configuration to 21.3 Establish RCP configuration to support pressurizer spray support pressurizer spray using lB RCP. using 1A 1C RCP(s).
21.3.1 Check lB RCP support a) Check support conditions conditions satisfied. satisfied for any RCP(s) to be started.
21.3.2 Start bearing oil lift pump. b) Start bearing oil lift pump(s) for any RCP(s) to RCP be started.
OIL LIFT PUMP
[1 lB RCP OIL LIFT PUMP 21.3.3 Check oil lift pressure [] 1A indicating light - LIT. [1 1C 21.3.4 Start lB RCP. c) Check oil lift pressure indicating light(s) - LIT RCP for any RCP(s) to be
[1 lB started.
21.3.5 WHEN LB RCP has operated d) Verify 1A 1C RCPs -
for one minute, STARTED.
THEN stop bearing oil lift pump. RCP
[] 1A RCP H lC OIL LIFT PUMP
[1 lB e) WHEN any RCP(s) that was started has operated for one minute, THEN stop bearing oil lift pump(s).
RCP OIL LIFT PUMP
[] 1A AND 1C Step 21 continued on next page.
Page 25 of 43
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 21.4 Check at least one RCP - 21.4 IF no RCP started, STARTED. THEN verify adequate natural circulation.
21.4.1 Check SG pressure stable or falling.
21.4.2 Check SUB COOLED MARGIN MONITOR indication greater than 16°P(45°F) subcooled in CETC mode.
21.4.3 Check RCS hot leg temperatures stable or falling.
RCS HOT LEG TEMP El TR 413 21.4.4 Check core exit T/Cs stable or falling.
21.4.5 Check RCS cold leg temperatures at saturation temperature for SG pressure.
RCS COLD LEG TEMP
[1 TR 410 21.4.6 IF natural circulation NOT adequate, THEN dump steam at a faster rate.
21.4.7 Begin taking natural circulation logs.
Page 26 of 43
FNP-1-ESP-J.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE: The intent of this step is to stabilize RCS pressure and restore the pressurizer to saturated conditions.
[CA] Maintain RCS pressure -
STABLE 22.1 IE normal pressurizer spray 22.1 Perform the following.
available, THEN control normal 22.1.1 IF normal letdown pressurizer spray for any RCS established, pressure reduction. THEN control auxiliary spray for any RCS pressure 1A(lB) LOOP reduction.
SPRAY VLV
[] PK 444C 22.1.1.1 Manually open both
[] PK 444D normal pressurizer spray valves.
[] PK 444C
[.1 PK 444D 22.1.1.2 Open auxiliary spray valve.
RCS PRZR AUX SPRAY
[1 Q1E21HV8145 22.1.1.3 Verify flow path aligned.
CHG FLOW
[] FK 122 manually open RCS NORMAL CHG LINE
[1 1E21HV8146 closed RCS ALT CHG LINE
[] Q1E21HV8147 closed Step 22 continued on next page.
Page 27 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 22.1.1.4 WHEN RCS pressure reduction required, THEN operate the following valves as required to control pressurizer pressure.
CHG FLOW
[1 FK 122 manually open 1A(1B) LOOP SPRAY VLV
[1 PK 444C manually open/closed
[} PK 444D manually open/closed RCS PRZR AUX SPRAY
[1 01E21HV8145 open/closed RCS NORMAL CHG LINE
[1 Q1E21HV8146 open/closed RCS ALT CHG LINE
[] 01E21HV8147 open/closed 22.1.2 normal pressurizer spray NOT available AND normal letdown NOT established, THEN open only one PRZR PORV for any RCS pressure reduction.
22.2 Control pressurizer heaters.
PRZR HTR GROUP VARIABLE
[] 1C PRZR HTR GROUP BACKUP
[1 1A
[] lB
[1 1D
[1 1E Page 28 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I CAUTION: IF a DC is already operating above its continuous load rating, THEN additional manual loads should not be added. Unanticipated plant emergency 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 DOs) . Diesel loading should be reduced within the diesel generator continuous load rating limit as soon as plant conditions allow.
23 Check diesel generators.
23.1 [CA] Monitor any loaded diesel generator for proper voltage, frequency and load.
23.2 WHEN offsite power available, THEN realign emergency busses to offsite power using FNP-0-SOP-38.0, DIESEL GENERATORS.
23.3 [CA] Secure any unloaded diesel generators using FNP-0-SOP-38.0, DIESEL GENERATORS.
23.4 WHEN emergency bus(es) re-energized from offsite power, THEN perform the following for affected bus(es):
23.4.1 Locally reset the loss of voltage indicating lamp on the B1E (BiG) sequencer auxiliary panel.
23.4.2 At the EPB for the B1F (BiG) sequencer, push the LANP RESET pushbuttons.
Page 2 of 43
FNP-1ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I 24 Monitor nuclear instrumentation.
24.1 [CA] WHEN intermediate range indication less than 10-10 amps BYP & PERMISSIVE SOURCE RANGE PERMISSIVE P-6 light off, THEN verify source range detectors energized.
25 Secure secondary components.
25.1 Stop both heater drain pumps.
HDP
[] 1A
[1 lB 25.2 IF started, 25.2 IF no condensate pumps are THEN stop all but one started, condensate pump. THEN ensure handswitches positioned to STOP.
CNDS PUMP
[1 lA CNDS PUMP
[1 lB
[1 1C [1 lA
[] lB H 1C 25.3 IF desired, THEN stop one circulating water pump.
CW PUMP
[1 lA
[1 lB 25.4 IF desired, THEN secure one SJAE.
1A SJAE
[j B SECTION ISO closed
[] A SECTION ISO closed lB SJAE
[1 B SECTION ISO closed
[] A SECTION ISO closed Step 25 continued on next page.
Page 30 of 43
FNP-l-ESP-1.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 25.5 Verify MSRs reset.
REHEATER CONTROL SYSTEM
[] CP 4054 26 [CA] Maintain stable plant conditions.
- Maintain RCS pressure -
STABLE AT EXISTING VALUE.
[] P1 402A
[1 P1 403A
- [CA] Maintain pressurizer level - 15%-50%{50%-60%}.
- Maintain RCS temperature -
STABLE AT EXISTING VALUE.
RCS HOT LEG TEMP
[1 TR 410
- [CA] Maintain intact SGs narrow range level 31%-65%{48%-65%}
Page 31 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 27 Verify SI flow not required.
27.1 Check SUB COOLED MARGIN 27.1 Perform the following.
MONITOR indication - GREATER THAN 16°F{45°F} SUBCOOLED IN 27.1.1 Establish HHSI flow using CETC MODE. ATTACHMENT 3, RE-ESTABLISHING HHSI FLOW 27.1.2 Go to FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
27.2 Check pressurizer level - 27.2 IE pressurizer level can NQI GREATER THAN 13%{43%}. be maintained by controlling charging flow, THEN perform the following.
27.2.1 Establish HHSI flow using ATTACHMENT 3, RE-ESTABLISHING HHSI FLOW 27.2.2 Go to FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
NOTE: Steps 28 through 34 may be performed in any order.
28 Restore RCDT to normal alignment per FNP-1-SOP-5O.O, LIQUID WASTE PROCESSING SYSTEM.
Page 32 of 43
FNP-l-ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
29 Restore CCW to normal alignment.
29.1 Check CCW radiation indication 29.1 Proceed to step 29.3.
NORMAL.
[1 R-17A CCW
[1 R-17B CCW 29.2 Verify CCW surge tank vent valves - OPEN.
[1 Q1P175V3028A
[1 Q1P175V3028B 29.3 Open CCW to/from evaporator packages and hydrogen recombiner valves.
CCW TO/FROM EVAP PKGS & 112 RECOMB
[] Q1P17HV3O96B&A 29.4 Open CCW to excess letdown/RCDT heat exchanger valves.
CCW TO EXC LTDN/RCDT HXS
[1 Q1P17HV3O95 29.5 Open CCW from excess letdown/RCDT heat exchanger valves.
CCW FROM EXC LTDN/RCDT HXS
[1 Q1P17HV3O67
[1 Q1P17HV3443 Step 29 continued on next page.
Page 33 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 29.6 Restore normal two train CCW alignment as follows.
29.6.1 Verify one CCW PUMP in each train - STARTED.
[1 A train (lC,1B)
[1 B train (lA,1B) 29.6.2 Verify one CHG PUMP in off service train - STARTED.
[1 A train (1A,1B)
[1 B train (lC,1B) 29.6.3 Verify all CHG PUMPs in on service train - STOPPED.
[1 A train (lA,1B)
[1 B train (lC,lB) 29.6.4 Verify RHR PUMP in off service train - STOPPED.
[1 A train (lA)
[1 B train (lB) 29.6.5 Verify off service SFP HX has its associated CCW supply MOV open.
[1 Q1P17MOV3O94B open OR
[] Q1P17MOV3O94A open 29.6.6 Verify off service RHR HX has its associated CCW supply MOV closed.
CCW TO 1A(1B)
[1 Q1P17MOV3185A closed OR
[1 Q1P17MOV3185B closed Page 34 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained 30 WHEN emergency 4160 V busses energized from offsite power, THEN restore SW to normal alignment.
30.1 Open SW to RCP motor air cooler valve.
[1 01P16MOV3135 30.2 Open SW from RCP motor air cooler valves.
[1 Q1P16MOV3131
[1 Q1P16M0V3134 30.3 Restore SW to blowdown and BTRS chillers.
& BTRS CHLRS
[] Q1P16MOV3149 SW FROM BLDN HX
& BTRS CHLRS
[1 Q1P16MOV315O Step 30 continued on next page.
Page 35 of 43
FNP-1-ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I 30.4 Restore SW to turbine building.
30.4.1 Open A train isolation 30.4.1 Locally open A train valves, isolation valves. (cover welded)
SW TO TURB BLDG ISO A TRN SW TO TURB BLDG ISO LI Q1P16V515 A TRN
[] Q1P16V516 [] Q1P16V515 (valve box 1VB- lA)
[1 QlPl6V5l6 (valve box 1 VB -1 B) 30.4.2 Open B train isolation 30.4.2 Locally open B train valves. isolation valves. (cover welded)
SW TO TURB BLDG ISO B TRN SW TO TURB BLDG ISO
[1 Q1P16V514 B TRN
[1 Q1P16V517 [1 QlPl6V5l4 (valve box 1 VB 1 B)
[1 Q1P16V517 (valve box 1VB-1A) 30.5 Verify only two SW PUMPs in each train - STARTED.
[1 A train (1A,lB,1C)
[] B train (1D,1E,1C) 31 Restore containment sump pumps to normal operation using FNP-1-SOP-50.2, LIQUID WASTE PROCESSING SYSTEM SUMP PUMP SYSTEM OPERATION.
Page 36 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
32 Restore ventilation systems to normal alignment.
32.1 Restore R-11/12 to normal alignment per FNP-1-SOP-12.2.
CONTAINMENT PURGE AND PRE-ACCESS FILTRATION SYSTEM.
32.2 Open reactor cavity cooling dampers. (BOP)
[1 Q1E12HV3999A
[1 Q1E12HV3999B 32.3 Stop reactor cavity hydrogen dilution fans. (BOP)
RX CAV H2 DILUTION FAN
[] lA
{] lB 32.4 Stop CTMT post accident mixing fans. (BOP)
POST ACCIDENT MIXING FAN
[1 1A
[1 lB
[1 1C
[1 1D 32.5 Open CTMT to penetration room AP isolations. (BOP)
[1 Q1E14MOV3318B
[1 Q1E14MOV3318A 32.6 Restore Aux Building Ventilation systems using FNP-l-SOP-58.O, AUXILIARY BUILDING HVAC SYSTEM.
Step 32 continued on next page.
Page 37 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
32.7 IF desired, THEN establish containment mini purge.
32.7.1 Reset containment ventilation isolation.
[] A TRN
[1 B TRN 32.7.2 Restore containment mini purge using FNP-1-SOP-12.2, CONTAINMENT PURGE AND PRE-ACCESS FILTRATION SYSTEM.
32.8 Return control room HVAC to normal using FNP-0-SOP-56.O, CONTROL ROOM HVAC SYSTEM.
32.9 Return containment coolers to normal using FNP-1-SOP-12.1, CONTAINMENT AIR COOLING SYSTEM.
32.10 Start battery room exhaust fans. (BOP)
[1 1A
[1 lB 33 Reset containment suinp to RIIR valve switches.
[1 A TRN H B TRN Page 38 of 43
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- The intent of step 34 is to restore automatic SI capability, if plant conditions permit. A check is made first to ensure either no automatic SI signals are present, or that automatic SI signals are blocked if blocking capability exists.
. Refer to table below when determining if SI signal present.
34 Restore automatic SI capability.
SI Signal Instrumentation Setpoint Coincidence (TSLB)
- 1. Pressurizer P1-455,456,457 1850 psig 2/3 pressure low (TSLB2 17-1,17-2,17-3)
(if not blocked)
- 2. Steam Line P1-474,484,494, 100 psig 1 steam line Differential P1-475,485,495, 100 psig less pressure P1-476,486,496 than other two (TSLB4 10-2,10-3,10-4, on 2/3 protection 11-2,11-3,11-4, sets 12-2,12-3,12-4, 13-2,13-3,13-4, 14-2,14-3,14-4, 15-2,15-3,15-4)
- 3. Low Steam Line P1-474,485,496 585 psig 2/3 pressure (TSLB4 19-2,19-3,19-4)
(if not blocked)
- 4. Containment P1-951,952,953 4 psig 2/3 pressure high (TSLB1 1-2,1-3,1-4)
- 5. Manual N/A N/A 1/2 34.1 Check no pressurizer pressure 34.1 Perform the following.
low SI signal - PRESENT.
34.1.1 Block low pressurizer pressure SI.
PRZR PRESS SI BLOCK - RESET H A TRN to BLOCK H B TRN to BLOCK Step 34 continued on next page.
Page 39 of 43
FNP-1-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 34.1.2 IE following blocked indication obtained, THEN proceed to step 34.2, IF NOT proceed to step 35.
BYP & PERMISSIVE PRZR SAFETY INJECTION
[1 TRAIN A BLOCKED light lit
[1 TRAIN B BLOCKED light lit 34.2 Check no steam line 34.2 Proceed to step 35.
differential pressure SI signal - PRESENT.
34.3 Check no low steam line 34.3 Perform the following.
pressure SI signal - PRESENT.
34.3.1 Block low steam line pressure SI.
STM LINE PRESS SI BLOCK - RESET El A TRN to BLOCK El B TRN to BLOCK 34.3.2 j following blocked indication obtained, THEN proceed to step 34.4, IF NOT proceed to step 35.
BYP & PERMISSIVE STM LINE ISOL.
SAFETY INJ
[1 TRAIN A BLOCKED light lit
[] TRAIN B BLOCKED light lit 34.4 Check no containment pressure 34.4 Proceed to step 35.
high SI signal - PRESENT.
34.5 Trip both CRDM MG set supply breakers.
MG SET SUPP BKR
[1 lA
[1 lB 34.6 Verify no reactor trip signals present.
Step 34 continued on next page.
Page 40 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 34.7 Close reactor trip breakers.
34.8 Manually trip reactor trip breakers.
35 Determine controlling procedure.
35.1 Check at least one RCP - 35.1 Perform the following.
STARTED.
35.1.1 Notify Chemistry to secure the zinc addition system (ZAS).
35.1.2 j cooldown required, THEN go to FNP-l-ESP-O.2, NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL HEAD STEAM VOIDING.
35.2 Go to FNP-1-UOP-2.1, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY.
- END -
Page 41 of 43
FNP-l-ESP-l.l SI TERMINATION Revision 25 START STEP CONTINUOUS ACTION 6.1 [CA] Maintain pressurizer level 25%-50%{50%-60%}.
l2 [CA] Verify 4160 V busses energized.
Dl3 [CA] Maintain RCS hot leg temperature - STABLE AT EXISTING VALUE.
fl14 [CA] WHEN pressurizer level greater than 25%{50%} AND CCW cooling established, THEN establish letdown.
l8 [CA] Check containment spray system.
18.3 [CA] WHEN containment spray recirculation flow has been aligned for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, AND containment pressure is less than 16 psig, THEN stop both CS PUMPs.
19.2 [CA] WHEN intact SG narrow range level greater than 3l%{48%}, THEN maintain intact SG narrow range level 31%-65%{48%-65%}
E120 20.1.3 [CA] Maintain seal injection flow - GREATER THAN 6 gpm.
D21 [CA] Check if RCP(s) should be reconfigured to optimize RCS flow and pressurizer spray performance.
D22 [CA] Maintain RCS pressure - STABLE D23 23.1 [CA] Monitor any loaded diesel generator for proper voltage, frequency and load.
23.3 [CA] Secure any unloaded diesel generators using FNP-0-SOP-38 .0, DIESEL GENERATORS.
E24 24.1 [CA] WHEN intermediate range indication less than 10-10 amps OR BYP & PERMISSIVE SOURCE RANGE PERMISSIVE P-6 light off, THEN verify source range detectors energized.
D26 [CA] Maintain stable plant conditions.
[CA) Maintain pressurizer level - l5%-50%{50%-60%}.
Page 42 of 43
FNP-l-ESP-l.1 SI TERMINATION Revision 25 START STEP CONTINUOUS ACTION
[CA] Maintain intact SGs narrow range level -
31%-65%{48%-65%}
Page 43 of 43
FNP-1-ESP-1.1 SI TERMINATION Revision 25 FIGURE 1 NO. 1 SEAL NORMAL OPERATING RANGE 2400 2250 uu 2000 1800 1600 No.1 Seal 1400 Differential Pressure (PSID, See 1200 Note 1) 1000 800 600 400 200 0
0 .2 1 2 3 4 5 6 No. 1 Seal Leak Rate (GPM)
Note 1: For No. 1 Seal Differential Pressures greater than 400 psid, use RCS pressure in psig.
FNP-4-ESP-1.1 SI TERMINATION Revision 25 FIGURE 2 RCP PRESSURE-TEMPERATURE OPERATING LIMITS 1800 1700 1600 1500 1400 1300 1200 1100 1000 RCS 900 Pressure (psig) 800 700 800 500 400 300 200 100 0
0 100 200 300 400 500 600 ROS Hot Leg Temperature °F>
L
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 VERIFYING 4160 V BUSSES ENERGIZED Verify 4160 V busses energized.
CAUTION: IF a DG is already operating above its continuous load rating, THEN additional manual loads should not be added. Unanticipated plant emergency 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 DGs) . Diesel loading should be reduced within the diesel generator continuous load rating limit as soon as plant conditions allow.
NOTE: Plant conditions may dictate establishment of contingency electrical lineups. FNP-l-AOP-5.1, CONTINGENCY ELECTRICAL ALIGNMENTS provides guidance for establishing those lineups.
1.1 Check offsite power - 1.1 Request Shift Manager AVAILABLE, coordinate efforts to restore offsite power.
1.2 Check BKR DFO1 (lA startup 1.2 Verify iF 4160 V bus energized transformer to iF 4160 V bus) by l-2A or 1C diesel
- CLOSED. generator.
1.3 Verify BKR DFO2 (iF 4160 V bus 1.3 j diesel generator cooling tie to 1K 4160 V bus) - supplied from Unit 2, CLOSED. THEN secure 1-2A and/or 1C diesel generator using ATTACHMENT 2, SECURING A DIESEL GENERATOR WITH A SAFETY INJECTION SIGNAL PRESENT.
1.4 Check BKR DG15 (lB startup 1.4 Verify 1G 4160 V bus energized transformer to 1G 4160 V bus) by lB diesel generator.
- CLOSED.
Step 1 continued on next page.
Page 1 of 7
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 1 1.5 Verify BKR DG02 (lG 4160 V bus 1.5 j diesel generator cooling tie to 1L 4160 V bus) -
Q[ supplied.
CLOSED. THEN secure lB diesel generator using ATTACHMENT 2.
SECURING A DIESEL GENERATOR WITH A SAFETY INJECTION SIGNAL PRESENT.
1.6 Verify all RCP busses -
ENERGIZED.
[1 1A 4160 V bus
[1 lB 4160 V bus
[1 1C 4160 V bus 1.7 Check 1E 4160 V bus - 1.7 Establish power to 1C 600 V LC ENERGIZED. emergency section loads.
1.7.1 Place handswitch for pressurizer heater group lB in OFF.
1.7.2 Open BKR ECO8-1.
1.7.3 Close BKRs EEO7-1 and EC1O-l.
CAUTION: To prevent diesel generator overloading, at least 0.3 MW of diesel generator capacity must be available prior to energizing a group of pressurizer heaters.
1.7.4 Energize pressurizer heater group lB as required.
1.8 Check 1D 4160 V bus - 1.8 Proceed to step 1.10.
ENERGIZED.
1.9 IF 1D 4160 V bus energized, THEN return to procedure and step in effect.
Step 1 continued on next page.
Page 2 of 7
FNP1ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 1 1.10 Establish power to 1A 600 V LC emergency section loads.
1.10.1 Place handswitch for pressurizer heater group 1A in OFF.
1.10.2 Verify open BKR EAO8l.
1.10.3 Verify closed BKRs EDO8-1 and EAO9-1.
CAUTION: To prevent diesel generator overloading, at least 0.3 MW of diesel generator capacity must be available prior to energizing a group of pressurizer heaters.
NOTE: The BYPASS position allows manual energization of pressurizer heater group 1A from the MCB handswitch, and automatic energization based on either pressurizer pressure 2210 psig or pressurizer level 5% above program.
1.10.4 WHEN pressurizer heater group 1A operation is desired, THEN place HTR GRP 1A BLOCKING BYPASS SW to BYPASS.
1.10.5 required, THEN manually energize pressurizer heater group 1A.
Step 1 continued on next page.
Page 3 of 7
FNP1-ESP-J.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 1 CAUTION: To ensure adequate supply voltage to all class lE loads and to meet short circuit analysis constraints, only one air compressor, 1C (preferred) or lA, 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 lA air compressor for service, service as follows.
1.11.1 Verify 1C air compressor a) Verify lC 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-l 1-1 not lit
[1 MLB-l 11-1 not lit c) IF LOSP has occurred, THEN place B1F Sequencer Test Trip Override Switch (TTOS)in OFF:
- 1) Obtain B1F Sequencer TTOS key from SSS office.
- 2) Insert key into ElF 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
ENP-l-ESP-1.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 CAUTION: IF offsite power is lost after sequencer is reset, THEN manual actions may be required to restart safeguards equipment.
d) Reset B1F 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-l-2A, THEN verify the B1F 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 iH 4160 V bus).
h) IF 1H 4160 V bus energized, THEN energize 1G 600 V LC from normal supply.
[1 BKR DHO1 closed
[1 BKR EGO2-i closed i) Start 1A AIR COMPRESSOR.
Step 1 continued on next page.
Page 5 of 7
FNP-1-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I 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-l-SOP-31.O, COMPRESSED AIR SYSTEM.
- 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
FNP-1-ESP-i.1 SI TERMINATION Revision 25 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-1-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 Return to procedure and step in effect.
1.13 Check instrument air to 1.13 Align instrument air to containment, containment. (BOP)
[1 MLB-3 1-2 QI lit [1 N1P19HV3825 open
[1 N1P19HV3885 open IA TO PENE RM PRESS LO
[] Annunciator KD1 clear IA TO CTMT
[1 Q1P19HV3611 open
-END Page 7 of 7
FNP-l-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 2 SECURING A DIESEL GENERATOR WITH A SAFETY INJECTION SIGNAL PRESENT Secure affected diesel 1 Secure affected diesel generator from EPB. generator from diesel local control panel (155 ft. DIESEL 1.1 Verify SI-RESET. BLDG).
[1 MLB-l 1-1 not lit a) Place affected diesel
[1 MLB-1 11-1 not lit generator MODE 4 SELECTOR SWITCH to MODE 4.
1.2 Place the affected diesel generator MODE SELECTOR SWITCH b) Depress affected diesel to MODE 2. generator local STOP pushbutton.
1.3 Depress affected diesel generator DIESEL EMERG START RESET pushbutton.
CAUTION: Failure to perform steps 1.5 and 1.6 immediately following step 1.4 may result in restart of the diesel generator when the low speed relay de-energizes.
1.4 Depress affected diesel generator STOP pushbutton.
[] DIESEL STOP light lit 1.5 Place affected diesel generator MODE SELECTOR SWITCH to MODE 3.
1.6 Depress affected diesel generator DIESEL EMERG START RESET pushbutton.
- END -
Page 1 of 1
FNP-l-ESP-l.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained ATTACHMENT 3 RE-ESTABLISHING HHSI FLOW Align charging pump suction to RWST.
RWST TO CHG PUMP F] Q1E21LCV115B open
[1 Q1E21LCV115D open CHG PUMP SUCTION HDR ISO
[1 Q1E21MOV813OA open
[1 Q1E21MOV813OB open
[1 Q1E21MOV8131A open
[1 Q1E21MOV8131B open VCT OUTLET ISO
[] Q1E21LCV115C closed
[1 Q1E21LCV115E closed 2 Verify charging pump miniflow valves - OPEN.
1A(1B,1C) CHG PUMP MINIFLOW ISO
[] Q1E21MOV81O9A F] Q1E21MOV81O9B F] Q1E21MOV81O9C CHG PUMP MINIFLOW ISO F] Q1E21MOV81O6 Page 1 of 3
FNP-l-ESP-1.l SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
ATTACHMENT 3 3 Isolate normal letdown and charging.
3.1 Isolate letdown LTDN ORIF ISO 45 GPM
[1 Q1E21HV8149A closed LTDN ORIF ISO 60 GPM
[1 Q1E21HV8149B closed
[] Q1E21HV8149C closed LTDN LINE CTMT ISO
[1 Q1E21HV8152 closed 3.2 Manually close charging flow control valve.
CHG FLOW
[1 FK 122 3.3 Verify charging flow path aligned.
3.3.1 Verify charging pump discharge flow path -
ALIGNED.
[] Q1E21MOV8132A open LI Q1E21MOV8132B open
[1 Q1E21MOV8133A open LI Q1E21MOV8133B open CHG PUMPS TO REGENERATIVE HX
[1 Q1E21MOV81O7 closed
[1 Q1E21MOV81O8 closed 4 Open HHSI isolation valves.
HHSI TO RCS CL ISO LI Q1E21MOV88O3A
[1 Q1E21MOV88O3B Page 2 of 3
FNP-l-ESP-l.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I
ATTACHMENT 3 5 Start additional CHG PUMPs as required.
6 Monitor charging pump ininiflow criteria.
6.1 Control charging pump miniflow valves based on RCS pressure.
[1 P1 4O2A
[1 P1 4O3A RCS PRESSURE <1300 psig 1300 psig- >1900 psig 1900 psig lA(lB,lC) CRC PUMP MINIFLOW ISO Q1E21MOV []8109A []8109A []8l09A closed as is open
[]81O9B []8109B []8l09B closed as is open
[1 81O9C [1 8109C [1 8109C closed as is open CHG PUMP MINIFLOW ISO Q1E21MOV [18106 [18106 [18106 closed as is open 7 Return to step in effect.
- END -
Page 3 of 3
FOLDOUT PAGE FNP-1-ESP-1.1 SI TERMINATION Revision 25 Step Action/Expected Response Response NOT Obtained I I I 1 Following SI termination monitor SI reinitiation criteria.
1.1 Greater than 16°F(45°F} 1.1 Establish HHSI flow using subcooled in CETC mode and PRZR ATTACHMENT 3, RE-ESTABLISHING level above 13%{43%}. HHSI FLOW and go to FNP-1-EEP--1, LOSS OF REACTOR OR SECONDARY COOLANT.
2 Monitor FNP-1-EEP--2. FAULTED STEAM GENERATOR ISOLATION branch criteria.
2.1 No SG pressure falling in an 2.1 L affected SG previously uncontrolled manner or less isolated, than 50 psig. THEN go to FNP-1-EEP-2, FAULTED STEAM GENERATOR ISOLATION.
3 Monitor switchover criterion.
3.1 CST level greater than 5.3 ft. 3.1 Align AFW pumps suction to SW using FNP-1-SOP-22.0.
3.2 RWST level greater than 3.2 Go to FNP-1-ESP-1.3, TRANSFER 12.5 ft. TO COLD LEG RECIRCULATION.
4 Monitor charging minif low criteria (during SI).
4.1 RCS pressure less than 4.1 Verify miniflow valves open.
1900 psig.
4.2 RCS pressure greater than 4.2 Verify miniflow valves closed.
1300 psig.
5 Monitor adverse containment criteria.
5.1 CTMT pressure less than 4 psig 5.1 Utilize bracketed adverse CTMT and radiation less than condition numbers.
iO R/hr.
FNP LT-35 JPM Page 1 of 13 SIMULATOR JPM C.
CRO-(NEW 2)
TITLE: Transfer Feedwater control from the Main Feed Regulating Bypass Valves to the Main Feed Regulating Valves.
EVALUATION LOCATION: SIMULATOR El CONTROL ROOM El CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-219 Fl ALTERNATE PATH El TIME CRITICAL El PRA JPM DIRECTIONS:
- 1. Examinee will be provided a marked up copy of UOP-1.2, complete up to Step 5.76. All other references of the simulator will be available at the examinees discretion.
- 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. All events are TRIGGERED, and NO Cues are required by the examiner, however the trigger may be initiated upon the Examiners request.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Perform the IOAs of AOP-4.0, Close MOV-3232A and the 1A FRV Bypass valve, and then trip the reactor.
o (safety significance) Overfill of the 1 A SG, possible Lo-Lo SGWL Rx Trip criteria and operating RCS Tavg <54 1°F at power.
Examinee:
Overall JPM Performance: Satisfactory 11 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer GT Ohmstede Date: 2/1/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 SIMULATOR JPM C. Page 2 of 13 (Guide pages = 12)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-2 19 for JPM C Base IC- IC-37 Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms ANN ACK Turn Horns ON ann horn VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
1ARCP trip imfcrcrcpl_co2 Manually insert failure IF required:
Setup Run quick setup BAT file 201 2nrcexamjpmc.txt
FNP ILT-35 SIMULATOR JPM C. Page 3 of 13 (Guide pages = 12)
BAT file contains fol1owin required presets:
- FCV-478 will stick open Imf &478-c 20 10 Blocks 1A SGFP auto trip Imf mal-fwml2a RTB A and B fails to open in auto but will manually imf cBKRXTRP_cc5 open imf cbkrxtrp cc6 open Trips 1A RCP -when any MFRV PB is taken to raise trig 1 10 sec delay imf crcrcpl_co2 (1 10)
Trigl activates on lA/B/C MFRV PB to raise trgset 1 x21I064R!! x21I065R!! x21I066R FREEZE the simulator SNP 219 [trnl
CONDITIONS When I tell you to begin, you are to Transfer Feedwater control from the Main Feed Regulating Bypass Valves to the Main Feed Regulating Valves.
The conditions under which this task is to be performed are:
- a. UOP-1 .2, Startup of Unit from Hot Standby to Minimum Load, step 5.76 is in progress.
- b. 1A SGFP is running.
- c. MFR Bypass Valves are open and in AUTO, Main FRVs are open and in MAN.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE: When the first MFRV RAISE pushbutton is depressed on the MFRV, THEN IA RCP will trip 10 sec later.
(step 5.76.2 of UOP-1.2)
- 1. Open the Main Feed Regulating Valves as Depress the OPEN Push S/U follows: button on MFRV controllers Slowly open Main Feed Regulating Valves until []FK478 1A SG FW FLOW the Main Feed Regulating Bypass Valves have controller.
automatically closed to a reliable controlling []FK488 lB SG FW FLOW position. (approximately 15-50%) controller.
[]FK498 IC SG FW FLOW controller.
D IDENTIFIES that EF1 and EF4 Alarms.
FNP ILT-35 SIMULATOR JPM C. Page 5 of 13 (Guide pages = 12)
AOP-4.0 is entered here; Steps 1 and 2 are Immediate Operator Actions (AOP-4.0 step 1)
- 2. Check 1A and lB RCPs RUNNING.
El CHECKS the following: S / U o 1A RCP handswitch-YLW light LIT o lB RCP handswitch- RED light LIT o 1A RCP amps 0 amps o lBRCPamps0.65 x 10 Amps (AOP-4.0 step I & RNO actions)
- 3. Manually close pressurizer spray valve for 1A El *DEPRESS the MANUAL and S / U RCP. LOWER pushbutton on PK
[]1A RCS loop spray valve PK-444C. 444C El CHECKS PCV-444C is closed o MAN light is LIT Demand- 0%
NOTE:
- 1A SG Water level will initially fall to -60% within 40 seconds of RCP trip, however level will return to> 65% within the next 2 minutes without ANY actions by the operator. The operator may or may not adjust FCV position immediately upon assessing SG water level.
- Element 5 will NOT be successful due to installed failure. IF sequence of elements 4 & 5 are reversed, then Element 4 may NOT be performed since isolation cannot be achieved.
(AOP-4.0 step 2)
- 4. [CA] Maintain SG narrow range level stable at El CHECK 1A SG Narrow Range S / U approximately 65% using: LEVEL instruments and notes
[]Main Feedwater Bypass Regulating Valves, level < but approaching 65%.
When level is 65%,
El CLOSE control FW Byp VLV valve for 1A SG by pushing the MAN Pushbutton and LOWER PUSHBUTTON o MAN light LIT o Demand0%
o FCV 479- GRN LIGHT LIT
FNP ILT-35 SIMULATOR JPM C. Page 6 of 13 (Guide pages = 12)
(AOP-4.0 step 2)
- 5. [CA] Maintain SG narrow range level stable at ATTEMPT to CLOSE control S / U approximately 65% using: FRV valve for 1A SG by
[]Main Feedwater Regulating Valves pushing the MAN Pushbutton and LOWER PUSHBUTTON o MAN light LIT o Demand 0%
o FCV 478- RED and GRN lights LIT IDENTIFIES that 1A SG LEVEL continues to RISE.
NOTE:
- The critical portion of Element 6 is for MOV3232A to be closed prior to 82% Hi-Hi SGWL which will automatically trip the Main Turbine. This will occur in approx. 3 mm.
(1A SGFP AUTO trip is blocked and the RTBs will not auto open.)
- If the Reactor is tripped prior to 82% SG level, then step 6 is NOT a critical step. The critical action would then be to isolate feedwater flow to IA SG (at step 16 of the JPM) prior to reaching SG OVERFILL.
- IF NO ACTIONS ARE TAKEN or are DELAYED the tirneline and actions of element 7&8 will differ:
1A S/G will >82% within 3-5 minutes from the RCP trip and a potential for SG OVERFILL exists. lB & 1C SG will fall <28% within the same 3-5 minutes.
If P-14 (82% HI LVL) is encountered a Turbine Trip WILL occur.
IF SGWL LO LO LVL (<28%) is encountered a RX trip WILL NOT automatically occur.
- SG OVERFILL is failure criteria. This condition must be checked if SG level> 100% NR level. (SG full when >0.995 1_. fTC ----
1(1 12)
(AOP-4.0 step 2 RNO)
- *POSITION handswitch
- 6. If Main Feedwater in service, then close the El S/U affected SG Main Feedwater stop valve(s) COUNTER-CLOCKWISE to
[]1A SG Q1N21M0V3232A Close:
[]MOV-3232A-GRN Light LIT
FNP ILT-35 SIMULATOR JPM C. Page 7 of 13 (Guide pages = 12)
(AOP-4.0 step 3)
- 7. [CA] Monitor Tavg for all three RCS loops Check RCS Tavg S / U 541°F. o TI-412D<539°F o TI-422D> 548°F o TI-432D>548°F (AOP-4.0 step 3 RNO)
- 8. IF the main generator is ON LINE, THEN trip POSITION EITHER the RX S / U the reactor and go to FNP-l-EEP-0, REACTOR TRIP switch(s) in the TRIP OR SAFETY INJECTION COUNTER CLOCKWISE DIRECTION.
El CENTER section switch El LEFT-SIDE switch (EEP-0.0 Step 1)
- 9. Check reactor trip. CHECKs that the RX has S / U Reactor trip and bypass breakers OPEN tripped.
Nuclear power FALLING Reactor trip and bypass IF DRPI available THEN rod bottom lights breakers OPEN LIT LI Nuclear power FALLING (EEP-0.0 Step 2)
- 10. Check turbine Trip. LI OBSERVES TSLB2 S/U
[1 TSLB2 14-1 LIT -
All TSLBs are LIT
[1 TSLB2 14-2 LIT
[] TSLB2 14-1 LIT-
[] TSLB2 14-3 LIT -
[] TSLB2 14-2 LIT
[1 TSLB2 14-4 LIT -
[] TSLB2 14-3 LIT-
[] TSLB2 14-4 LIT-
FNP ILT-35 SIMULATOR JPM C. Page 8 of 13 (Guide pages 12)
(EEP-0.0 step 3) 1 1.Verify power to 4160 V ESF busses. CHECKS the following: S / U (EEP-0.0 step 3.1) LI iF 4160V bus power available 4160 V ESF busses AT LEAST TRAIN light LIT ONE ENERGIZED Li lK4l60Vbuspower
- iF 4160V bus power available light LIT available light LIT
- 1G 4160V bus power available light LIT LI IG4i6oVbuspower available light LIT (EEP-0.0 step 3.2) LI 1L 4160V bus power available 4160 V ESF busses BOTH TRAINS light LIT ENERGIZED
- A Train (iF & 1K) power available lights lit i-2A, lB. IC DIESELS for
- B Train (1G & 1L) power available lights lit operation using any means:
LI MLB-4 (pump status)
(EEP-0.0 step 3.3)
LI SEQ Status lights
[CA] Verify operating diesel generator(s) -
LI DG output bkrs SUPPLIED FROM AT LEAST ONE SW PUMP LI DG speed LI IF DG running: then LI 1 A OR 1 B SW pump brkr RED light LIT LI IC or 1D SW pump brkr RED light LIT LI SW header pressure in both A & B trains > 60 psig
FNP ILT-35 SIMULATOR JPM C. Page 9 of 13 (Guide pages = 12)
(EEP-0.0 step 4)
(EEP-O.O step 4.1)
Check any SI actuated indication BOTH MLB1 1-1 & 11-1 -
BYP & PEPJvI Panel SI actuated LIT LIT MLB 11-1-LIT MLB 111-1LIT IF SI has NOT actuated, (EEP-0 RNO step 4.1) CHECKS the following If any setpoint and coincidence shown in the PT-950 through PT-954 < 4 table below has been reached or exceeded psig.
THEN SI is required. TSLB-1 for 2/3 col 1 NOT LIT (EEPO RNO STEP 4.1.2) TSLB-2 for 2/3 col 17-NOT IF SI is required, Actuate SI. LIT PT-402/403 OR PT (EEP-O.0 step 4.2) 455/456/457> 1850 psig.
Verif BOTH TRAINS of SI -ACTUATED SG pressures> 585 psig TSLB 4 NO coincidence met.
If SI is NOT required, go to ESP 0.1, Reactor Trip Response.
ESP-0. 1 entered.
(ESP-0.1 step 1)
- 13. IF any RCP running, THEN check RCS Checks lB & 1C RCPs running, S / U average temperature STABLE AT OR and then checks RCS Tavg.
APPROACHING 547°F.
TI 422D B Loop LI T1432DC Loop
FNP ILT-35 SIMULATOR JPM C. Page 10 of 13 (Guide pages = 12)
(ESP-0.1 step 2)
- 14. [CAl WHEN RCS average Checks lB & 1C RCPs running, S / U temperature less than 554°F, and then checks RCS Tavg.
THEN verify feedwater status.
El TI 422D B Loop (ESP-0.1 step 2.1) El TI 432D C Loop Verify main feedwater flow control and bypass valves CLOSED. El ATTEMPT to CLOSE FRV for 1A SG by pushing the MAN Pushbutton and LOWER PUSHBUTTON o MAN light LIT o Demand0%
o FCV 478- RED and GRN lights LIT El IDENTIFIES that 1A SG LEVEL continues to RISE.
NOTE:
- Performance of either step 15 or 17 of the JPM is required for the critical actions to be accomplished. Either one will satisfy those actions.
(ESP-0.1 step 2.1 RNO)
- 15. Close main feedwater stop valves. El *PO5ITION handswitch S / U COUNTER-CLOCKWISE to Close:
[1 MOV-3232A-GRN Light LIT An alternate and additional action that may be taken to terminate the level rise in 1A SG (this is not required):
- POSITION handswitch COUNTER-CLOCKWISE to Close:
[1 1A SGFP DISCH valve MOV-503A-GRN Light LIT
- EXAMINER. CHECK CHECK SG OVERFILL has NOT occurred.
FNP ILT-35 SIMULATOR JPM C. Page 11 of 13 (Guide pages 12)
(ESP-0.l step 2.2)
- 16. Defeat MDAFWP auto start on SGFP trip. POSITION AUTO/DEFEAT handswitches:
[]IA in DEFEAT
[]1BinDEFEAT (ESP-0.1 step 2.3)
- 17. Verify both SGFPs - TRIPPED.
- Verify both SGFPs tripped:
[ ] 1A SGFP Trip pushbutton depressed.
STOP TIME Terminate when the Immediate Operator Actions of EEP-0 have been completed if feedwater flow has been isolated, OR after ESP-0.l step 2.3 is complete if feedwater has not previously been isolated.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-UOP-1.2, Version 102.0 FNP-l-AOP-4.0, Version 19.0 FNP-1-EEP-0.0, Version 43 FNP-1-ESP-0.l, Version 32
- 2. K/As: 003A1.07 RO-3.4 SRO-3.4 003A2.02 RO-3.7 SRO-3.9 APEO15/017AA1.08 RO-3.0 SRO-2.9 APEO15/O17AA1.09 RO-3.1 SRO-3.2 GENERAL TOOLS AND EQUIPMENT:
Provide/Acciuire:
- 1. An unmarked up copy of FNP-l-UOP-l.2; will be provided in the briefing room as part of the pre job brief.
- 2. AOP-4.0, EEP-0, and ESP-0. 1 will be available in the simulator. Pages marked up will be replaced after each JPM.
FNP ILT-35 SIMULATOR JPM C. Page 12 of 13 (Guide pages = 12)
Critical ELEMENT justification:
STEP Evaluation I Not critical This is part of the assigned task to start the JPM this element is ONLY intended to initiate the event and may be bypassed at the discretion of the examiner.
2 Not critical checking which RCP tripped is not critical as long as the correct spray valve is closed.
3 CRITICAL- Closing the spray valve is an IOA and critical to proper RCS pressure control.
RCS pressure will remain low but could increase depending on applicant response.
4 Not critical Since FRV will stick open this action alone will NOT prevent oveifill Element 6 becomes the critical element.
5 Not critical Since FRV will stick open, this action alone will NOT pievent overfill Element 6 becomes the critical element.
6 CRITICAL- Task objective, isolates Feed flow to the 1A SG. PRIOR to overfill of the SG.
7 Not critical step is a check step 8 CRITICAL- Since the RTBs will not auto open and this is a step in AOP-4.O to trip the reactor, this is critical. There are many evaluation points where this may become critical:
- 1. AOP-4.O, step 3 RNO (With the Main Generator on line, this is required to be done in a timely manner, but not more than double the time of the 3PM or 30 minutes, whichever is less)
- 2. When lA SO WR WL reaches 82%, then the lB/iC SO FRVs and bypass valves go closed; SGWL will decrease to 28% where a reactor trip is required; then failure criteria is double the time of the 3PM and successful progress being made.
- 3. If the plant continues to run with no action to isolate the lA SG then failure criteria is overfill of the 1A SG or double the time of the 3PM, whichever is less.
9 14 Not critical steps are foi checking plant status 15 CRITICAL- if not previously performed, meets the task objective, isolates Feed flow to the 1A SG. PRIOR to overfill of the SO.
16 Not critical task is not affected by perfoimance oi lack of peiformance of this step 17 CRITICAL- if not previously performed, meets the task objective, isolates Feed flow to the 1A SG. PRIOR to overfill of the SO.
COMMENTS:
FNP ILT-35 JPM SIMULATOR JPM c. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to Transfer Feedwater control from the Main Feed Regulating Bypass Valves to the Main Feed Regulating Valves.
The conditions under which this task is to be performed are:
- a. UOP-1.2, Startup of Unit from Hot Standby to Minimum Load, step 5.76 is in progress.
- b. IA SGFP is running.
- c. MFR Bypass Valves are open and in AUTO, Main FRVs are open and in MAN.
07/13/10 8:10:54 FNP- 1 -AOP-4.0 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 FNP-0-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
07/13/10 8:10:54 FNP-1-AOP-4.O LOSS OF REACTOR COOLANT FLOW Version 19.0 Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 11 Attachment 1 2 Page 1 of 1
07/13/10 8:10:54 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 I SG level in any affected ioop 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 loop.
5 In order to prevent a possible reactor power excursion, NO RCP should be restarted while the reactor is critical.
6 I B RCP is NQI running, THEN 1 A & IC RCPs are required to provide adequate spray flow through the 1A RCS loop spray valve.
Page 1 ofll
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 I I NOTE: Steps I through 2.1 are IMMEDIATE OPERATOR actions.
Check l and lB RCPs RUNNING.
- 1 Manually close pressurizer spray valve for affected RCP.
[1 IA RCS loop spray valve PK-444C
[j lB RCS loop spray valve PK-444D 2 [CAl Maintain SG narrow range level 2 SG level rise cannot be controlled, stable at approximately 65% using: THEN perform the following:
[1 Main Feedwater Regulating Valves
[1 Main Feedwater Bypass Regulating Valves. 2.1 Ii main feedwater in service, THEN close the affected SG Main
[1 Auxiliary Feedwater Control Valves.
Feedwater Stop Valve(s)
[1 1A SG Q1N21MOV3232A
[1 lB SG Q1N21MOV3232B
[J lC SG QIN21MOV3232C 2.2 IF auxiliary feedwater in service, THEN close the affected SG AFW Stop Valve(s)
[] 1A SG Q1N23MOV335OA
[] lB SG Q1N23M0V3350B
[1 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-l-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
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 3.2.2 Verify rod control in MANUAL 3.2.3 Stabilize Tavg in the idle loop(s)
> 54 1°F while maintaining the running loop(s) < 554°F by adjusting rod position and/or boron concentration 3.2.4 IF unable to restore Tavg 54 1°F, THEN trip the reactor and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 4 (CA] Maintain PRZR pressure 2200-2300 psig.
4.1 Control PRZR heaters as required.
4.2 IA and lB RCPs running, 4.2 Perform the following THEN, control pressurizer pressure with both normal spray valves. 4.2.1 fl lB RCP running, THEN control pressurizer pressure with PK-444D.
NOTE: Running 1A and IC RCPs will be required to provide adequate spray flow through the 1A RCS ioop spray valve.
4.2.2 ffl 1A & IC RCPs are running, THEN control pressurizer pressure with PK-444C.
4.2.3 IF spray flow is adequate, THEN proceed to step 5.
4.2.4 no spray valves are available, THEN proceed to step 4.4.
4.3 Proceed to step 5.
Step 4 continued on next page Page Completed Page 3 of 11
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 II CAUTION: To prevent PRZR PORV failure, cycling of PRZR PORVs should be minimized.
4.4 IF normal spray valves are not available 4.4 Perform the following:
AND letdown is on service, THEN establish auxiliary spray.
4.4.1 Open RCS loop spray valves a) WHEN needed for immediate pressure
[] PK 444C manually open ontrol pressurizer pressure with
[1 PK 444D manually open PRZR PORV.
[1 Q1E21HV8146 closed
- 2) Maintain PRT parameters normal using FNP-l-SOP-1.2, REACTOR COOLANT 4.4.3 Close RCS ALT CHG LINE PRESSURE RELIEF SYSTEM
[1 Q1E21HV8147 closed
- 3) IF any PRZRPORV fails to recluse, 4.4.4 Open RCS PRZR AUX SPRAY THEN close associated PRZR PORV ISO.
[1 Q1E21HV8145 open b) Proceed to step 5 Response Not Obtained Column AND establish normal letdown.
Step 4 continued on next page Page Completed Page 4 of 11
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: Changes in charging flow will cause PRZR pressure fluctuations when auxiliary spray is established.
4.4.5 Operate the following valves as required:
[1 CHG FLOW FK-122 manually adjusted as required to control pressure
[] 1A LOOP SPRAY VLV PK-444C manually openlclosed
[1 lB LOOP SPRAY VLV PK-444D manually open/closed
[1 RCS PRZR AUX SPRAY Ql E2 1 HV8 145 open/closed
[J RCS NORMAL CHG LINE Qi E2 1 HV8 146 open/closed
[1 RCS ALT CHG LINE Qi E2 1 HV8 147 open/closed 4.4.6 Proceed to Step 6.
5 Check normal letdown ESTABLISHED.
- 5 Perform the following:
CAUTION: CCW to the miscellaneous header is required to prevent damage to the letdown heat exchanger.
5.1 Verify the CCW miscellaneous header is aligned to an operating CCW loop.
Step 5 continued on next page Page Completed Page 5 of 11
07/13/10 8:10:54 FNP-l-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 Step Action/Expected Response Response Not Obtained II I 5.2 IF letdown has isolated due to a plant transient, THEN establish normal letdown using ATTACHMENT 1, RESTOIUNG LETDOWN.
5.3 j a letdown isolated due to a system malfunction, THEN perform the following:
[1 Attempt to restore any letdown flow using FNP-1-AOP-16.0, CVCS MALFUNCTION.
[] Continue with applicable steps of this procedure.
5.4 WHEN normal letdown restored AND required, THEN return to step 4.4 to establish auxiliary spray.
6 [CA] Maintain PRZR level at approximately 22%.
Page Completed Page 6 of 11
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 I NOTE: In Mode 3 with reactor trip breakers closed AND rod control enabled, loss of two RCP busses requires actions to restart RCP(s) or de-energize all CRDMs within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per Tech Spec 3.4.5, Condition C.
7 Within six hours of the loss of RCS flow complete the following:
7.1 IF theunit is in Model or2, THEN place unit in Mode 3 using the following procedures:
[] FNP-l-UOP-3.l, POWER OPERATION
[] FNP- I -UOP-2. I, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY 7.2 WHEN unit in Mode 3 or 4, 7.2 Secure both CRDM MG sets using THEN verify all reactor trip and reactor FNP- 1 -SOP-41 .0, CONTROL ROD trip bypass breakers open. DRIVE AND POSITION INDICATION SYSTEM.
[] Reactor Trip Breaker A
[] Reactor Trip Breaker B
[j Reactor Trip Bypass Breaker A
[] Reactor Trip Bypass Breaker B NOTE: Step 7 must be complete before continuing with this procedure.
8 Check at least one RCP RUNNING.
- 8 Perform the following.
8.1 Secure any dilution in progress.
8.2 Start one RCP using FNP-1-SOP-1.1, REACTOR COOLANT SYSTEM.
Step 8 continued on next page Page Completed Page 7 of 11
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 8.3 WHEN at least one RCP running, THEN go to FNP-1-UOP-2.1, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY.
8.4 IE no RCP can be established running, THEN proceed to step 10.
9 Go To FNP-1-UOP-2.1, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY NOTE:
- During natural circulation, loop transit time will be on the order of 10 minutes. Temperature trends will be of more value than actual temperatures
- As natural circulation develops, RCS AT should stabilize at less than 65°F. This will take 20 to 30 minutes
10 Verify adequate natural circulation.
10.1 Check SG pressures stable or falling.
10.2 Check SUB COOLED MARGIN MONITOR indication greater than 16°F subcooled in CETC mode.
10.3 Check RCS hot leg temperatures stable or falling.
RCS HOT LEG TEMP
[1 TR413 10.4 Check core exit T/Cs stable or falling.
10.5 natural circulation NQI adequate, THEN dump steam at a faster rate.
Step 10 continued on next page Page Completed Page 8 of 11
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 10.6 Begin taking natural circulation logs.
CAUTION: During natural circulation with low decay heat loads, overfeeding the SGs will result in excessive cooldown with no apparent rise in SG level.
11 [CAt Maintain SG narrow range levels at approximately 65%.
- Control MDAFWP flow.
MDAFWP TO 1A(1B,lC) SG FLOW CONT
[] HIC 3227AA adjusted
[j HIC 3227BA adjusted
[] HIC 3227CA adjusted
- Control TDAFWP flow.
TDAFWP TO lA(lB,1C) SG FLOW CONT
[j HIC 3228AA adjusted
[] HIC 3228BA adjusted
[] HIC 3228CA adjusted 12 [CAl Monitor CST level.
12.1 LI-4005 remains in the normal operating 12.1 Contact Chemistry to maximize make up to band 32-39. the CST.
12.2 LI-4005 indicates >26 ft 12.2 adequate make up can NQI be LI-4l32A indicates >11 ft established, LI-4 1 32B indicates >11 ft THEN notify the Shift Manager and consideration should be given to reducing SGBD flow.
12.3 LI-4005 indicates >5.3 ft 12.3 IF CST level less than 5.3 ft.
LI-4132A indicates >5.3 ft THEN align AFW pump suction to SW LI-4132B indicates >5.3 ft using FNP-1-SOP-22.0, AUXILIARY FEEDWATER SYSTEM.
Page Completed Page 9 of 11
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 13 Verify reactor makeup system aligned. 13 Manually control reactor makeup system using FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR 13.1 Verify BORIC ACID MKUP FLOW FK MAKEUP CONTROL SYSTEM.
113- ADJUSTED TO DELIVER GREATER THAN EXISTING RCS BORON CONCENTRATION.
13.2 Verify reactor makeup system IN AUTOMATIC MODE.
MKUP MODE SEL SWITCH
[1 N1E21HS2100QinAUTO MKUP MODE CONT SWITCH
[1 N1E21HS2 lOOP to START 14 [CAl Maintain shutdown margin adequate.
14.1 Direct Chemistry to sample RCS for boron concentration using FNP-1-CCP-651, SAMPLING THE REACTOR COOLANT SYSTEM at least once per two hours.
Step 14 continued on next page Page Completed Page lOofil
07/13/10 8:10:54 FNP-1-AOP-4M LOSS OF REACTOR COOLANT FLOW Version 19.0 Step Action/Expected Response Response Not Obtained NOTE: Natural circulation may cause inadequate RCS mixing. Any boration should be at a continuous rate not exceeding 65 gpm.
14.2 Verify shutdown margin using: 14.2 Borate RCS using FNP- 1 -AOP-27.0, EMERGENCY BORATION.
[1 FNP-l-STP-29.1, SHUTDOWN MARGIN CALCULATION (TAVG 547°F)
[1 FNP-1-STP-29.2, SHUTDOWN MARGIN CALCULATION (TAVG < 547 °F OR BEFORE THE INITIAL CRITICALITY FOLLOWING REFUELING).
14.3 Monitor source range count rate stable or 14.3 Borate RCS using FNP-1-AOP-27.0, falling. EMERGENCY BORATION.
15 [CAl Maintain hot standby conditions.
- Maintain steam header pressure less than or equal to 1005 psig.
- Maintain average core exit T/C temperature less than 600°F.
16 IF RCS cooldown NOT required, 16 Go to FNP-1-ESP-0.2, NATURAL THEN return to step 8. CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL STEAM HEAD VOIDING to initiate RCS cooldown.
-END Page Completed Page 11 of 11
07/13/10 8:10:54 FNP-1-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 ATTACHMENT 1 RESTORING LETDOWN NOTE: This attachment assumes that letdown was lost due to a plant transient and that no system malfunction has occurred.
1 [CA] WHEN plant conditions permit, THEN restore normal letdown flow as follows:
1.1 Verify closed all letdown orifice isolation valves.
LTDN ORIF ISO 45 GPM
[1 Q1E21HV8149A LTDN ORIF ISO 60 GPM
[1 Q1E21HV8149B
[1 Q1E21HV8149C 1.2 Verify LP LTDN PRESS PK 145 in MANUAL and adjust the demand signal to 50% or less.
1.3 Verify that LTDN HX OUTLET TEMP TK 144 is in AUTO, and set at 3.3 to maintain temperature at approximately 100 °F.
1.4 Verify that the VCT HI LVL DIVERT VLV LCV- 11 5A position indicator VCT light is lit and the handswitch is in the AUTO position.
1.5 Verify that LTDN HI TEMP DIVERT VLV Q1E21TCV143, DEMIN light is lit and the handswitch is in the AUTO position.
1.6 IF necessary,,
THEN OPEN both LTDN LINE PENE RM ISO s Q1E21HV8175A and B from the Penetration Room T
Isolation Panel.
1.7 Verify open LTDN LINE CTMT ISO Q1E21HV8152 1.8 Verify open both LTDN LINE ISO Q1E21LCV459 and Q1E2ILCV46O.
1.9 Verify CHG FLOW FK 122 is in MAN AND establish the required minimum charging flow for the number of orifices to be placed on service. (18 gpm for 1 orifice or 40 gpm for two orifices) 1.10 OPEN LTDN ORIF ISO 60 GPM Ql E2 1 HV8 1 49B or C to establish approximately 60 gpm Letdown flow.
Step 1 continued on next page Page 1 of2
07/13/10 8:10:54 FNP-1-AOP-4.0 LOSS OF REACTOR COOLANT FLOW Version 19.0 ATTACHMENT 1 RESTORING LETDOWN 1.11 Verify that LP LTDN PRESS PK 145 is set between 4.3-7.5 to maintain the desired Letdown Pressure between 260-450 psig.
1.12 IF necessary, THEN adjust LP LTDN PRESS PK 145 in MANUAL to stabilize Letdown Pressure at the desired value.
1.13 Place LP LTDN PRESS PK 145 in AUTO and verify that Letdown pressure is maintained at the desired value.
1.14 Verify that LTDN HX OUTLET TEMP TK 144 is maintaining Letdown temperature at approximately 100 °F.
[] TI-II6VCTTEMP
[] TI-143 DIVERT LTDN HX TEMP
[] TI-144 CCW LTDN HX TEMP 1.15 IF normal letdown flow NOT established, THEN attempt to restore any letdown flow using FNP-l-AOP-16.0, CVCS MALFUNCTION.
-END Page 2 of 2
FNP ILT-35 JPM Page 1 of 8 SIMULATOR JPM D.
CRO-(NEW 3)
TITLE: Start Containment Spray in accordance with EEP-O.O step 6 RNO actions.
EVALUATION LOCATION: 11 SIMULATOR El CONTROL ROOM El CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-220 E ALTERNATE PATH El TIME CRITICAL El PRA JPM DIRECTIONS:
- 1. Examinee will obtain all references from the simulator.
- 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:
- Secure all three Reactor Coolant Pumps.
- Establish Containment Spray flow using the 1A CS pump.
- Shutdown the lB CS pump following an inability to establish a discharge flowpath.
Examinee:
Overall JPM Performance: Satisfactory 1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 2/1/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM SIMULATOR JPM D. Page 2 of 8 (Guide pages = 7)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-220 for JPM D Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
- a. EEP-Opg8&9
- b. EEP-O attachment 5 Setup
- BASE IC-073 Run quick setup BAT file 201 2nrcexamjpmd.txt BAT file contains folIowin required presets:
- malf/MAL-RCS2C (TRUE)
Inserts malfunction to prevent Auto CS actuation cmFmalf/Imf cBK882OA_d_cc5 open cMFmalf/ imf cBKPO1A_dcc5 open cmfmalf/ imf cBKPO lBdcc5 open Fails closed MOV-8820B.
cmFmalf/ imfrbk882OBO-m 0 Trigger setup:
trgset I NBKPOlB==l trg 1 dmfcBKPOlB_d_cc5 FRZ after I-2 minutes.
SNP 220 [tm]
CONDITIONS When I tell you to begin, you are to Start Containment Spray in accordance with EEP-O.O step 6 RNO actions.
The conditions under which this task is to be performed are:
- a. EEP-O.O, Reactor Trip or Safety Injection, is in progress.
- b. Containment Pressure is 33 psig.
- c. A second operator will VERIFY proper operation of PRF using SOP-60.O.
- d. You are to complete EEP-O.O, step 6 RNO actions.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE: UPON recognizing that CTMT Spray has NOT actuated, the examinee may START the CS pumps and OPEN the discharge valves without first checking MLB-3 status using the guidance of SOP-O.8 section 4.2.8.2. If this is done, Element 3 conditions will be different.
(RNO step 6.1)
[1 MLB-3 1-1 lit
[] MLB-3 6-1 lit (RNO step 6.2)
- 2. Stop all RCPs. S / U E POSITIONS the following COIJNTER-CLOCKWISE to STOP
[]RCP IA -GRN light LIT
[]RCP lB -GRN light LIT
[]RCP 1C -GRN light LIT
FNP ILT-35 JPM SIMULATOR JPM D. Page 4 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(RNO step 6.3)
- 3. Verify PHASE B CTMT ISO alignment. CHECKS all MLB-3 lights lit: S/U 6.3.1 Check all MLB-3 lights lit. The following lights will NOT be lit:
6.3.2 jf any MLB-3 light NOT lit, THEN []CS 1A PUMP ON verify PHASE B CTMT ISO using []CS RM CLR l ON
[]8820A OPEN ATTACHMENT 5, PHASE B
[]CS lB PUMP ON CONTAINMENT ISOLATION. []CS RM CLR lB ON
[]8820B OPEN
--the following MA V/MA YNOT be LIT
[1 3361B OPEN
[1 3361A OPEN NOTE:
- ONLY A Train Containment Spray alignment is CRITICAL for Element 4
- MOV-8820B will NOT OPEN when demanded in the following element.
- Since MOV-8820B will not open, the candidate may choose to NOT start the associated lB CS pump. This is acceptable and shows that the operator is thinking about his actions and the plant response. If the lB CS Pump is started here, it will have to be secured at Element 8.
- The CS Pump Room Coolers will automatically start when the pump is started. ALSO, MOV-336 lA/B will automatically open during the PRF manipulations required by the Second Operator. Manually opening these dampers is acceptable, but not required.
(ATTACHMENT 5, step 1)
- 4. Check all MLB-3 lights lit. El POSITIONS the following S/U components hand switches in (ATTACHMENT 5, RNO step 1) the CLOCKWISE direction.
VERIFY associated component status. [ I CS l PUMP- RED light LIT
- [ 8820A OPEN- RED light LIT The following lights will NOT be lit:
- [ Cs 1A PUMP ON I
[]CSRMCLR 1AON (This valve will not open when
[I 8820A OPEN demanded)
[]336lA OPEN []8820B OPEN- GRN light LIT
[]CS IBPUMPON
[jCSRMCLR IBON (The candidate may choose to NQI
[]8820B OPEN start this pump since its associated
[]3361B OPEN discharge valve, 8820B, did not open.)
[]CS lB PUMP ON- RED light LIT CHECKS the following:
[]3361A OPEN- RED light LIT
[]3361B OPEN- RED light LIT
[1 CS RM CLR 1A ON- RED light LIT
[1 CS RM CLR lB ON- RED light LIT
FNP ILT-35 JPM SIMULATOR JPM D. Page 5 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ATTACHMENT 5 step 2)
- 5. Verify proper PRF system operation using FNP- D Per INSTRUCTIONS this step S / U 1-SOP-60.O, PENETRATION ROOM is to be performed by another FILTRATION SYSTEM. operator.
IF NEEDED, CUE: A second operator will VERIFY proper operation of PRF using SOP-60.O.
(ATTACHMENT 5 step 3)
- 6. Notify control room of phase B containment REPORTS to SS: S / U isolation status. o MOV-8820B will NOT OPEN, and o CS had to be manually actuated.
IF NEEDED, CUE: SS acknowledges.
(RNO step 6.4)
- 7. Check containment Spray. S / U (RNO step 6.4.1) CHECKS CS FLOW Check containment spray flow in both trains [1 Fl 958A> 2.7 x 1 O GPM greater than 0 gpm. []FI 958B 0 GPM (RNO step 6.4.2) El CHECKS RWST TO 1A IF containment spray flow in both trains NOT (1B) CS PUMP-OPEN greater than 0 gpm, THEN verify containment {]MOV-88 1 7A-RED light LIT spray pump suction valves open. []MOV-8817B-RED light LIT NOTE: If the lB CS Pump was NOT started at Element 4, Elements 8 and 9 are N/A.
(RNO step 6.4.3)
- 8. IF unable to establish spray flow in a train, El RESETS the B Train CS S / U THEN secure containment spray pump in Signal-DEPRESS the CS affected train. RESET B TRN pushbutton CS RESET TRN A(B) containment spray El CHECKS Annunciator EE4-signals RESET NOT CLEAR (Annunciator EE4 clear).
NOTE: Alarm will NOT clear unless BOTH TRAINS reset.
FNP ILT-35 JPM SIMULATOR JPM D. Page 6 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(RNO step 6.4.3 continued)
- 9. CTMT SPRAY PUMP 1A(B) -STOPPED in POSITIONS pump lB hand S / U affected train switch in the COUNTER Clockwise direction.
[]IB Cs PUMP- GRN light LIT STOP TIME I Terminate when completion of the step has been reported to the SS.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-EEP-O.O, v43.O
- 2. K/As: 026A2.03 RO-4.1 SRO-4.4 026A2.04 RO-3.9 SRO-4.2 GENERAL TOOLS AND EOUIPMENT:
Provide/Acquire:
- 1. All procedures will be acquired from the simulator.
FNP ILT-35 JPM SIMULATOR JPM D. Page 7 of 8 (Guide pages = 7)
Critical ELEMENT justification:
STEP Evaluation 1 Not cntical check step only 2 CRITICAL- Failure to stop the RCPs will cause irreversible Motor bearing damage within minutes following a Phase B actuation. These pumps are necessary to preserve, if possible, to facilitate Accident mitigation strategies.
3 Not critical check step only 4 CRITICAL- STARTING the A Train CS is the task objective and necessary for protecting CNMT integrity.
STARTING the B TRAIN CS may or may not occur due to the malfunction on MOV 8820B. This action is NOT critical.
Starting /Realigning other components will occur automatically given sufficient time, or are not required (lB CS Room cooler) due to the failure.
5 Not entical Initial conditions dismiss this activity to another operator, further the system will be operating correctly, with both trains in service. Shutdown of One train is NOT the targeted action of this JPM.
6 Not critical NOTIFICATION step only 7 Not criticalstep is a check step 8-9 Not critical stopping the lB CS pump While this is important to protect the lB CS Pump, if started, and procedurally is required to be accomplished, this does not affect the successful completion of the task, which is to get 1 CS pump running and aligned to the CS header with a suction from the RWST.
COMMENTS:
Failures that could be added-(IC-183) if more critical steps are necessary.
Irnf ccc3046_d_cc7 open Imf ccc3 1 82_d_cc7 open Imf ccc3052_d_cc7 open
FNP ILT-35 JPM SIMULATOR JPM D. HANDOUT Pg 1 of I CONDITIONS When I tell you to begin, you are to Start Containment Spray in accordance with EEP-O.O step 6 RNO actions.
The conditions under which this task is to be performed are:
- a. EEP-O.O, Reactor Trip or Safety Injection, is in progress.
- b. Containment Pressure is 33 psig.
- c. A second operator will VERIFY proper operation of PRF using SOP-60.O.
- d. You are to complete EEP-O.O, step 6 RNO actions.
FNP-1-EEP-O I REACTOR TRIP OR SAFETY INJECTION I Revision 43 Step Action/Expected Response Response NOT Obtained I
5 Verify actuation signal automatic actions using ATTACHMENT 2. AUTOMATIC ACTIONS VERIFICATION.
NOTE: Step 6 is a continuing action step while in this procedure.
6 [CA] Check containment pressure 6 Perform the following.
- HAS REMAINED LESS THAN 27 psig. 6.1 Verify PHASE B CTMT ISO -
ACTUATED.
CTMT PRESS
[1 PR 950 [1 MLB-3 1-1 lit
[] MLB-3 6-1 lit 6.2 Stop all RCPs.
[1 1A
[1 lB
[] lC 6.3 Verify PHASE B CTMT ISO alignment.
6.3.1 Check All MLB-3 lights lit.
6.3.2 any MLB-3 light lit, THEN verify PHASE B CTMT ISO using ATTACHMENT 5, PHASE B CONTAINMENT ISOLATION.
Step 6 continued on next page.
Page 8 of 35
FNP-1-EEP-O REACTOR TRIP OR SAFETY INJECTION Revision 43 Step Action/Expected Response Response NOT Obtained I I I 6.4 Check containment spray.
6.4.1 Check containment spray flow in both trains greater than 0 gpm.
[1 Fl 958B 6.4.2 IF containment spray flow in both trains greater than 0 gpm, THEN verify containment spray pump suction valves open.
[1 O1E13MOV8817A
[] Q1E13MOV8817B 6.4.3 IF unable to establish spray flow in a train, THEN secure containment spray pump in affected train.
[1 CS RESET TRN A(B) containment spray signals - RESET (Annunciator EE4 clear)
Ii CTMT SPRAY PUMP 1A(B) -
STOPPED in affected train 7 Announce Unit 1 reactor trip and safety injection.
Page 9 of 35
FNP-l-EEP-O REACTOR TRIP OR SAFETY INJECTION Revision 43 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 5 PHASE B CONTAINMENT ISOLATION NOTE:
- ATTACHMENT 5, FIGURE 1 provides a listing of component names corresponding to each MLB-3 location.
. ATTACHMENT 10 provides a listing of sequenced loads.
- Position of dampers 336lA (B) is dependent on penetration room pressure/inleakage, and may not be open in all cases.
. IF PRF has been aligned in the post-LOCA mode per FNP-l-SOP-6O.O, PENETRATION ROOM FILTRATION SYSTEM, THEN only one train of equipment may be in operation.
1 Check all the following NLB3 1 Verify associated component indicating lights lit. status.
I 2 3 4 5 6 7 B 9 10 CS MP PENS RM Cs PMP PENS RM CTMT ISO 3052 CTMT ISO 3046 1 IA EXH FAN 18 EXH FAN PHASE B CLOSED PHASE 8 CLOSED ON IAON ON lEON 3611 CSRM 3045 PENERM CSRM PENS RN 2 CtR IA RECIRO FAN 2226 3184 CLOSED CISE{) CLR 18 RECIRC FAN ON IA ON CLOSED CLOSED ON lEON
. 8820A 3182 3381A 88208 33618 OPEN CLOSED OPEN OPEN OPEN 3382A 33628 OPEN OPEN 2 Verify proper PRF system operation using FNP-1-SOP-60.O.
PENETRATION ROOM FILTRATION SYSTEM.
3 Notify control room of phase B containment isolation status.
-END-Page 1 of 3
FNP-1-EEP-O REACTOR TRIP OR SAFETY INJECTION Revision 43 ATTACHMENT 5 FIGURE 1 LOCATION COMPONENT NUMBER NAME 1-1 N/A CTMT ISO PHASE B - ACTUATED 1-2 Q1P19HV3611 IA TO CTMT (BOP) - CLOSED 1-3 N/A SPARE 1-4 N/A SPARE 2-1 Q1E13POO1A 1A CS PUMP - ON 2-2 Q1E16MOO2A 1A CS PUMP RM CLR FAN (BOP) - ON 2-3 Q1E13MOV882OA 1A CS PUMP TO SPRAY HDR ISO - OPEN 2-4 N/A SPARE 3-1 Q1P17MOV3O52 CCW TO RCP CLRS - CLOSED 3-2 01P17HV3045 CCW FROM RCP THRM BARR - CLOSED 3-3 01P17M0V3182 CCW FROM RCP OIL CLRS - CLOSED 3-4 N/A SPARE 4-1 Q1E15MOO1A 1A PRF EXH FAN - ON 4-2 Q1E15MOO2A 1A PRF RECIRC FAN - ON 4-3 01E15M0V3361A 1A PRF RECIRC FAN RECIRC DMPR - OPEN 4 4 Q1E15M0V3362A 1A PRF SUCTION DMPR - OPEN 5-1 N/A SPARE 5-2 N/A SPARE 5-3 N/A SPARE 5-4 N/A SPARE 6-1 N/A CTMT ISO PHASE B - ACTUATED 6-2 01P19HV2228 PORV BKUP AIR SUPPLY (PRIP) - CLOSED 6-3 N/A SPARE 6-4 N/A SPARE Page 2 of 3
FNP-1-EEP-O REACTOR TRIP OR SAFETY INJECTION RevIsion 43 ATTACHMENT 5 FIGURE 1 LOCATION COMPONENT NUMBER NAME 7-1 Q1E13POO1B lB CS PUMP ON 7-2 Q1E16MOO2B lB CS PUMP RM CLR FAN (BOP) - ON 7-3 01E13M0V8820B lB CS PUMP TO SPRAY HDR ISO - OPEN 7-4 N/A SPARE 8-1 O1P17MOV3O46 CCW FROM RCP OIL CLRS - CLOSED 8-2 01P17HV3184 CCW FROM RCP THRM BARR - CLOSED 8-3 N/A SPARE 8-4 N/A SPARE 9-1 Q1E15MOO1B lB PRF EXH FAN - ON 9-2 Q1E15MOO2B lB PRF RECIRC FAN - ON 9-3 Q1E15MOV3361B lB PRF RECIRC FAN RECIRC DMPR - OPEN 9-4 O1E1SMOV3362B lB PRF SUCTION DMPR - OPEN 10-1 N/A SPARE 10-2 N/A SPARE 10-3 N/A SPARE 10-4 N/A SPARE Page 3 of 3
FNP ILT35 JPM Page 1 of 7 SIMULATOR JPM E.
CR0258 (MODIFIED)
TITLE: Start the lB DG and energize the 1G 4160V Bus using ECP-O.O step 5.2.2 RNO.
EVALUATION LOCATION: ll SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 5 MIN SIMULATOR IC NUMBER: IC-221 I1 ALTERNATE PATH TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee will be obtain all references from the simulator.
- 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 JPM, the examinee will:
- StartthelBDG.
- Close the output breaker, DGO8-1.
Examinee:
Overall JPM Performance: Satisfactory tJ Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: working LNRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM SIMULATOR JPM E. Page 2 of 7 (Guide pages = 6)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-221 for JPM E Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
- a. ECP-O.O step 5.2
- b. RETURN keys to their storage location.
Setup
- BASE IC-0142 Run quick setup BAT file 20 I2nrcexamjpme.txt BAT file contains following required presets:
TAGOUT 2C DG: RACKOUT DJO6-i & DJ-02 & Place MODE selector Switch to MODE 3 irf cBK1DJ06_d_cd2 open irf cBK2DJO6_d_cd2 open set X431006B1 Blocks Auto start of the lB DG & prevent autoclosure of DG-08 imf MAL-DSGO 17 IMF cBKlDGO8dcc8 open INSERTS Loss of All AC (c1eraded prid 50%) & l-2A PG trip after 30 sec.
imfMAL-EPS4A (0 30)
IMF MAL-EPSI 50 Isolate letdown by closing HV-8149A & HV-8149C FRZ after 4-2 minutes.
SNP 221 [tm]
FNP ILT-35 JPM SIMULATOR JPM E. Page 3 of 7 (Guide pages = 6)
CONDITIONS When I tell you to begin, you are to Start the lB DG and energize the 1G 4160V Bus using ECP-O.O step 5.2.2 RNO.
The conditions under which this task is to be performed are:
- a. ECP-O.O, Loss of All AC Power, is in progress.
- b. The 2C DG is Tagged Out.
- c. The 1 -2A DG has tripped on an electrical fault.
- d. The I B DG has failed to start.
- e. All actions preceding step 5.2.2 RNO, including the load shed verification, have been completed.
- f. You are to start the lB DG in MODE 2 and energize the IG 4160V Bus per ECP-O.O beginning at step 5.2.2 RNO.
INITIATiNG CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE: There is a Caution in the procedure that states the DG will overheat if SW flow is not aligned to the DG within 3 minutes of start. This time frame is based on DG load when it is running without SW.
When the DG is lightly loaded, that time may be extended. On the simulator, the DG may trip in about 4 minutes when unloaded.
[ CRITICAL IF the DG trips, THEN FAILURE criteria has been exceeded.
CAUTION: A running diesel generator will overheat if adequate SW flow is not provided within 3 (step 5.2) minutes. Steps 5.3 through 5.7 must be performed immediately to verify adequate SW flow once a diesel generator has been started.
(RNO step 5.2.2.1)
- 1. Start diesel generator from EPB in Mode 2 Obtains a KEY S / U using START pushbutton. INSERT the KEY and ROTATE the 2B DG MODE SELECTOR Switch-CLOCKWISE to the MODE 2 position.
D DEPRESS the 2B DG START pushbutton.
FNP ILT-35 JPM SIMULATOR JPM E. Page 4 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 5.3)
- 2. Check l-2A, 1C or lB diesel generator El CHECKS 2B DG output: S/U output.
(step 5.3.1)
Verify diesel generator frequency 58-62 Hz.
[]Frequency 59.7 HZ (step 5.3.2)
Verify diesel generator voltage 4.0-4.3 kV.
[j Voltage -4.2 kV.
(step 5.4)
Running DG 1-2A lB 1C []DG-08 - NOT CLOSED.
BKR DFO8 DGOS DHO7 (RNO step 5.4)
- 4. Close diesel generator output breaker. S/U (RNO step 5.4.1)
Place mode selector switch in MODE 2. CHECK mode selector remained in MODE 2 (RNO step 5.4.2) El POSITIONS SYNCH Place SYNCH SWITCH in MAN. SWITCH for DGO8-l CLOCKWISE to MAN position.
(RNO step 5.4.3) El POSITIONS SWITCH for WHEN load shed verified, THEN close DGO8-l CLOCKWISE DGO8-1 AND proceed to step 5.5.
FNP ILT-35 JPM SIMULATOR JPM E. Page 5 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 5.5)
- 5. IF 1 F 4160 V bus energized, THEN proceed CHECK 1F4160V Power S/U to step 5.7. available lights NOT LIT (RNO step 5.5)
IF IC diesel generator running for UNIT 1, Checks IC DG aligned to THEN perform the following, IF NOT, UNIT 2. Proceeds to step 5.6 proceed to step 5.6.
(step 5.6)
- 6. Check IG 4160 V bus energized. CHECK lG4l6OVPower S / U available lights LIT (step 5.7)
- 7. Verify adequate SW flow. CHECK B Train SW pumps S/U (RNO step 5.7.1) [1 1D SW pump RED light Verify two SW PUMPS in energized train LIT RUNNING [liE SW pumpRED light
{] A Train (1A, 1B, or 1C) LIT
[]B Train (ID, IE, or 1C)
(RNO step 5.7.2)
IF A train energized, THEN verify SW This step is N/A TO/FROM DG BLDG A HDR -
Q1P16V519/537 open.
(RNO step 5.7.2)
LI CHECK B Train SW supply IF B train energized, THEN verify SW and discharge from DG bldg.
Q1P16V518/536 open. [1 MOV-518/536 RED light LIT STOP TIME Terminate when 1 B 41 60V bus has been reported as energized from the 1 B DG. Element 7 is the natural termination point for this 1PM.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP ILT-35 JPM SIMULATOR JPM E. Page 6 of 7 (Guide pages = 6)
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-l-ECP-0.0, Version 25.0
- 2. KIAs: 064A3.06 RO-3.3 SRO-3.4 064A4.06 RO-3.9 SRO-3.9 EPEO55EA1.06 RO-4.I SRO-4.5 EPEO55EA2.03 RO-3.9 SRO-4.7 GENERAL TOOLS AND EOUIPMENT:
Provide/Acquire:
I. All procedures will be acquired from the simulator.
Critical ELEMENT justification:
STEP Evaluation I CRITICAL- TASK objective 2 Not cntical check step only 3 Not cntical check step only 4 CRITICAL- TASK OBJECTIVE:
Failure to complete this element (or manually stopping the DG) before the lB DG automatically trips is FAILURE criteria.
Since this will result in damaging the only available power source to UNIT I.
Not cntical the B1G sequencer will automatically opelate to restoie SW cooling NO throu g h action required. These steps are for the natural termination of the task.
COMMENTS:
FNP ILT-35 JPM SIMULATOR JPM E. HANDOUT Pglofl CONDITIONS When I tell you to begin, you are to Start the lB DG and energize the 1G 4160V Bus using ECP-O.O step 5.2.2 RNO.
The conditions under which this task is to be performed are:
- a. ECP-O.O, Loss of All AC Power, is in progress.
- b. The 2C DG is Tagged Out.
- c. The 1 -2A DG has tripped on an electrical fault.
- d. The lB DG has failed to start.
- e. All actions preceding step 5.2.2 RNO, including the load shed verification, have been completed.
- f. You are to start the lB DG in MODE 2 and energize the 1G 4160V Bus per ECP-O.O beginning at step 5.2.2 RNO.
FNP-1-ECP-O.0 2-22-2012 Revision 25 PARLEY NUCLEAR PLANT EMERGENCY CONTINGENCY PROCEDURE FNP-1-ECP-0. 0 LOSS OF ALL AC POWER S
A F
PROCEDURE USAGE REQUIREMENTS per NMP-AP-003 SECTIONS E T
Continuous Use Remainder of Y Procedure Reference Use Steps 1-2 R E
Information Use L A
T E
D Approved:
Operations Manager Date Issued:
FNP-1ECP-O.O LOSS OF ALL AC POWER Revision 25 Table of Contents Procedure Contains Number of Pages Body 44 Attachment 1 1 Attachment 2 3 Attachment 3 2 Attachment 4 5 Attachment 5 4 Attachment 6 1 Page 1 of 1
FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 25 A. Purpose This procedure provides actions to respond to a loss of all AC power.
B. Symptoms or Entry Conditions I. This procedure is entered when all AC power has been lost; from the following:
- a. Operator determination that both trains of 4160 V emergency busses (A Train: iF and 1K, B Train: 10 and lL) are deenergized.
- b. FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION, step 3, on the indication that all AC emergency busses are deenergized.
Page 1 of 45
FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- This procedure is applicable in modes 1 thru 4 only.
FNP-l-AOP-5.O. LOSS OF A OR B TRAIN ELECTRICAL POWER, is applicable for all other plant modes.
- Steps 1 and 2 are IMMEDIATE ACTION steps.
- Critical safety function status trees should be monitored for information only. No function restoration or other procedure should be implemented during a loss of all AC power.
- The Plant Emergency Alarm cannot be activated until AC power is restored.
Check reactor trip. 1 Perform the following.
[J Reactor trip and bypass 1.1 Manually trip reactor.
breakers - OPEN
[1 Nuclear power - FALLING 1.2 IF reactor can NQI be tripped, THEN trip both MG set supply breakers.
[1 N1C11EOO5A
[] N1C11EOO5B 2 Check turbine trip. 2 Perform the following.
[1 TSLB2 14-1 lit 2.1 Place main turbine emergency
[1 TSLB2 14-2 lit trip switch to TRIP for at
[j TSLB2 14-3 lit least 5 seconds.
[1 TSLB2 14-4 lit 2.2 IF turbine can NOT be tripped.
THEN reduce GV position demand signal to zero from DEll panel.
[1 TURBINE MANUAL depressed
[1 GV CLOSE depressed H FAST ACTION depressed 2.3 IF steam flow to main turbine is NOT secured, THEN close all main steam line isolation and bypass valves.
Page 2 of 45
FNP-l-ECP-0,O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE: Load shed verification per Step 5.1 may be performed concurrently with Steps 3 and 4 if resources permit.
3 Verify RCS isolated.
3.1 Verify normal letdown 3.1 Perform the following.
isolated.
a) Locally close letdown 3.1.1 Verify all letdown line line penetration room orifice isolation valves isolation valves. (121 CLOSED. ft. ATJX BLDG rad side at PRIP)
LTDN ORIF ISO 45 GPM LTDN LINE
[1 Q1E21HV8149A PENE RN ISO
[] Q1E21HV8175A LTDN ORIF ISO [] Q1E21HV8175B 60 GPM
[1 Q1E21HV8149B OR
[] Q1E21HV8149C b) Locally close LTDN REHT OR HX TCV inlet iso and REHEAT HX BYPASS TCV 3.1.2 Verify letdown line BYPASS. (100 ft. AUX BLDG isolation valves - CLOSED, storage room across from lB Charging pump room)
LTD LINE ISO El 01E21V145
[1 01E21LCV459 El Q1E21V348
[1 Q1E21LCV46O 3.2 WHEN RCS pressure less than 2335 psig, THEN verify both PRZR PORVs closed.
3.3 Verify excess letdown line -
ISOLATED, EXC LTDN ISO VLV El 01E21HV8153 closed
[I 01E21HV8154 closed Step 3 continued on next page.
Page 3 of 45
FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained r I I 3.4 Verify all reactor vessel head vent valves - CLOSED.
RX VESSEL HEAD VENT OUTER ISO
[1 Q1B13SV2213A
[1 01B13SV2213B RX VESSEL HEAD VENT INNER ISO
[1 Q1B13SV2214A
[I 01B13SV2214B CAUTION: The TDAFWP will become unreliable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a loss of all AC power, unless power is restored. This will occur due to a loss of air to the steam supply valves and a loss of control power from the UPS.
4 Verify total AFW flow GREATER 4 Verify proper AFW alignment.
THAN 395 gpm.
4.1 Verify TDAFWP running.
AFW FLOW TO 1A(1B,1C) SC TDAFWP STM SUPP
[I Fl 3229A FROM 1B(1C) SC El Fl 3229B [I MLB-4 1-3 lit El Fl 3229C [1 MLB-4 2-3 lit
[I MLB-4 3-3 lit AFW TOTAL FLOW TDAFWP SPEED
[] Fl 3229 El SI 3411A > 3900 rpm TDAFWP SPEED CONT El SIC 3405 adjusted to 100%
4.2 TDAFWP running, THEN locally verify TDAFWP TRIP THROTTLE VLV 01N12M0V34O6 open. (100 ft, AUX BLDG TDAFWP room)
Step 4 continued on next page.
Page 4 of 45
FNP-1-ECP-0.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I 4.3 Verify AFW flow path to each SO.
TDAFWP FCV 3228
[1 RESET reset TDAFWP TO 1A(1B,1C) SO
[] Q1N23HV3228A in MOD El Q1N23HV3228B in MOD El 01N23HV3228C in MOD TDAFWP TO 1A(1B,1C) SG FLOW CONT El HIC 3228AA open El HIC 3228BA open El HIC 3228CA open CAUTION: LE power is not restored to the 125 V DC battery chargers on each train within 30 minutes, THEN there may not be enough DC capacity to start a DO and sequence needed loads.
5 [CA] Restore power to any emergency bus.
5.1 Verify supply breakers for major loads on emergency 4160 V busses - OPEN.
El BKR DFO1 (1A S/U XFMR TO iF 4160 V BUS)
El BKR DF1S (lB S/U XFMR TO iF 4160 V BUS)
El BKR DF-13-1 (iF 4160 V BUS TIE TO 1H 4160 V BUS)
El BKR DGO1 (1A S/U XFMR TO 10 4160 V BUS)
El BKR DG15 (lB S/U XFMR TO 10 4160 V BUS El 1C CCW PUMP BKR DF-04-1 El lB CCW PUMP BKR DF-05-l El lB CCW PUMP BKR DO-OS-i El 1A CCW PUMP BKR DG-04-1 Step 5 continued on next page.
Page 5 of 45
FNP-i-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I
[1 1A SW PUMP BKR DK-03-1
[1 lB SW PUMP BKR DK-04-i
[] 1C SW PUMP BKR DK-05-1
[] 1C SW PUMP BKR DL-05-l
[] 1D SW PUMP BKR DL-03-i
[1 1E SW PUMP BKR DL-04-i
[] #4 RW PUMP BKR DJ-03-i
[] #5 RW PUMP BKR DJ-04-i
[1 #8 RW PUMP BKR DH-03-i
[1 #9 RW PUMP BKR DH-04-i
[1 #10 RW PUMP BKR DH-05-l
[1 lB CRDM CLG FAN BKR ED-li-i
[] lA CRDM CLG FAN BKR EE-13-i
[] 1A CS PUMP BKR DF-li-l
[] lB CS PUMP BKR DG-il-i
[] iA RHR PUMP BKR DF-09-i
[1 lB RHR PUMP BKR DG-O9-i
[1 1A CHG PUMP BKR DF-06-b
[] lB CHG PUMP A TRN BKR DF-07-b
[1 lB CHG PUMP B TRN BKR 00-07-b
[1 1C CEO PUMP BKR DG-06-b
[1 1A MDAFWP BKR DF-i0-i
[1 lB MDAFWP BKR DO-b-i Step 5 continued on next page.
Page 6 of 45
FNP-1-ECp--O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I CAUTION: A running diesel generator will overheat if adequate SW flow is not provided within 3 minutes. Steps 5.3 through 5.7 must be performed immediately to verify adequate SW flow once a diesel generator has been started.
NOTE: Load shed of bus loads must be completed prior to closing the output breaker for any diesel generator.
5.2 Check 1-2A. 1C or lB diesel 5.2 Perform the following:
generator running for Unit 1.
5.2.1 Perform 2C DG SBO start as
- Check DIESEL SPEED follows.
indication - GREATER THAN o rpm. 5.2.1.1 Verify 2C DG MODE SELECTOR switch in MODE 1.
- Check FREQUENCY METER 5.2.1.2 Place 2C DG UNIT indication - GREATER THAN SELECTOR switch in UNIT 58 Hz. 1.
OR 5.2.1.3 WHEN load shed verified, THEN depress 2C DG
- Check DIESEL AT SYN SPEED DIESEL START pushbutton.
light - LIT.
5.2.1.4 Verify 2C DG starts.
Step 5 continued on next page.
Page 7 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I NOTE: The LOSP sequencer should run when output breaker closes, if no SI signal is present. If an SI signal is present, neither sequencer will run and SI loads must be started manually.
5.2.1.5 Check Unit 1 2C DO output breaker DJO6 closes.
5.2.1.6 Verify breaker DG13 closed. (1G 4160 V bus tie to 1J 4160 V BUS) 5.2.1.7 Verify breaker D002 closed. (10 4160 V bus tie to 1L 4160 V bus) 5.2.1.8 IF 10 4160V bus energized, THEN proceed to step 5.7.
Step 5 continued on next page.
Page 8 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE:
- Starting 1-2A or lB diesel generator should be attempted first.
Any attempted start of a diesel generator which has automatically tripped should be performed locally in Mode 4.
5.2.2 IF unable to start 2C diesel generator AND energize 1G 4160V bus, THEN start any diesel generator.
5.2.2.1 Start diesel generator from EPB in Mode 2 using START pushbutton.
OR 5.2.2.2 Direct diesel operator to start diesel generator in MODE 4 using FNP-O-SOP-38.1, EMERGENCY STARTING OF A DIESEL GENERATOR.
OR 5.2.2.3 Direct diesel operator to perform a manual emergency start of 1-2A or lB diesel generator using FNP-O-SOP-38.l, EMERGENCY STARTING OF A DIESEL GENERATOR.
OR 5.2.2.4 jj attempts to start a diesel generator fail, THEN proceed to step 5.9.
Step 5 continued on next page.
Page 9 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I NOTE: Diesel generator and diesel generator output breaker must be controlled locally (DG BLDG) while diesel generator is in MODE 4.
5.3 Check 1-2A, 1C or lB diesel 5.3 Restore diesel generator generator output. field.
5.3.1 Verify diesel generator a) Locally reset exciter. (DG frequency 58-62 Hz. BLDG at local control panel) 5.3.2 Verify diesel generator voltage - 4.0-4.3 kV. b) IE diesel generator frequency indicates 58-62 Hz AND diesel generator voltage indicates 4.0-4.3 kV, THEN proceed to step 5.4, IF NOT, verify diesel generator DC control power breakers closed. (121 ft.
AUX BLDG battery charger rooms)
Running DG 1-2A 1C lB 2C Battery Supply [1 BKR LAO5 [] BKR LAOS [1 BKR LB18 [1 BKR LB18 DG Control [] BKR LA17 [1 BKR LAO6 [1 BKR LB19 [1 BKR LB11 Panel Supply c) IF unable to restore excitation to diesel generator, THEN secure the diesel generator using ATTACHMENT 1, SHUTDOWN OF A DIESEL GENERATOR AND proceed to step 5.6.
Step 5 continued on next page.
Page 10 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I 5.4 Check l-2A, 1C or lB diesel 5.4 Close diesel generator output generator output breaker breaker.
closed.
5.4.1 Place mode selector switch in MODE 2.
Running DO l-2A lB 1C BKR [1 DFO8 [] DGO8 [] DHO7 5.4.2 Place SYNCH SWITCH in MAN.
5.4.3 WHEN load shed verified, THEN close running diesel generator output breaker proceed to step 5.5.
Running DG 1-2A lB 1C BKR [1 DFO8 [1 DGO8 [1 DHO7 5.4.4 running diesel generator output breaker can NOT be closed Ij diesel generator is supplying Unit 2, THEN secure the diesel generator using ATTACHMENT 1, SHUTDOWN OF A DIESEL GENERATOR AND proceed to step 5.6.
Step 5 continued on next page.
Page 11 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I 5.5 IF iF 4160 V bus energized, 5.5 IE 1C diesel generator running THEN proceed to step 5.7. for Unit 1, THEN perform the following, IF NOT, proceed to step 5.6.
5.5.1 IF SI signal present, THEN reset SI.
[1 MLB1 1-1 not lit
[1 MLB-1 11-1 not lit 5.5.2 IF SI signal was present, THEN reset B1F sequencer.
(139 ft. AUX BLDG A train SWGR room) 5.5.3 Place BKR DF13 SYNCH SWITCH in MAN.
NOTE: The LOSP sequencer may run when breaker is closed.
5.5.4 WHEN load shed verified, THEN close BKR DF13 (iF 4160 V bus tie to 1H 4160 V bus).
5.5.5 Verify BKR DFO2 closed.
(iF 4160 V bus tie to 1K 4160 V bus) 5.5.6 Monitor 1C diesel generator load, voltage and frequency.
5.5.7 IF iF 4160 V bus energized, THEN proceed to step 5.7.
Step 5 continued on next page.
Page 12 of 45
FNPl-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I 5.6 Check 1G 4160 V bus - 5.6 IF 2C DG available for SBO ENERGIZED. start, THEN perform 2C DO SBO start as follows, IF NOT, proceed to step 5.8 5.6.1 Verify 2C DO MODE SELECTOR SWITCH in MODE 1.
5.6.2 Place 2C DO UNIT SELECTOR SWITCH in UNIT 1.
5.6.3 WHEN load shed verified, THEN depress 2C DO DIESEL START pushbutton.
5.6.4 Verify 2C DG starts.
NOTE: The LOSP sequencer should run when output breaker closes, if no SI signal is present. If an SI signal is present, neither sequencer will run and SI loads must be started manually.
5.6.5 Check UNIT 1 2C DO output BKR DJO6 closes.
5.6.6 Verify BKR D013 closed.
(10 4160 V bus tie to 1J 4160 V bus) 5.6.7 Verify breaker D002 closed.
(10 4160 V bus tie to 1L 4160 V bus) 5.6.8 Monitor 2C diesel generator load, voltage and frequency.
Step 5 continued on next page.
Page 13 of 45
FNP-1-ECp-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I
5.7 Verify adequate SW flow.
5.7.1 Verify two SW PUMPS in energized train - RUNNING.
[] A Train (1A, lB or 1C)
[] B Train (lD, 1E or 1C) 5.7.2 IF A train energized, THEN verify SW TO/FROM DG BLDG - A HDR Q1P16V519/537 open.
5.7.3 IF B train energized.
THEN verify SW TO/FROM DG BLDG - B HDR Q1P16V518/536 open.
Step 5 continued on next page.
Page 14 of 45
FNP-1ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I 5.7.4 Check no running diesel 5.7.4 Isolate non essential SW.
generator lube oil temperature annunciator in 5.7.4.1 Close the following SW alarm. (155 ft. DG BLDG valves.
local control panel)
[1 01P16V515
[1 01P16V516 SW TO TURB BLDG ISO B TRN
[1 Q1P16V517
[1 01P16V514 SW FROM TURB BLDG A HDR ISO
[1 Q1P16V54O
[1 01P16V542 SW FROM TURB BLDG B HDR ISO
[1 Q1P16V543
[] 01P16V541 SW TO RCP MTR AIR CLRS
& BTRS CHLR
[] 01P16MOV3149 5.7.4.2 IF diesel generator lube oil temperature still in alarm, THEN evaluate stopping affected diesel generator.
Step 5 continued on next page.
Page 15 of 45
FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 25 Step Action/Expected Response Response NOT Obtained I I I CAUTION: j both Unit 1 and Unit 2 B Train 4160 V busses become de-energized, THEN one attempt per unit should be made to restore power to at least one units B Train 4160 V bus by starting DC lB or 2B.
AND j power cannot be restored using either lB or 2B DGs, THEN the SBO DC should be immediately aligned and started to provide power to one units B Train 4160 V bus.
5.8 IF lF OR lG 4160 V bus 5.8 Continue efforts to start at energized, least one diesel generator.
THEN go to procedure and step in effect and implement function restoration procedures as necessary.
Step 5 continued on next page.
Page 16 of 45
FNPILT-35JPM JPMSIMULATORJPMF. HANDOUT I Pg 1 of2 SIMULATOR 3PM F.
CRO-127A TITLE: Perform actions of AOP-100 for a NI-42 failure.
EVALUATION LOCATION: I SIMULATOR D CONTROL ROOM D CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-222 LI ALTERNATE PATH LI TIME CRITICAL LI PRA 3PM DIRECTIONS:
- 1. Examinee will be provided AOP- 100, Instrumentation Malfunction. All other references of the simulator will be available at the examinees discretion.
- 2. The actions of this task are intended to be performed on an Active Simulator in which the exarninee 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:
- Perform the actions of AOP-100. NI-42 will be removed from service.
. SRO candidates will evaluate Tech Specs for Required Conditions and Actions.
Examinee:
Overall 3PM Performance: Satisfactory 11 Unsatisfactory EJ Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-222 for JPM F Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run I Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
Setup
- Run quick setup BAT file NONE FREEZE the simulator n.-...
SNP 222 [tm]
- FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 CONDITIONS When I tell you to begin, you are to Perform actions of AOP-100 for an NI-42 failure.
The conditions under which this task is to be performed are:
- a. The Plant is at 95% power with the ramp on hold for a calorimetric.
- b. N-42 upper detector current indicator has failed low.
- c. The Shift Supervisor has directed you to perform Section 1.12 of AOP- 100 starting at step 1.
- d. A pre-job brief is not required.
SRO Licensed personnel only: (to be done in the simulator OR classroom)
When I tell you to begin, you are to Evaluate and determine the current Tech Spec requirements and MOST LIMITING REQUIRED ACTION associated with the failure of N-42.
The conditions under which this task is to be performed are:
- a. The Plant is at 95% power with the ramp on hold for a calorimetric.
- b. N-42 upper detector current indicator has failed low.
- c. The required actions have been taken to stabilize the plant in accordance with FNP- I -AOP- 100.
- d. The following interlocks have been checked to be in their required state for existing unit conditions:
P-7 P-8 P-9 P-b
- e. Evaluate and determine the current Tech Spec requirements and MOST LIMITING TECH SPEC REQUIRED ACTION associated with the failure of N-42.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME HO #1:
(step 1 of AOP- 100)
- 1. Verify rod control is in manual. This step is N/A since this only S / U applies to N-44 (step 2 of AOP- 100)
- 2. STOP any load change in progress. Turbine DEH control console S / U checked and the GO light is not illuminated.
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 3 of AOP- 100)
- 3. Within one hour, check P-10 interlock in the Shift Supervisor informed to S/U required state for existing unit conditions. (TS check P-b interlock in the 3.3.1 Function 17t) required state per TS 3.3.1 Function 17t.
CUE if notification attempted:
Shift Supervisor acknowledges.
OR Li Checks BYPASS &
PERMISSIVE panel light NUCLEAR AT POWER PERMISSIVE P-b is lit.
OR Checks TSLB 3, at least 2 of 4 lights lit in column 5 for PRP1O.
FNP ILT-35 JPM JPM SIMULATOR JPM F HANDOUT I Pg 1 of2 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 4 of AOP-100)
- 4. Within one hour, check the following Shift Supervisor informed to S/U interlocks are in the required state for check P-7, P-8, P-9 interlock in existing unit conditions: (TS 3.3.1 Function the required state per TS 3.3.1 17b, c, d) P-7 P-8 P-9 Function 17b, c, d).
CUE if notification attempted:
Shift Supervisor acknowledges.
OR E Checks BYPASS &
PERMISSIVE panel lights not lit for the following:
- LOW POWER TRIP BLOCK P-7
- LOW POWER LOW FLOW TRIP BLOCK P-8
- TURB TRIP-RX TRIP BLOCK P-9 OR Checks TSLB 3, at least 2 of 4 lights lit in:
- colurnn4forPRP8
- colunrn 5 for PR PlO (feeds P-7 interlock)
- column 9 for PR P9.
(step 5 of AOP-100)
- 5. Check THERMAL POWER -
Thermal Power Checked to be S/U GREATER THAN OR EQUAL TO 75%. at 95% power.
(step 6 of AOP-IOO)
- 6. Perform FNP-l-STP.-122.O, QUADRANT Shift Supervisor notified of S/U POWER TILT MEASUREMENT WITH AN Technical Specification INOPERABLE EXCORE DETECTOR as requirements.
required by Tech Spec SR 3.2.4.2 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR Reduce power to <75% thermal CUE if notification attempted:
power within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Shift Supervisor acknowledges.
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 7 of AOP- 100)
- 7. Defeat the rod stop bypass for N-42. ROD STOP BYPASS switch S I U taken to the BYPASS PR N42 position.
FC5 PR CH DEV will clear when the comparator channel defeat switch is selected to N-42.
(step 7 of AOP-100)
- 8. Defeat the channel comparator for N-42. LI COMPARATOR CHANNEL S / U DEFEAT switch taken to the N42 position.
(step 7 of AOP-l00)
- 9. Defeat the upper and lower detector on the For the DETECTOR CURRENT S / U detector current comparator drawer for COMPARATOR:
N-42. Ei UPPER SECTION taken to the PRN42 position.
(NOTE: Annunciators FB4 and FB5 should clear LI LOWER SECTION taken to when these actions are complete.) the PRN42 position.
(step 7 of AOP-100)
- 10. Reset rate trip on the A drawer for the No action is required for this S / U affected channel. step since the RATE TRIP bistables should not have actuated.
Actions that the candidate may perform:
LI RATE MODE handswitch on the A drawer for N-42 taken to RESET and spring returns to NORMAL.
LI Checks POSITIVE RATE TRIP light not LIT.
(step 8 of AOP-100)
- 11. Restore Tavg to program as necessary: LI Tavg to Tref checked. S / U CUE: The extra operator will restore Tavg to program.
FNPILT-35JPM JPMSIMULATORJPMF. HANDOUT I Pg 1 of2 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 9 of AOP- 100)
- 12. IF N-44 is NOT failed, THEN place rods in Rods may be in MAN or S / U AUTO, if desired. AUTO (step 10 of AOP-100)
- 13. IN-43 has failed... N-43 has not failed. This step is S / U N/A.
(step 11 of AOP- 100)
- 14. Monitor operable Power Range Channels NR-45B located and the S / U on NR-45B. remaining operable PR Channels are monitored.
(step 12 of AOP-l00)
- 15. Submit a condition report on the failed Candidate states that they S / U instrument channel, and notifi the Work would submit a CR or request Week Coordinator (Maintenance ATL on that a CR be written.
backshifts) of the condition report.
CUE if notification attempted:
Shift Supervisor acknowledges.
(step 13 of AOP-l00)
- 16. Remove the AC Control Power Fuses Candidate removes the control S / U on the A drawer for N-42. power fuses for N-42.
(Note: Candidate may mention that annunciators FC1 and FC3 will alanm)
(step 13 of AOP-l00)
- 17. Trip overtemperature delta-T bistables E Candidate requests that the OT S / U for affected channel. delta-T bistables for N-42 are placed in TRIP.
CUE: Shift Supervisor acknowledges.
(step 14 of AOP-100)
- 18. IF the plant computer is inoperable OR The step is determined to be S / U annunciator FC4 is otherwise inoperable, N/A.
THEN within one hour perform STP37.0
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 15 of AOP-100)
- 19. Notify the Shift Manager. LI Notifies the Shift Manager S I U CUE: Shift Manager acknowledges.
Terminate after the Shift Manager has been notified.
STOP TIME HO #1 THIS ENDS THE RO PORTION OF THE JPM.
FOR SROs PART 2 IS CONTINUED ON THE NEXT PAGE AND MAY BE PERFORMED IN THE SIMULATOR OR IN A CLASSROOM/OFFICE AREA.
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 SRO handout #2 below:
HO #2 START TIME ISSUE HANDOUT #2- FOR SRO CANDIDATES ONLY (step 16 of AOP-100)
- 20. For SROs ONLY: Determines TS applicable actions S/U Evaluate Tech Specs and determine for 3.3.1 Condition A, enter Condition and Actions required. condition referenced in table 3.3.1-1 for the channel:
Grading criteria: 3.3.1 Function 2a Condition D 3.3.1 Function 3 Condition D To be SAT, the most limiting REQUIRED 3.3.1 Function 6 Condition E ACTIONS are required to be identified. 3.3.1 Function 17 c, d Condition U This is Condition D. 3.3.1 Function 17e Condition T Condition E does not require reducing power or performing SR 3.2.4.2. Actions of Condition D: Place channel in Condition T & U have been previously trip within 72 hrs AND Reduce verified, but documentation of the LCO is Thermal power to 75% RTP S/U required. within 78 hrs.
-OR-:
Place channel in trip within 72 hrs AND perform SR 3.2.4.2 once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
-OR-Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
Condition E: Place channel in trip within 72 hrs S/U
-OR-Be in MODE 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
Condition T & U: Verify interlock is in required state for S/U existing plant conditions within I hour
-OR-Be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Evaluator Note: Examinee may also identify Function 1 7b as an admin LCO item. This is not required for acceptable completion of #20.
HO #2 STOP TIME Terminate after Tech Spec requirements have been determined and evaluator is informed.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP fLT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-AOP-i00, vi 1.0
- 2. KIAs: 015A2.0i RO-3.5 SRO-3.9 015A3.02 RO-3.7 SRO-3.9 015A4.03 RO-3.8 SRO-3.9 015G2.2.40 SRO-4.7 GENERAL TOOLS AND EqUIPMENT:
Provide/Acguire:
- 1. An unmarked up copy of FNP-1-AOP-100 will be provided via normally available Simulator procedures.
Critical ELEMENT justification:
STEP Evaluation 1 Not critical since this applies to N 44 only 2 Not critical no load change in piogress, no action iequiied 3-6 Not critical interlocks are in the required state or actions not required due to power level CRITICAL- Task objective, required to place N42 in the required state to trip interlocks and remove the detector from service.
10 Not critical this step is not requii ed to be pei formed 11 Not critical an extia operatoi will perfoim this task 12, 13 Not critical does not apply to N-42 14, 15 Not critical monitoi and submit CR is not ciitical to task completion CRITICAL- to place bistables in the correct condition for a failed channel. Part of Tech 16 17 Spec RAS.
18, 19 Not critical Natuial teimination point of assigned task SRO step 20 CRITICAL-to evaluate and determine the most limiting LCO and apply the correct Required Actions to this failure.
COMMENTS:
The SRO portion (second part) may be completed in the simulator or in a classroom/office area.
FNPILT-35JPM JPMSIMULATORJPMF. HANDOUT I Pg 1 of2 COMMENTS:
The SRO portion (second part) may be completed in the simulator or in a classroomloffice area.
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT I Pg 1 of2 CONDITIONS When I tell you to begin, you are to Perform actions of AOP-100 for an NI-42 failure.
The conditions under which this task is to be performed are:
- a. The Plant is at 95% power with the ramp on hold for a calorimetric.
- b. N-42 upper detector current indicator has failed low.
- c. The Shift Supervisor has directed you to perform Section 1.12 of AOP- 100 starting at step 1.
- d. A pre-job brief is not required.
FNP ILT-35 JPM JPM SIMULATOR JPM F. HANDOUT 2 Pg 2 of 2 SRO Licensed personnel only:
CONDITIONS When I tell you to begin, you are to Evaluate and determine the current Tech Spec requirements and MOST LIMITING REQUIRED ACTION associated with the failure of N-42.
The conditions under which this task is to be perforrried are:
- f. The Plant is at 95% power with the ramp on hold for a calorimetric.
- g. N-42 upper detector current indicator has failed low.
- h. The required actions have been taken to stabilize the plant in accordance with FNP- 1 -AOP- 100.
- i. The following interlocks have been checked to be in their required state for existing unit conditions:
P-7 P-8 P-9 P-b
- j. Evaluate and determine the current Tech Spec requirements and MOST LIMITING TECH SPEC REQUIRED ACTION associated with the failure of N-42.
10/10/11 12:58:34 FNP-1-AOP-100 INSTRUMENTATION MALFUNCTION Version 11.0 Step Action/Expected Response Response Not Obtained SECTION 1.12 NUCLEAR INSTRUMENTATION - POWER RANGE CHANNEL NOTE: Step 1 is an IMMEDIATE OPERATOR ACTION.
1 IF N-44 has failed, THEN place rods in manual.
2 STOP any load change in progress.
3 Within one hour, check P-1O interlock in 3 Be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of the LCO the required state for existing unit entry.
conditions. (TS 3.3.1 Function 17e) 4 Within one hour, check the following 4 Be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
interlocks are in the required state for existing unit conditions: (TS 3.3.1 Function 17b, c, d)
- P-7
- P-8
- P-9 5 Check THERMAL POWER - 5 Go to step 7.
GREATER THAN OR EQUAL TO 75%.
6 Perform FNP-1-STP-122.O, QUADRANT 6 Be in Mode 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> POWER TILT MEASUREMENT WITH AN INOPERABLE EXCORE DETECTOR as required by Tech Spec SR 3.2.4.2 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR Reduce power to <75% thermal power within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
Page 2 of 6
10/10/11 12:58:34 FNP- 1 -AOP- 100 INSTRUMENTATION MALFUNCTION Version 11.0 Step Action/Expected Response Response Not Obtained SECTION 1.12 NUCLEAR INSTRUMENTATION - POWER RANGE CHANNEL NOTE: Annunciator FC5 PR CII DEV should clear when the comparator channel defeat switch is selected to the failed NI.
7 Perform the following:
a) Select the affected channel on:
- ROD STOP BYPASS switch (Misc Control and Indication Panel)
- COMPARATOR CHANNEL DEFEAT switch (Comparator and Rate Drawer)
- UPPER SECTION switch (Detector Current Comparator Drawer)
- LOWER SECTION switch (Detector Current Comparator Drawer) b) Reset rate trip on the A drawer for the affected channel by placing Rate Mode switch in RESET allow to spring return to NORMAL.
8 Restore Tavg to program as necessary:
- Adjust turbine load
- Use of control rods
- DilutionlBoration 9 IF N-44 is NOT failed, THEN place rods in AUTO if desired.
Page 3 of 6
10/10/11 12:58:34 FNP- 1 -AOP- 100 INSTRUMENTATION MALFUNCTION Version 11.0 Step Action/Expected Response Response Not Obtained II SECTION 1.12 NUCLEAR INSTRUMENTATION - POWER RANGE CHANNEL 10 IF N-43 has failed AND it is desired to use the R-70s to determine the presence of elevated activity in the Steam Generators, THEN have Counting Room personnel place the R-70s in the ME mode per FNP-0-CCP-31, LEAK RATE DETERMINATION.
11 Monitor operable Power Range Channels on NR-45B.
12 Submit a condition report on the failed instrument channel, and notify the Work Week Coordinator (Maintenance ATL on backshifts) of the condition report.
13 Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, place the inoperable 13 Be in Mode 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> Power Range Channel in trip by performing the following: (TS 3.3.1)
NOTE: Removing control power thses will cause annunciators FCI and FC3 to alarm.
a) Remove the AC Control Power Fuses on the A drawer for the affected channel.
Step 13 continued on next page Page4of6
10/10/11 12:58:34 FNP- 1 -AOP- 100 INSTRUMENTATION MALFUNCTION Version 11.0 Step Action/Expected Response Response Not Obtained SECTION 1.12 NUCLEAR INSTRUMENTATION - POWER RANGE CHANNEL b) Trip overtemperature delta-T bistables for affected channel:
CHANNEL TEST CARD STATUS ANNUNCIATOR SWITCH LOCATION LIGHT N41 TS/412 C-i Ci-421 TSLB2, 7.1 FD4 EG1 TS/412C-2 Ci-421 TSLB1,8.1 FD4 EG1 N42 TS/422 C-I C2-421 TSLB2, 7.2 FD4 EGI TS/422 C-2 C2-421 TSLB1, 8.2 FD4 EG1 N43 TS/432 C-I C3-721 TSLB2, 7.3 FD4 EGI TS/432 C-2 C3-721 TSLB1, 8.3 FD4 EG1 14 IF the plant computer is inoperable OR annunciator FC4 is otherwise inoperable, THEN within one hour perform FNP-1-STP-37.O, POWER DISTRIBUTION SURVEILLANCE.
15 Notify the Shift Manager.
16 Initiate the applicable actions of the following Technical Specifications:
- Table 3.3.1-1 Function 2
- Table 3.3.1-1 Function 3
- Table 3.3.1-1 Function 6
- Table 3.3.1-1 Function 17 b, c, d, e 17 WHEN repairs and surveillances are complete, RESTORE the failed instrument using applicable sections of FNP-1-SOP-39.O, NUCLEAR INSTRUMENTATION SYSTEM.
Page 5 of 6
10/10/11 12:58:34 FNP-1-AOP-100 INSTRUMENTATION MALFUNCTION Version 11.0 Step Action/Expected Response Response Not Obtained II I SECTION 1.12 NUCLEAR INSTRUMENTATION - POWER RANGE CHANNEL 18 Return to procedure and step in effect.
C-END Page 6 of 6
FNP ILT-35 JPM Page 1 of 7 SIMULATOR JPM G.
CRO-091A TITLE: Place the 1C CCW Hx in Service and remove lB CCW Hx from service.
EVALUATION LOCATION: Il SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 20 MN SIMULATOR IC NUMBER: IC-223 LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee will be provided SOP-23.0, CCW System. All other references of the simulator will be available at the examinees discretion.
- 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 JPM, the examinee will:
- Perform the actions of SOP-23 .0 and place the 1 C CCW Hx on service and remove the lB CCW Hx from service.
Examinee:
Overall JPM Performance: Satisfactory L Unsatisfactory EJ Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer GT Ohmstede Date: 2/2/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM SIMULATOR JPM G. Page 2of7 (Guide pages = 6)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-223 for JPM G Base IC-73 Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
Setup *
- Run quick setup BAT file NONE FREEZE the simulator
-I SNP 223 [tm]
CONDITIONS When I tell you to begin, you are to Place the 1C CCW Hx in Service and remove lB CCW Hx from service.
The conditions under which this task is to be perfonued are:
- a. Unit I is at 100% power.
- b. A TRAIN is the ON-SERVICE TRAIN.
- c. lB CCW Hx is on service and lC CCW Hx is aligned for standby operation on A Train per Appendix 23.OC.
- d. You are directed to swap the on service A Train CCW HX from lB CCW Hx to the 1C CCW Hx per SOP-23.0, section 4.4.
- e. A pre-job brief is not required.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME HO #1:
(step 4.4.2 of SOP-23.0)
- 1. Verify SW FROM 1C CCW HX FV-3009C Z CHECK FV-3009C handswitch S / U handswitch is in MOD. is in the MOD position.
(step 4.4.3)
- 2. Verify 1 C CCW HX DISCH FCV HIC- E CHECK HIC-3009C indicates S / U 3009C is demanding the valve to be fully 100% demand.
closed (100% demand).
(step 4.4.4)
- 3. Direct the SO to locally verify SW FROM IC E CALLs Rover on phone. S / U CCW HX FV-3009C is closed.
CUE from ROVER:
FV-3009C is CLOSED.
(step 4.4.5)
- 4. Open SW TO lC CCW HX MOV3I3OC. POSITIONS MOV313OC S / U handswitch to the OPEN position and verifies RED light LIT.
FNP ILT-35 JPM SIMULATOR JPM G. Page 4 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 4.4.6)
- 5. Adjust 1C CCW HX DISCH FCV, HIC- ADJUSTS HIC-3009C while S / U 3009C to obtain approx. 2000 gpm flow on monitoring FI-3009CA to FI-3009CA. obtain 2000 gpm.
(step 4.4.7)
- 6. Direct SO to open IC CCW HX OUTLET CALLS Rover on phone. S / U ISO valve, Q1P17VOO8C, to place IC CCW HX on service. Booth operator open VOO8C.
CUE from ROVER:
Q1P17VOO8C is OPEN.
(step 4.4.8)
- 7. Verify flow increase on FI-3043CA. CHECK FI-3043CA- flow is S / U increasing (step 4.4.9)
- 8. Slowly adjust 1C CCW HX DISCH FCV, OPENS HIC-3009C S / U HIC-3009C open while closing lB CCW HX CLOSES HIC-3009B DISCH FCV, HIC-3009B, maintaining CHECKS CCW temperature is current SW pressure & temperature. maintained < 105°F.
(step 4.4.9)
- 9. Locally check 1C CCW HX DISCH FCV El CALLS Rover on phone. S / U 3009C responds to controller demand.
CUE from ROVER:
FCV-3009C has proper movement.
(step 4.4.10)
- 10. After Temperature has stabilized, direct the El CALLS Rover on phone. S / U SO to close lB CCW HX OUTLET VLV Q1P17VOO8B. Booth operator close VOO8B.
CUE from ROVER:
El Q1PI7VOO8B is CLOSED.
FNP ILT-35 JPM SIMULATOR JPM G. Page 5 of 7 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 4.4.11)
- 11. Verify flow on FI-3043BA decreases CHECKs FI-3043BA flow is
- S/U decreasing.
(step 4.4.12)
- 12. Verify lB CCW HX DISCH FCV HIC u CLOSES HIC-3009B fully S/U 3009B is fully closed. closed -100% DEMAND.
(step 4.4.13)
- 13. Direct the Rad Side SO to CLOSE breaker Li CALLS Radman on phone. S/U FV-D5, SW TO lB CCW HX MOV313OB.
Booth operator close FV-D5 Then call:
CUE from Radman:
Li FV-D5 is CLOSED.
(White power available light will be LIT on MCB)
(step 4.4.14)
- 14. Close SW TO lB CCW HX MOV-3130B. Li POSITION MOV-3130B HS to S / U the CLOSE position and verifies the GREEN light is LIT.
STOP TIME Terminate JPM when MOV-3130B is CLOSED.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-SOP-23.0, V 91.1
- 2. KIAs: 008A4.01 RO-3.3 SRO-3.1 008A4 .09 RO-3.0 SRO-2.9
FNP ILT-35 JPM SIMULATOR JPM G. Page 6 of 7 (Guide pages = 6)
GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire:
- 1. An unmarked copy of FNP-l-SOP-23.O will be provided via normally available Simulator procedures.
Critical ELEMENT justification:
STEP Evaluation t
Error Not cntical Veiify steps only Reference source not found.-3 4, 5 CRITICAL- places SW on the heat exchanger 6 CRITICAL- places the CCW side of the Hx on service 7 Not critical verify step CRITICAL- adjusting SW flow to one Hx while ensuring the other Hx maintains 8
flow.
9 Not critical verify step 10 CRITICAL- removes the lB CCW Hx from service CCW side 11,12 Not critical verify step Not critical directing the step is not critical but failure to complete this activity will 13 prevent element 14 from being satisfied.
14 CRITICAL- this is an Appendix R concern and is critical to close this valve.
COMMENTS:
FNP ILT-35 JPM JPM SIMULATOR JPM G. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to Place the IC CCW Hx in Service and remove lB CCW Hx from service.
The conditions under which this task is to be performed are:
- a. Unit I is at 100% power.
- b. A TRAIN is the ON-SERVICE TRAIN.
- c. lB CCW Hx is on service and 1C CCW Hx is aligned for standby operation on A Train per Appendix 23.OC.
- d. You are directed to swap the on service A Train CCW HX from I B CCW Hx to the 1 C CCW Hx per SOP-23.0, section 4.4.
- e. A pre-job brief is not required.
Procedure Number Ver U NIT I Farley Nuclear Plant A FNP-1-SOP-23.o 91.1 2/15/2012 06:07:45 Page Number COMPONENT COOLING WATER SYSTEM 1 of 185 S
A F
E T
Y COMPONENT COOLING WATER SYSTEM R
E L
A T
E D
PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: February 05, 2012 Operations Manager
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 2/15/2012 06:07:45 Page Number COMPONENT COOLING WATER SYSTEM Procedure Version Description Version Number Version Description 88.0 Updated procedure to requirements of NMP-OS-008-OO1, Operations Procedure Writing Instructions Revised P&L 3.17 to reflect the different stop setting for 30090.
Added P&L 3.20 and 3.21 per Al 2010296567, REA 01-2458-02 Added P&L 3.35 to reflect that both trains of COW room coolers should not be removed from service at the same time.
Revised Step 4.18.4 to maintain COW Surge Tank level to a range of 35-50 inches.
Revised Step 4.19.4 to maintain COW Surge Tank level to a range of 35-50 inches.
Revised Step 4.23 NOTE to reflect the different stop setting for 3009C.
App 11 Moved old Steps 3.20 and 3.21 to Steps 3.15 and 3.16 so the mechanical IV is performed prior to the electrical line-up in the event of an auto start signal.
89.0 Corrected unite designator in header.
Deleted redundant steps 2.13 thru 2.15 in appendix 13.
Added missing valve at step 3.2.14 in appendix 13.
Clarified wording of step 3.2.15 in appendix 13.
Corrected component to be manipulated at step 3.4.8 in appendix 13.
90.0 Updated due to the completion of FV3009B change out per DCP1O7O1 38701 adjusted full open position to a nominal 47° open and deleted old sections 4.22 & 4.23 about placing and removing valve from the jack. Updated to NMP-AP-002 format.
91.0
- Page 9, added step 2.38.
- Page 22, corrected imbedded step reference in note before step 4.12.
Corrected imbedded step reference in step 4.12.3.
- Page 23, corrected imbedded step reference in note before step 4.13.
Corrected imbedded step reference in step 4.13.3.
- Page 33, corrected imbedded step reference in step 4.25.2 and 4.25.3.2.
- Page 34, corrected imbedded step reference in step 4.25.10.
- Page 54, corrected imbedded step reference in note before step 9.0.
- Page 69, corrected imbedded step reference in note before step 9.0.
- Page 193, corrected imbedded step reference in note before step 4.1.1.
- __Implemented_CR_348399_and_Al_289687.
91.1 Added checkboxes to notes & cautions. Corrected referenced step contained in App. 7, step 4.30. CR 396287
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 3 of 185 Table of Contents Page 1.0 Purpose 5 2.0 PRECAUTIONS AND LIMITATIONS 5 3.0 INITIAL CONDITIONS 10 4.0 INSTRUCTIONS 10 4.1 A Train CCW System Startup for Normal Operation 10 4.2 B Train CCW System Startup for Normal Operation 11 4.3 A Train on Service, Shifting to the Standby HX 1 B 12 4.4 A Train on Service, Shifting to the Standby HX 1C 14 4.5 B Train on Service, Shifting to the Standby HX 1 B 15 4.6 B Train on Service, Shifting to the Standby HX 1A 16 4.7 Shifting CCW Pumps on the On Service Train 17 4.8 Operation of Off Service CCW Train - Train A 18 4.9 Operation of Off Service CCW Train Train B
- 19 4.10 Aligning CCW for Plant Cooldown with A Train 21 4.11 Aligning CCW for Plant Cooldown with B Train 21 4.12 Aligning Additional CCW Cooling to the SEP HX--A Train 22 4.13 Aligning Additional CCW Cooling to the SFP HX--B Train 23 4.14 Rernoving_CCW from Plant Cooldown LineupA Train On Service 24 4.15 Removing CCW from Plant Cooldown LineupB Train On service 24 4.16 Shifting On Service Train from A Train to B Train 24 4.17 Shifting On Service Train from B Train to A Train 24 4.18 Normal Makeup to CCW Surge Tank 25 4.19 Emergency Makeup to CCW Surge Tank 26 4.20 Chemical Mixing 26 4.21 Lowering Surge Tank Level 27 4.22 Venting the CCW Heat Exchangers, SW Side 27 4.23 Alternate_Method of Opening CCW FROM RCP THRM BARR Q1P17HV3045 with High P Suspected (OR 2 99 603) 28 4.24 Alternate Method of Opening CCW FROM RCP THRM BARR Qi P17HV3184 with High AP Suspected (OR 2 99 603) 30
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 4 of 185 4.25 Restoring COW Flow to the RCP Thermal Barriers after an Extended (>4 hour)
Loss 33 4.26 Placing Q1P17HV3O96A&B COW TO/FROM EVAP PKGS & H2 RECOMB on the MANUAL JACK 35 4.27 Removing Qi P1 7HV3096A&B COW TO/FROM EVAP PKGS & H2 RECOMB from the MANUAL JACK 36
5.0 REFERENCES
36 APPENDIX 23.OA CHEMICAL MIXING 37 APPENDIX 23.OB SHIFTING ON SERVICE TRAIN FROM TRAIN A TO TRAIN B 42 APPENDIX 23.00 SHIFTING ON SERVICE TRAIN FROM TRAIN B TO TRAIN A 57 APPENDIX 1 B TRAIN COW SURGE TANK FEED AND BLEED 72 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED 79 APPENDIX 3 COW PROCESSING USING TEMPORARY DEMIN LINER 86 APPENDIX 4 FEED AND BLEED OF THE ON SERVICE COW TRAIN 98 APPENDIX 5 PROCESSING CONTAINERS OF WASTE COW USING TEMPORARY DEMIN LINER 106 APPENDIX 6 COW SYSTEM REFILL FROM DRUMS 113 APPENDIX 7 PROCESSING WASTE COW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM 116 APPENDIX 8 ALIGNING B TRAIN COW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE 125 APPENDIX 9 ALIGNING B COW PUMP AND B COW HX TO B TRAIN WITH A COW PUMP AND A COW HX NOT AVAILABLE OR NOT IN SERVICE 135 APPENDIX 10 RETURNING 1A COW PUMP TO SERVICE AFTER MAINTENANCE 144 APPENDIX 11 RETURNING I B COW PUMP TO SERVICE AFTER MAINTENANCE 149 APPENDIX 12 RETURNING 1000W PUMP TO SERVICE AFTER MAINTENANCE 155 APPENDIX 13 ALIGNING A TRAIN COW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE 160 APPENDIX 14 ALIGNING B COW PUMP AND B COW HX TO A TRAIN WITH C COW PUMP AND C COW HX NOT AVAILABLE OR NOT IN SERVICE 169 APPENDIX 15 ENABLING THE lB COW PUMP TO AUTO-START FOR 10 COW PUMP 178 APPENDIX 16 ENABLING THE lB COW PUMP TO AUTO-START FOR IA COW PUMP 182
Procedure Number Ver U NIT I Farley Nuclear Plant A FNP-1-SOP-23.0 91.1 2/15/2012 06:07:45 Page Number COMPONENT COOLING WATER SYSTEM 5 of 185 1.0 Purpose This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for operation of the Component Cooling Water System (CCW).
2.0 PRECAUTIONS AND LIMITATIONS 2.1 At least two independent component cooling water loops shall be OPERABLE while in operational modes 1, 2, 3, and 4.
2.2 CCW is normally lined up so that
- One CCW pump and one CCW heat exchanger is in operation supplying the on-service train and the secondary heat exchangers.
- The remaining pump and heat exchanger are valved into a closed loop with the redundant safety train. The off-service train is normally in operation in modes 14 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and COW to the RHR HX isolated. (Reference RER 1080944901) 2.3 Control circuitry does not allow auto start of two pumps in the same train. In order for 1 B COW pump to be started by the ESS or LOSP sequencers; the train to which it is aligned must have the train dedicated pump supply breaker racked out.
2.4 In order to maintain a train operable with the dedicated pump/breaker inoperable AND racked in, the cell switch should be jumpered for the swing breaker to ensure the swing breaker will close on an auto start signal with the dedicated pump breaker racked in. Additionally, a link should be opened in the autostart circuitry of the dedicated pump to prevent an autostart of the dedicated train breaker. This arrangement should remain in place until such time the dedicated breaker is declared operable or surveillance testing is started. (Al 2008205335) 2.5 Do not operate more than one COW pump through one COW heat exchanger.
2.6 During normal operation of an operating train, component cooling heat exchanger outlet temperature should be maintained between 60°F and 105°F.
(CR 2004000155) 2.7 If the COW HX outlet temperature is maintained below 60°F for extended periods of time and is supplying cooling to the SECURED charging pump, then notify ES and begin sampling the Charging Pump oil for water and contaminants twice per month (reference Westinghouse Letter BPO-88-549). (Al 2009200595)
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 6 of 185 2.8 The following is required during plant cooldown
- Component cooling water outlet temperature should not exceed 120°F.
- The off-service train is to be used for RHR.
2.9 Frequent starting may damage the component cooling water pump motors. Limit pump starts as follows:
- Two successive starts from ambient temperature.
- One start from rated temperature.
- Subsequent starts: allow 30 minutes running time or 60 minutes idle time between starts.
2.10 The off-service train CCW pump must be running before starting the off-service train charging pump or RHR pump.
2.11 When the off-service CCW train is not in operation, the off-service train RHR Heat Exchange supply MOV should be maintained open to prevent lifting CCW system relief valves on pump auto starts.
- If pump flow falls below 2100 gpm, then the flow must be maintained greater than 1000 gpm.
- The time with flow less than 2100 gpm must be limited to less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per month. (ABN 97-01080)
- The pump miniflow is sized to pass 1000 gpm.
2.13 If the CCW pump miniflow is closed, such as for in-service testing, then at least 2 of the following 3 flow paths shall be aligned for pump discharge flow.
- The RHR heat exchanger
- The SEP heat exchanger
- The miscellaneous header This alignment will ensure greater than 2100 gpm flow with allowance for spurious MOV closure (ABN 97-0-1080).
2.14 CCW surge tank level must be maintained above 13 inches.
2.15 Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank.
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.o 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 7 of 185 2.16 If the CCW surge tank vents are closed for reasons other than an actual high radiation alarm, then with Shift Supervisor concurrence, the CCW surge tank vents should be cycled once every shift (eight hours) and documented in the Control Room Log 2.17 The SW FROM CCW HXfIow control valves, QIP16FCV3009A, B & C have mechanical valve travel Open and Close stops.
- The Open Stop for QI P1 6FCV3009A is set by the manual handwheel and should not be moved from a nominal setting of 450 open.
- The Open Stop for Q1P16FCV3009C is set by the manual handwheel and should not be moved from a nominal setting of 47° open.
- The Open Stop for Q1P16FCV3009B is set by the manual handwheel and should not be moved from a nominal setting of 47° open.
- If the Open Stop has been moved or one of the Open Stop hex nuts loosened, then a flow test may be required to reset the position of the Open Stop. (DCP-92-2-7928! DCP 1070138701) 2.18 CCW flow to the SEP HXs should be regulated as follows:
2.18.1 When in Modes 1 4, then the CCW outlet valve for the SFP HX should be throttled to limit CCW flow to 1500 gpm through the SEP HX with a RHR HX on service on that train.
2.18.2 If desired to lower SEP temperature while in Modes 5, 6 or defueled, then throttle CCW flow through the on service RHR HX and raise CCW flow in the SEP HX as necessary.
- This special condition will be documented by an admin LCO.
- The limit must be reinstated prior to entering Mode 4.
- The limit is reinstated by establishing CCW flow through the RHR HX and then verifying flow through the SEP HX is 1500 gpm with that train being the ON SERVICE TRAIN.
2.18.3 When the core is off loaded into the SEP, then CCW flow to the SEP HX should be maintained in accordance with ENP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIEICATION SYSTEM. Refer to the guidance in step 3.19.2 if CCW flow must be adjusted above the 1500 gpm limit.
2.18.4 CCW flow rates in excess of 3100 gpm through the SEP HX should be avoided. Flows exceeding 3100 gpm for brief periods, such as during performance of STPs is acceptable. (AlT 2002200675)
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-Sop-23.o 91.1 2/15/2012 06:07:45 Page Number COMPONENT COOLING WATER SYSTEM 8 of 185 2.19 HZ core offload begins < 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> after shutdown, THEN the COW inlet temperature to the SEP HX should be maintained < 105°E.
2.20 HZ core offload begins < 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> after shutdown, core offload is prohibited when CCW inlet temperature to the SEP HX exceeds 105°E.
2.21 Service water supply to the standby CCW HX must be closed except when shifting the standby COW HX. This ensures adequate SW flow is available to the on-service COW HX and other vital loads in the event of an accident coincident with a loss of air. (Al 2004204513) 2.22 COW supply valve to SEP heat exchanger must remain open whenever COW supply valve to RHR heat exchanger in the same train is closed.
2.23 If possible, SFP cooling should be aligned opposite from a train that is carrying both the miscellaneous header and an in-service RHR HX.
2.24 Component cooling water flow to an idle RCP should not be isolated unless reactor coolant system temperature less than 150°E.
2.25 If COW will be secured to the RCP motor oil coolers for longer than 2 months, then contact Maintenance to have the oil coolers drained and dried per RCP Technical Manual Technical Bulletin 81-02.
2.26 COW FROM ROP THRM BARR Q1P17HV3184 may experience hydraulic sticking while opening similar to Q1P17HV3045 and Section 4.22 should be used for guidance.
- If this occurs, closely monitor ROP bearing temperatures and seal injection flow.
- When the valve opens verify these parameters return to normal.
(CR #2000005361) 2.27 When COW is to be drained from the system with the intent to reuse, then appropriately labeled and clean 55 gallon two bunghole drums should be obtained from the Storeroom (Main Warehouse) or EAC Group. (CIR 2-94-010) 2.28 All hoses and pumps to be used in draining or pumping reusable COW should be flushed with demin water before use. (ClR 2-94-01 0) 2.29 All COW intended for reuse will be sampled by Chemistry and the sample results obtained prior to placing in the COW system. (CIR 2-94-010) 2.30 Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, REACTIVITY MANAGEMENT PROGRAM. (Al 2008203128)
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 9 of 185 2.31 To eliminate the requirement for Appendix R Kaowool raceway fire barriers for certain raceways in fire areas 2-006 Zone 1 and 2-020, Kaowool Fire Protection Administrative Controls have to be implemented when the swing CCW pump is placed in service for a corresponding dedicated Train pump that is not available.
Therefore, when Train A or Train B CCW pump is made unavailable and the swing pump is placed in service on that Train, then the following Kaowool FP administrative controls must be established:
- Begin tracking (e.g., LCO) the amount of time the swing component is in service for the unavailable dedicated Train component.
- If the swing component remains in service for the unavailable dedicated Train component for more than 30 days, then hourly fire watches must be established in the appropriate fire area per FNP-0-SOP-0.4 Table 13 until the unavailable dedicated Train pump is available.
2.32 Pipe internals can be potentially degraded. Proceed with caution. Do not subject vent/drain piping to any undue stress during removal of pipe cap/plug.
(AI2009202698).
2.33 Changes to CCW temperature will have an effect on RCP seal leakoff flow rates. If desired to adjust CCW temperature due to RCP seal leakoff flow rate concerns, the guidance in Sections 4.1 and 4.2 concerning adjustment of FCVs 3009 as desired may be used. However, CCW heat exchanger outlet temperature should be maintained between 60°F and 105°F per P&L 2.6.
2.34 While in modes 1-4, both trains of CCW room coolers should not be removed from service at the same time.
2.35 When the 4160VC disconnects are operated, it is important to visually ensure (with a flashlight) that all three Stabs have either opened up or closed successfully due to the disconnect operation. (CR2010104131) 2.36 To maintain SFP temperature as low as possible during the core off load, consideration should be given to maximizing CCW cooling to the SEP HX(s) early in the fuel transfer to the SEP. Throttle CCW flow to the on service RHR HX(s) as required to maintain appropriate cooling to the on-service train(s) of RHR during core off load. CCW flow rates in excess of 3100 GPM through the SEP HX should be avoided. (1 R23 OLLI 03 CR2010114600) 2.37 When SW is isolated to a CCW HX, (ie, standby heat exchanger), Chemistry shall be notified of the isolated heat exchanger so they may begin monitoring chlorine levels in the idle heat exchanger. (TE 289687)
Procedure Number Ver U NIT I Farley Nuclear Plant A FNP-1-SOP-23.0 91.1 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM Page Number 10 of 185 3.0 INITIAL CONDITIONS 3.1 The electrical distribution system is energized and aligned for normal operation per FNP-1-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted.
3.2 The compressed air system is in normal operation per FNP-1-SOP-31 .0, COMPRESSED AIR SYSTEM.
3.3 The component cooling water system valves and electrical distribution systems are aligned per system checklist FNP-1-SOP-23.OA, with exceptions noted. {CMTs 0008598 & 0008599}
3.4 The component cooling water system is filled and vented, with the component cooling surge tank filled to a level of approximately 42 inches.
3.5 The service water system is in normal operation per FNP-1-SOP-24.0, SERVICE WATER SYSTEM.
3.6 The demineralized water system and/or the reactor makeup water system is aligned to the component cooling water surge tank per FNP-1-SOP-5.0, DEMINERALIZED MAKEUP WATER SYSTEM, and/or FNP-1-SOP-4.0, REACTOR MAKEUP WATER SYSTEM.
3.7 Radiation monitors R-17A and R-17B are in normal operation per FNP-1-SOP-45.0, RADIATION MONITORING SYSTEM.
4.0 INSTRUCTIONS 4.1 A Train COW System Startup for Normal Operation NOTE If required, then the standby pump may be started in place of the on service pump.
4.1.1 Verify 18 CCW pump and 1 B COW HX are aligned to A Train per Appendix 23.OC.
4.1.2 Check lB COW HX COW OUTLET ISO, Q1P17VOO8B is closed. Q1P17VOO8B may be open if standby heat exchanger in service per Section 4.3 or 4.5.
4.1.3 Verify that SW FROM 10 CCW HX Qi P1 6FV3009C QE SW FROM lB COW HX Q1P16FV3009B handswitch is in MOD.
4.1.4 Throttle 10 COW HX DISCH FCV HIC 30090 OR lB COW HX DISCH FCV HIC 3009B as necessary to control COW temperature.
4.1.5 Verify on-service COW HX outlet valve Qi P1 7V0080 or Q1P17VOO8B open.
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 2/15/2012 06:07:45 Page Number COMPONENT COOLING WATER SYSTEM 11 of 185 4.16 Verify open CCW TO 1A RHR HX Q1P17MOV3185A.
CAUTION Q Q] operate more than one CCW pump through one CCW heat exchanger.
4.1.7 Start 1C or lB COW PUMP. LI 4.1.8 Verify flow increase on Fl 3043CA OR BA, for the on-service heat exchanger.
4.1.9 Monitor CCW FROM COW HX TEMP TI 30240 OR TI 3024B to ensure COW temperature is maintained less than 105°F. El 4.1.10 Monitor service water header pressure while adjusting HIC 3009C or B.
4.1.11 After system is stable then CCW TO 1A RHR HX Q1P17MOV3185A may be closed.
4.2 B Train CCW System Startup for Normal Operation NOTE LIE required, THEN the standby pump may be started in place of the on service pump.
4.2.1 Verify lB COW pump and lB CCW HX are aligned to B Train per Appendix 23.OB 4.2.2 Check lB COW HX COW OUTLET ISO, Q1PI7VOO8B closed.
Qi P1 7V008B may be open if standby heat exchanger in service per Section 4.4 or 46.
4.2.3 Verify that SW FROM 1A CCW HX Qi PI6FV3009A SW FROM lB COW HX Q1P16FV3009B handswitch is in MOD.
4.2.4 Throttle 1A CCW HX DISCH FCV HIC 3009AOR lB COW HX DISCH FCV HIC 3009B as necessary to control COW temperature.
4.2.5 Verify on-service COW HX outlet valve Qi P1 7V008A Q.
Q1P17VOO8B open.
4.2.6 Verify open COW TO lB RHR HX Q1P17MOV3185B. LI
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 12 of 185 CAUTION
,Q NOT operate more than one CCW pump through one COW heat exchanger. LI 4.2.7 Start 1AOR lB COW PUMP, LI 4.2.8 Verify flow increase on Fl 3043AA OR BA, for the on-service heat exchanger.
4.2.9 Monitor CCW FROM COW HX TEMP T13024A or T13024B to ensure COW temperature is maintained less than 105°F.
4.2.10 Monitor service water header pressure while adjusting HIC 3009A or HIC 3009B LI 4.2.11 After system is stable then CCW TO 1 B RHR HX Q1P17MOV3185B may be closed.
4.3 A Train on Service, Shifting to the Standby HX 1 B 4.3.1 Ensure lB COW HX is aligned to the A Train COW and A Train SW per Appendix 23.00.
4.3.2 Verify SW FROM lB COW HX Q1P16FV3009B handswitch is in MOD. LI 4.3.3 Verify lB COW HX DISOH FCV HlC 3009B is demanding the valve to be fully closed (100% demand). LI 4.3.4 Locally verify closed SW FROM I B COW HX Qi P1 6FV3009B.
4.3.5 Open SW TO lB COW HX Q1PI6MOV3I3OB.
4.3.6 Adjust 1 B COW HX DISCH FCV, HIC 3009B to obtain approximately 2000 gpm SW flow on Fl 3009BA LI 4.3.7 Open lB COW HX COW OUTLET ISO, Q1P17VOO8B to place lB COW HX on service. LI 4.3.8 Verify flow increase on Fl 3043BA. LI
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-1-SOP-23.0 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 13 of 185 CAUTION COW temperature should be maintained as stable as possible to minimize effects on the following:
- Reactivity changes due to changes in letdown temperature
- RCP Oil Levels 4.3.9 Throttle open lB CCW HX DISCH FCV HIC 3009B while throttling closed 10 CCW HX DISCH FCV HIC 30090
- Maintain existing service water pressure.
- Ensure CCW temperature is maintained less than 105°F.
(120°F if aligned for plant cooldown.)
- Locally check lB COW HX DISCH FCV 3009B responds to controller demand. (CR 2009107460) 4.3.10 After temperature stabilized with I B HX on service, place 1 C CCW HX in Standby by closing 10 COW HX OUTLET VLV Q1 P1 7V008C. El 4.3.11 Verify flow on Fl 3043CA decreases.
4.3.12 Verify 1C COW HX DISCH FCV HIC 30090 fully closed.
4.3.13 Close SW TO 10 COW HX QIP16MOV31300.
NOTE Opening the breaker in the following step is only required when COW is required to be operable. Breaker may be left closed in Mode 5 or 6 if an Admin LCO is written to ensure it is opened prior to Mode 4. El 4.3.14 Open power supply breaker Q1RI7BKRFVD5, SW TO lB COW HX Q1P16MOV313OB.
4.3.15 Notify Chemistry of current alignment of COW HXs, for monitoring purposes. LI
Procedure Number Ver U NIT I Farley Nuclear Plant FNP-l.SOP-.23.O 91.1 Page Number 2/15/2012 06:07:45 COMPONENT COOLING WATER SYSTEM 14 of 185 4.4 A Train on Service, Shifting to the Standby HX 1 C 4.4.1 Ensure 1 B CCW HX is aligned to the A Train COW and A Train SW per Appendix 23.00.
442 Verify SW FROM 1C COW HX Q1P16FV3009(. handswitch is n MOL).
443 Verify 1C COW HX DISCH FCV HIC 30090 is demanding the valve to be fully closed (100% demand).
4.4.4 Locally verify closed SW FROM 1C COW HX Q1P16FV3009C.
4.4.5 Open SW TO 1C COW HX Q1P16MOV313OC.
4.4.6 Adjust IC CCW HX DISCH FCV, HIC 3009C to obtain approximately 2000 gpm SW flow on Fl 3009CA 4.4.7 Open IC CCW HX 00W OUTLET ISO, Q1P17VOO8C to place IC COW HX on service.
4 4.8 Verify flow increase on Fl 3043CA.
CAUTION COW temperature should be maintained as stable as possible to minimize effects on the following:
. Reactivity changes due to changes in letdown temperature
. ROP Oil Levels 449 Throttle open 10 COW HX DISOH FCV HIC 30090 while throttling closed lB COW HX DISOH FCV HIO 3009B.
. Maintain existing service water pressure.
. Ensure COW temperature is maintained less than 105°F.
(120°F if aligned for plant cooldown.) E
. Locally check IC COW HX DISCH FCV 30090 responds to controller demand. (CR 2009107460) 4.4.10 After temperature stabilized with 10 HX on service, place lB COW HX in Standby by closing I B COW HX OUTLET VLV QI P1 7V008B.
4.4.11 Verify flow decrease on Fl 3043 BA.
4.4.12 Verify SW FROM lB COW HX QIP16FV3009B fully closed.
4.4.13 Close power supply breaker Qi Ri 7BKRFVD5, SW TO 18 COW HX Q1P16MOV313OB.
4.4.14 Close SW TO lB COW HX Q1P16MOV313OB.
4.4.15 Notify Chemistry of current alignment of COW HXs, for monitoring purposes.
FNPILT-35JPM Page 1 ofIl SIMULATOR JPM H.
CRO-333A TITLE: Perform The Required Actions For Cold Leg Recirculation.
EVALUATION LOCATION: II SIMULATOR LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-224 LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Examinee will be provided ESP-1 .3, Transfer to Cold Leg Recirculation. Steps 1 through 7.5 will be signed off and/or circle slash method of place keeping already completed. All other references of the simulator will be available at the examinees discretion.
- 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 JPM, the examinee will:
. Perform the actions of ESP- 1.3 starting at step 7.6. When complete, BOTH Trains of ECCS will be on service in the recirculation mode and SI flow stable at step 7.33.
Examinee:
Overall JPM Performance: Satisfactory I Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer GT Ohmstede Date: 2/2/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP !LT-35 JPM SIMULATOR JPM H. Page 2 of 11 (Guide pages = 10)
Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-224 for JPM G Base IC-151 Put OPS group on MCB CRT Acknowledge computer alarms Verify RODS updated.
Run / Freeze Simulator--
Acknowledge Alarms Turn Horns ON VERIFY Simulator PRINTER and 1) REPLACE/CLEAN marked up procedures are cleaned, procedures and Operator aids.
Setup*
CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS TO TRANSFER TO COLD LEG RECIRCULATION ON BOTH TRAINS OF ECCS.
The conditions under which this task is to be performed are:
- 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.
- d. Recirculation Disconnects are closed per Attachment 1 of EEP-1.0.
- e. You are directed to transfer to Cold Leg Recirculation by performing ESP-1 .3, starting at Step 7.6.
- f. A pre-job brief is not required.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME (step 7.6)
- 1. Stop BOTH RHR pumps. *POSITION handswitches S / U Counter-Clockwise to STOP; 1 A RHR PP-GRN light LIT D IA RHR purnp-GRN light LIT Check pump amps o Amps fall to zero, (step 7.7)
- 2. Close RWST TO 1A RHR PUMP *POSITION handswitch S / U Q1E1 1MOV88O9A. Counter-Clockwise to CLOSE; D MOV-8809A-GRN light LIT (step 7.8)
- 3. Align CTMT sump to 1A RHR PUMP. *POSITION handswitches S / U OPEN MOV-881 1A Clockwise to OPEN; OPEN MOV88 1 2A i MOV-88 11 A-RED light LIT El MOV-8812A-RED light LIT
FNP ILT-35 JPM SIMULATOR JPM H. Page 4 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE NOTE: ONLY one valve, MOV-8887A or B is required to be CLOSED. Either one will satisfy the critical function of separating RHR Trains. Either Element 4 or 9 must be performed.
(step 7.9)
MOV-8887A. Counter-Clockwise to CLOSE; Li MOV-8887A-GRN light LIT (step 7.10)
- 5. Start IA RHR PUMP. *PO5ITION handswitch S / U Clockwise to START; Li lA RHR PMP -RED light LIT CHECKS pump amps Li IARHRPUMP-47amps (step 7.11)
- 6. Verify A Train LHSI flow STABLE on Fl- CHECKs A Train RHR flow S / U 605A. Li FI-605A -3.1 x103 and stable (step 7.12)
- 7. Close RWST TO lB RHR PUMP MOV- *POSITION handswitch S / U 8809B. Counter-Clockwise to CLOSE; Li MOV-8809B-GRN light LIT (step 7.13)
- 8. Align CTMT sump to lB RHR PUMP. *POSITION handswitches S / U OPEN MOV-8811B Clockwise to OPEN; OPEN MOV-8812B Li MOV-881 lB-RED lightLIT Li MOV-8812B-RED light LIT (step 7.14)
- 9. Close RHR to RCS HOT LEGS XCON *POSITION handswitch S / U (NOTE) MOV-8887B. Counter-Clockwise to CLOSE; Li MOV-8887B-GRN light LIT (step 7.15)
- 10. Start lB RHR PUMP. *POSITION handswitch S / U Clockwise to START; Li 1 B RHR PMP -RED light LIT CHECKS pump amps Li lB RHRPUMP-45 amps
FNP ILT-35 JPM SIMULATOR JPM H. Page 5 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 7.16)
- 11. Verify B Train LHSI flow - STABLE on Fl- CHECKs B Train RHR flow S / U 605B. LI FI-605B -2.4 x1O and stable (step 7.17)
- 12. Verify at least one train of RHR in operation LI CHECKS Both Trains of RHR S I U providing recirc flow, are in operation and providing flow.
(step 7.18)
- 13. Verify charging pump miniflow valves CHECKs mini-flow position: S I U CLOSED. LI MOV-8 1 09A-GRN light LIT LI MOV-8 1 09B-GRN light LIT LI MOV-8 1 09C-GRN light LIT LI MOV-8 1 06-GRN light LIT (step 7.19)
- 14. Verify seal return flow valves CLOSED. CHECKS seal return valves S I U CLOSED:
LI MOV-8 11 2-GRN light LIT LI MOV-8100-GRN light LIT (step 7.20)
- 15. lB Charging Pump Suction Header isolation CHECKS lB Chg Pump suction S / U valves checked OPEN. header isolation valves to A Train:
LI MOV-8 1 30A-RED light LIT LI MOV-8 I 30B-RBD light LIT NOTE: For Element 16 ONLY one valve, MOV-8131A or B is required to be CLOSED. Either one will satisfy the critical function of separating Charging pump suction trains.
(step 7.20)
- 16. CLOSE- lB Chg Pump Suction Header *POSITIONS lB Chg Pump S I U isolation valves from B Train, suction header isolation valves to B Train handswitch Counter Clockwise to CLOSE:
LI MOV-8 131 A-GRN light LIT LI MOV-8 131 B-GRN light LIT
FNP ILT-35 JPM SIMULATOR JPM H. Page 6 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 7.21)
- 17. OPEN- RHR Supply to A Train Chg Pump *POSITIONS RHR to Chg pump S / U suction MOV-8706A. suction handswitch CLOCKWISE to OPEN El MOV-8706A-RED light LIT (step 7.22)
- 18. Verify A Train CHG Pump STARTED. CHECKS IA CHG pump S I U Running El 1A CHG Pump-RED light LIT El 1A CHG Pump amps-105 amps (step 7.23)
El LI-115> 30%
(step 7.24)
- 20. CLOSE A Train RWST to Chg pump
- POSITIONS Chg pump suction S / U suction valve LCV-1 I 5B. handswitch Counter CLOCKWISE to CLOSE:
El LCV-115B -GRN light LIT (step 7.25)
- 21. lB Charging Pump Suction Header isolation CHECKS lB Chg Pump suction S / U valves checked in proper position. header isolation valves to A Train:
El MOV-8 1 30A-RED light LIT El MOV-8130B-RED light LIT El MOV-8 131 A-GRN light LIT El MOV-8 131 B-GRN light LIT (step 7.26)
- 22. OPEN- RHR Supply to B Train Chg Pump *POSITIONS RHR to Chg pump S / U suction MOV-8706B. suction handswitch CLOCKWISE to OPEN El MOVs 8706B-RED light LIT
FNP ILT-35 JPM SIMULATOR JPM H. Page 7 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(step 7.27)
- 23. Verify B Train CHG Pump STARTED. CHECKS 1C CHG pump S / U Running El 1 C CHG Pump-iuD light LIT El 1C CHG Pump amps-105 amps (step 7.28)
El LI-115> 30%
(step 7.29)
- 25. CLOSE B Train RWST to Chg pump
- POSITIONS Chg pump suction S / U suction valve LCV-115D.
handswitch Counter CLOCKWISE to CLOSE:
El LCV- 11 5D -GRN light LIT (step 7.30)
- 26. Check one charging pump in each train CHECKS 1C CHG pump S / U running. Running El 1A CHG Pump amps-lOS amps El 1C CHG Pump amps-lOS amps NOTE: Element 27 is NOT critical if Element 29 is not performed. I (step 7.31)
- 27. Open charging pump recirc to RCS cold legs *POSITIONS Chg pump recirc S / U MOV- 8885. to RCS cold leg handswitch CLOCKWISE to OPEN El MOVs 8885-RED light LIT (step 7.32)
- 28. CLOSE B Charging Pump Discharge Header CHECKS lB Chg Pump suction S / U isolation valves to B Train, header isolation valves to A Train:
El MOVs 81 32A-RED light LIT El MOVs 81 32B-pu light LIT
FNP ILT-35 JPM SIMULATOR JPM H. Page 8 of 11 (Guide pages = 10)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
NOTE: For Element 289 ONLY one valve, MOV-8133A or B is required to be CLOSED. Either one will satisfy the critical function of separating Charging pump discharge trains.
(step 7.32)
- 29. CLOSE B Charging Pump Discharge Header *POSITIONS lB Chg Pump S / U isolation valves to B Train, discharge header isolation valves to B Train handswitch Counter Clockwise to CLOSE:
Li MOVs 8133A-GRN light LIT El MOVs 8l33B-GRN light LIT (step 7.33)
- 30. Verify SI flow is stable. CHECKs SI flow: S / U Li FI-943, HHSI Recirc Flow A train, 0.65 xl 0 and stable El FI-940, HHSI Recirc Flow B train, 0.65 xl 0 and stable El FI-605A, RHR HDR flow -2.O 3 and stable x10 E FI-605B, RHR HDR flow 2.0 xlO and stable STOP TIME Terminate JPM when SI flow is determined to be stable.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP- 1 -ESP- 1.3, Version 22
- 2. K/As: EPEOIIEAI.13 RO-4.l SRO-4.2 EPEO11EG2.1.20 RO-4.6 SRO-4.6 EPEOI 1EG2.l.31 RO-4.6 SRO-4.3 GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire:
- 1. A marked up copy of FNP-1-ESP-l.3 will be provided.
FNP ILT-35 JPM SIMULATOR JPM H. Page 9 of 11 (Guide pages = 10)
Critical ELEMENT justification:
STEP Evaluation 1 CRITICAL- the suction of the pumps will be closed in subsequent steps and pump damage could occur if the pumps remain running.
2,3 CRITICAL- realigning the suction valves places the suction on the ctmt sump which is the objective of the task.
4 or 9 CRITICAL- closing one of the cross connect valves is part of the accident analysis to protect the trains in the case of certain pipe failures. Only step 4 or 9 is critical, NOT BOTH.
5 CRITICAL-Starting the RHR pump provides flow to the core as well as that trains HHSI pump.
6 Not cntical verify step 7,8 CRITICAL- realigning the suction valves places the suction on the ctmt sump which is the objective of the task.
9 or 4 Not critical This is a redundant action to split the Tiains This task is NOT ciitical if the redundant component was already closed. ONLY one of the two Valves closed satisfies this condition.
10 CRITICAL-Starting the RHR pump provides flow to the core as well as that trains HHSI pump.
11 15 Not critical verify step 16 CRITICAL-splits the suction of the HHSI pump closing one of the cross connect valves is part of the accident analysis to protect the trains in the case of certain pipe failures.
17 CRITICAL- this places the suction supply of the HHSI pumps to the RHR pump discharge.
This is critical since in future steps the suction header will be split out and the RWST water will decrease.
18 19 Not cntical vei ify step 20 CRITICAL- closing LCV- 11 SB isolates flow from the RHR pump to the RWST that would prevent flow of radioactive water to the RWST past a check valve that would protect the safety and health of the public.
21 Not critical Vei ify steps only 22 CRITICAL- this places the suction supply of the HHSI pumps to the RHR pump discharge.
This is critical since in future steps the suction header will be split out and the RWST water will decrease 23, 24 Not critical Veiify steps only 25 CRITICAL- this places the suction supply of the HHSI pumps to the RHR pump discharge.
This is critical since in future steps the suction header will be split out and the RWST water will decrease 26 Not critical vei ify step 27 CRITICAL- This step is only critical if step 29 is accomplished properly. This is b/c step 29 splits out the discharge flow path of the HHSI pump and if MOV-8885 were not opened, it would be deadheaded.
28 Not critical vei ify step 29 CRITICAL- splits the discharge of the HHSI pump closing one of the cross connect valves is part of the accident analysis to protect the trains in the case of certain pipe failures.
30 Not critical veiify step
FNP ILT-35 JPM SIMULATOR JPM H. Page 10 of 11 (Guide pages = 10)
COMMENTS:
If CH415 RWST LVL A/B TRN LO-LO, comes into alarm, the extra operator will take the appropriate actions of ESP-l.3 which is to secure the CS pumps. This is the expectation of the station so the operator performing ESP- 1.3 will not be diverted.
FNP ILT-35 JPM JPM SIMULATOR JPM H. HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS TO TRANSFER TO COLD LEG RECIRCULATION ON BOTH TRAINS OF ECCS.
The conditions under which this task is to be performed are:
- b. ESP-1 .3 has been entered and all steps through step 7.5 have been completed.
- c. 1 B Charging pump is aligned to A Train.
- d. Recirculation Disconnects are closed per Attachment 1 of EEP- 1.0.
- e. You are directed to transfer to Cold Leg Recirculation by performing ESP-1 .3, starting at Step 7.6.
- f. A pre-job brief is not required.
6/1/2011 15:09 FNP-1-ESP-1.3 2-09-2011 Revision 22 PARLEY NUCLEAR PLANT EVENT SPECIFIC PROCEDURE FNP-1-ESP-1 .3 TRANSFER TO COLD LEG RECIRCULATION S
A F
PROCEDURE USAGE REQUIREMENTS-per FNP-0-AP-6 SECTIONS E T
Contintious Use ALL Y Reference Use R E
Information Use L A
T E
0 Approved:
David L. Reed (for)
Operations Manager Date Issued: 02/10/11
6/1/2011 15:09 FNP4ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Table of Contents Procedure Contains Number of Pages Body 19 Attachment 1 3 Pagelofi
6/1/2011 15:09 FNP-l-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 A. Purpose This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode.
B. Symytoms or Entry Conditions I. This procedure is entered when RWST level is less than 12.5 ft; from the following:
- a. FNP-l-EEP-l, LOSS OF REACTOR OR SECONDARY COOLANT, step 15
- b. FNP-1ESP-l.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, step 1
- c. FNP-l-ECP-2.l, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, step 13
- d. FNP-l-FRP-C.2, RESPONSE TO DEGRADED CORE COOLING, step 1
- e. FNP-l-FRP-C.3. RESPONSE TO SATURATED CORE COOLING, step 1
- f. FNP-1-FRP-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 20
- g. A Foldout Page Page 1 of 19
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: To ensure that SI recirculation flow is maintained at all times, the following steps should be performed without delay.
CAUTION: No Function Restoration Procedure should be implemented until step 7 has been completed.
CAUTION: Switchover to recirculation may cause high radiation levels in the auxiliary building.
1 [CA] Check RWST level - GREATER 1 alignment for recirculation THAN 4.5 ft. is NOT imminent, THEN stop any pump taking suction from the RWST.
CHG PUMP
[1 1A Ii lB
[1 1C RHR PUMP
[] 1A
[] lB
[1 CS RESET TRN A(B) containment spray signals - RESET (Annunciator EE4 clear)
CS PUMP
[] 1A
[1 lB Page 2 of 19
6/1/2011 15:09 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I NOTE: The intent of Step 2 is to differentiate between a steam line break event (with SI terminated and RWST drain down only from containment spray operation) and a loss of reactor coolant event (RWST drain down from one or more ECCS pumps).
2 Check SI in service. 2 Perform the following.
A TRN CTMT SUMP TO RHR HHSI FLOW PUMP RESET
[1 Fl 943 [1 A TRN
[1 B TRN OR 2.2 Proceed to step 8.
Started RHR PUMP 1A lB RWST TO lA(1B) RHR PUMP Q1E11MOV [1 88O9A [] 88O9B open open 1C(1A) RCS LOOP TO 1A(1B) RHR PUMP Q2E11MOV [1 87O1A [1 87O2A closed closed
[1 870lB [] 87O2B closed closed Page 3 of 19
6/1/2011 15:09 FNP 1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I 3 Verify SI RESET. 3 Perform the following:
[] MLB-l 1-1 not lit (A TRN) 3.1 jj any train will IQ[ reset
[1 MLB-l 11-1 not lit (B TRN) using the MCB SI RESET pushbuttons, THEN place the affected train S821 RESET switch to RESET.
(SSPS TEST CAB.)
3.2 IF a failure exists in SSPS such that SI cannot be reset, THEN reset SI using FNP-1-SOP-4O.O, RESPONSE TO INADVERTENT SI AND INABILITY TO RESET OR BLOCK SI, Appendix 2.
4 Verify at least one train of PRF in operation using FNP-l-SOP-60.O, PENETRATION ROOM FILTRATION SYSTEM in conjunction with the remaining steps of this procedure.
5 Check CCW to RHR heat 5 Open any closed CCW to RHR heat exchangers MOVs - OPEN. exchanger valve(s) continue with this procedure while CCW TO valves stroke open.
[1 Q1P17MOV3185A open CCW TO
[1 Q1P17MOV3185B open 1A(1B) RHR HX
[] O1P17MOV3185A open
[1 01P17M0V3185B open 6 Establish only one CHG PUMP in each train - RUNNING.
[1 A Train (1A or 1B) amps > 0
[1 B Train (1C or 1B) amps > 0 Page 4 of 19
6/1/2011 15:09 FNP-1ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response - Response NOT Obtained I 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 suinp to the RCS cannot be established or maintained.
7 Align ECCS for cold leg recircula-tion.
7.1 Check large break LOCA has 7.1 Proceed to step 7.4.
occurred as indicated by accumulators discharged.
7.2 Check containment sump level - 7.2 both containment sump level GREATER THAN 3.4 ft (3.8 ft}. indications less than 3.4 ft (3.8 ft},
CTMT SUMP THEN go to FNP-1-ECP-l.l. LOSS LVL OF EMERGENCY COOLANT
{] LI 3594A RECIRCULATION.
POST ACCIDENT CTMT WTR LVL
[] LR 3594B 7.3 Proceed to step 7.5.
7.4 Check containment sump level - 7.4 both containment sump level GREATER THAN 2.5 ft (2.9 ft). indications less than 2.5 ft
[2.9 ft(,
CTMT SUMP THEN go to FNP-l--ECP-1.1, LOSS LVL OF EMERGENCY COOLANT
{] LI 3594A RECIRCULATION.
POST ACCIDENT CTMT WTR LVL H LR 3594B 7.5 Verify recirculation valve disconnects - CLOSED USING ATTACHMENT 1.
7:6 Stop both RHR PUMPs.
Step 7 continued on next page.
Page 5 of 19
6/1/2011 15:09 FNP-l-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I 7.7 Close RWST TO 1A RHR PUMP 7.7 Perform the following.
OlEl 1M0V8809A.
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 LI Q1E11MOV8811A open 7.8.2 Proceed to step 7.12.
LI Q1E11MOV8812A open 7.9 Close RHR to RCS HOT 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 lA amps > 0 CHG PUMP.
7.10.2 Proceed to step 7.12.
7.11 Verify A Train LHSI flow STABLE.
[1 Fl 605A 7.12 Close RWST TO lB RHR PUMP 7.12 Perform the following.
Q1E11MOV88O9B.
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 CHG PUMP.
TO lB RHR PUMP
[1 Q1E11MOV8811B open 7.13.2 Proceed to step 7.17.
[1 Q1E11MOV8812B open Step 7 continued on next page.
Page 6 of 19
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 7.14 Close RHR to RCS HOT LEGS XCON 01E11M0V8887B.
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
6/1/2011 15:09 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 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 lA RHR HX Q1P17MOV3185A 7.17.2 IF A Train RHR 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 AND start any available charging pump aligned to the RWST.
Step 7 continued on next page.
Page 8 of 19
6/1/2011 15:09 FNP4-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-1-ECP-l.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 IQI 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.
1A(1B,1C) CHG PUMP MINIFLOW ISO
[1 Q1E21MOV81O9A
[] Q1E21MOV81O9B
[] Q1E21MOV81O9C CHG PUMP MINIFLOW ISO
[1 Q1E21MOV81O6 7.19 Verify seal return flow valves - CLOSED.
[1 Q1E21MOV8100 closed
[1 Q1E21MOV8112 closed Step 7 continued on next page.
Page 9 of 19
6/1/2011 15:09 FNP-l-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I I 7.20 IF 1A RHR PUMP started. 7.20 IF 1A 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 O1E21MOV [1 813OA El 813OA [I 813OA open closed closed
[I 8130B [I 813OB [I 8130B open closed closed
[] 8131A [I 8131A [I 8131A closed open closed El 8131B [I 8131B El 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
[1 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
6/1/2011 15:09 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I 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 O1E21MOV [1 8130A [1 8130A El 8l30A open closed closed El 8130B [I 8130B [1 813DB open closed closed El 8l3lA [1 8131A [I 8131A closed open closed El 8l3lB El 8131B El 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 HX 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
6/1/2011 15:09 FNP-l-ESP-l.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 O1E11MOV87O6B 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
[1 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
[] Q1E21MOV8885 7.30.2 Close HHSI isolation valves.
[] Q1E21MOV88O3A
[1 Q1E21MOV88O3B 7.30.3 Proceed to step 7.32.
Step 7 continued on next page.
Page 12 of 19
6/1/2011 15:09 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.
CHG PUMP RECIRC TO RCS COLD LEGS
[1 Q1E21MOV8885 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 [I 8132A [] 8132A [1 8132A open closed closed
[1 8132B El 8132B [1 8132B open closed closed El 8l33A [] 8133A [1 8133A closed open closed El 8133B [1 8133B [1 8133B closed open closed 7.33 Verify SI flow - STABLE. 7.33 IF 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(lB)
RHR HDR FLOW El Fl 605A E] Fl 6O5B Page 13 of 19
6/1/2011 15:09 FNP-l-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I 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.
8 Verify ECCS 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 [CAl Monitor ECCS pump suction maintained, conditions NO INDICATION OF THEN go to FNP-1-ECP-1.3, LOSS CAVITATION. OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP CHG PUMP BLOCKAGE.
[] 1A
[] lB
[1 iC RHR PUMP
[1 1A
[] lB CS PUMP
[1 1A
[1 lB Page 14 of 19
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I NOTE: Containment spray pumps that have been secured due to RWST level less than 4.5 ft should not be started in the following step.
9 [CAl Check containment spray.
IN OPERATION.
9.1 Check any containment spray 9.1 Verify all available pump STARTED. containment spray pumps -
RUNNING.
CS PUMP
[1 1A
[1 lB 9.2 Check containment spray flow 9.2 Perform the following.
in both trains - GREATER THAN 0 gpm. 9.2.1 IF RWST - GREATER THAN 4.5 ft.
CS FLOW THEN verify containment
[1 Fl 958A spray pump suction aligned
[1 Fl 958B for injection.
[1 Q1E13MOV8817A open El O1E13MOV88]7B open 9.2.2 Verify containment spray pump discharge aligned.
[I Q1E13MOV882OA open
[I Q1E13MOV882OB open 9.2.3 IF unable to establish spray flow in a train, THEN secure containment spray pump in affected train.
[1 CS RESET TRN A(B) containment spray signals - RESET (Annunciator EE4 clear)
[1 CTMT SPRAY PUMP 1A(B) -
STOPPED in affected train Page 15 of 19
6/1/2011 15:09 FNP-l-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I 10 [CA] WREN RWST level less than 4.5 ft.
THEN align containment spray for recirculation.
[] MLB-3 1-1 not lit
[1 MLB-3 6-1 not lit 10.2 Open containment spray pump 10.2 IF unable to open a containment sump suction containment suinp suction isolation valves, isolation valve, THEN perform the following:
CTMT SUMP TO 1A(1B) CS PUMP 10.2.1 Secure containment spray
[] 01E13MOV8826A pump in affected train.
[] 01E13MOV8827A
[1 01E13MOV8826B [1 CS RESET
[] Q1E13MOV8827B TRN A(B) containment spray signals - RESET (Annunciator EE4 clear).
[] CTMT SPRAY PUMP 1A(B) -
STOPPED in affected train 10.2.2 Verify closed BOTH containment sump suction isolation valves in affected train.
[1 Q1E13MOV8826A
[] Q1E13MOV8827A CTMT SUMP TO lB CS PUMP H Q1E13M0V8826B
[1 Q1E13MOV8827B Step 10 continued on next page.
Page 16 of 19
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I 10.3 Close containment spray pump 10.3 IE unable to isolate RWST RWST suction isolation valves, suction in a train, THEN perform the following:
RWST TO 1A(1B) CS PUMP 10.3.1 Secure containment spray
[] Q1E13MOV8817A pump in affected train.
[] Q1E13MOV8817B
[] CS RESET TRN A(B) containment spray signals - RESET (Annunciator EE4 clear).
[] CTMT SPRAY PUMP 1A(B) -
STOPPED in affected train 10.3.2 Close containment spray pump containment sump suction isolation valves in affected train.
[1 Q1E13MOV8826A
[1 Q1E13MOV8827A CTMT SUMP TO lB CS PUMP
[1 Q1E13MOV8826B
[1 Q1E13MOV8827B 10.4 WHEN containment spray aligned for recirc, THEN start containment spray pumps IF secured due to RWST level less than 4.5 ft.
CS PUMP
[1 1A
[] lB 10.5 [CA] WHEN containment spray recirculation flow has been established for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, AND containment pressure is less than 16 psig, THEN stop both CS PUMPs.
Step 10 continued on next page.
Page 17 of 19
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: If Q1E11MOV88O9A & B are not closed, any makeup to the RWST would be pumped into the RCS by the RHR pumps rather than increasing RWST level. This could result in containment flooding.
10.6 Makeup to the RWST as necessary.
10.6.1 Makeup to the RWST in accordance with FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM.
OR 10.6.2 Consult TSC staff to determine alternate method of makeup to the RWST.
11 [CA] Determine criteria to be used for TRANSFER TO SIMULTANEOUS COLD AND HOT LEG RECIRCULATION requirements.
11.1 Check FNP-1-EEP-1, LOSS OF 11.1 Consult TSC to determine REACTOR OR SECONDARY COOLANT TRANSFER TO SIMULTANEOUS COLD procedure in effect. HOT LEG RECIRCULATION requirements.
12 Go to procedure and step in effect.
END Page 18 of 19
6/1/2011 15:09 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION I vision 22/2-09-20 1 START STEP CONTINUOUS ACTION LI 1 [CA] Check RWST level - GREATER THAN 4.5 ft.
1[R] IF alignment for recirculation is NOT imminent, THEN stop any pump taking suction from the RWST.
8.1 [CA] Monitor ECCS pump suction conditions - NO INDICATION OF CAVITATION.
9 [CA] Check containment spray.- IN OPERATION.
El 10 [CA] WHEN RWST level less than 4.5 ft. THEN align containment spray for recirculation.
10.5 [CA] WHEN containment spray recirculation flow has been established for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, AND containment pressure is less than 16 psig, THEN stop both CS PUMPs.
Page 19 of 19
6/1/2011 15:09 FNP-1-ESP-l.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 1 Close the following disconnects.
B Train Disconnects Disconnect Description Position Key Location TPNS No.
01R18B033-B Disconnect FV-T2 MOV 8884-B ON Z-91 01R18B034-B Disconnect FV-J2 MOV 8132B-B ON Z-89 01R18B035-B Disconnect FV-S2 MOV 8808B-B ON Z-86 139 hallway across from Q1R18B036-B Disconnect FV-B2 MOV 8889-B ON Z-88 chemistry sample room 01R18B041-B Disc for MOV 8130B-B ON Z-408 01R18B042-B Disc for MDV 8131B-B ON Z-412 Q1R18BO43-B Disc for MDV 8133B-B ON Z-416 Page 1 of 3
6/1/2011 15:09 FNP-1-E5P-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I I ATTACHMENT 1 2 Close the following disconnects.
A Train Disconnects Disconnect Description Position Key Location TPNS No.
01R18B030-A Disconnect FU-J2 MOV 8132A-A ON Z-2O3 01R18B029-A Disconnect FU-R2 MOV 8886-A ON Z-90 01R18BO38-A Disc for MOV 8130A-A ON Z-4O5 139 hallway across from 01R18B039-A Disc for MOV 8131A-A ON Z-410 MCC 1A 01R18B040-A Disc for MOV 8133A-A ON Z-415 Q1R18BO31 A Disconnect FU-Z3 MOV 88O8C-A ON Z-85 01R18B032-A Disconnect FU-Z2 MOV 88O8A-A ON Z-84 3 Verify recirculation valves MCB indication - POWER AVAILABLE.
[1 Q1E21MOV813OA
[1 Q1E21MOV813OB
[1 Q1E21MOV8131A
[1 Q1E21MOV8131B CHG PUMP DISCH HDR ISO
[1 01E21M0V8132A
[1 Q1E21MOV8132E
[1 01E21M0V8133A
[] Q1E21MOV8133B 1A(1B,1C) ACCUM DISCH ISO
[1 Q1E21MOV88O8A
[1 01E21M0V8808B I:] Q1E21MOV88O8C Step 3 continued on next page.
Page 2 of 3
6/1/2011 15:09 FNP-1-ESP-1.3 TRANSFER TO COLD LEG RECIRCULATION Revision 22 Step Action/Expected Response Response NOT Obtained I I ATTACHMENT 1 CHG PUMP RECIRC TO RCS HOT LEGS
[1 Q1E21MOV8884
[1 01E21M0V8886 RHR TO RCS HOT LEGS ISO
[1 Q1E11M0V8889 4 Notify control room of recircula-tion valve disconnect status.
END Page 3 of 3
FNP ILT-35 JPM Page 1 of 8 JPM I.
SO-430 B&C (Combined)
TITLE: MECHANICALLY ALIGN THE 1C SW PUMP TO THE B TRAIN AND SELECT THE 1C SW PUMP FOR B TRAIN AUTO START.
EVALUATION LOCATION: PLANT D CONTROL ROOM D CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A D ALTERNATE PATH D TIME CRITICAL Ii PRA JPM DIRECTIONS:
- 1. The actions of this task are to be SIMULATED.
- 2. Examinee will be provided a marked up copies of SOP-24.OD and SOP-24.0 Appendix 6.
- a. SOP-24.OD will be marked as follows:
- i. The situation requiring completion will be completed on the cover page.
ii. All applicable steps of section 1.0 will be marked as complete using current plant
- place-keeping.
iii. Step 2.7.2 and all of section 3.0 will be marked N/A as allowed by NOTES.
- b. SOP-24.0 Appendix 6 will be marked up as follows:
- i. All of step 2 will be marked N/A.
- 3. This Task is designed to be performed on UNIT 1. Due to the orientation of equipment and access to areas, concurrent performance of this JPM on both units should NOT be performed due to cueing of other examinees.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Select the 1 C SW pump for B Train auto-start per Appendix 6 of SOP-24.0 step 1.
o SAFETY sinificance: from the PRA-Huinan Rellabilitv Analysis:1O.36 JSWPMJCB---H: Oyerator Fails to Re-ali2n SWpniny JC to STBY Train REQUIRED to ensure PRA Margins.
Examinee:
Overall JPM Performance: Satisfactory EJ Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 2/23/20 12 NRC Approval SEE NUREG 1021 FORM ES-30l-3
FNP ILT-35 JPM JPM I. Page 2 of 8 (Guide pages = 7)
CONDITIONS When I tell you to begin, you are to MECHANICALLY ALIGN THE 1C SW PUMP TO THE B TRAIN AND SELECT THE 1C SW PUMP FOR B TRAIN AUTO START.
The conditions under which this task is to be performed are:
- a. An LOSP has occurred on Unit 1.
- b. 1D SW pump has tripped.
- d. You have KEY #1454 turned over to you from the team completing section 1.0 of SOP-24.OD.
- e. You are to complete aligning 1 C SW PUMP to B Train using SOP-24.OD section 2.0 and THEN select 1 C SW pump for B Train AUTO START per SOP-24.0 Appendix 6 section 1.0.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
NOTE:
- Element 1 contains two sets of valves, ONE valve in EACH set satisfies the CRITICAL ELEMENT, although BOTH are expected to be closed.
Multiple ELEMENTS/procedure steps will require Concurrent Verification. PROVIDE the following CUE whenlif a conculTent verification is requested.
CUE as required: A CONCURRENT VERIFICATION request is acknowledged, continue as though it were satisfied.
(SOP-24.OD step 2.1)
- 1. On Service Water Pumps lube and cooling S / U D LOCATE and CLOSE the header, close or verify closed the following following valves by turning valves: CLOCKWISE until stern travel
- 1C SW PUMP A TRN LUBE WTR HDR ISO, stops.
Q1P16V708.
- IC SW PUMP A TRN LUBE WTR HDR ISO, A TRN LUBE WTR HDR ISO
- 1C SW PUMP A TRN MTR CLG WTR HDR ISO, Q1P16V712. o V709
- IC SW PUMP A TRN MTR CLG WTR HDR ISO, Q1P16V713. A TRAIN MTR CLG WTR HDR ISO o V712 o V713
- NOTE: AT least one valve in each of the A CUE: the identified Valve(s) train flowpaths is REQUIRED for the operated as you described critical element of this task.
FNP ILT-35 JPM JPM I. Page 3 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(SOP-24.OD step 2.2)
- 2. Open or verify open the following valves: LOCATE and OPEN the S/U
- 1C SW PUMP B TRN LUBE WTR HDR ISO, following valves by turning QIPI6V7IO.
Counter-CLOCKWISE until
- IC SW PUMP B TRN LUBE WTR HDR ISO, Q1PI6V7I 1. stem travel stops, then back-off.
- 1C SW PUMP B TRN MTR CLG WTR HDR ISO, Q1P16V714. B TRN LUBE WTR HDR ISO
- 1C SW PUMP B TRN MTR CLG WTR HDR ISO, o V710 Q1P16V715. o V7l1 B TRAIN MTR CLG WTR HDR ISO o V714
- NOTE: BOTH valves in each of the B train o V715 flowpaths are REQUIRED for the critical element of this task. CUE: the identified Valve(s) operated as you described (SOP-24.OD step 2.3)
- 3. At the SW structure, close the following LOCATE and CLOSE the S/U breakers: following breakers by turning the OPERATING mechanism FK-C2, 1C SW PUMP TO A HDR ISO, Q1P16V507. COUNTER-CLOCKWISE.
FL-C2, 1C SW PUMP TO B HDR ISO, Q1P16V506.
o FK-C2 o FL-C2 CUE: the identified breaker(s) operated as you described (SOP-24.OD, step 2.4 and 2.5)
- 4. On the Main Control board close or verify closed LI Contact the MCR and direct S/U (verification may be performed locally if desired) perfonnance of step 2.4 & 2.5 IC SW PUMP TO A HDR ISO, QIP16V5O7. of SOP-24.OD.
On the main control board open or verify open Assuming the breakers were (verification may be performed CV locally if properly identified/operated.
desired) 1C SW PUMP TO B HDR ISO, Q1P16V506. CUE: The MCR acknowledges and reports that steps 2.4 & 2.5 are complete.
FNP ILT-35 JPM JPM I. Page 4 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(SOP-24.OD step 2.6)
- 5. At the SW structure, verify open the following LOCATE and OPEN the S / U breakers: following breakers by turning the OPERATING mechanism FK-C2, IC SW PUMP TO A HDR ISO, Q1P16V507. CLOCKWISE.
FL-C2, 1C SW PUMP TO B HDR ISO, Q1P16V506.
o FK-C2 o FL-C2 CUE: the identified breaker(s) operated as you described (SOP-24.OD, step 2.7.1)
- 6. IF desired, THEN place the IC Service Water Contact the MCR and direct S / U Pump on-service, performance of step 2.7 of SOP-24.OD.
CUE: Depending on location:
You hear the Pump start /breaker operate.
CUE: The MCR acknowledges and reports that this step is complete.
(SOP-24.OD, step 2.8)
- 7. IF desired to select 1C SW pump for B tm auto- Transitions to Appendix 6.
start, THEN perform Appendix 6.
FNP ILT-35 JPM JPM I. Page 5 of 8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(SOP-24.0 Appendix 6 step 1.1)
- 8. Verify that 1C SW pump is aligned mechanically Reviews Checklist 24.OD and S / U and electrically to B Train per sections 1.0 and identifies that this is 2.0 of System Checklist 24.OD. completed.
NOTE-1.2 identifies that if 1C pump is already running and step 1.2 may be marked N/A.
(SOP-24.0 Appendix 6 step 1.2)
Bump the I C Service Water Pump to verify that Marks step 1.2 N/A.
it will start and run normally.
(SOP-24.0 Appendix 6 step 1.3) U Marks step 1.3 as complete IF NOT obtained in section 1.0 of System key #1454 SUPPLIED IN Checklist 24.OD, THEN obtain Key #1454 from INITIAL CONDITIONS the Shift Support Supervisor. IF REQUIRED CUE: you have key #1454.
(SOP-24.0 Appendix 6 step 1.4) LOCATES and CHECKS the ON the UNIT ONE ATRAIN SPARE SW UNIT I A Train SW PUMP PUMP SELECTOR SWITCH, check the switch selector Switch is in the 1C in the 1C position. IF NOT, THEN stop and position.
notify the Shift Supervisor.
CUE: The switch is in the 1C positiol-1.
FNP LT-35 JPM JPM I. Page6of8 (Guide pages = 7)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(SOP-24.0 Appendix 6 step 1.5)
- 9. Insert Key #1454 into the UNIT ONE B *INSERTS the KEY into the S/U TRAIN SPARE SW PUMP SELECTOR UNIT ONE B TRAIN SWITCH lock. (Directly above spare pump SPARE SW PUMP selector switch.). SELECTOR SWITCH lock.
(SOP-24.0 Appendix 6 step 1.6) D *ROTATES the KEY in the Turn Key # 1454 clockwise. The key is now held CLOCKWISE direction.
in place. Select ID or I E SW position on the UNIT ONE B TRAIN SPARE SW PUMP
- POSITION the UNIT ONE SELECTOR SWITCH. B TRAIN SPARE SW PUMP SELECTOR SWITCH Record position selected. COUNTER-CLOCKWISE to the 1D SW position.
RECORDs ID SW CUE: the components operated as you described (SOP-24.0 Appendix 6 step 1.7)
- 10. Place a CAUTION TAG on the MCB B Train E REPORTS to the MCR. S/U handswitch for SW pump 1 C noting the auto start selector switch position.
CUE: That completes this JPM.
STOP TIME Terminate when task has been reported as complete.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-l-SOP-24.0, V 76.0
- 2. DRAWING: D1770133sh001
- 3. KIAs: 076A2.01 RO-3.5 SRO-3.7 076A2.02 RO-2.7 SRO-3.1
FNP ILT-35 JPM JPMI. Page7of8 (Guide pages = 7)
GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire:
- 1. A marked up copy of FNP-1-SOP-24.0 APPENIDIX 6 and Checklist 24.OD; mark up as described in INSTRUCTIONS.
Critical ELEMENT justification:
STEP Evaluation CRITICAL- TRAIN SEPARATION; failure to properly close AT LEAST ONE A TRN 1 isolation valve in EACH flowpath could result in making BOTH TRAINS of SW inoperable.
CRITICAL- Required for task completion; Failure to align cooling water to the 1C SW 2 pump would cause equipment damage and prevent the SW pump from satisfying its mission time.
CRITICAL- Required for task completion; TRAIN SEPARATION, energizing these 3
MOVs allows for proper alignment of the 1C SW.
CRITICAL- Required for task completion. Directing the action is required to 4
accomplish the alignment.
CRITICAL- Required for task completion; TRAIN SEPARATION, De-energizing these 5
MOVs is required for Appendix R concerns.
Not critical Directing this action is an if desired step and the control room will make the 6
determination start the 1 C SW pump or not.
Not critical these ai e placekeeping/check steps Components will be configui ed as 78 required.
CRITICAL- Required for task completion. KEY insertion/rotation is required to permit 9 operation of the selector switch. The selector switch position in the 1D position is the TASK OBJECTIVE to restore 1 C SW pump operability (PRA goal).
Not critical this step is non consequential to the task but is the natuial teimination point of 10 this task.
COMMENTS:
FNP ILT-35 JPM JPM SIMULATOR JPM A. HANDOUT Pg 1 of I CONDITIONS When I tell you to begin, you are to MECHANICALLY ALIGN THE 1C SW PUMP TO THE B TRAIN AND SELECT THE 1C SW PUMP FOR B TRAIN AUTO START.
The conditions under which this task is to be performed are:
- a. An LOSP has occurred on Unit I.
- b. 1D SW pump has tripped.
- d. You have KEY #1454 turned over to you from the team completing section 1.0 of SOP-24.OD.
- e. You are to complete aligning 1C SW PUMP to B Train using SOP-24.OD section 2.0 and THEN select IC SW pump for B Train AUTO START per SOP-24.0 Appendix 6 section 1.0.
02/15/12 06:07:54 FNP-1 -SOP-24.OD SYSTEM CHECKLIST SYSTEM CHECKLIST SOP-24.OD ALIGNING I C SW PUMP TO B TRAIN Situation Requiring Completion Of Check List:
1 D SW pump Tripped, Aligning IC SW pump to B Train and selecting it for Auto Start on B Train.
Verified by: Date Performed by: Date Reviewed by: Date This checklist consists of 5 pages 1 of 5 Version 76.0
02/15/12 06:07:54 FNP-1-SOP-24.OD SYSTEM CHECKLIST SYSTEM CHECKLIST SOP-24.OD ALIGNING IC SW PUMP TO B TRAIN 0 If 1C SW pump alignment is unknown, Section 3.0 of this procedure may be used to make that determination. Otherwise, section 3.0 will be N/A.
1.0 Electrical Alignment 1.1 The version of this Official Test Copy has been verified to be the current version for the task. (OR 1-98-498) 1.2 The version of this Official Test Copy has been verified to be the correct unit for the task. (OR 1-98-498) 2 1.3 IF 1C Service Water Pump is to be aligned for auto-start per Appendix 6, THEN obtain key #1454 from the Shift Support Supervisor.
2- 1.4 Stop or verify stopped IC Service Water Pump.
2_ 1.5 On the UNIT ONE A TRAIN SPARE SW PUMP SELECTOR SWITCH, CHECK the selector switch in the 1C position. IF NOT, THEN stop and notify the Shift Supervisor.
2.... 1.6 Open DC control power breaker for DKO5- 1, SERVICE WATER PUMP 1 C Q1PI 6MOO1C-AB.
N : During the performance of the following steps of racking out the breaker and removing it from the cubicle, special consideration should be given to prevent damage to the key or to the interlock. (OR 1-98-009)
Rack out circuit breaker DKO5-l, SERVICE WATER PUMP 1C Cv Q1P16MOO1C-AB to the DISC (disconnect) position.
1.8 Turn key #RE-11126 in mechanical interlock on circuit breaker DKO5-1, SERVICE WATER PUMP 1C Q1P16MOO1C-AB and remove key.
1.9 IF required for seismic considerations, THEN remove circuit breaker DKO5-1, SERVICE WATER PUMP IC Q1 P1 6M00 1 C-AB from the cubicle and take appropriate actions.
1.10 Insert key #RE- 11126 into mechanical interlock on SERVICE WATER PUMP IC 4KV DISC SW IA, QIR18A5OIA-A, and turn key. Key #RE-1 1126 is now held in place.
Page 1 of 5 Version 76.0
02/15/12 06:07:54 FNP- I -SOP-24.OD SYSTEM CHECKLIST 2i.i 1 Open SERVICE WATER PUMP 1C 4KV DISC SW 1A, Q1R18A5O1A-A cv and verify the position indicator reads SW OPEN.
1.12 Turn key #RE- 14226 in its mechanical interlock on SERVICE WATER PUMP 1C 4KV DISC SW 1A, Q1R18A5O1A-A and remove key. Disconnect 1A is now locked open.
1.13 Insert key #RE- 14226 into its mechanical interlock on SERVICE WATER PUMP 1C 4KV DISC SW 1B, QIRI8A5O1B-B, and turn key. Key #RE-14226 is now held in place.
Close SERVICE WATER PUMP 1C 4KV DISC SW 1B, Q1R18A5OIB-B CV and verify the position indicator reads SW CLOSED.
2.-. 1.15 Turn key #RE- 11119 in its mechanical interlock on SERVICE WATER PUMP 1C 4KV DISC SW 1B, Q1R18A5O1B-B and remove key. Disconnect switch lB is now locked closed.
N During the performance of the following steps of returning the breaker to the cubicle and racking it in, special consideration should be given to prevent damage to the key or to the interlock. (OR 1-98-008) 1.16 Rack or verify racked circuit breaker DLO5- 1, SERVICE WATER PUMP 1 C Q1P16MOO1C-AB to the DISC (disconnect) position.
1.17 Insert key #RE- 11119 into the mechanical interlock on circuit breaker DLO5- 1, SERVICE WATER PUMP 1C Q1P16MOO1C-AB, and turn key. Key #RE-1 1119 is now held in place.
Rack circuit breaker DLO5-1, SERVICE WATER PUMP 1C Q1P16MOO1C-AB cv to the connected position.
.19 Close DC control power breaker for DLO5-1, SERVICE WATER PUMP 1 C Cv Q1 P1 6M00 1 C-AB and verify breaker spring charges.
Page 2 of 5 Version 76.0
02/15/12 06:07:54 FNP- 1 -SOP-24.OD SYSTEM CHECKLIST 2.0 Mechanical Alignment 2.1 On Service Water Pumps lube and cooling header, close or verify closed the following valves:
/ 2.1.1 1C SW PUMP A TRN LUBE WTR HDR ISO, Q1P16V708.
cv
/ 2.1.2 1C SW PUMP A TRN LUBE WTR HDR ISO, Q1P16V709.
cv
/ 2.1.3 1C SW PUMP A TRN MTR CLG WTR HDR ISO, Q1P16V712.
cv
/ 2.1.4 1C SW PUMP A TRN MTR CLG WTR HDR ISO, Q1P16V713.
cv 2.2 Open or verify open the following valves:
/ 2.2.1 IC SW PUMP B TRN LUBE WTR HDR ISO, Q1P16V71O.
cv
/ 2.2.2 1C SW PUMP B TRN LUBE WTR HDR ISO, Q1P16V71 1.
cv
/ 2.2.3 1C SW PUMP B TRN MTR CLG WTR HDR ISO, Q1P16V714.
cv
/ 2.2.4 1C SW PUMP B TRN MTR CLG WTR HDR ISO, Q1P16V715.
cv 2.3 At the SW structure, close the following breakers:
Page 3 of 5 Version 76.0
02/15/12 06:07:54 FNP-1-SOP-24.OD SYSTEM CHECKLIST NOTE: 1C Service Water pump train A and B header isolation valves Q1P16V506 and Q1P16V507 should not be open or stroking simultaneously to prevent cross connection of trains.
/ 2.4 On the Main Control board close or verify closed (verification may be performed Cv locally if desired) IC SW PUMP TO A HDR ISO, Q1P16V507.
/ 2.5 On the main control board open or verify open (verification may be performed Cv locally if desired) 1C SW PUMP TO B HDR ISO, Q1P16V506.
2.6 At the SW structure, verify open the following breakers:
/
Cv
/
Cv NOTE: The next step preferred action is to start the 1C SW pump and place it on-service. If extenuating circumstances preclude placing the pump on-service, then bumping the pump is allowed with the shift supervisors permission 2.7 Perform one of the following:
2.7.1 IF desired, THEN place the 1C Service Water Pump on-service.
N/A 2.7.2 IF desired, THEN bump Service Water Pump 1 C 2.8 IF desired to select 1C SW pump for B tm auto-start, THEN perform Appendix 6.
Page 4 of 5 Version 76.0
02/15/12 06:07:54 FNP-1-SOP-24.OD SYSTEM CHECKLIST Checklist for determination of 1C SW pump alignment.
3.1 Record the position of the following components to determine 1 C SW pump alignment.
N/A per\
NOTE \ . UNIT ONE ATRAJN SPARE SW PUMP SELECTOR SWITCH.
- UNIT ONE BTRAIN SPARE SW PUMP SELECTOR SWITCH.
SERVICE WATER PUMP 1C4KV DISC SW 1B, Q1RI8A5OIB-B
- Ciit breaker DKO5-l Position
- Circuit bker DLO5-1 Position
sition
Positi
Page 5 of 5 Version 76.0
02/15/12 06:07:54 FNP- I -SOP-24.O APPENDIX 6 APPENDIX 6 SELECTING 1 C SW PUMP FOR B TRAIN AUTO-START Completed By: Date Reviewed By: Date This appendix consists of 2 pages Page 1 of 1 Version 76.0
02/15/12 06:07:54 FNP- I -SOP-24.0 APPENDIX 6 1M Selecting 1 C SW pump for B Train auto-start NOTES:
- The following steps may be performed even if 1C SW pump is already running.
- IF 1C SW pump is selected for auto-start in B Train, THEN the lB or the 1E SW pump it replaces will NOT sequence on following an SI or LOSP.
NOTE: If 1C SWP has been previously aligned to B train, THEN it is not necessary to perform Step 1.1 and may be marked N/A.
1.1 Verify that 1 C SW pump is aligned mechanically and electrically to B Train per sections 1.0 and 2.0 of System Checklist 24.OD.
NOTE: The following step is performed to ensure that the 1C SW Pump will start and run normally prior to selecting it for autostart. (OR 2-98-070) fl the 1C SW Pump is already running, THEN step 1.2 may be marked N/A.
1.2 Bump the 1 C Service Water Pump to verify that it will start and run normally.
1.3 IF NOT obtained in section 1.0 of System Checklist 24.OD, THEN obtain Key
- 1454 from the Shift Support Supervisor.
1.4 ON the UNIT ONE ATRAIN SPARE SW PUMP SELECTOR SWITCH, check the switch in the 1 C position. IF NOT, THEN stop and notify the Shift Supervisor.
NOTE: Key may only be inserted or removed if switch is in the 1C position.
1.5 Insert Key #1454 into the UNIT ONE B TRAIN SPARE SW PUMP SELECTOR SWITCH lock. (Directly above spare pump selector switch.)
1.6 Turn Key # 1454 clockwise. The key is now held in place. Select 1D or 1E SW CV position on the UNIT ONE B TRAIN SPARE SW PUMP SELECTOR SWITCH. Record position selected.
Position I.
I I
CAUTION: THERE IS NO INDICATION OR ALARM ON THE MCB FOR 1C PUMP AUTO-START SELECTOR SWITCH POSITION. I 1.7 Place a caution tag on the MCB B Train handswitch for SW pump 1 C noting the auto-start selector switch position.
Page 1 of2 Version 76.0
02/15/12 06:07:54 FNP- I -SOP-24.0 APPENDIX 6 2.0 Returning IC Service Water pump auto-start to normal.
NOTES: IF it is not desired to return the 1C SW Pump auto-start to normal, THEN section 2.0 may be marked N/A. (CR 2008109373)
HBF mm/ddlyy N/A 2.1 Record the position selected on the spare pump selector switch.
Position OTES: Steps 2.2 and 2.3 are performed to ensure that the de-selected B Train SW Pump will start and run normally prior to selecting it for autostart. (OR 2-98-070) IF the de-selected B Train SW Pump is already running, THEN steps 2.2 and 2.3 may be marked N/A.
2.2 Verify that the pump recorded in step 2.1 is aligned per System Checklist FNP-1 -SOP-24.OA.
2.3 Bump the B Train pump identified in step 2.1 to verify that it will start and run normally.
/ 2.4 On the UNIT ONE B TRAIN SPARE SW PUMP SELECTOR SWITCH, C place the switch in the 1 C position.
/ 2.5 On the UNIT ONE B TRAIN SPARE SW PUMP SELECTOR SWITCH, turn C key # 1454 counterclockwise and remove key.
2.6 Return key # 1454 to the Shift Support Supervisor.
2.7 Remove the caution tag from the MCB B Train handswitch for 1 C SW Pump.
Page 2 of 2 Version 76.0
FNP ILT-35 JPM Page 1 of 11 JPM J.
SO-35 1-Modified TITLE: PERFORM A MANUAL EMERGENCY START FOR A 4075 KW DG IN MODE 4.
EVALUATION LOCATION: J PLANT LI CONTROL ROOM LI CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL XI PRA JPM DIRECTIONS:
- 1. The actions of this task are to be SIMULATED.
- 2. Examinee will be provided a copy of SOP-38. 1.
- 3. This Task is designed to be performed on ANY of the 4075 kW DGs. This is to facilitate minimizing impact to a PROTECTED TRAIN component.
- 4. There is a separate STUDENT HANDOUT for each DG to ensure there is NO confusion when providing the task. PROVIDE the examinee ONLY the desired handout.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- START the assigned 4075 kW DG in MODE 4 using the AIR START Solenoid override.
- ENERGIZE the 1G 4160V AC Bus from the Diesel Local Control Panel.
o SAFETY si2nificance: from the PRA-Human Reliability Analysis:
10.11 IDGCBOPCLOSE-H, OPERA TOR FAILS TO MANUALLY CLOSE D/G OUTPUT BRKR Examinee:
Overall JPM Performance: Satisfactory 11 Unsatisfactory C Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 2/23/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNPILT-35JPM JPMJ. Page2ofll (Guide pages = 8)
CONDITIONS When I tell you to begin, you are to PERFORM A MANUAL EMERGENCY START FOR A 4075 KW DG IN MODE 4.
EXAMINER, IDENTIFY and SELECT the DO on which this task will be performed:
l-2A DO PROVIDE HANDOUT l-2A; x=1 in the elements below Er lB DO PROVIDE HANDOUT 1B; x 2 in the elements below LI 2B DO PROVIDE HANDOUT 2B; x = 3 in the elements below The conditions under which this task is to be performed are:
- a. A Loss of ALL AC has occurred on Unit 1 (or 2 if 2B is being operated).
- c. The (select one) 1-2A I lB / 2B DO is the only DO available.
- d. Attempts to start the Diesel Oenerator from the EPB have been unsuccessful.
- e. No Damage to the DO has occurred.
- f. You are to perform a manual Emergency Start of the (select one) 1 -2A I lB I 2B DO AND close the output breaker from the Diesel Local Control Panel per SOP-38.1, Emergency Starting of a Diesel Oenerator.
INITIATINO CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
(4.x.1)
- 1. Check engine for any apparent damage caused LI Using initial conditions OR by S / U during starting attempts. performing a walk around of the diesel this task is satisfied.
CUE: as you see it (4.x.2)
- 2. Verify at least one receiver greater than 150 psig. LI CHECKS one or both air S / U receiver pressure instruments.
CUE: as you see it
FNP ILT-35 JPM JPM J. Page 3 of 11 (Guide pages = 8)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.x.3)
- 3. Prime fuel oil system using hand pump. LOCATES and OPERATES S/U the fuel priming pump by stroking back and forth until resistance is felt.
CUE: you feel resistance (4.x.4)
- 4. Position Mode 4 selector switch to Mode 4 position.
- ON the DG LCP, S/U POSITION the Mode 4 selector switch to the MODE NOTE: a KEY IS NOT required to perform this 4 position by turning the ACTION, though if requested provide the switch CLOCKWISE.
following CUE: You are the DG Building System Operator and have the watchstation o OBSERVES that the RED keys. MODE 4 LIGHT is LIT CUE: The switch operates as described, the RED light above the switch is LIT (4.x.5)
- 5. Verify the following for 4160V bus to be supplied by El Utilizes initial conditions or S / U diesel generator (on EPB or locally at switchgear): CALLS the MCR to validate 41 60V bus is de-energized.
the 4160V bus is DE
- Supply breakers to IF/i G/2G (as applicable for this task) 4160V bus are open. Energized.
If required CUE: The 4l6OV bus is de-energized as required.
(4.x.6)
- 6. Verify Essential Protection Auxiliary Relay (86A) is El Checks RED light above 86A S / U reset. (on diesel local relay panel) RELAY LIT.
If required CUE: The RED light above 86A RELAY is LIT or it is how you see it.
FNP ILT-35 JPM JPM J. Page 4 of 11 (Guide pages = 8)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.x.7)
- 7. Depress Engine Reset pushbutton (on diesel local DEPRESS the Engine RESET S / U control panel). pushbutton on the DGLCP.
If required CUE: Alarm window 43 is clear.
CAUTION: Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
(4.x.8)
- 8. WHEN at least 140 seconds has elapsed since all Li Waits .2 mins S / U engine shutdown signals have been reset (Engine Reset) THEN check Ready for Auto Start light CUE: 140 secs have elapsed.
illuminated on diesel local control panel.
CHECKS READY for AUTO Start light illuminated.
If required CUE: The LIGHT is LIT (4.x.9)
- 9. IF Ready for Auto Start light is NOT illuminated, N/As step 4.x.9 S / U THEN verify barring device is NOT inserted (annunciator 54 NOT illuminated).
NOTE: Element 10 should be evaluated as NOT APPLICABLE, However if the actions are performed the examinee should return to Element 7.
Performing this iteration DOES NOT DAMAGE any equipment since the DG does not start.
IF this iteration continues to occur, it would be considered as NOT making PROGRESS and at 2 Times the validation time of the JPM, the JPM could be TERMINATED.
FNP ILT-35 JPM JPM J. Page 5 of 11 (Guide pages = 8)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.x.10)
- 10. IF desired to start the 1 -2A Diesel Generator from the LI IDENTIFIES that step 4.x.10 S/U Diesel Local Control Panel with the selector switch is NOT Applicable per the in Mode 4, THEN perform the following: conditions provided and
- Depress and hold START pushbutton. proceeds to step 4.x.l1.
- WHEN diesel is running or start failure occurs, THEN release START pushbutton.
HOWEVER, if these actions ARE PERFORMED:
If required then CUE: there is
- IF diesel fails to start, THEN return to step 4.x.7. no response, to your actions.
LI RETURN to element/step
- 7.
NOTE: ONLY one AIR START SOLENOID is required to be overridden to satisfy the START conditions required by the diesel and OPERATING ONLY one would satisfy the CRITICAL portion of Element 11; although the procedure requires both air start solenoids to be overridden simultaneously.
(4.x.1 1)
- 11. IF desired to perform a manual Emergency Start of LI *LOCATES BOTH air start S / U the l-2A Diesel Generator, THEN perform the solenoids and override tool.
following:
Place air start solenoid override tool in position on *POSITIONS override tool LI each end of engine (two operators required).
with the PIN in the hole and
- Simultaneously pull down and hold both air start the hook on the PIVOT point.
solenoid override tools.
fl *Coordinates operation with
- WHEN engine starts, or approximately 7 seconds another operator to has elapsed, THEN release and remove both air DEPRESS on the override start solenoid override tools. tool.
- IF the 1 -2A Diesel fails to start, THEN return to If required then CUE: A second step 4.x.7.
operator will perform as you direct him to WHEN the override tool is depressed, CUE:
The diesel STARTS
FNPILT-35JPM JPMJ. Page6ofll (Guide pages = 8)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.x.1 1.5)
- 12. Perform the following at the 1-2A DIESEL LOCAL CHECKS DG Voltage. S / U CONTROL PANEL:
CUE: Voltage is 4150V
- Adjust generator voltage to 4160V using JJ{J55 DG voltage by AUTOMATIC VOLTAGE ADJUST switch. rotating the Automatic Voltage adjust switch
- Adjust generator frequency 60 Hz using SPEED CLOCKWISE to RAISE.
CONTROL switch.
CUE: Voltage is 4160 V D CHECKS DG Frequency.
CUE: Frequency is 61 Hz
- ADJUSTS DG frequency by rotating the SPEED CONTROL switch COUNTER-CLOCKWISE to LOWER.
CUE: Frequency is 60 Hz.
(4.x.1 1.6)
- 13. IF DESIRED to shift control of diesel generator to LI This step is N/A. S / U the EPB, THEN unlock the MODE 4 selector switch and select the OFF position.
FNP ILT-35 JPM JPM J. Page 7 of 11 (Guide pages = 8)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.x.1 1.7)
- 14. IF DESIRED to control the diesel generator at the CLOSES the output breaker S/U DLCP, THEN perform one of the following: by rotating the GEN BREAKER CONTROL
-IF aligning the 1 -2A DG to Unit 1, THEN energize SWITCH UNIT 1 (2 if 2B DG the dead iF 4160V AC Bus using the GEN is being operated)
BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel. CLOCKWISE to CLOSE.
-IF aligning the 1 -2A DG to Unit 2, THEN energize o OBSERVES breaker is the dead 2F 41 60V AC Bus using the GEN closed by red light lit and BREAKER CONTROL SWITCH UNIT No. 2 on the Green Light NOT lit.
diesel local control panel.
CUE: GREEN LIGHT is NOT LIT, RED LIGHT is LIT.
(4.x.1 1.8)
- 15. Verify the 1 -2A Diesel Generator is supplied from at LI CONTACT the MCR and S/U least one SW pump. direct this action!report the DG has been started.
CUE: That completes this 1PM START TIME:
Terminate when task has been reported as complete. 1 CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. PROCEDURE: FNP-1-SOP-38.1, V 17.0
- 2. K/As: 064A2.05 RO-3.1 SRO-3.2 056AA2.21 RO-3.6 SRO-3.8 055EA1.02 RO-4.3 SRO-4.4
FNPILT-35JPM JPMJ. Page8ofll (Guide pages = 8)
GENERAL TOOLS AND EOUIPMENT:
Provide/Acciuire:
- 1. A copy of FNP-1-SOP-38.l.
Critical ELEMENT justification:
STEP Evaluation 1- 2 Not critical this step is a check step 3 Not critical this step is a check step failuie to piirne the fuel oil system should not pievent successful completion of this task.
4 CRITICAL- Required for task completion; Failure to perform this action would prevent any further successful actions.
5 Not cntical this step is a check step this condition is established upon start of the task 6 Not cntical this step is a check step, this condition is established upon start of the task 7-8 CRITICAL- Required for task completion; Failure to complete this action would prevent RESETING the DO S/D relay and this would in turn prevent the fuel racks from opening and simply deplete the available starting air; thus preventing future success.
9-10 Not critical, these actions ai e N/A however if element 10 is performed it will require a return to element 7. This action can occur multiple times without failure, however progress is no longer being made and the double the validation time would become the termination point for this task.
11 CRITICAL- Required for task completion; Though it is expected that BOTH be located and coordinated operation be done per procedure, locating/operating ONLY one air start solenoid would be sufficient to start the DO under these conditions, and therefore this is the minimum required to satisfy the CRITICAL component of this element.
12 Not critical failui e to establish pi opei speed/voltage would not pi event i estoi ation of the ESF components.
13 Not critical this step is NOT applicable 14 CRITICAL- Required for task completion; Operation of this breaker completes the task and restores AC power to the ESF bus (PRA required action).
15 Not critical Under the conditions of this task, the ESF sequencer would operate immediately upon closing the DO output breaker and automatically align Service water.
THIS however is a natural termination point for this JPM.
COMMENTS:
FNPILT-35JPM JPMJ. 1-2A DG HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM A MANUAL EMERGENCY START A 4075 KW DG IN MODE 4.
The conditions under which this task is to be performed are:
- a. A Loss of ALL AC has occurred on Unit 1.
- d. Attempts to start the Diesel Generator from the EPB have been unsuccessful.
- e. No Damage to the diesel has occurred.
- f. You are to perform a manual Emergency Start of the 1 -2A DG AND close the UNIT I output breaker from the Diesel Local Control Panel per SOP-38.l.
FNPILT-35JPM JPMJ. lB DG HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM A MANUAL EMERGENCY START FOR A 4075 KWDG IN MODE 4.
The conditions under which this task is to be performed are:
- a. A Loss of ALL AC has occurred on Unit 1.
- d. Attempts to start the Diesel Generator from the EPB have been unsuccessful.
- e. No Damage to the diesel has occurred.
- f. You are to perform a manual Emergency Start of the lB DG AND close the output breaker from the Diesel Local Control Panel per SOP-38.1.
FNPILT-35JPM JPMJ. 2B DG HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to PERFORM A MANUAL EMERGENCY START A 4075 KW DG IN MODE 4.
The conditions under which this task is to be performed are:
- a. A Loss of ALL AC has occurred on Unit 2.
- d. Attempts to start the Diesel Generator from the EPB have been unsuccessful.
- e. No Damage to the diesel has occurred.
- f. You are to perform a manual Emergency Start of the 2B DG AND close the output breaker from the Diesel Local Control Panel per SOP-38. 1.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 1 of 18 15:11:07 DIESEL GENERATOR S
A F
E T
Y EMERGENCY STARTING OF A DIESEL GENERATOR R
E L
A T
E D
PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: February 24, 2012 Operations Manager
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 2 of 18 15:11:07 DIESEL GENERATOR Procedure Version Description Version Number Version Description 14.0 Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions 15.0 Al 2009209977 16.0 Changed guidance for performing M4 start of2C DG. CR 389904.
Separated the guidance for each DG to make the procedure more specific.
17.0 1. Sect 4.5 Reordered steps for electrically aligning 2C DIG
- 2. Sect 4.5 Removed IF option from local breaker closure for 2C D/G
- 3. Removed IF/THEN & WHEN/THEN THEN statements
- 4. Pg 14 Step 4.4.9 & Pg 16 Step 4.5.10 Deleted Annunciator location 54 check
- 5. Pg 14 Step 4.4.9 & Pg 16 Step 4.5.10 Removed requirement for IF Ready For Auto Start Light NOT lit for verifying barring device removed
Procedure Number Ver S HARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 3of 18 15:11:07 DIESELGENERATOR Table of Contents Page 1.0 PURPOSE 4 2.0 INITIAL CONDITIONS 4 3.0 PRECAUTION AND LIMITATIONS 4 4.0 INSTRUCTIONS 5 4.1 Mode 4 Emergency start of the 1-2A DIG 5 4.2 Mode 4 Emergency start of the 1 B D/G 8 4.3 Mode 4 Emergency start of the 2B D/G 11 4.4 Mode 4 Emergency start of the IC D/G 14 4.5 Mode 4 Emergency start of the 2C D/G 16
5.0 REFERENCES
18
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 4of 18 15:11:07 DIESELGENERATOR 1.0 PURPOSE 1.1 This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for emergency operation of a diesel generator.
2.0 INITIAL CONDITIONS 2.1 Diesel generator(s) are required for operations and can not be started using normal starting methods.
2.2 If starting an opposed piston DG (1C or 2C) AND oil temperature has decreased to less than lOOT with the keep warm lube oil system in service, then cylinders have been blown down and engine barred over.
2.3 Obtain the following keys as required to restore their respective DG to EPB control from Mode 4 control (located on the Diesel Building SO key ring and in the SSS office):
Key# Tab# Key Name 12B288 B29 1-2A DG Mode 3-4 Sel Switch 12B822 B30 lB DG Mode 3-4 Sel Switch 12B160 B31 IC DG Mode 3-4 Sel Switch 12B160 B32 2C DG Mode 3-4 Sel Switch 10B629 U2 Key Locker 2B DG Mode 3 4 Sel Switch 3.0 PRECAUTION AND LIMITATIONS 3.1 To ensure adequate air start capacity is maintained for one additional start, start attempts should be minimized if the engine turns over but fails to start. One air receiver should be maintained greater than 150 psig for the 4075 kW DGs or greater than 90 psig for the 2850 kW DGs 3.2 When a Diesel Generator is started and Service Water is not available due to a dead bus, actions should be taken to energize the bus and start two Service Water pumps as soon as possible. Diesel generators are only capable of operating 3 minutes without cooling water flow.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP..38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 5oflS 15:11:07 DIESELGENERATOR 4.0 INSTRUCTIONS 4.1 Mode 4 Emergency start of the 1 -2A DIG.
4.1.1 Check engine for any apparent damage caused during starting attempts.
4.1.2 Verify at least one receiver greater than 150 psig.
4.1.3 Prime fuel oil system using hand pump.
4.1.4 Position Mode 4 selector switch to Mode 4 position. LI 4.1.5 Verify the following for 4160V bus to be supplied by diesel generator (on EPB or locally at switchgear):
4.1.5.1 if aligning 1-2A DC to Unit 1, verify the following:
- 1 F 4160V bus is de-energized.
- Supply breakers to iF 4160V bus are open o Normal supply, Q1R15BKRDFO1 open.
o Alternate supply, Q1R15BKRDF15 open.
4.1.5.2 H aligning 1-2A DC to Unit 2, verify the following:
- 2F 4160V bus is de-energized.
- Supply breakers to 2F 4160V bus are open o Normal supply, Q2R15BKRDFO1 open.
o Alternate supply, Q2R15BKRDF15 open.
4.1.6 Verify Essential Protection Auxiliary Relay (86A) is reset.
(on diesel local relay panel) 4.1.7 Depress Engine Reset pushbutton (on diesel local control panel).
CAUTIONS
- After resetting engine shutdown signals, the Ready for Auto Start light is delayed for 140 seconds for 4075 kW DC.
- Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
4.1.8 WHEN at least 140 seconds has elapsed since all engine shutdown signals have been reset (86A and Engine Reset), check Ready for Auto Start light illuminated on diesel local control panel.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 6of 18 15:11:07 DIESELGENERATOR 4.1.9 IF Ready for Auto Start light is NOT illuminated, verify barring device is NOT inserted (annunciator 54 NOT illuminated).
CAUTIONS
- Repeated start attempts should be minimized if engine turns over but fails to start to ensure adequate air start capacity.
- To ensure adequate air start capacity is maintained for one additional start, one air receiver should be maintained greater than 150 psig for 4075 kW DG.
- When a Diesel Generator is started and Service Water is not available due to a dead bus, action should be taken to energize the bus and start two Service Water pumps as soon as possible.
Diesel generators are only capable of operating 3 minutes without cooling water flow.
4.1.10 IF desired to start the 1-2A Diesel Generator from the Diesel Local Control Panel with the selector switch in Mode 4, perform the following:
4.1.10.1 Depress and hold START pushbutton.
4.1.10.2 WHEN diesel is running Qj start failure occurs, release START pushbutton.
4.1.10.3 lFdieselfails to start, return to step 4.1.7. LI 41.10.4 Perform the following at diesel local control panel:
4.1.10.4.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch. LI 4.1.10.4.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch.
4.1.10.5 IF DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.1.10.6 IF DESIRED to control the diesel generator at the DLCP, perform the following:
4.1.10.6.1 E aligning the 1-2A Diesel Generator to Unit 1, energize the dead 1F416OVAC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel. LI 4.1.10.6.2 E aligning the 1-2A Diesel Generator to Unit 2, energize the dead 2F 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel.
4.1.10.7 Verify the 12A Diesel Generator is supplied from at least one SW pump. LI
SHARED Farley Nuclear Plant A Procedure Number Ver FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 7of18 15:11:07 DIESELGENERATOR 4.1.11 IF desired to perform a manual Emergency Start of the 1 -2A Diesel Generator, perform the following:
4.1.11.1 Place air start solenoid override tool in position on each end of engine (two operators required). LI 4.1.11.2 Simultaneously pull down and hold both air start solenoid override tools. LI 4.1.11.3 WHEN engine starts, OR approximately 7 seconds has elapsed, release and remove both air start solenoid override tools. LI 4.1.11.4 IF the 1-2A Diesel fails to start, return to step 4.1.7. LI 4.1.11.5 Perform the following at the 1-2A DIESEL LOCAL CONTROL PANEL:
4.1.11.5.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.1.11.5.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch. LI 4.1.11.6 IF DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.1.11.7 IF DESIRED to control the diesel generator at the DLCP, perform one of the following:
4.1.11.7.1 E aligning the 1-2A DG to Unit 1, energize the dead iF 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel.
4.1.11.7.2 IF aligning the 1-2A DG to Unit 2, energize the dead 2F 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel.
4.1.11.8 Verify the 1-2A Diesel Generator is supplied from at least one SW pump.
SHARED Farley Nuclear Plant A Procedure Number Ver FNP-0-SOP-38.1 17.0 Page Number 2/2812012 EMERGENCY STARTING OF A 8of 18 15:11:07 DIESELGENERATOR 4.2 Mode 4 Emergency start of the 1 B DIG.
4.2.1 Check engine for any apparent damage caused during starting attempts.
4.2.2 Verify at least one receiver greater than 150 psig.
4.2.3 Prime fuel oil system using hand pump.
4.2.4 Position Mode 4 selector switch to Mode 4 position.
4.2.5 Verify the following for 1G 4160V bus (on EPB or locally at switchgear):
- 1G 4160V bus is de-energized.
- Supply breakers to 1G 4160V bus are open o Normal supply, Q1R15BKRDG15 open.
o Alternate supply, Q1R15BKRDGO1 open.
4.2.6 Verify Essential Protection Auxiliary Relay (86A) is reset.
(on diesel local relay panel) 4.2.7 Depress Engine Reset pushbutton (on diesel local control panel).
CAUTIONS
- After resetting ji engine shutdown signals, the Ready for Auto Start light is delayed for 140 seconds for 4075 kW DG.
- Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
4.2.8 WHEN at least 140 seconds has elapsed since all engine shutdown signals have been reset (86A and Engine Reset) check Ready for Auto Start light illuminated on diesel local control panel.
4.2.9 IF Ready for Auto Start light is NOT illuminated, verify barring device is NOT inserted (annunciator 54 NOT illuminated).
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0.SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 9of 18 15:11:07 DIESELGENERATOR CAUTIONS
- Repeated start attempts should be minimized if engine turns over but fails to start to ensure adequate air start capacity.
- To ensure adequate air start capacity is maintained for one additional start, one air receiver should be maintained greater than 150 psig for 4075 kW DG.
- When a Diesel Generator is started and Service Water is not available due to a dead bus, action should be taken to energize the bus and start two Service Water pumps as soon as possible.
Diesel generators are only capable of operating 3 minutes without cooling water flow.
4.2.10 IF desired to start the lB Diesel Generator from the Diesel Local Control Panel with the selector switch in Mode 4, perform the following:
4.2.10.1 Depress and hold START pushbutton.
4.2.10.2 WHEN diesel is running Qj3, start failure occurs, release START pushbutton.
4.2.10.3 IF diesel fails to start, return to step 4.2.7.
4.2.10.4 Perform the following at diesel local control panel:
4.2.10.4.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.2.10.4.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch. LI 4.2.10.5 IF DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.2.10.6 IF DESIRED to control the diesel generator at the DLCP, energize the dead 1G 416OVAC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel.
4.2.10.7 Verify the lB Diesel Generator is supplied from at least one SW pump.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A lOofl8 15:11:07 DIESELGENERATOR 4.2.11 IF desired to perform a manual Emergency Start of the 1 B Diesel Generator, perform the following:
4.2.11.1 Place air start solenoid override tool in position on each end of engine (two operators required).
4.2.11.2 Simultaneously pull down and hold both air start solenoid override tools.
4.2.11.3 WHEN engine starts, OR approximately 7 seconds has elapsed, release and remove both air start solenoid override tools.
4.2.11.4 fl the 1 B Diesel fails to start, return to step 4.2.7.
4.2.11.5 Perform the following at the 1 B DIESEL LOCAL CONTROL PANEL:
4.2.11.5.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.2.11.5.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch 4.2.11.6 IE DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.2.11.7 IF DESIRED to control the diesel generator at the DLCP, energize the dead 1G 416OVAC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel.
4.2.11.8 Verify the lB Diesel Generator is supplied from at least one SW pump
S HARED Farley Nuclear Plant A Procedure Number Ver FNP-O-SOP38. 1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 11 of 18 15:11:07 DIESELGENERATOR 4.3 Mode 4 Emergency start of the 2B DIG.
4.3.1 Check engine for any apparent damage caused during starting attempts.
4.3.2 Verify at least one receiver greater than 150 psig.
4.3.3 Prime fuel oil system using hand pump.
4.3.4 Position Mode 4 selector switch to Mode 4 position.
4.3.5 Verify the following for 2G 4160V bus (on EPB or locally at switchgear):
- 2G 4160V bus is de-energized.
- Supply breakers to 2G 41 60V bus are open o Normal supply, Q2R15BKRDGI5 open.
o Alternate supply, Q2R15BKRDGO1 open.
4.3.6 Verify Essential Protection Auxiliary Relay (86A) is reset.
(on diesel local relay panel) 4.3.7 Depress Engine Reset pushbutton (on diesel local control panel).
CAUTIONS
- After resetting j[ engine shutdown signals, the Ready for Auto Start light is delayed for 140 seconds for 4075 kW DG,
- Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
4.3.8 WHEN at least 140 seconds has elapsed since all engine shutdown signals have been reset (86A and Engine Reset) check Ready for Auto Start light illuminated on diesel local control panel.
4.3.9 IF Ready for Auto Start light is NOT illuminated, verify barring device is NOT inserted (annunciator 54 NOT illuminated).
SHARED Farley Nuclear Plant A Procedure Number Ver FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 12of18 15:11:07 DIESELGENERATOR CAUTIONS
- Repeated start attempts should be minimized if engine turns over but fails to start to ensure adequate air start capacity.
- To ensure adequate air start capacity is maintained for one additional start, one air receiver should be maintained greater than 150 psig for 4075 kW DG.
- When a Diesel Generator is started and Service Water is not available due to a dead bus, action should be taken to energize the bus and start two Service Water pumps as soon as possible.
Diesel generators are only capable of operating 3 minutes without cooling water flow.
4.3.10 IF desired to start the 2B Diesel Generator from the Diesel Local Control Panel with the selector switch in Mode 4, perform the following:
4.3.10.1 Depress and hold START pushbutton.
4.3.10.2 WHEN diesel is running OR start failure occurs, release START pushbutton.
4.3.10.3 H diesel fails to start, return to step 4.3.7.
4.3.10.4 Perform the following at diesel local control panel:
4.3.10.4.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.3.10.4.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch.
4.3.10.5 E DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.3.10.6 IF DESIRED to control the diesel generator at the DLCP, energize the dead 2G 416OVAC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel.
4.3.10.7 Verify the 2B Diesel Generator is supplied from at least one SW pump.
Procedure Number Ver S HARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A l3of 18 15:11:07 DIESELGENERATOR 4.3.11 IF desired to perform a manual Emergency Start of the 2B Diesel Generator, perform the following:
4.3.11.1 Place air start solenoid override tool in position on each end of engine (two operators required).
4.3.11.2 Simultaneously pull down and hold both air start solenoid override tools.
4.3.11.3 WHEN engine starts, OR approximately 7 seconds has elapsed, release and remove both air start solenoid override tools.
4.3.11.4 IF the 2B Diesel fails to start, return to step 4.3.7.
4.3.11.5 Perform the following at the 2B DIESEL LOCAL CONTROL PANEL:
4.3.11.5.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.3.11.5.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch.
4.3.11.6 IF DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position. El 4.3.11.7 IF DESIRED to control the diesel generator at the DLCP, energize the dead 2G 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel. El 4.3.11.8 Verify the 2B Diesel Generator is supplied from at least one SW pump. El
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 iTO Page Number 2/28/2012 EMERGENCY STARTING OF A 14of18 15:11:07 DIESELGENERATOR 4.4 Mode 4 Emergency start of the 1 C DIG.
4.4.1 Check engine for any apparent damage caused during starting attempts.
4.4.2 Verify at least one receiver greater than 90 psig.
4.4.3 Prime fuel oil system using hand pump.
4.4.4 Position Mode 4 selector switch to Mode 4 position.
4.4.5 Verify the following for 4160V bus to be supplied by diesel generator (on EPB or locally at switchgear):
4.4.5.1 if aligning 1 C DG to Unit 1, verify the following:
- 1 H 4160V bus is de-energized.
- Supply breakers to IF 4160V bus are open o Normal supply, Q1R15BKRDFO1 open. LI o Alternate supply, Q1R15BKRDF15 open. LI 4.4.5.2 E aligning 1C DG to Unit 2, verify the following:
- 2H 4160V bus is de-energized.
- Supply breakers to 2F 4160V bus are open o Normal supply, Q2R15BKRDFO1 open. LI o Alternate supply, Q2R15BKRDF15 open. LI 4.4.6 Verify Essential Protection Auxiliary Relay (86A) is reset.
(on diesel local relay panel) 4.4.7 Depress Engine Reset pushbutton (on diesel local control panel).
CAUTIONS
- After resetting all engine shutdown signals, the Ready for Auto Start light is delayed for 100 seconds for 2850 kW DG.
- Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
4.4.8 WHEN at least 100 seconds has elapsed since all engine shutdown signals have been reset (86A and Engine Reset) check Ready for Auto Start light illuminated on diesel local control panel.
4.4.9 Verify barring device is NOT inserted.
Procedure Number Ver S HARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A l5of 18 15:11:07 DIESELGENERATOR CAUTIONS
- Repeated start attempts should be minimized if engine turns over but fails to start to ensure adequate air start capacity.
- To ensure adequate air start capacity is maintained for one additional start, one air receiver should be maintained greater than 90 psig for 2850 kW DG.
- When a Diesel Generator is started and Service Water is not available due to a dead bus, action should be taken to energize the bus and start two Service Water pumps as soon as possible.
Diesel generators are only capable of operating 3 minutes without cooling water flow.
4.4.10 IF desired to start the IC Diesel Generator from the Diesel Local Control Panel with the selector switch in Mode 4, perform the following:
4.4.10.1 Depress and hold START pushbutton.
4.4.10.2 WHEN diesel is running Q start failure occurs, release START pushbutton.
4.4.10.3 IF diesel fails to start, return to step 4.4.7.
4.4.10.4 Perform the following at diesel local control panel:
4.4.10.4.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.4.10.4.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch.
4.4.10.5 ffl DESIRED to shift control of diesel generator to the EPB, unlock the MODE 4 selector switch and select the OFF position.
4.4.10.6 E DESIRED to control the diesel generator at the DLCP, perform the following:
4.4.10.6.1 IF aligning the 1C Diesel Generator to Unit 1, energize the dead 1H 416OVAC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. I on the diesel local control panel.
4.4.10.6.2 i.E aligning the 1C Diesel Generator to Unit 2, energize the dead 2H 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel.
4.4.10.7 Verify the 1C Diesel Generator is supplied from at least one SW pump. E
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A l6of 18 15:11:07 DIESELGENERATOR 4.5 Mode 4 Emergency start of the 2C DIG.
4.5.1 Verify 2C MODE SELECTOR SWITCH in Mode 1 position. LI 4.5.2 Check engine for any apparent damage caused during starting attempts. LI 4.5.3 Verify at least one receiver greater than 90 psig. LI 4.5.4 Prime fuel oil system using hand pump. LI 4.5.5 Position Mode 4 selector switch to Mode 4 position. LI 4.5.6 Verify the following for 4160V bus to be supplied by diesel generator (on EPB or locally at switchgear):
4.5.6.1 IF aligning 2C DG to Unit 1, verify the following:
- 1J 4160V bus is de-energized.
- Supply breakers to 1G 4160V bus are open o Normal supply, QIR15BKRDG15 open. LI o Alternate supply, QIR15BKRDGOI open. LI 4.5.6.2 jE aligning 2C DG to Unit 2, verify the following:
- 2J 4160V bus is de-energized.
- Supply breakers to 2F 4160V bus are open o Normal supply, Q2RI5BKRDGI5 open.
o Alternate supply, Q2R15BKRDGO1 open.
4.5.7 Verify Essential Protection Auxiliary Relay (86A) is reset.
(on diesel local relay panel) LI 4.5.8 Depress Engine Reset pushbutton (on diesel local control panel). LI CAUTIONS
- After resetting all engine shutdown signals, the Ready for Auto Start light is delayed for 100 seconds for 2850 kW DG.
- Attempting to start an engine prior to completion of the time delay will result in the engine trying to start with fuel racks closed, causing a loss of starting air.
4.5.9 WHEN at least 100 seconds has elapsed since all engine shutdown signals have been reset (86A and Engine Reset), check Ready for Auto Start light illuminated on diesel local control panel.
4.5.10 Verify barring device is NOT inserted.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP..38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 17of18 15:11:07 DIESELGENERATOR CAUTIONS
- Repeated start attempts should be minimized if engine turns over but fails to start to ensure adequate air start capacity.
- To ensure adequate air start capacity is maintained for one additional start, one air receiver should be maintained greater than 90 psig for 2850 kW DG.
- When a Diesel Generator is started and Service Water is not available due to a dead bus, action should be taken to energize the bus and start two Service Water pumps as soon as possible.
Diesel generators are only capable of operating 3 minutes without cooling water flow.
4.5.11 IF desired to start the 2C Diesel Generator from the Diesel Local Control Panel with the selector switch in Mode 4, perform the following:
4.5.11.1 Depress and hold START pushbutton. El 4.5.11.2 WHEN diesel is running OR start failure occurs, release START pushbutton.
4.5.11.3 IF diesel fails to start, return to step 4.5.8.
4.5.11.4 Perform the following at diesel local control panel:
4.5.11.4.1 Adjust generator voltage to 4160V using AUTOMATIC VOLTAGE ADJUST switch.
4.5.11.4.2 Adjust generator frequency to 60 Hz using SPEED CONTROL switch.
4.5.11.5 Perform the following for the desired Unit alignment:
4.5.11.5.1 IF aligning the 2C Diesel Generator to Unit 1, energize the dead 1J 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 1 on the diesel local control panel. El 4.5.11 .5.2 aligning the 2C Diesel Generator to Unit 2, energize the dead 2J 4160V AC Bus using the GEN BREAKER CONTROL SWITCH UNIT No. 2 on the diesel local control panel. LI 4.5.11.6 IF DESIRED to shift control of diesel generator to the EPB, perform the following:
4.5.11.6.1 Verify 2C MODE SELECTOR SWITCH in Mode 1 position.
4.5.11.6.2 Unlock the MODE 4 selector switch and select the OFF position.
4.5.11.7 Verify the 2C Diesel Generator is supplied from at least one SW pump.
Procedure Number Ver SHARED Farley Nuclear Plant FNP-0-SOP-38.1 17.0 Page Number 2/28/2012 EMERGENCY STARTING OF A 18of18 15:11:07 DIESELGENERATOR
5.0 REFERENCES
5.1 FN P-0-SOP-38.0, Diesel Generators 5.2 FNP-l-ECP-0.O, Loss Of All Ac Power 5.3 FNP-2-ECP0.O, Loss Of All Ac Power 5.4 Technical Specification 3.8.3 5.5 D172550, D172551, D172552, D172554, D172774, D172778, D172782, D172793, D172763, D202551, D202778 END OF PROCEDURE TEXT
FNP LT-35 JPM Page 1 of 8 JPM K.
SO-372B modified TITLE: Initiate a #2 WMT RELEASE PER SOP-5O.1, APP. 2.
EVALUATION LOCATION: Ll PLANT D CONTROL ROOM CLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: N/A ll ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:
- 1. The actions of this task are to be SIMULATED.
- 2. The Exarninee will be provided at the start of the JPM a copy of SOP-50.1, Appendix 2 and a RELEASE permit that is marked up as follows:
- a. SOP-50.1, appendix 2 all actions through step 4.4.9 are complete.
- b. RELEASE permit is filled out as required by SOP-SO. 1.
- 3. When needed, and after the examinee identifies the location of the ARP in the plant, then a copy of the ARP window 14 response will be provided by the examiner.
- 4. This Task is designed to be performed on UNIT 1.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
. Initiate a liquid release using SOP-50. 1, Appendix 2, and
- Upon alarm of RCV-1 8, terminate the release using ARP-13.2 window 14 guidance.
o SAFETY si,viificance: Termination ofRadioactive Release when exceeding RELEASE Permit limits; protecting health and safety ofpublic.
Examinee:
Overall JPM Performance: Satisfactory 11 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Howard Fitzwater Date: 3/05/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP ILT-35 JPM JPM J. Page 2 of 8 (Guide pages = 6)
CONDITIONS When I tell you to begin, you are to Initiate a #2 WMT RELEASE PER SOP-50.l, APP. 2.
The conditions under which this task is to be performed are:
- a. SOP-50. 1, App. 2, has been completed up to the Liquid Waste Release section.
- b. The Unit 1 #2 WMT has been recirculated and sampled and has been authorized for release by chemistry.
- c. Liquid waste release permit No. XXX.012.YYY.L has been issued.
- d. You have the watchstation keys.
- e. The #2 WMT level is 90%.
- f. All instrumentation is operable.
- g. You are to commence the #2 WMT Release per SOP-50. 1, appendix 2 on UNIT 1.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
START TIME:
(4.4.9)
- 1. Open WMT DISCH TO ENVIRONMENT, E On the LWPP POSITION S / U N1G21V1 13 (1-LWP-RCV-18). hand-switch for RCV-18 to OPEN.
o OBSERVES RED light LIT; GRN light Dark.
CUE: the RED light above the hand-switch is LIT, Green light is dark.
NOTE: Concurrent Verification is required for Element 2; IF/WHEN required provide the following CUE: Concurrent Verification Request acknowledged, Continue as though it were satisfied.
FNP ILT-35 JPM JPM J. Page 3 of 8 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.4.10)
- 2. Unlockandopen#2WMTDISCH,QIG21V114(1- LOCATEandUNLOCK S / U LWP-V-7448) using the Master Z key. Vi 14.
OPEN VI 14 by turning COUNTER-Clockwise until motion stops then 4- V 2 turn off backseat.
CUE: the valve operates as you described (4.4.11)
- 3. Obtain max release rate from CHM FORM 1700.1, IDENTIFIES from the S / U Liquid Waste Release Permit, Part II, and record. RELEASE permit that the
- m. maximum flowrate is 50 gpm.
(4.4.11.1)
Subtract 5 gpm from max release rate entered in CALCULATES the MAX Step 4.4.11. RATE per step 4.4.11.1 is gpm-5gpm= 45gpm.
(Step 4.4.11) (MAX RATE)
(4.4.12)
IF WMT FI-1085A is operable, THEN Slowly and Throttles throttle open #2 WMT Pump Disch, N1G21VIO8A OPEN V1O8A by turning (1-LWP-V-7443A) until FI-1085B or the totalizer handwheel COUNTER-processor RATE display indicates the desired release rate, not to exceed the MAX RATE calculated Clockwise.
in Step 4.4.11.1 above.
MONITORS FI-i085A while opening V1O8A.
El *STOPS throttling open when flow rate approaches 45 gpm.
CUE provide RISING flow rate cues correlating to the operation of the valve (between 0 and 45 gpm).
The flow indicated is gpm.
(4.4.13)
- 4. IF WMT Fl-i 085B is inoperable, THEN perform E This step is N/A the following [...]
FNPILT-35JPM JPMJ. Page4of8 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(4.4.14)
- 5. RECORD the following information on release LI Documents RELEASE start S / U permit: time on permit.
- Release start time.
LI LOCATES FI-1085A and/or
- Release flow rate.
flow totahzer RATE and RECORDS flowrate.
CUE: The display indicates 40 gpm.
LI Documents RELEASE flowrate on the permit.
NOTE: Local indication may be used from LIQUID RADWASTE DISCHARGE INDICATOR, NID1 lRIOl8, located on the liquid waste panel.
(4.4.15)
- 6. IF R-18 is operable, THEN record monitor RE-18 LI WAITS 10 minutes S / U count rate 10 minutes into discharge on release permit. CUE: 10 minutes has elapsed.
LI LOCATES and Reads R-18 reading on the LWPP.
OR LI May call the CR and ask for R- 18 reading.
CUE: R-18 indication is 55000 cprn and rapidly rising.
Annunciator window 14 is in alarm NOTE to
- ONCE the examinee identifies where ARP- 13.2 is located, then provide to the student the final examiner: handout.
- Element 7 lists the expected response, however, any of the following actions will effectively terminate the release and are acceptable:
o CLOSE RCV-0l8 o CloseVll4 o Close V1O8A o STOP the WMT pump
FNPILT-35JPM JPMJ. Page5of8 (Guide pages = 6)
ELEMENTS: STANDARDS: RESULTS:
(CIRCLE)
(ARP-13.2 window 14)
- 7. AUTOMATIC ACTIONS: CHECKS RCV-018 closed S / U Closes liquid waste release valve 1 -LWP-RCV- by LIGHT status above hand 018 (N1G21VI 13). switch on LWPP.
OPERATOR ACTION: CUE: the RED LIGHT is LIT,
- Ensure automatic actions have occurred. the GREEN light is DARK El OPERATES the hand-switch for RCV-018 by placing it in the CLOSE position.
If required CUE: The GREEN LIGHT is LIT, the RED light is DARK
CUE: That completes this JPM.
START TIME:
Terminate when the release is terminated and MCR is informed. I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
I. PROCEDURE
- FNP-I-SOP-50.1, V 69.5 FNP-l-ARP-13.2, v 9.0
- 2. K/As: 068A2.04 RO-3.3 SRO-3.3 068A3.02 RO-3.6 SRO-3.6
FNP ILT-35 JPM JPM J. Page 6 of 8 (Guide pages = 6)
GENERAL TOOLS AND EQUIPMENT:
Provide/Acciuire:
- 1. A copy of FNP-1-SOP-50.1 appendix 2, marked up as described in the Instructions.
- 2. WHEN required, a copy of ARP-13.2 window 14 response will be provided.
Critical ELEMENT justification:
STEP Evaluation 1- 2 CRITICAL- Required for task completion; Failure to perform this action would prevent any further successful actions.
3 CRITICAL- Required for task completion; Failure to perform this action correctly could result in either:
- NOT completing the assigned task or
- exceeding release limits.
4 Not critical this step is not applicable for the conditions provided 56 Not critical these steps ai e documentation steps Failure to propei ly complete these steps will not affect any subsequent actions. This action is a convenient time to insert the ALTERNATE PATH failure.
7 CRITICAL- Required for task completion; Failure to complete this task will allow for a RADIOACTIVE release to continue. The CRITICAL portion of this task is to terminate the RELEASE; there are several success mechanisms for this activity.
Error Not critical, This is a natural termination point for this task Reference source not found.
COMMENTS:
FNPILT-35JPM JPMJ. HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to Initiate a #2 WMT RELEASE PER SOP-50.1, APP. 2.
The conditions under which this task is to be performed are:
- a. SOP-50. 1, App. 2, has been completed up to the Liquid Waste Release section.
- b. The Unit 1 #2 WMT has been recirculated and sampled and has been authorized for release by chemistry.
- c. Liquid waste release permit No. XXX.012.YYY.L has been issued.
- d. You have the watchstation keys.
- e. The #2 WMT level is 90%.
- f. All instrumentation is operable.
- g. You are to Initiate the #2 WMT Release per SOP-50. 1, appendix 2 on UNIT 1.
FNP ILT-35 JPM JPM J. HANDOUT Pg 2 of 2 LIQUID WASTE RELEASE PERMIT PARLEY NUCLEAR PLANT Unit I LWRP# XXX.012.YYY.L PART I: ANALYSIS REQUEST DISCHARGE SOURCE TANK #2 WMT Date Todays a. Tank Content 4i)i (gal) d. Recite start hhMM Time Todays b. Recite Rate_ _ (gpm) e. Sample After hhMM + 237 mins Initials PEW c. Recite Time Minimum (2xa/b) 237 (mm)
- f. Reviewed by: j]
SOP 50.1 OTC ii Todays date and time PART EL: PRE-RELEASE CALCULATIONS (CI-IM)
Unit # j_ Tank # Sampled @ XXXX Recite Duration 74 (mm)
RE- 18 Background QQ cpm (must exceed PART I c. Limit)
Maximum Permissible Release Rate 50 GPM Possible Release Conditions and Dose Projections SEE ATTACHMENTS SPECIAL C9ITIONS: Set RE-I 8 to 55.000 cpm prior to release. Reset RE-18 to 7900 cnm after Use 20.000 onm di1iifin f1nxT ID of Sample, Prerelease & LWRP Verified Composite Stored By and Release Approved By j__
Shift Radiochemist Date/Time MM/DDfY hh:mm PART EU: ACTUAL RELEASE DATA (OPS)
Dilution Flow Rate gpm Monitor Trip Setpoint 10,000 cpm Tank Flow Rate gpm Calibration Due Date / /
Totalizer Tank Level Date Time (gal)
Dilut WMT s 4500 148643 000 Finish Net Monitor Reading 10 minutes into Discharge cpm Monitor Reading Afler Plush cpm Discharge Completed By Data Reviewed By DateiTime PART TV: Release Records Update (CBM)
Actual Release Conditions and Dose Calculations SEE ATTACHMENTS Data Updated & Checked By___________ Date/Time /
CHM Form 1700.1
11/25/08 07 43 59 FNP-1-ARP-13 2 LOCATION 14 SETPOINT: Variable As specified on Liquid Waste Release Permit.
WATER DISCHARGE ORIGIN: Radiation Monitor R- 18 LINE HI-RAD PROBABLE CAUSE High radiation level in liquid waste effluent.
AUTOMATIC ACTION Closes liquid waste release valve 1 -LWP-RCV-01 8 (Ni G2 iVi I 3).
OPERATOR ACTION
- 1. Ensure automatic actions have occurred.
References:
D-175042; U-216157 Page 1 of 1 Version 9.0
UNIT I Farley Nuclear Plant A Procedure Number Ver FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 22 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT Performed by: Date:
Verified by: Date:
Reviewed by: Date:
This appendix consists of 14 pages
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 23 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 1 of 14)
NOTES This procedure and the liquid waste release permit, when issued, must be in the possession of the systems operator at all times during the performance of this procedure.
Each step must be signed off immediately after completion of that step.
10 Purpose This appendix provides the Initial Conditions, Precautions, Limitations, and Instructions for the Waste Monitor Tank 2 release to the environment.
2.0 Initial Conditions 2.1 The version of this procedure has been verified to be the current version. (OR 1-98-498) 2.2 The version of this procedure has been verified to be the correct unit for the task. (OR 1-98-498) 2.3 Waste monitor tank 2 is aligned per system check list FNP-1-SOP-50.1A, Liquid Waste Processing System Liquid Waste Release from Waste Monitor Tank.
3.0 Precautions and Limitations 31 Either WMT FLOW TOTALIZER, (NIG21FQI1O85) OR #2 WMT LI, (N1G21LIS1O83) should be operable to discharge a WMT. If both instruments are inoperable, the Shift Support Supervisor should be notified.
3.2 If the WMT FLOW TOTALIZER, (Ni G21 FQI 1085) is out of service, the totalizers reading may be derived from the #2 WMT LI, (N1G21LIS1O83). One gallon discharged from the WMT equals one gallon on the WMT totalizer. (Either the WMT totalizer or the WMT level indication should be operable.)
3.3 If the #2 WMT LI (N1G21LIS1O83) is out of service, the volume released (Net Tank Level) may be derived from the net INVENT totalizer reading or the TOTAL totalizer reading.
3.4 If the SERVICE WATER DILUTION FLOW TOTALIZER, (Ni P16FR41O7) is out of service, the dilution totalizer reading may be derived by taking the average dilution flowrate during the release, multiplying this by the release duration (net time), and dividing by 10,000. Each totalizer integration equals 10,000 gal of water.
Procedure Number Ver UNIT i Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 24 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 2 of 14) 3.5 Either the SERVICE WATER DILUTION FLOW TOTALIZER, (N1P16FR41O7) or the SW DILUTION FLOW RECORDER, (N1P16FR41O7) should be operable to discharge a WMT. If both instruments are inoperable, then the Shift Support Supervisor should be notified.
3.6 Technical Specification 5.5.1 and Chapter 2 of FNP-0-M-01 1, Offsite Dose Calculation Manual, are applicable to the WASTE MONITOR PUMP DISC, (N1G2IFI1O85B) and the SW DILUTION FLOW RECORDER, (N1P16FR41O7).
3.7 Initial each step as completed. Instructions for completion of liquid waste release permit are specified in FNP-0-CCP-212, Liquid Waste Release Program.
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 25 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 3 of 14) 4.0 Instructions N
Initial each step as completed. lnstructio s for completion of liquid waste release permit are specified in FNP-0-CCP-212, Liquid Waste Release Program.
DO NOT enter the TEST/CALIB or the PARAM SET modes of the WMT totalizer processor. Any changes in these modes will affect the channel calibration.
4.1 Determine recirculation flowpath.
4.1.1 IF waste monitor tank 2 is to be recirculated through the N/A Demineralizer, THEN proceed to Step 4.2.
4.1.2 H normal recirculation is to be used, THEN proceed to Step 4.3.
Qf)
Recirculation time through the demineralizers does not count towards recirculation time necessary to obtain a representative sample. Section 4.3 must be performed.
(Ref. FNP-1-CCP-212)
L jy)one tank may be recirculated through the demineralizer at a time.
tIWf1T is aligned for recirc through the demin while WCT is being pumped to the f94sosable Demineralizer System, then the two tanks will be cross-connected.
4.2 Recirculate through Demineralizer as follows:
4.2.1 Verify FDT STRAINER DISCH, NIG2IVII8(1-LWP-V-7421)
CLOSED.
4.2.2 Start #2 WMT PUMP, N1G21POO6A.
4.2.3 Close EDT DISCH TO WASTE EVAP, Q1G21V267 (1 -LWP-V-7427).
4.2.4 Close #2 WMT DEMIN BYP, QIG2I VI 25 (1-LWP-V-7428).
4.2.5 Open EDT FILTER OUTLET, Q1G2I Vi 89 (1-LWP-V-7456).
Procedure Number Ver UNIT i Farley Nuclear Plant FNP..1SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 27 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 5 of 14) 4.2.20 Close WMT DEMIN DISCH TO #2 WMT, QIG21VO93B (1 -LWP-V-7438B). N I44 4.2.21 Close FDT TO WMT DEMIN, Q1G21VO91B (1 -LWP-V-7452B).
4.2.22 Open FDT DISCH TO WASTE EVAP, Q1G21V267 (1 -LWP-V-7427).
4.2.23 Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428).
4.2.24 Close EDT FILTER OUTLET, Q1G21 Vi 89 (1-LWP-V-7456).
4.2.25 Go To Step 4.3 for recirculation to obtain sample.
4.3 Align normal recirc to #2 WMT as follows:
4.3.1 Close #2 WMT INLET ISO, Q1G21V135 (i-LWP-V-7429).
4.3.2 Verify #2 WMT PUMP DISCH, Ni G21V1O8A (1 -LWP-V-7443A), CLOSED.
4.3.3 Start #2 WMT PUMP, Ni G21 POO6A.
4.3.4 Record #2 WMT pump discharge pressure from WASTE MONITOR PUMP DISCHARGE PRESSURE INDICATOR, NiG2iPliO84B.
115 psig 4.3.5 IF pressure recorded in Step 4.3.4 114 psig and 118 psig, THEN continue with 4.3.6, IF NOT, the flow value specified in Step 4.3.6 is NOT conservative and will have to be re-determined using Appendix 3 prior to proceeding with this release.
4.3.6 Recirculate tank contents for a minimum of two (2) tank volumes based on the following flow rate and the volume of liquid in the tank.
Flow Rate 38 gpm Recirculation Time hr.
23 mm.
4.3.7 Verify sample has been drawn and analyzed after required recirculation time. r CHEM
Procedure Number Ver UNIT i Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 28 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 6 of 14) 4.3.8 Proceed to Step 4.4.
4.4 Liquid Waste Release 4.4.1 Liquid waste release permit number XXX.O12YYY.L has been issued.
4.4.2 Calculate time that tank low level and pump shutoff will occur by using the following formula.
Time (minutes) = A 750 (cial)
B A = Quantity of liquid to be released from permit, gal.
B = Expected Release rate, gal/mm.
750 gal = pump lo lo level trip setpoint 4.4.3 Shift Support Supervisor has performed a review of the release permit and has verified that #2 WMT is the tank to be released.
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.i 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 29 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 7 of 14)
With R-1 8 out of service, FNP-0-M-01 1 ,te Dose Calculation Manual Chapter 2 should be referred to for release limitations.
4.4.4 fl LIQ WASTE DISCH R-18 is operable, THEN perform test on LIQ WASTE DISCH R-18 per the following:
4.4.4.1 H operable, THEN verify RR-0200 (point RR-18) recorder in operation.
4.4.4.2 Verify meter responds in the top scale direction on channel R-18 by inserting check source.
4.4.4.3 11 check source is NOT sufficient, THEN notify Health Physics source check with a portable source.
4.4.4.4 H RR-0200 (point RR-i 8) recorder is operable, THEN verify source check caused on upscale on point RR-18.
4.4.4.5 Document R-18 source check in FNP-1-STP-i.0, Operations Daily and Shift Surveillance Requirements.
4.4.4.6 Verify the following valves are LOCKED CLOSED.
- #1 WMT DISCH, Q1G2I Viii (1-LWP-V-7446)
- #2 WMT DISCH, Q1G21V114 (1-LWP-V-7448) 4.4.4.7 Coordinate with the Control Room to perform test on LIQ WASTE DISCH R-i 8 per Section 4.3 of the procedure body.
4.4.5 H R-i8 is operable, THEN adjust the monitor setpoint for RE-18 to the value obtained from the discharge permit and the pot setting in Unit I Volume Ill Curve R18.
P0 LSD IV
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 30 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 8 of 14)
If the Service Water dilution flow recorder is out of service, then the limitations of FNP-0-M-01 1, Offsite Dose Calculation Manual Chapter 2 apply.
4.4.6 Verify the dilution flow rate is greater than or equal to the minimum, as stated in Part II of the liquid waste release permit. (Utilize the largest dilution flow which can practically be attained.)
4.4.7 H the WMT totalizer is operable, THEN 4.4.7.1 Verify the DISPLAY light is lit. IF not lit, THEN depress the DISPLAY pushbutton.
4.4.7.2 Depress the TOTAL pushbutton AND verify the display reads TOT GAL in the message display.
4.4.7.3 Reset the numeric display to 0 by depressing the TOTAL RESET pushbutton.
4.4.8 Record the following information on the release permit.
- Tank level.
- Waste monitor tank totalizer
- SW dilution totalizer vft
- R18 setpoint.
4.4.9 Open WMT DISCH TO ENVIRONMENT, NIG2IVI13 (1 -LWP-RCV-1 8).
4.4.10 Unlock and open #2 WMT DISCH, Q1G21V114 (1.tWP-V-7448) using the Master Z key.
CV
Procedure Number Ver UNIT i Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 31 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 9 of 14) 4.4.11 Obtain max release rate from CHM FORM 1700.1, Liquid Waste Release Permit, Part II, and record. gpm.
4.4.11.1 Subtract 5 gpm from max release rate entered in Step 4.4.11.
gpm-Sgpm=
(Step 4.4.11) (MAX RATE) 4.4.12 IF WMT Fl-i 085A is operable, THEN slowly open #2 WMT PUMP DISCH, N1G21V1O8A (1-LWP-V-7443A) until Fl-i 085A OR the totalizer processor RATE display indicates the desired release rate, not to exceed the MAX RATE calculated in Step 4.4.11.labove.
4.4.13 IF WMT Fl-i 085A is inoperable, THEN perform the following:
4.4.13.1 Subtract 10 gpm from max release rate entered in Step 4.4.11.
gpm - 10 gpm =
(Step 4.4.11) (MAX RATE) 4.4.13.2 Determine minimum pump discharge pressure corresponding to the MAX RATE entered in Step 4.4.13.1, using Table 1 and record.
psig 4.4.13.3 Slowly throttle open #2 WMT PUMP DISCH, N1G21V1O8A (1-LWP-V-7443A) such that pump discharge pressure does drop below the pressure recorded in Step 4.4.13.2.
4.4.14 Record the following information on release permit:
- Release start time
- Release flow rate
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SORSO.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 32 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 10 of 14)
NOTE Local indication may be used from LIQUID RADWASTE DISCHARGE INDICATOR, N1D11RIO18, located on the liquid waste panel.
4.4.15 IF R-18 is operable, THEN record monitor RE-18 count rate 10 minutes into discharge on release permit.
4.4.16 Verify pump tripped at low level set point or secure pump.
4.4.17 Close WMT DISCH TO ENVIRONMENT, N1G21RCV18 (N1G21V1 13).
4.4.18 Perform the following:
4.4.18.1 Record the following information on the release permit:
- Release stop time
- SW dilution totalizer
- WMT totalizer
- Final tank level 4.4.18.2 Record the following information on the WMT flow recorder paper:
- Release stop time
- Release date 4.4.19 Close and lock #2 WMT DISCH Q1G21V114 (1 -LWP-V-7448).
4.4.20 Close #2 WMT PUMP DISCH, N1G21V1O8A (1 -LWP..V-7443A).
Procedure Number Ver UNIT I Farley Nuclear Plant FNP1SOP.50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 33 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page ii of 14) 4.4.21 the EDT OR WECT is being pumped to #1 WMT, THEN verify #2 WMT INLET ISO Q1G21V135 (1-LWP-V-7429) is closed.
4.4.22 the EDT OR WECT is NOT being pumped to #1 WMT, THEN verify #2 WMT INLET ISO, Q1G21V135(i-LWP-V-7429)is open.
4.4.23 INDEPENDENTLY verify #2 WMT DISCH Qi G21 Vi 14 (1 -LWP-V-7448) LOCKED CLOSED.
Iv 4.5 Obtain the pre-release background count rate on R-18 from Liquid Waste Release Permit and record cpm.
4.6 IF the post-release count rate is greater than the pre-release count rate, THEN back flush radiation monitor R-18 as follows:
4.6.1 Close WMT DISCH TO ENVIRONMENT ISO, N1G21V281.
4.6.2 Open R-18 FLUSHING DRN, N1G21V283.
4.6.3 Attach hose between R-18 DW FLUSH SUPP, N1P11VO24 and DW BACK FLUSH CONN, Q1G21V112 (1-LWP-V-7447).
4.6.4 Open R-i8 DW FLUSH SUPP, NIP1IVO24.
4.6.5 Open DW BACK FLUSH CONN, Q1G2IVI12 (1 -LWP-V-7447).
4.6.6 Throttle open R-i8 DW FLUSH ISO, N1P11VO66.
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 34 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 12 of 14)
CAUTION Leaving the R-18 FLUSHING DRN, N1G21V283 closed, with R-18 DW FLUSH ISO, NI P1 1V066 throttled open could over pressurize the flushing water supply hose.
4.6.7 While flushing for a minimum of 5 minutes, cycle R-18 FLUSHING DRN, N1G21V283 open and closed several times to ensure the chamber volume is filled completely.
4.6.8 WHEN 5 minutes have elapsed, THEN contact the control room for the R-1 8 background reading and compare it to the reading recorded in Step 4.5.
4.6.8.1 IF the post flush reading is the same or less than the reading recorded in Step 4.5, THEN secure flushing.
4.6.8.2 if the reading on RR-0200 (point RR-18) recorder is above pre-release levels, THEN continue flushing for an additional 5 minutes.
4.6.8.3 Record post flush background count rate cpm 4.6.8.4 if the reading on RR-0200 (point RR-18) recorder is above pre-release levels by a factor of two, THEN generate a CR for Chemistry to evaluate the condition of RE18 due to the change in background count rate fj.Q determine if the detector needs cleaning.
(Al2005204200) 4.6.8.5 IF the background count rate exceeds 7900 cpm, THEN generate a CR to have the R18 detector cleaned.
4.6.9 Close R-18 DW FLUSH SUPP, NIPIIVO24.
4.6.10 Close R-18 DW FLUSH ISO, N1PI1VO66.
4.6.11 Close DW BACK FLUSH CONN, QIG2IV1I2 (1 -LWP-V-7447).
4.6.12 Close R-18 FLUSHING DRN, N1G21V283.
Procedure Number Ver UNIT i Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 35 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 13 of 14) 4.6.13 Disconnect both ends of hose between R-18 DW FLUSH SUPP, N1P11V024 and DW BACK FLUSH CONN, QI G21 Vi 12 (1-LWP-V-7447).
4.6.14 Ensure proper FME covers are in place after flushing of RE-18 is completed. (Al 2008207655) 4.6.15 Open WMT DISCH TO ENVIRONMENT ISO, N1G21V281.
NOTE Local indication may be used from LIQUID RADWASTE DISCHARGE INDICATOR, N1D11RIO18 located on the liquid waste panel.
4.7 HZ R-i8 is operable, THEN 4.7.1 Observe R-18 count rate for approximately two minutes.
4.7.2 Record the highest observed count rate on the release permit.
4.7.3 Complete all applicable post release information.
4.8 IF R-i8 is operable, THEN reset R-i8 to the value specified on the release permit.
P0 IV
Procedure Number Ver UNIT I Farley Nuclear Plant FNP-1-SOP-50.1 69.5 LIQUID WASTE PROCESSING SYSTEM Page Number 2/15/2012 06:10:48 LIQUID WASTE RELEASE FROM WASTE 36 of 55 MONITOR TANK APPENDIX 2 WASTE MONITOR TANK 2 RELEASE TO THE ENVIRONMENT (Page 14 of 14)
TABLE I
- 2 WMT PUMP DISCHARGE PRESSURE VS. RELEASE FLOW RATE RELEASE FLOW RATE DISCH PRESSURE (PSIG) 117 5.0 116 6.0 115 7.0 114 9.0 113 11.0 112 13.0 111 14.0 110 17.0 109 19.0 108 21.0 107 22.5 106 24.5 105 26.5 104 29.0 103 30.0 102 31.0 101 32.5 100 34.5 99 36.5 98 38.0 97 39.5 96 41.0 95 42.0 94 43.5 93 45.5 92 47.0 91 48.0