ML14084A048
| ML14084A048 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/21/2014 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-269/13-302, 50-270/13-302, 50-287/13-302, ES-D-1 50-269/13-302, 50-270/13-302, 50-287/13-302 | |
| Download: ML14084A048 (122) | |
Text
Appendix D Scenario Outline Form ES-D-1 ILT44 NRC Exam Facility: Oconee Scenario No.: 1 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO
________________________ ________________________OATC
________________________ ________________________BOP Initial Conditions:
- Reactor Power = 100% Unit 2: 100%, Unit 3: 100%
Turnover:
- Reactor power at 100%
- Pressurize LDST with Hydrogen
- SASS in Manual Event Malfunction Event Event Type* Description No. No.
0a Override SASS in Manual 0b Override` 1HP-24 failed closed 1 Pressurize LDST with H2 (1H-1 will fail open Override C: BOP, SRO (TS) requiring LDST vent to return to acceptable LDST pressure) 2 Override C, BOP, SRO HPSW Jockey Pump trips MPI 281, 3 I: OATC, SRO Tc Controller Fails HIGH (A Loop Hot) 68%
4 MPS061, 10 C, BOP, SRO 1A Letdown Cooler Leak MSI070 5 I: OATC, SRO 1A SG Outlet Pressure Fails HIGH MSI261 60 gpm leak in 1A SG requiring a manual power 6 MPS010,1.3 R: OATC, SRO (TS) reduction MSS010 MSS020 Loss of Main and Emergency Feedwater 7 MSS260 M: ALL LOHT Tab MSS270 CBP feed MSS330 CBPs trip requiring HPI Forced cooling 8 Override ALL 1HP-24 will not open Transfer to HPI CD Tab
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 1 Page 1 of 3 Event
Description:
Pressurize LDST with Hydrogen (TS)
Time Position Applicant's Actions or Behavior Crew response:
- Direct the BOP to add H2 to the LDST using OP/1/A/1106/017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition).
SRO/BOP
- Enclosure 4.5 (Unit 1 LDST H2 Addition) will:
2.1 Notify Chemistry of hydrogen addition prior to adding hydrogen.
NOTE:
- OP/0/A/1108/001 (Curves And General Information) and computer may be referred to for LDST Pressure vs. Level curve.
- LDST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LDST.
2.2 Immediately prior to pressurization determine lowest reading of diverse LDST level indications: _85.2__ inches.
2.3 For existing LDST level determine LDST Pressure allowable per LDST Pressure vs. Level curve: _42_ psig.
2.4 Notify Operator at H2 Cage to pressurize primary hydrogen.
NOTE: Operator should be in constant communication with CR to close 1H-26 if 1H-1 fails open.
BOOTH CUE: When directed to open 1H-26, use Manual Valves and position 1H-93 approximately 20% open 2.5 Direct Operator to open 1H-26 (LDST Block).
2.6 Direct Operator in field to monitor explosive detector.
2.7 Cycle 1H-1 (LDST SUPPLY) as required to pressurize LDST per LDST Pressure vs Level curve.
Examiner Booth Note: Once LDST pressure is being increased, 1H-1 (LDST SUPPLY) will fail open.
2.8 WHEN Hydrogen addition complete, ensure closed 1H-1(LDST SUPPLY).
This event is complete when LDST pressure has been returned to the acceptable range and the SRO has made the Tech Spec determination OR as directed by lead examiner.
Page 2 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 1 Page 2 of 3 Event
Description:
Pressurize LDST with Hydrogen (TS)
Time Position Applicant's Actions or Behavior Plant response:
- LDST pressure will continue to increase.
SRO/BOP
Examiner Note: 1H-26 will not be closed until LDST pressure is outside acceptable range.
- Refer to the ARG.
- Verify LDST pressure/level are within the acceptable operating region of SRO the LDST PRESSURE vs. LEVEL enclosure in OP/0/A/1108/001 (Curves and General Information).
IF necessary, vent LDST to GWD per OP/1/A/1104/002 (HPI System).
- LDST PRESSURE vs. LEVEL enclosure in OP/0/A/1108/001 (Curves and General Information) directs the following: (See curve on page 34)
- If LDST Pressure vs. Level is above and to the left of Curve 1, then SRO/BOP declare BOTH trains of HPI INOPERABLE.
o Immediately depressurize LDST below Curve 1.
o Refer to TS 3.0.3 for shutdown requirements.
o Make notifications as required by OMP 1-14 (Notifications).
SRO Applicable Tech Specs:
3.5.2 Condition C (Action C.3) 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time 3.5.2 Condition H (Action H.1) Enter 3.0.3 Immediately LCO 3.0.3 requires Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Encl. 4.16, (Lowering LDST Pressure)
- Review Limits and Precautions 3.1 Direct Operator to Close 1GWD-20 (LDST Vent Blk).
3,2 Open 1GWD-19 (LDST VENT).
3.3 Direct Operator to throttle open 1GWD-20 (LDST Vent Blk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header.
Note: 1SA-9/C-12 (GWD VENT HEADER PRESSURE HIGH/LOW) may actuate.
1SA-9/C-12 ARG:
- Adjust setpoint to maintain 0 H2O pressure on vent header
- Determine and correct cause of alarm This event is complete when LDST pressure has been returned to the acceptable range and the SRO has made the Tech Spec determination OR as directed by lead examiner.
Page 3 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 1 Page 3 of 3 Event
Description:
Pressurize LDST with Hydrogen (TS)
Time Position Applicant's Actions or Behavior BOP 3.4 IF required, start Standby GWD Compressor per OP/1-2/A/1104/018 (GWD System). (See below) 3.5 WHEN desired LDST pressure obtained, close 1GWD-19 (LDST VENT) 3.6 If started, stop Standby GWD Compressor 3.7 Throttle 1/4 turn open 1GWD-20.
OP/1-2/A/1104/018 (GWD System) Enclosure 4.1
- 1. Initial Conditions None
- 2. Procedure 2.1 IF desired to start 'A' GWD Compressor, perform the following:
2.1.1 Begin monitoring Vent Header pressure.
2.1.2 Open DW-140 ('A' GWD COMP DW MAKEUP).
2.1.3 Start 'A' GWD COMPRESSOR.
2.1.4 Place DW-140 ('A' GWD COMP DW MAKEUP) in "AUTO".
2.1.5 Verify GWD-8 ('A' SEPARATOR TANK DRAIN) closed.
2.2 IF desired to start 'B' GWD Compressor, perform the following:
2.2.1 Open DW-142 ('B' GWD COMP DW MAKEUP).
2.2.2 Start 'B' GWD COMPRESSOR.
2.2.3 Place DW-142 ('B' GWD COMP DW MAKEUP) in "AUTO".
2.2.4 Verify GWD-9 ('B' SEPARATOR TANK DRAIN) closed.
2.3 IF desired to stop 'A' GWD Compressor, perform the following:
2.3.1 Ensure another compressor is carrying the header.
2.3.2 Stop 'A' GWD COMPRESSOR.
2.4 IF desired to stop 'B' GWD Compressor, perform the following:
2.4.1 Ensure another compressor is carrying the header.
2.4.2 Stop 'B' GWD COMPRESSOR.
This event is complete when LDST pressure has been returned to the acceptable range and the SRO has made the Tech Spec determination OR as directed by lead examiner.
Page 4 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 2 Page 1 of 1 Event
Description:
HPSW Jockey Pump trips Time Position Applicant's Actions or Behavior Plant Response:
- OAC Alarm - O1D2146 (HPSW Jockey Pump) OFF
BOP Refer to ARG 1SA-9/D-8 3.1 Verify automatic actions until jockey pump is restarted 3.2 IF there is NO evidence of breaker and/or pump motor problem, attempt to restart jockey pump one time. If restart is unsuccessful, notify Maintenance Department.
Booth Cue: If the crew dispatches a AO to determine if a problem exists with HPSW Jockey Pump motor/breaker, as SPOC, use TIME COMPRESSION and inform the RO that no problem was found with the Jockey Pump motor or breaker The crew may refer to ARG 1SA-9/A-8 3.1 Verify proper jockey pump operation 3.2 Refer to SLC 16.9.8a 3.3 Verify HPSW pumps start (start manually if NOT already in operation per OP/0/A/1104/011) when preset levels in EWST are reached 3.4 IF both HPSW Pumps NOT available, Go To EP/1/A/1800/001 Enclosure 5.31 for method of back charging the HPSW system.
3.5 IF HPSW Header Pressure continues to decrease AND Elevated Storage Tank Level is NOT dropping; i.e., altitude valve stuck closed and jockey pump not providing adequate supply, manually start a HPSW Pump.
- Refer to OP/0/A/1104/011 (High Pressure Service Water).
3.6 Refer to AP/1-2/A/1700/030 (Aux Building Flood) 3.7 Investigate and correct reason for excessive HPSW usage 3.8 Verify BASE and STANDBY HPSW Pumps stop at 80,000 gals 3.9 IF manually started, return HPSW Pumps when NO longer needed The crew may refer to the ARG for O1D2146 (HPSW Jockey Pump)
- 1) IF there is NO evidence of breaker and/or pump motor problem, THEN attempt to restart jockey pump one time. If restart is unsuccessful, contact SPOC.
- 2) Refer to OP/0/A/1104/011 (High Pressure Service Water)
This event is complete when the Jockey Pump has been restarted, or as directed by the Lead Examiner.
Page 5 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 3 Page 1 of 3 Event
Description:
TC Controller Fails HIGH (A Loop Hot)
Time Position Applicant's Actions or Behavior Plant Response:
- FDW flow will ratio incorrectly based on the failure
- A FDW flow will increase causing A loop TC to decrease.
- B FDW flow will decrease causing B loop TC to increase.
- This will cause actual TC to increase (become more negative). Failure to adjust FDW flow will result in QPT.
Crew Response:
SRO/OATC
- Crew should perform Plant Transient Response (PTR)
- Diagnose the TC failure by observing the TC meter on 1UB1. It should return to zero but is staying at + 3.5 degrees.
- OATC reports to the SRO reactor power level and direction of movement.
- Take the Diamond and Feedwater Masters to MANUAL and re-ratio feedwater using the Loop TC meters and/or OAC (RCS01) to return actual TC to near zero.
- BOP reports no valid runback.
- SRO should direct the BOP to reference Statalarm 1SA-02/B-5 (may not get if ICS taken to manual quickly)
- SRO will refer to AP/28 (ICS Instrument Failures) 4.1 Provide control bands as required (per OMP 1-18 Attach I)
- NI Power +/- 1% not to exceed the pre-transient or allowable power
- Current Tave +/- 2°F
- Delta Tc 0°F +/- 2°F This event is complete when the SRO reaches the WHEN step (4) in Section 4F, or as directed by the Lead Evaluator.
Page 6 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 3 Page 2 of 3 Event
Description:
TC Controller Fails HIGH (A Loop Hot)
Time Position Applicant's Actions or Behavior 4.2 Initiate notification of the following:
__ OSM to reference OMP 1-14 and Emergency Plan
__ STA 4.3 Verify a power transient 5% has occurred 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following , as necessary, to determine the applicable section from table in Step 4.6
- OAC alarm video, OAC display points, Control Board indications, SPOC assistance 4.6 GO TO the applicable section per the following table:
Section Failure 4F Delta TC AP/28 Section 4F NOTE
- This section applies to Delta TC controller failures. TC input signal failures are addressed in Section 4A The following may occur when an ICS Delta TC controller fails:
- Delta TC controller may re-ratio loop FDW flows
- Possible ICS RUNBACK
- 1. Ensure the following in HAND:
__ 1A and 1B FDW MASTERS
__ DELTA TC CAUTION Total feedwater flow should be maintained constant while individual loop flows are adjusted to establish the desired Tc. Maintaining total FDW flow constant will prevent unwanted changes in reactor power.
This event is complete when the SRO reaches the WHEN step (4) in Section 4F, or as directed by the Lead Evaluator.
Page 7 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 3 Page 3 of 3 Event
Description:
TC Controller Fails HIGH (A Loop Hot)
Time Position Applicant's Actions or Behavior
- 2. Re-ratio feedwater flow, as required, to establish desired DELTA TC while maintaining total feedwater flow constant
- 3. Notify SPOC to perform the following:
__ Investigate and repair the failed Delta TC controller Booth Cue: When notified to investigate and repair the failed TC controller, respond as SPOC and state that the TC controller will be repaired as soon as possible.
- 4. WHEN notified by SPOC that DELTA TC controller has been repaired, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto)
NOTE: ICS will remain in manual for the remainder of the scenario.
This event is complete when the SRO reaches the WHEN step (4) in Section 4F, or as directed by the Lead Evaluator.
Page 8 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 4 Page 1 of 4 Event
Description:
1A Letdown Cooler Leak Time Position Applicant's Actions or Behavior Plant Response:
Statalarms:
- 1SA-08/B-9 (PROCESS MONITOR RADIATION HIGH)
Crew Response:
SRO/ BOP 1SA-08/B-9 3.1 Determine radiation monitors in alarm.
3.1.1 IF VIEW node OR either SCADA node is NOT in service, refer to OP/1/A/1103/026, (Loss of Sorrento Radiation Monitor).
NOTE TO EXAMINER: Steps 3.2 through 3.10 are IF statements for which RIA is in alarm. In this case, the crew determines the radiation monitor alarming is 1RIA-50, so step 3.9 applies.
3.9 IF any of the following RIAs have valid alarms, GO TO AP/18 (Abnormal Release of Radioactivity).
SRO/BOP AP/18 (Can be performed by Unit 2 if AP/2 has been entered) 4.1 Perform the following:
At the discretion of the CR SRO, make a PA announcement of the event including any necessary precautions to be observed.
Notify OSM to reference the following:
RP /0/B/1000/001 (Eme rge ncy Cla s s ifica tion).
NS D-202 (Reportability)
OMP 1-14 (Notifications)
This event is complete when 1A Letdown cooler has been isolated or as directed by the lead examiner.
Page 9 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 4 Page 2 of 4 Event
Description:
1A Letdown Cooler Leak Time Position Applicant's Actions or Behavior SRO /BOP AP/18 (cont) 4.2 GO TO appropriate sections for any monitors in High or Alert alarm:
NOTE TO EXAMINER: Crew should go to Section 4I for 1RIA-50.
Section 4I 1 Verify either of the following:
- CC SURGE TANK increasing 5
/hour
- CC SURGE TANK off-scale high
- 2. __ Initiate AP/2 (Excessive RCS Leakage).
Note: Crew may enter AP/2 directly because the following entry condition is met: Reactor Coolant leakage into CC system at 5/hour on CC Surge Tank ( 0.65 gpm) or CC Surge Tank level off-scale high SRO /BOP AP/2 Immediate Actions 3.1 Verify HPI operating.
3.2 IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5.
3.3 IAAT all the following exist:
- HPI flow is > NORMAL MAKEUP CAPABILITY (160 gpm) with letdown isolated
- Pzr level decreasing
- SG Tube Leakage NOT indicated
A. Ensure Rx is tripped.
B. Initiate Unit 1 EOP.
Subsequent Actions NOTE Other than a SGTR, 1HP-26 should NOT need be open with the Rx critical.
4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP Encl 5.5 (Pzr and LDST Level Control), as necessary.
4.2 Announce AP entry using the PA system.
4.3 IAAT LPI DHR in service, AND RCS leakage > LDST makeup capability ( 50 gpm ),
THEN GO TO AP/26 (Loss of Decay Heat Removal).
This event is complete when 1A Letdown cooler has been isolated or as directed by the lead examiner.
Page 10 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 4 Page 3 of 4 Event
Description:
1A Letdown Cooler Leak Time Position Applicant's Actions or Behavior SRO /BOP AP/2 (Cont) 4.4 Initiate the following notifications:
__ OSM to reference the following:
- RP/0/B/1000/001 (Emergency Classification)
- OMP 1-14 (Notifications)
- Encl 5.9 (Oversight Guidelines)
__ STA
__ RP 4.5 Monitor the following trends to determine leak area (AB or RB) and trend for degradation:
- "T6 AP02"
- "T6 WASTE"
- RIAs 4.6 Verify specific leak location is identified.
4.7 Initiate Encl 5.1 (Leak Rate Determination). (This will calculate RCS leakage based on CC surge tank level increase and is a very gross calculation since there is no OAC point for CC surge tank level and therefore control room gage must be used.)
4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure:
4.16 Verify all of the following:
- CC Surge Tank level increasing at 5 gpm) or level is 0.65 off-scale high
- 1RIA-50 in alarm or increasing 4.17 IAAT CC Surge Tank level is off-scale high, THEN notify Radwaste that the CC Surge Tank has overflowed to the LAWT.
4.18 IAAT RCS leakage is flashing the CC system, OR threatens to overflow the LAWT, THEN perform the following: N/A at this time 4.19 Verify leakage indicated by change in RCP cooler outlet temperatures (Turn-on code "GD AP02"): (No leakage indicated)
RNO GO TO Step 4.24 This event is complete when 1A Letdown cooler has been isolated or as directed by the lead examiner.
Page 11 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 4 Page 4 of 4 Event
Description:
1A Letdown Cooler Leak Time Position Applicant's Actions or Behavior SRO /BOP AP/2 (cont)
NOTE RCS leakage to CC in the letdown coolers may be indicated by a cooler outlet temperature increasing more than the other cooler. Due to CC system setup, letdown cooler CC outlet temperatures may be different. A historical OAC temperature trend may be required to determine if leakage exists and if actions taken are successful in leak isolation. If leaking cooler CANNOT be identified, the coolers will be isolated one at a time starting with the 1A Letdown Cooler.
4.24 Monitor letdown cooler outlet temperatures to determine which cooler is leaking (Turn-on code "GD AP02"):
- O1A0065 (LETDOWN COOLER 1A CC OUTLET TEMP)
- O1A0066 (LETDOWN COOLER 1B CC OUTLET TEMP) 4.25 GO TO the appropriate step to isolate affected cooler:
NOTE TO EXAMINER: According to the Note above and the table below, the crew ends up in the same place whether they have diagnosed which cooler is leaking or not. Either path is acceptable and ends up with the 1A cooler isolated.
4.26 Verify 1B Letdown Cooler is isolated.
RNO: 1 Isolate the 1A Letdown Cooler by performing the following:
A. Close 1CC-1/1HP-1.
B. Close 1HP-3.
- 2. GO TO Step 4.31.
Examiner note: 1SA-2/C-1 (HP Letdown Temp High) will actuate, expected alarm.
4.31 Verify the leak isolation was successful:
- Decrease in RCS leakage This event is complete when 1A Letdown cooler has been isolated or as directed by the lead examiner.
Page 12 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 5 Page 1 of 3 Event
Description:
1A SG Outlet Pressure Fails High Time Position Applicant's Actions or Behavior Plant Response:
- 1A TBVs open
- Main Turbine Control valves close to control THP at setpoint.
- Generated Megawatts decrease.
- OAC Alarms:
SG 1A Outlet Press Mismatch AFIS1A SG 1A Outlet Press Deviation
- Reactor power increases initially but returns to pre-transient values.
OATC
- RCS temperature and pressure change initially but return to pre-transient values.
Crew Response:
- The OATC should recognize a transient is in progress, and then perform PTR.
o OATC reports to the SRO reactor power level and direction of movement.
o OATC takes the Diamond and Feedwater Masters to MANUAL and stabilizes the plant.
o BOP reports no valid runback.
- SRO will refer to AP/28 (ICS Instrument Failures) 4.1 Provide control bands as required (per OMP 1-18 Attach I)
- NI Power +/- 1% not to exceed the pre-transient or allowable power
- Current Tave +/- 2°F
- Delta Tc 0°F +/- 2°F 4.2 Initiate notification of the following:
__ OSM to reference OMP 1-14 and Emergency Plan
__ STA 4.3 Verify a power transient 5% has occurred. GO TO Step 4.5 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following , as necessary, to determine the applicable section from table in Step 4.6
- OAC alarm video, OAC display points, Control Board indications, SPOC assistance This event is complete when the A TBVs have been closed, or as directed by the Lead Examiner.
Page 13 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 5 Page 2 of 3 Event
Description:
1A SG Outlet Pressure Fails High Time Position Applicant's Actions or Behavior Crew Response:
OATC 4.6 GO TO the applicable section per the following table:
Section Failure 4N SG Outlet Pressure 4P TBV Failure Note: Either section of AP/28 above will mitigate this event. Both sections are shown below.
AP/28 Section 4N (SG Outlet Pressure)
- 1. Ensure the affected TBVs in HAND and closed:
- 1A TURBINE BYPASS VALVES and 1B TURBINE BYPASS VALVES
- 2. Notify SPOC to perform the following:
- Select a valid SG Outlet Pressure input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).
- Investigate and repair the failed SG Outlet Pressure instrumentation.
- 3. WHEN notified by SPOC that a valid SG Outlet Pressure input has been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).
AP/28 Section 4P (TBV Failure)
- 1. GO TO the first applicable step per the following table:
Failure Step 1A TURBINE BYPASS VALVES fail open any 2 amount.
- 2. Verify the TURBINE MASTER IN Automatic.
- 3. IAAT it is desired to close 1A TURBINE BYPASS VALVES, THEN perform the following:
A. Place 1A TURBINE BYPASS VALVES in HAND B. Close 1A TURBINE BYPASS VALVES This event is complete when the A TBVs have been closed, or as directed by the Lead Examiner.
Page 14 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 5 Page 3 of 3 Event
Description:
1A SG Outlet Pressure Fails High Time Position Applicant's Actions or Behavior Crew Response:
OATC 4. Verify ICS responds as expected.
- 6. Verify ICS responds as expected
- 8. IAAT the 1B TBVs have failed open (does not apply)
This event is complete when the A TBVs have been closed, or as directed by the Lead Examiner.
Page 15 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 6 Page 1 of 3 Event
Description:
60 gpm leak in 1A SG Requiring a manual power reduction (TS)
Time Position Applicant's Actions or Behavior Plant response:
- 1SA8/A9 (RM AREA MONITOR RADIATION HIGH)
- 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)
- 1SA8/B9 (RM PROCESS MONITOR RADIATION HIGH)
- 1RIA-40 in alarm
- 1RIA 59 in alarm and indicating 60 gpm.
Crew response:
EXAMINER NOTE: Direct entry into the SGTR Tab is SGTL 25 gpm.
EOP SGTR TAB EOP Parallel Actions SRO
- Announce plant conditions using PA system.
- Notify OSM to reference the Emergency Plan and NSD 202 (Reportability).
- Notify plant staff that Emergency Dose Limits are in affect using PA system.
SRO/BOP/ 1. Verify Rx tripped.
OATC RNO: 1. Maintain Pzr level 220 - 260 by initiating Encl 5.5 (Pzr and LDST Level Control). (page 26)
- 2. GO TO Step 9.
9 IAAT Pzr level decreasing with all available HPI, AND Rx power is > 18%,
THEN perform the following:
A. Trip the Rx.
B. GO TO IMA tab.
- 10. Verify all:
- Rx power > 40%
- 11. Determine leak rate using:
- 1RIA-60 This event is completed when > 10% power reduction has occurred and auxiliaries have been transfered or when directed by the lead examiner.
Page 16 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 6 Page 2 of 3 Event
Description:
60 gpm leak in 1A SG Requiring a manual power reduction (TS)
Time Position Applicant's Actions or Behavior EOP SGTR TAB (continued)
- 13. Verify ICS capable of power reduction in AUTO.
SRO/OATC RNO: 1. Initiate manual power reduction to < 15%.
- 2. GO TO Step 15.
NOTE Encl 5.19 (Control of Plant Equipment During Shutdown for SGTR) will swap auxiliaries.
SRO/BOP 15 Initiate Encl 5.19 (Control of Plant Equipment During Shutdown for SGTR). (See next page)
- 16. WHEN both exist:
- Reactor power is 15% FP
- Unit auxiliaries have been transferred THEN continue.
EXAMINER NOTE: The Tech Spec for this SGTR is TS 3.4.13 for leakage
>150 gpd. Condition B applies (Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />)
BOOTH CUE: Ensure the OATC has reduced Reactor Power >10% AND the BOP has transferred auxiliaries prior to initiating the next event (Timer 7)
This event is completed when > 10% power reduction has occurred and auxiliaries have been transfered or when directed by the lead examiner.
Page 17 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 6 Page 3 of 3 Event
Description:
60 gpm leak in 1A SG Requiring a manual power reduction (TS)
Time Position Applicant's Actions or Behavior Encl 5.19 (Control of Plant Equipment During Shutdown for SGTR)
BOP/SRO
- 1. Perform the following:
A. Monitor RIAs to identify all SGs with a tube rupture:
- 1RIA-59 when Rx power > 40%
- 1RIA-60 when Rx power > 40%
B. Inform CR SRO of results.
- 2. Place 1TA AUTO/MAN transfer switch in MAN.
- 3. Place 1TB AUTO/MAN transfer switch in MAN.
- 4. Close 1TA SU 6.9 KV FDR.
- 5. Close 1TB SU 6.9 KV FDR.
- 6. Place MFB1 AUTO/MAN transfer switch in MAN.
- 7. Place MFB2 AUTO/MAN transfer switch in MAN.
- 8. Close E11 MFB1 STARTUP FDR.
- 9. Close E21 MFB2 STARTUP FDR.
- 10. Notify CR SRO that unit auxiliaries have been transferred.
- 11. Start:
- TURBINE TURNING GEAR OIL PUMP
- 1A through 1E TURBINE BRNG OIL LIFT PUMPs
- TURBINE MOTOR SUCTION PUMP
- 12. Start:
- A OUTSIDE AIR BOOSTER FAN
- B OUTSIDE AIR BOOSTER FAN
- 13. Notify Unit 3 to start:
- 3A OUTSIDE AIR BOOSTER FAN
- 3B OUTSIDE AIR BOOSTER FAN This event is completed when > 10% power reduction has occurred and auxiliaries have been transfered or when directed by the lead examiner.
Page 18 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 7 Page 1 of 4 Event
Description:
Loss of Main and Emergency Feedwater - LOHT Tab - CBP feed Time Position Applicant's Actions or Behavior Plant Response:
When directed by the Lead Examiner, a Loss of Main and Emergency Feedwater will occur.
SRO/OATC Crew Response:
Perform Immediate Manual Actions (IMAs) 3.1 Depress REACTOR TRIP pushbutton.
3.2 Verify reactor power < 5% FP and decreasing.
3.3 Depress turbine TRIP pushbutton.
3.4 Verify all turbine stop valves closed.
3.5 Verify RCP seal injection available.
BOP will perform a Symptom Check and initiate Rule 3 (Loss of Main and /
or Emergency Feedwater)
SRO will transfer to the Loss Of Heat Transfer Tab based on Parallel Actions page.
This event is complete when RCS temperature is stabilized on Condensate Booster Pump feed or as directed by the lead Examiner.
Page 19 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 7 Page 2 of 4 Event
Description:
Loss of Main and Emergency Feedwater - LOHT Tab - CBP feed Time Position Applicant's Actions or Behavior Rule 3 BOP/OATC
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding.
RNO: GO TO Step 3.
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs.
- 5. Verify any EFDW pump operating.
RNO: GO TO Step 7.
- 7. Place the following in MANUAL and close:
- 8. Verify both of the following:
- Any CBP operating
- 13. Perform the following:
- Place 1FDW-31 switch in CLOSE.
- Place 1FDW-40 switch in CLOSE.
- Close 1FDW-32.
- Close 1FDW-41.
This event is complete when RCS temperature is stabilized on Condensate Booster Pump feed or as directed by the lead Examiner.
Page 20 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 7 Page 3 of 4 Event
Description:
Loss of Main and Emergency Feedwater - LOHT Tab - CBP feed Time Position Applicant's Actions or Behavior Rule 3 (Continued)
BOP/OATC
- 14. Verify Rule 4 (Initiation of HPI Forced Cooling) in progress.
RNO: (CT-11, Control SG Pressure to Maintain RC Temperature Constant)
Examiner note: To meet the CT, the candidate must show the ability to stop the RCS temperature increase and then maintain RCS temperature stable or slightly decreasing.
- 2. Control FDW flow to stabilize RCS P/T by throttling the Startup Control valves and TBVs as necessary:
- 6. GO TO step 16
- 16. Verify 1 TD EFDW PUMP is operable and available for manual start.
- 17. Dispatch an operator to perform Encl 5.26 (Manual Start of TDEFDWP).
- 18. Verify cross-tie with Unit 2 is desired.
- 20. Dispatch an operator to 1FDW-313 and have them notify the CR when in position.
- 21. Notify Unit 2 to:
- Manually Close 2FDW-315 & 316.
- Start their U2 TDEFWP
- 22. WHEN, either of the following exists: 1FDW-313 Operator in position OR Unit 1 TDEFWP has been manually started; THEN continue.
This event is complete when RCS temperature is stabilized on Condensate Booster Pump feed or as directed by the lead Examiner.
Page 21 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 7 Page 4 of 4 Event
Description:
Loss of Main and Emergency Feedwater - LOHT Tab - CBP feed Time Position Applicant's Actions or Behavior Loss Of Heat Transfer Tab
- 1. Ensure Rule 3 in progress or complete.
NOTE: Transfer to LOSCM tab is NOT required if RCS heats to the point SRO/BOP/
where core SCM = 0°F.
OATC
- 2. IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4.
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
RNO:
NOTE: 1A1 RCP provides the best Pzr spray.
- 1. Reduce operating RCPs to one pump/loop.
- 2. WHEN any of the following exists:
- EFDW flow has been re-established by existing Rules/Enclosures
- EFDW aligned from another unit
- Operator performing Rule 3 (Loss of Main or Emergency FDW) or Encl 5.27 (Alternate Methods for Controlling EFDW Flow) reports EFDW available THEN GO TO Step 48 Examiner Note: The SRO will wait at the WHEN step until one of the bullets are met or until an outstanding IAAT is met. The crew may initiate EOP Encl 5.5 for inventory control. These steps are included beginning on page 23. To initiate Event 8, IAAT step 3 will be met by tripping the CBPs.
The EOP path for Event 8 continues on Page 20.
This event is complete when RCS temperature is stabilized on Condensate Booster Pump feed or as directed by the lead Examiner.
Page 22 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 8 Page 1 of 3 Event
Description:
CBPs trip requiring HPI Forced cooling, 1HP-24 will not open, Transfer to HPI CD Tab Time Position Applicant's Actions or Behavior Loss of CBP's Plant Response:
- CBPs trip
- Feedwater flow decreases
- RCS temperature increases Crew Response:
SRO SRO may direct RO to re-perform Rule 3 however there are no EFDWP's available and all required actions will already have been performed during the initial performance of Rule 3.
At 2300 psig RCS pressure, direct performance of Rule 4 (HPI Forced Cooling).
Rule 4 (CT-14 Initiate HPI Forced Cooling Within 5 minutes of BOP/OATC meeting criteria)
Examiner note: HPI F/C criteria met:
Start ______
Stop ______
- 1. Verify any HPI pump can be operated.
Examiner Note: 1HP-24 will NOT open requiring the RNO actions.
RNO: IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following:
A. IF three HPI pumps are operating, THEN secure 1B HPI PUMP.
B. IF < 2 HPI pumps operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C. GO TO Step 4.
Examiner Note: When 1HP-26 is opened, the standby HPI pump may start due to low seal injection flow. If so, the student should stop one of the HPI pumps because only 1 BWST suction valve is open (1HP-24 would not open). The guidance to do this is contained in Rule 6.
- 4. Open 1HP-26 and 1HP-27 This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.
Page 23 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 8 Page 2 of 3 Event
Description:
CBPs trip requiring HPI Forced cooling, 1HP-24 will not open, Transfer to HPI CD Tab Time Position Applicant's Actions or Behavior Rule 4 (Cont.)
BOP/OATC 5. Open 1RC-4.
- 7. Open PORV. (Switch to OPEN, depress OPEN permit)
- 8. Verify at least two HPI pumps operating.9. Verify flow in both HPI headers is in the acceptable region of Figure
- 12. Verify > one RCP operating.
- 14. IAAT the following limits are exceeded,
THEN throttle HPI to maximize flow flow lim it.
- 15. De-energize all Pzr heaters.
- 16. Close 1HP-5.
- 19. WHEN directed by CR SRO, THEN EXIT this rule.
Booth Cue: If the crew requests that Unit 2 handle AP/18 due to RIA alarms, reply that Unit 2 WILL handle AP/18.
This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.
Page 24 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 1 Event No.: 8 Page 3 of 3 Event
Description:
CBPs trip requiring HPI Forced cooling, 1HP-24 will not open, Transfer to HPI CD Tab Time Position Applicant's Actions or Behavior LOHT tab SRO/OATC/
BOP Determine that IAAT step 3 is met:
- 4. PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- 5. Verify all the following:
- At least two HPI pumps operating
- PORV open
- 1RC-4 open
- 6. GO TO HPI CD tab.
HPI CD tab SRO/OATC/ 1. IAAT BWST level is 19', THEN initiate Encl 5.12 (ECCS Suction BOP Swap to RBES).
- 2. IAAT either of the following exists:
- 3. Verify all of the following exist:
- PORV open
- 1RC-4 open
- Two HPI trains injecting
- CETCs °F 640
- 4. Perform the following:
- Ensure all RBCUs in low speed.
- 5. Initiate Encl 5.35 (Containment Isolation)
This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.
Page 25 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 1 of 8 EXAMINER NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See excerpt below.
ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
- 1. Utilize the following as necessary to maintain __ IF 1HP-26 will NOT open, desired Pzr level: THEN throttle 1HP-410 to maintain
- 1A HPI Pump desired Pzr level.
- 1B HPI Pump
- 1HP-120 setpoint or valve demand
- 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
- 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.
- 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
__ 1CS-26
__ 1CS-41 B. Position 1HP-14 to BLEED.
C. Notify SRO.
- 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.
Page 26 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 2 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. IAAT 1C HPI PUMP is required, __ GO TO Step 10.
THEN perform Steps 7 - 9.
- 7. Open: 1. __ IF both BWST suction valves
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 8.
A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.
B. __ IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C. __ GO TO Step 9.
Page 27 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 3 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. Start 1C HPI PUMP. __ IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level.
- 9. Throttle the following as required to 1. __ IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain
- 1HP-26 desired Pzr level.
- 2. __ IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.
Page 28 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 4 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. IAAT LDST level CANNOT be __ GO TO Step 12.
maintained, THEN perform Step 11.
- 11. Perform the following: 1. __ IF both BWST suction valves
- Open 1HP-25.
A. __ Start 1A LPI PUMP.
- Close 1HP-16.
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 12.
- 2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP.
Page 29 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 5 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
- 13. IAAT two Letdown Filters are desired, THEN perform the following:
- Open 1HP-17.
- Open 1HP-18
- 14. IAAT all of the following exist: __ GO TO Step 34.
- Letdown isolated
- LPSW available
- Letdown restoration desired THEN perform Steps 15 - 33. {41}
- 15. Open: 1. __ Notify CR SRO that letdown CANNOT be
- 1CC-8 system.
- 2. __ GO TO Step 34.
- 16. Ensure only one CC pump running.
- 17. Place the non-running CC pump in AUTO.
- 1HP-1 close,
- 1HP-2 THEN GO TO Step 20.
- 19. GO TO Step 22.
NOTE Verification of leakage requires visual observation of East Penetration Room.
- 20. Verify letdown line leak in East __ GO TO Step 22.
Penetration Room has occurred.
- 21. GO TO Step 34.
Page 30 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 6 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. Monitor for unexpected conditions while restoring letdown.
- 23. Verify both letdown coolers to be placed 1. __ IF 1A letdown cooler is to be placed in in service. service, THEN open:
__1HP-1
__1HP-3
- 2. __ IF 1B letdown cooler is to be placed in service, THEN open:
__1HP-2
__1HP-4
- 3. __ GO TO Step 25.
- 24. Open:
- 25. Verify at least one letdown cooler is Perform the following:
aligned. A. __ Notify CR SRO of problem.
B. __ GO TO Step 34.
- 26. Close 1HP-6.
- 27. Close 1HP-7.
- 28. Verify letdown temperature < 125°F. 1. __ Open 1HP-13.
- 2. Close:
__1HP-8
__1HP-9&11
- 3. __ IF any deborating IX is in service, THEN perform the following:
A. __Select 1HP-14 to NORMAL.
B. __Close 1HP-16.
- 4. __ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 31 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 7 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 29. Open 1HP-5.
- 30. Adjust 1HP-7 for 20 gpm letdown.
- 31. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
- 32. Open 1HP-6.
- 33. Adjust 1HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
- 34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
- 35. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A. Obtain SRO concurrence to reduce running HPI pumps.
B. Secure the desired HPI pumps.
C. Place secured HPI pump switch in AUTO, if desired.
- 36. IAAT all the following conditions exist:
- Makeup from BWST NOT required
- LDST level > 55
- All control rods inserted
- Cooldown Plateau NOT being used THEN close:
- 1HP-25 Page 32 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 8 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 37. Verify 1CS-48 (1A BHUT Recirc) has __ GO TO Step 39.
been closed to provide additional makeup flow to LDST.
- 38. WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A. Stop 1A BLEED TRANSFER PUMP.
B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
C. Close 1CS-46.
D. Start 1A BLEED TRANSFER PUMP.
E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure.
F. Stop 1A BLEED TRANSFER PUMP.
- 39. Verify two Letdown Filters in service, __ GO TO Step 41.
AND only one Letdown filter is desired.
- 40. Perform one of the following:
- Place 1HP-17 switch to CLOSE.
- Place 1HP-18 switch to CLOSE.
- 41. WHEN directed by CR SRO, THEN EXIT this enclosure.
- *
- END
- Page 33 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 34 of 36
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam CRITICAL TASKS
- 1. CT-11, Control SG Pressure to Maintain RC Temperature Constant. page 18
- 2. CT-14 Initiate HPI Forced Cooling. page 20 Page 35 of 36
SAFETY: Take a Minute UNIT 0 (SM)
SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CRS)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 897 100% Power 100% Power RCS Leakage: .024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: .01 gpm Technical Specifications/SLC Items (CRS)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time Shift Turnover Items (CRS)
Primary
- SASS in Manual for I&E
- LDST needs Hydrogen addition. Direct the BOP to add H2 to the LDST using OP/1/A/1106/017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition).
Secondary
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
Reactivity Management (CRS)
RCS Boron: 6 ppmB Gp 7 Rod Position: 91%
Human Performance Emphasis (SM)
Procedure Use and Adherence
Appendix D Scenario Outline Form ES-D-1 ILT44 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO
________________________ ________________________OATC
________________________ ________________________BOP Initial Conditions:
- Reactor Power = 75% Unit 2: 100%, Unit 3: 100%
Turnover:
- 1B FDWP on Handjack
- SASS in manual for I&E
- Voltage Regulator is in MANUAL for I&E
Event Malfunction Event Event Type* Description No. No.
0a Override SASS in Manual 0b Override AFIS Disabled 1 Place Voltage Regulator Mode in AUTO and decrease N: BOP, SRO VARs.
2 MPS250 C: BOP, SRO 1B2 RCP seal failure Re-occurring Hi Vibration on 1C RBCU degrades to 3 MSS470 C: BOP, SRO (TS)
Cooler Rupture 4 Overrides C: OATC, SRO 1HP-120 (RC Volume Control) Fails OPEN Dropped control rod with failure of auto runback circuit 5 MCR021 C: OATC, SRO (TS)
(requires 1B FDWP adjustment) 1TB 6900v lockout trips 2nd RCP (1A2) requiring 6 MEL220 C: OATC, SRO manual Rx trip MSS390, 1B MSLB outside the reactor building (EHT tab) with 7 14% M: ALL Auto AFIS actuation blocked 8 Override ALL 1FDW-315 fails open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 1 Page 1 of 1 Event
Description:
Place Voltage Regulator Mode in AUTO and Decrease VARs Time Position Applicant's Actions or Behavior Crew Response:
SRO The SRO will direct the BOP to reduce Generator MVARs to 150 +/- 10 MVARs in accordance with OP/1/A/1106/001, enclosure 4.8.
OP/1/A/1106/001 Enclosure 4.8 CAUTION Do NOT exceed limits as shown on Enclosure 4.5 (Capability Curve).
NOTE Minimum of 18.05 Generator kV must be maintained.
Operation with leading PF is acceptable.
2.1. Notify other online units of VAR change.
SRO/BOP 2.2. Select VARS on WATT/VAR TRANSFER Switch.
2.3. Ensure MVARS are indicated on MWATT/MVAR meter.
2.4. IF VOLTAGE REGULATOR MODE will be swapped between AUTO &
MANUAL, notify System Operating Center (SOC) that VOLTAGE REGULATOR MODE will be swapped.
2.5. IF AUTO adjustment is required, perform the following:
NOTE:
VOLTAGE REGULATOR MODE Ready Light (Amber light) should be ON.
CRD AC Power Fault 'A' and/or 'B' alarms along with CRD Global System Fault may be received during generator voltage changes.
2.5.1. Ensure VOLTAGE REGULATOR MODE in AUTO.
2.5.2. Use VOLTAGE ADJUST to slowly modify Generator voltage to increase/decrease MVARS.
2.6. IF MANUAL adjustment is required, perform the following: N/A This event is completed when MVARs have been adjusted to 150 +/- 10 MVARs, or when directed by the lead examiner.
Page 2 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 2 Page 1 of 4 Event
Description:
1B2 RCP lower seal failure Time Position Applicant's Actions or Behavior Plant response:
- 1SA-06/D-5, RC PUMP 1B2 SEAL CAVITY PRESS HI/LOW
- OAC Alarm RCP 1B2 LOWER SEAL CAVITY PRESSURE HI HI
- OAC Alarm RCP 1B2 UPPER SEAL CAVITY PRESSURE HI HI Crew response:
Refer to the ARGs BOP 3.1 Upper/Lower Seal Cavity Pressure High 3.1.1 Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action 3.2 Upper/Lower Seal Cavity Pressure Low 3.2.1 IF in Mode 1 or 2, Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action Refer to AP/1/A/1700/016 (Abnormal RCP Operation) 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP SRO Immediate Trip Criteria), THEN perform Steps 4.2 - 4.11.
RNO: GO TO Step 4.12.
4.12 IAAT either of the following apply:
- It is desired to secure a RCP THEN perform Steps 4.13 - 4.15.
RNO: GO TO Step 4.16 (next page)
EXAMINER Note: It is acceptable for the SRO to take either procedure path to secure the 1B2 RCP. Step 4.16 is on the next page.
4.13 Verify Rx Power > 70%
4.14 Initiate Encl 5.2 (Rapid Power Reduction) (see page 6) 4.15 WHEN Rx Power is 70%,
THEN GO TO Step 4.2 4.2 Verify MODE 1 or 2 4.3 Verify Rx power is 70% as indicated on all NIs 4.4 Verify three RCPs will remain operating after affected RCP is tripped 4.5 Verify any SG on Low Level Limits RNO: GO TO Step 4.8 4.8 Verify FDW masters in Auto 4.9 Stop affected RCP 4.10 Verify ICS re-ratios feed water to establish desired TC This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 3 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 2 Page 2 of 4 Event
Description:
1B2 RCP lower seal failure Time Position Applicant's Actions or Behavior Crew response:
AP/1/A/1700/016 (Abnormal RCP Operation)
SRO 4.16 Announce AP entry using the PA system 4.17 Notify OSM to request evaluation by RCP Component Engineer 4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
Section Failure 4A Seal Failure 4B Abnormal Vibration 4C High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP Temper tures AP/1/A/1700/016 Section 4A, RCP Seal Failure SRO 1. IAAT any RCP meets immediate trip criteria of Encl 5.1, THEN perform Steps 2-11 RNO: GO TO Step 12
- 12. IAAT any of the following indicate external RCP seal leakage:
- RB RIAs increasing or in alarm
- RCS Tave constant with LDST level decreasing more than normal
- Quench Tank level rate increasing
- Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage)
- 13. Verify the following are open:
- 14. Verify the following is open for the affected RCP:
This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 4 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 2 Page 3 of 4 Event
Description:
1B2 RCP lower seal failure Time Position Applicant's Actions or Behavior Crew response:
SRO AP/1/A/1700/016 Section 4A, RCP Seal Failure
- 15. IAAT either of the following conditions apply to an operating RCP:
RCS Pressure P across any seal
> 1000 psig 100 psid 1000 psig 35 psid THEN GO TO Step 16 to shut down the affected RCP since shut down of the RCP is desired due to a seal failure.
16 IAAT shut down of an RCP is desired, THEN perform Steps 17-27
- 17. Verify MODE 1 or 2
- 19. Verify Rx power is 70% as indicated on all NIs RNO: 1. Direct an RO to initiate Encl 5.2 (Rapid Power Reduction) (next page)
OATC 2. WHEN Rx power is 70% on all NIs, THEN continue this procedure
- 20. Verify any SG on Low Level Limits RNO: GO TO Step 23
- 23. Verify FDW masters in Auto
- 24. Stop affected RCP
- 26. Initiate Encl. 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power).
OP/1/A/1102/004 Encl. 4.3 (Special Instructions for < 4 RCP Operation) 2.1 IF conditions permit, log the current quadrant power tilt and the position of the TC controller prior to securing a RCP during power operations.
NOTE: Instructions for performing OAC trends are located in Working With Trends enclosure of OP/0/A/1103/020 A (Operator Aid Computer Use).
Only the first 6 points will be displayed initially; press "Page Down" key to see second 6 points.
2.2 Using turn-on code T6 3RCP, digitally trend the following data at one minute intervals 2.3 After steady state conditions are attained, check NI calibration.
This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 5 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 2 Page 4 of 4 Event
Description:
1B2 RCP lower seal failure Time Position Applicant's Actions or Behavior Crew response:
AP/16 Enclosure 5.2, Rapid Power Reduction SRO
- 1. Verify ICS in AUTO
- 2. Initiate MAXIMUM RUNBACK to 70% as indicated by all NIs
- 3. WHEN Rx Power is 70% as indicated by all NIs, THEN press MAXIMUM RUNBACK to stop runback OATC 4. Notify CR SRO that Rx Power is 70%
__ 1E1 HTR DRN PUMP
__ 1E2 HTR DRN PUMP
- 7. Verify Rx Power was reduced 15% within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- 8. Notify Primary Chemistry to perform Tech Spec SR 3.4.11.2 as required
- 9. EXIT this enclosure This event is complete when Rx power is reduced to 70% and the 1B2 RCP is secured, or as directed by the Lead Examiner.
Page 6 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 3 Page 1 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicant's Actions or Behavior Plant response:
- OAC alarm O1D1363, RBCU Fan 1C Vib Crew response:
SRO/BOP
- BOP will pull up the OAC alarm response guide BOOTH CUE: The first time the high vibration timer is fired, Timer 15 will automatically fire 5 seconds later to allow the Hi Vib alarm to be reset by the operator. Three minutes after the initial Hi Vib alarm, a second Hi Vib alarm will occur that cannot be reset.
OAC Alarm Response for O1D1363 (RBCU FAN 1C VIB) 1 Depress the RBCU OAC Vibration Alarm Reset Pushbutton.
2 If the alarm does not clear, STOP the RBCU EXAMINER NOTE: The first time this OAC alarm comes in, it will reset and clear when the alarm reset pushbutton is depressed. 3 minutes after the initial alarm, there will be another HIgh Vibration alarm. The second time it will not clear when reset.
3 Notify Engineering for an evaluation.
BOOTH CUE: Using time compression, Engineering requests the crew to start the 1B RBCU in HIGH speed in accordance with OP/1/A/1104/015, Reactor Building Cooling System, Enclosure 4.3 Section 4 (Starting RBCUs)
OP/1/A/1104/015, Enclosure 4.3, Section 4 NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes. {8}
4.1 Verify RB pressure within limits of PT/1/A/0600/001 (Periodic Instrument Surveillance).
4.2 Begin monitoring RB absolute pressure. (OAC Turn On Code: 1RBPA) 4.3 IF personnel inside containment, announce over plant page that starting RBCU 1B.
NOTE: Starting RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1RIA-47 level, RB pressure/temperature.
This event is complete when the 1C RBCU rupture is isolated, or as directed by the lead examiner.
Page 7 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 3 Page 2 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicant's Actions or Behavior OP/1/A/1104/015, Enclosure 4.3, Section 4 (continued)
SRO/BOP 4.4. Place desired switch to "HIGH" or "LOW":
- 1A RBCU
- 1B RBCU
- 1C RBCU NOTE:
When changing LPSW flows, RB pressure will change as RB temperature changes.
Each RBCU must have 550 gpm Inlet Flow or 750 gpm Outlet Flow to meet flow requirements of SLC 16.9.12.
4.5 Position valves as required for RB cooling:
- 1LPSW-18 (1A RBCU OUTLET)
- 1LPSW-21 (1B RBCU OUTLET)
- 1LPSW-24 (1C RBCU OUTLET)
Examiner/Booth Note: When the 1C RBCU is stopped, Timer 15 will automatically fire and insert a 1C RBCU cooler rupture. See page 9 for actions related to the 1C RBCU cooler rupture)
This event is complete when the 1C RBCU rupture is isolated, or as directed by the lead examiner.
Page 8 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 3 Page 3 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicant's Actions or Behavior Plant Response:
- 1C RBCU LPSW flow indicator indicates low on VB2 Crew Response:
SRO/BOP ARG for 1SA-9/D-9 (Manual Actions) 3.1 Verify alarm is valid by checking RBCU 1C Inlet Flow and RBCU 1C delta flow.
3.2 Verify 1LPSW-24 (RBCU 1C Outlet) open 3.3 Verify adequate LPSW flow is available; check LPSW pump operation 3.3.1 Verify 1LPSW-22 (1C RBCU INLET) is open.
3.3.2 IF 1LPSW-22 (1C RBCU INLET) is NOT open, refer to Technical Specifications and Selected Licensee Commitments 3.4 Monitor RBNS Level for any unexplained increase 3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample RBNS for boron to determine if a cooler rupture has occurred.
3.6 IF RBCU 1C Cooler rupture or line break is indicated, then:
NOTE: This sequence prevents having to call LPSW and Containment inoperable per SLC 16.9.12.
EXAMINER/BOOTH CUE: As BOP performs step 3.6.1, fire timer #4 to initiate PZR Level #1 failure (1HP-120 fails OPEN).
SRO/BOP 3.6.1 Isolate the 1C RBCU Cooler as follows:
A. Close 1LPSW-22 (1C RBCU INLET).
B. Close 1LPSW-24 (RBCU 1C OUTLET). (may already be closed)
C. Perform TS 3.6.3 Condition C (C.1 = 4 hrs & C.2 = 31 days) for closed containment system (as required).
D. Enter TS 3.6.5 Condition B (7 days and 14 days from discovery of failure to meet LCO) for RBCU inoperable.
E. Continue to monitor RBNS level for increase.
F. IF RBNS level is still increasing, notify TSC to evaluate further isolation of 1C RBCU.
This event is complete when the 1C RBCU rupture is isolated, or as directed by the lead examiner.
Page 9 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 3 Page 4 of 4 Event
Description:
Re-occurring Hi Vibration on 1C RBCU Degrades to Cooler Rupture (TS)
Time Position Applicant's Actions or Behavior Crew Response (cont.):
EXAMINER NOTE: The crew may decide to pump the RB Normal Sump. If so, see the steps below from OP/1/A/1104/007 LWD System, Enclosure 4.1 Pumping RBNS to 6" SRO 3.6.2 Refer to Technical Specifications 3.6.3 Refer to SLC 16.9.12 OP/1/A/1104/007 Enclosure 4.1 SRO/BOP 3.1 Verify MWHUT level adequate to receive waste volume.
3.2 Position the following:
- Changes in LAWT levels may occur during pumping.
RIA Alarms may be indicative of gas leakage.
If RBNS level was above 14" when pumps were started, a level increase following securing the RBNS pumps may occur. {7}
3.4 WHEN RBNS is at desired level OR at 6" (low level alarm), ensure the following:
3.5 IF required to close the valves, position the following:
EXAMINER NOTE: The SRO should identify that the inoperability of the 1C RBCU results in entry into TS 3.6.5 Condition B (7 days and 14 days from discovery of failure to meet LCO). Also, as required, the crew may need to perform the required actions for TS 3.6.3 Condition C (C.1 = 4 hrs
& C.2 = 31 days). SRO refers to SLC 16.9.12, but it is not entered because of the sequence by which step 3.6.1 above was performed.
This event is complete when the 1C RBCU rupture is isolated, or as directed by the lead examiner.
Page 10 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
1HP-120 (RC Volume Control) Fails OPEN Time Position Applicant's Actions or Behavior Plant Response:
- OAC alarm for O1E2175 (ICS PZR Level Setpoint) Hi
- PZR level will increase on all channels
- LDST level will decrease
- OAC alarms for all 4 RCP seal injection flow low
- 1SA-2/C-3 (Pressurizer Level HIGH/LOW)
BOP Crew Response:
EXAMINER NOTE: The crew may notice the increase in PZR level prior to receiving statalarm 1SA-2/C-3. If so, they may (IAW OMP 1-18) take manual control of 1HP-120 to restore PZR level to the desired band. If not, they will use the direction of the ARG below to restore PZR level. Either is SRO acceptable.
Alarm Response Guide 1SA-2/C-3 (Pressurizer Level HIGH/LOW))
3.1 Check alternate PZR level indications.
3.2 Check for proper Makeup/Letdown flows and adjust to restore proper level.
3.3 Refer to the following procedures as required:
- AP/1/A/1700/002 (Excessive RCS Leakage)
- AP/1/A/1700/032 (Loss of Letdown).
EXAMINER NOTE : Above statalarm is at 260. If action is not taken until the statalarm actuates, TS 3.4.9 Condition A would be entered with a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time to restore level to within limit (because this 260 indicated is equivalent to the 285 TS limit).
3.4 Refer to Technical Specification 3.4.9. (see above examiner note) 3.5 Refer to Technical Specification 3.3.8.(N/A) 3.6 Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)
This event is complete when Pressurizer Level has been restored to its normal band, or as directed by the lead examiner.
Page 11 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 5 Page 1 of 5 Event
Description:
Dropped control rod with failure of auto runback circuit (TS)
Time Position Applicant's Actions or Behavior Plant Response:
- Group 2 Rod 6 drops into the core
- Statalarm 1SA-4/C-1 (QUADRANT POWER TILT) (in at 2 minutes)
Crew Response:
OATC/BOP/ Crew should perform Plant Transient Response (PTR)
OATC
- OATC reports to the SRO reactor power level and direction of movement.
- The BOP reports expected AUTO Runback did not occur, and monitors RCS pressure and inventory and inserts Control Rods as needed.
- The OATC will adjust FDW and/or control rods as necessary to restore reactor power to the desired control band.
SRO should enter AP/1/A/1700/001 (Unit Runback)
AP/1/A/1700/001 4.1 GO TO the most limiting section per the following table:
Section Runback 4H Asymmetric Control Rod (1%/min to 55%power)
Section 4H 1 IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1.
2 IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx.
NOTE NIs should NOT be calibrated per guidelines contained in OP/1/A/1102/004 (Operation at Power) due to actual power re-distribution within the core as a result of a dropped/misaligned rod.
3 Verify Rx is critical.
- 4. Verify power > 55% when the rod was dropped or misaligned.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 12 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 5 Page 2 of 5 Event
Description:
Dropped control rod with failure of auto runback circuit (TS)
Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Section 4H (continued)
EXAMINER NOTE: Malfunction set to fail Auto runback. Candidate will proceed to RNO 5 Verify Rx runback to 55% core thermal power in progress.
SRO/OATC
- CTPD set at 55%
- ASYMETRIC RODS Runback Light lit
- CTP Demand decreasing
- Reactor power will decrease when the runback catches up with the initial power decrease from the dropped rod.
RNO: 1. Initiate power reduction to 55% core thermal power at 1%/min.
- 2. IF control rods will not insert manually, THEN perform the following:
A. Trip reactor.
B. GO TO Unit 1 EOP.
6 Initiate Encl 5.1 (Control of Plant Equipment During Shutdown). (see page 15)
NOTE The following actions should be performed as quickly as possible due to the complexity of resetting RPS trip setpoints and Tech Spec time limits.
7 Notify SPOC to perform the following:
- Investigate cause of dropped or misaligned control rod.
- Prepare to reduce the following trip setpoints:
o RPS Flux/Flow-Imbalance o RPS High Flux 8 Notify the OSM to ensure the requirements of the following Tech Specs SRO are met:
- TS 3.1.4 (Control Rod Group Alignment Limits)
- TS 3.1.5 (Safety Rod Position Limits)
- TS 3.2.3 (Quadrant Power Tilt)
Booth Cue: When OSM is contacted, inform the team that the OSM is occupied on Unit 3 and cannot verify TS requirements at this time.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 13 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 5 Page 3 of 5 Event
Description:
Dropped control rod with failure of auto runback circuit (TS)
Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Section 4H (continued)
SRO/OATC/ 9 Notify OSM to make notifications as required per OMP 1-14 BOP (Notifications).
10 Verify > 1% SDM with allowance for the inoperable control rod per PT/1/A/1103/015 (Enclosure 13.18, Reactivity Balance Calculation) within one hour.
11 Reduce core thermal power the following limits , ba s e d on the number of RCPs operating, within two hours:
RCPs Allowable Thermal Power (% FP) 3 45 4 60 NOTE:
The following ensures adequate margin in preparation for resetting RPS trip setpoints.
12 IAAT the power decrease is complete, AND any NI is > the following:
RCPs Maximum NI Power (% FP) 3 40 4 55 THEN reduce power until all NIs are the Maximum NI Power limit for the operating RCP combination per Encl 5.4 (Power Reduction).
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 14 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 5 Page 4 of 5 Event
Description:
Dropped control rod with failure of auto runback circuit (TS)
Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Enclosure 5.1 1 IAAT SRO determines all appropriate actions have been taken, SRO/BOP AND the runback is complete, THEN EXIT this Enclosure.
2 Notify the WCC SRO to initiate Enclosure 5.2 (WCC SRO Support During Unit Runback; EXAMINER NOTE: This scenario begins at 75% so steps 3 &4 have already been accomplished.
3 Start the following pumps:
- 1A FDWP SEAL INJECTION PUMP
- 1A FDWP AUXILIARY OIL PUMP
- 1B FDWP AUXILIARY OIL PUMP
- 1B FDWP SEAL INJECTION PUMP.
4 WHEN CTP is 80% ,
THEN stop the following pumps
- 1E1 HTR DRN PUMP
THEN continue this Enclosure.
6 Place the following in MANUAL and close:
- 1FDW-65 NOTE:
1B FDWP is the preferred pump to shut down first.
7 Verify both Main FDWPs operating.
8 Verify 1B FDWP to be shut down first.
9 Adjust the FWP bias counter-clockwise to lower 1B FWP suction flow 1 x 106 lb/hr < 1A FWP suction flow.
10 GO TO Step 12.
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 15 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 5 Page 5 of 5 Event
Description:
Dropped control rod with failure of auto runback circuit (TS)
Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Enclosure 5.1 (continued)
SRO/BOP 12 IAAT both Main FDW pumps running, AND both of the following exist:
- 1B Main FDW pump is first pump to be shut down
- Any of the following alarms occur:
o 1SA-16/A-3 (FWP B FLOW MINIMUM) o 1SA-16/A-4 (FWP B FLOW BELOW MIN),
THEN trip 1B Main FDW Pump.
13 IAAT both Main FDW pumps running, AND both of the following exist:
- 1A Main FDW pump is first pump to be shut down
- Any of the following alarms occur:
o 1SA-16/A-1 (FWP A FLOW MINIMUM) o 1SA-16/A-2 (FWP A FLOW BELOW MIN),
THEN trip 1A Main FDW Pump.
14 IAAT the operating FDWP suction flow < 1.5 x 106 lb/hr, THEN slowly throttle the associated recirc control valve to establish 2300 - 6000 gpm total Condensate flow:
- 1FDW-65 15 Maintain Pzr level between 220 - 250.
EXAMINER NOTE: The SRO should refer to Tech Specs and make the following determinations:
- TS 3.1.4 (Control Rod Group Alignment Limits), Condition A applies.
- TS 3.1.5 (Safety Rod Position Limits), Condition A applies (Safety rods are in Groups 1 - 4)
- TS 3.2.3 (Quadrant Power Tilt), Condition A applies (due to misaligned control rod) (If the highest Incore QPT exceeds +7.11 then Condition B would apply)
This event is complete when Rx Power has decreased at least 10% and FWP suction has been adjusted, or as directed by the lead examiner.
Page 16 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event
Description:
1TB 6900v lockout trips 2nd RCP (1A2) requiring manual Rx trip Time Position Applicant's Actions or Behavior Plant Response:
1TB lockout will occur. This will cause a loss of 6900V power to the 1A2 and 1B2 RCP (1B2 already tripped). RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power.
Crew Response:
Recognizes the reactor should have tripped (< 3 RCPs operating with OATC Reactor power >2%. (OMP 1-18 Att. A), therefore manually trips the Reactor and then perform Immediate Manual Actions of the EOP.
3.1 Depress REACTOR TRIP pushbutton.
3.2 Verify reactor power < 5% FP and decreasing.
3.3 Depress turbine TRIP pushbutton.
3.4 Verify all turbine stop valves closed.
3.5 Verify RCP seal injection available.
EXAMINER NOTE: The steam line break is automatically fired when the rods hit the bottom from the manual Rx trip. With an Excessive Heat Transfer in progress the SRO should not get an opportunity to take any of the Subsequent actions in the SA Tab.
- The BOP will perform a symptom check. See Event #7 (next page) for expected results of symptom check.
This event is complete when an operator has manually tripped the Reactor and the IMAs have been performed, or as directed by the lead examiner.
Page 17 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 1 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior Plant response:
- 1SA-2/D-3, RC Press High/Low
- 1SA-02/A-9 (MS PRESS HIGH/LOW)
- ES Channels 1& 2 will actuate Crew response:
BOP will perform a Symptoms Check (per OMP 1-18 Attachment C)
SROBOP
- Reactivity Control o Power Range NIs < 5% and decreasing
- ICC/Loss of Subcooling Margin (SCM) o If any SCM 0°F, perform Rule 2
- Loss of Heat Transfer (LOHT) o Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)
- Excessive Heat Transfer (EHT) o Uncontrolled Main Steam Line(s) pressure decrease
- Steam Generator Tube Rupture o CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA-16/17)
OATC/BOP Perform Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (details on page 22)
If SCM reaches 0°F at the beginning of the MSLB, Rule #2 will be performed (details on page 19)
SRO will direct performance of EOP Enclosure 5.1 (ES Actuation) (details begin on page 27)
SRO refers to Parallel Actions page of the Subsequent Actions Tab and
- if SCM > 0°F transfers to the Excessive Heat Transfer Tab (page 31)
- if SCM = 0°F transfers to LOSCM tab (page 30)
The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202 This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 18 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 2 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior BOOTH CUE: Notify the NRC is SCM is lost.
OATC/BOP EOP Rule 2
- 1. IAAT all exist:
- Any SCM 0°F
- Rx power 1%
- 2 minutes elapsed since loss of SCM THEN perform Steps 2 and 3
- 2. Stop all RCPs (CT-1) (Within 2 minutes of LOSCM)
- 4. Verify Blackout exists RNO: GO TO Step 6
- 7. Start all available HPI pumps
- 8. GO TO Step 13
- 14. Verify at least two HPI pumps are operating using two diverse indications
- 15. IAAT 2 HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps 16 - 21.
RNO: GO TO Step 17
- 17. IAAT flow limits are exceeded Pump Operation Limit 1 HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI Total flow of 950 pumps operating gpm (incl. seal with 1HP-409 injection) open THEN perform Steps 18 - 20 RNO: GO TO Step 21 This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 19 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 3 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior Rule 2 (cont.)
OATC/BOP 21. Notify CR SRO of HPI status.
- 22. Verify RCS pressure > 550 psig.
- 23. IAAT either exists:
- 35. IAAT TBV's are unavailable, THEN A Dispatch two operators to perform Encl 5.24 (Operation of ADVs)
B Notify CR SRO the ADVs are being aligned for use.
RNO: Select OFF for both digital channels on AFIS HEADER A.
RNO: Select OFF for both digital channels on AFIS HEADER B.
- 38. Verify any EFDW pump operating.
- 1A MD EFDWP
- 40. Verify any EFDW pump operating.
- 43. Verify both MD EFDWPs operating.
RNO: If 1 TDEFWP is operating, OR NO Main FDW Pumps are operating THEN GO TO step 45.
- 45. Trip both Main FDW pumps.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 20 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 4 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior Rule 2 (cont.)
OATC/BOP 46. Place FDW block valve switches in CLOSE:
If Main FDW is feeding any SG, Rule 7 provides a different SG Level Control Point.
TS cooldown rates are 50°F/1/2 hr when Tcold > 280°F and 25°F/1/2 hr when Tcold 280°F.
- 47. Begin feeding all intact SGs to the appropriate SG Level Control Point in Rule 7 (SG Feed Control) using available feed sources;
- 48. IAAT SG Level Control Point is reached, Then maintain SG Level Control Point by feeding and steaming as necessary.
CAUTION If 1 TD EFDW PUMP is being used for SG feed and Unit 1 is supplying the Auxiliary Steam header, reducing SG pressure below 250 psig can result in reduced pumping capability.
- Dispatch two operators to perform Encl 5.24 (operation of the ADVs)
- 51. Verify any Main FDW pump operating.
RNO: GO TO Step 58.
- 58. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete.
- 59. WHEN directed by CR SRO, THEN EXIT this rule.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 21 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 5 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Rule 5 OATC/BOP
- 1. Perform the following on affected headers:
EXAMINER NOTE: AFIS did not auto actuate because a malfunction is preventing it, but the manual initiation below does work.
- Select OFF for 1B MDEFDW Pump EXAMINER NOTE: Overcooling must be stopped prior to violating NDT limits. The critical task is to stop feeding the affected SG.
- Trip both Main FDW pumps
- Close 1FDW-316, 1FDW-42, and 1FDW-40 EXAMINER NOTE: TD EFDW Pump tripped by AFIS and 1A MD EFDWP did not start and will not manually start.
- 2. Verify 1 TD EFDW PUMP operating.
RNO: 1. IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5
- 2. Start 1 TD EFDW Pump
- 3. Verify 1 TD EFDW Pump is feeding affected SG.
RNO: GO TO Step 5
- 7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either:
- Send two operators to perform Encl 5.24 (Operation of ADVs)
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 22 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 6 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Rule 5 (continued)
OATC/BOP CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
- 8. WHEN all of the following exist:
- Core SCM >0° F
- Rx Pwr 1%
- Pzr Level increasing, THEN continue
- 10. Place Diverse HPI in BYPASS
- 12. Perform the following to stabilize RCS P/T:
- Throttle HPI
- Reduce 1HP-120 setpoint to > 100 (180 ACC)
- 14. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (see next page)
- 15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete (see page 26)
- 16. WHEN directed by CR SRO, THEN EXIT this rule This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 23 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 7 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Rule 3 (as directed by Rule 5)
OATC/BOP 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding.
RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- 5. Verify any EFDW pump operating.
- 6. GO TO Step 37.
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42.
RNO: GO TO Step 43
- 43. Verify any SCM 0°F.
RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),
THEN throttle EFDW, as necessary.
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation). (see next page)
- 45. WHEN directed by CR SRO, THEN EXIT this rule.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 24 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 8 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior OATC/BOP Encl 5.9 (Extended EFDW Operation) as directed by Rule 3
- 1. Monitor EFDW parameters on EFW graphic display.
- 2. IAAT UST level is < 4',
THEN GO TO Step 120
- 8. Perform the following as required to maintain UST level > 7.5':
- Makeup with demin water.
- Place CST pumps in AUTO.
- 9. IAAT all the following exist:
- Rapid cooldown NOT in progress
- EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
- 10. Verify 1 TD EFDW PUMP operating.
- 11. Start TD EFDWP BEARING OIL COOLING PUMP.
NOTE
- Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open.
- If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 25 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 9 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior OATC/BOP Rule 8 (as directed by Rule 5)
EXAMINER NOTE: Neither of the criteria in the note below are met so no actions are required in Rule 8. If the crew pulls Rule 8 as directed by Rule 5, they should immediately EXIT back out based on the note at the beginning.
NOTE This rule is invoked under either of the following conditions:
- A cooldown below 400°F Tc at > 100 °F/hr has occurred.
- SCM must be minimized. The following methods may be used at the discretion of the CR SRO:
- De-energizing Pzr heaters
- Using Pzr normal spray
- Using Pzr aux spray
- Using PORV
- Throttling LPI {22}
- Once RCS temperature is stable, a 1-hour hold of RCS temperature must be performed unless a LOCA or SGTR is in progress. Use Tc in loop with an operating RCP or use CETCs if NO RCPs are operating.
- Once invoked, SCM shall remain minimized until Engineering has performed an evaluation and determined that PTS restrictions NO longer apply. Starting RCPs and/or restoring cool down rates to normal values do NOT negate the need for this evaluation.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 26 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 10 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Enclosure 5.1 (ES Actuation)
OATC/BOP
- RCS 1600 psig: Channels 1, 2
- 2. Verify all ES digital channels associated with actuation setpoints have actuated.
- 3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1-2.
- 4. Place Diverse HPI in BYPASS
- 6. Verify Rule 2 in progress or complete.
RNO: GO TO Step 73
- 74. Ensure at least two HPI pumps are operating
- 75. Verify 1HP-26 and 1HP-27 are open NOTE TO EXAMINER: Conditions not met to require opening 1HP-410 or 1HP-409. No operator action required at this time by step 76.
- 76. IAAT at least two HPI pumps are operating, AND HPI flow in any header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:
1A Header 1B Header 1HP-410 1HP-409
- 77. Verify any RCP operating
- 79. IAAT all exist:
- Voter associated with ES channel is in OVERRIDE
- An ES channel is manually actuated
- Components on that channel required manipulation THEN depress RESET on the required channel This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 27 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 11 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Enclosure 5.1 (ES Actuation) (continued)
OATC/BOP
- 80. IAAT any RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 81 - 84 RNO: GO TO Step 85
- 85. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 86 RNO: GO TO Step 123.
123. Start A & B Outside Air Booster Fans.
124. Notify Unit 3 to Start 3A & 3B Outside Air Booster Fans.
125. Verify open 1CF-1 and 1CF-2.
126. Verify 1HP-410 closed.
127. Secure makeup to the LDST.
128. Verify all ES channel 1 & 2 components are in the ES position.
129. Verify Unit 2 turbine tripped.
RNO: GO TO Step 132 132. Close 1LPSW-139.
133. Place in FAIL OPEN:
- 1LPSW-251 FAIL SWITCH
135. Verify either:
- Three LPSW pumps operating
- Two LPSW pumps operating when Tech Specs only requires two operable 136. Open 1LPSW-4 and 1LPSW-5 137. IAAT BWST level 19',
THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).
138. Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service).
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 28 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 12 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Enclosure 5.1 (ES Actuation) (continued)
OATC/BOP 139. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.
140. Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary.
141. IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).
142. WHEN CR SRO approves, THEN EXIT.
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 29 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 13 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP LOSCM tab SRO The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202
- 1. Ensure Rule 2 in progress or complete
- 2. Verify Station ASW feeding SG (it is not).
RNO: GO TO step 4
- 4. Verify LOSCM caused by Excessive Heat Transfer
- 5. Verify EHT tab has been performed (it has not been).
RNO: GO TO EHT tab (details begin on next page)
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 30 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 14 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EOP Excessive Heat Transfer Tab (EHT)
SRO The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202
- 1. Verify any SG pressure < 550 psig
- 2. Ensure Rule 5 (Main Steam Line Break) in progress or complete
- 3. Place the following in HAND and decrease demand to zero on all affected SGs:
- 4. Close the following on all affected SGs:
- 5. Verify level in both SGs < 96% O.R.
- 6. IAAT core SCM is > 0°F, THEN perform Steps 7 and 8
Note: HPI flow must be throttled and RCS temperature controlled to prevent a solid Pzr and subsequent operation of the PORV.
- 8. Verify letdown in service.
RNO: IF desired to restore letdown, THEN initiate Encl 5.5 (Pzr and LDST Level Control) (see page 37)
NOTE If only one SG is intact and has been isolated for SGTR, the following steps will unisolate and use it for heat removal.
- 10. Open the following on all intact SGs
- 11. Start MDEFDWP associated with all intact SGs
- 1A MD EFDWP RNO: Start TDEFDWP
- Dispatch two operators to perform Encl 5.24 (Operation of the ADVs)
This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 31 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 7 Page 15 of 15 Event
Description:
1B MSLB outside the reactor building Time Position Applicant's Actions or Behavior EHT Tab (continued)
SRO 13. GO TO Step 32
- 32. Verify any of the following:
- A cooldown below 400°F at > 100°F/hr has occurred RNO: GO TO Step 34 BOOTH CUE: Fire Timer 8 after step 11 to fail 1FDW-315 OPEN.
- 35. Open 1AS-8
- 36. Close 1SSH-9
- 37. Perform the following notifications:
- Notify Secondary Chemistry to check for indications of SGTR
- Notify RP to check for indications of a SGTR This event is complete when step 11 complete in EHT Tab or as directed by the lead examiner Page 32 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 8 Page 1 of 2 Event
Description:
1FDW-315 fails OPEN Time Position Applicant's Actions or Behavior ALL Plant response:
- 1FDW-315 will indicate full open
- 1A SG level will increase above the setpoint (30 inches XSUR)
Crew response:
The crew should determine that 1FDW-315 is open and perform Rule 3 IAAT step 37 or may re-perform Rule 3.
Rule 3 will:
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding.
RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- 5. Verify any EFDW pump operating.
- 6. GO TO Step 37.
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42.
- 38. Place EFDW valve in MANUAL.
- 39. Control EFDW flow with EFDW valve in MANUAL. (will not work)
RNO: GO TO Step 41
- 41. Notify CR SRO that Encl 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiated.
This event is complete when EFDW flow has been established to the 1A SG via the startup control valves or as directed by the lead examiner.
Page 33 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Op-Test No.: ILT44 Scenario No.: 2 Event No.: 8 Page 2 of 2 Event
Description:
1FDW-315 fails OPEN Time Position Applicant's Actions or Behavior ALL EOP Encl 5.27 (Alternate Methods for Controlling EFDW Flow)
- 1. Identify the failure: 1FDW-315 failed OPEN. GO TO Step 16.
- 16. Verify 1A MD EFDWP operating.
- 17. Stop 1A MD EFDWP.
- 18. Place 1TD EFDW PUMP in PUMP TO LOCK.
- 19. Place 1FDW-35 in HAND and set demand to 0%.
- 20. Close 1FDW-33.
- 21. Verify 1A MD EFDWP will be used.
- 22. Perform the following:
- Close 1FDW-372
- Open 1FDW-374
- 23. Verify the following:
- 1FDW-36 closed
- 1FDW-38 open
- 24. Start 1A MD EFDWP
- 25. Verify either of the following exists:
- HP Forced Cooling is maintaining core cooling
- 25. RNO
- 2. IF NO SG is being fed, AND Tc > 550ºF, THEN perform the following:
A. Throttle 1FDW-35 to establish a maximum of 100 gpm.
B. Initiate cooldown to 550ºF by feeding with 1FDW-35 and steaming intact SGs at a rate that prevents RCS saturation.
- 3. IF NO SG is being fed, AND Tc 550ºF, THEN perform the following:
A. Throttle 1FDW-35 to establish a maximum of 100 gpm.
B. Feed with 1FDW-35 and steam intact SGs to stabilize Tc to 550ºF.
This event is complete when EFDW flow has been established to the 1A SG via the startup control valves or as directed by the lead examiner.
Page 34 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 1 of 8 EXAMINER NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See excerpt below.
ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
- 1. Utilize the following as necessary to maintain __ IF 1HP-26 will NOT open, desired Pzr level: THEN throttle 1HP-410 to maintain
- 1A HPI Pump desired Pzr level.
- 1B HPI Pump
- 1HP-120 setpoint or valve demand
- 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
- 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.
- 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
__ 1CS-26
__ 1CS-41 B. Position 1HP-14 to BLEED.
C. Notify SRO.
- 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.
Page 35 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 2 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. IAAT 1C HPI PUMP is required, __ GO TO Step 10.
THEN perform Steps 7 - 9.
- 7. Open: 1. __ IF both BWST suction valves
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 8.
A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.
B. __ IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C. __ GO TO Step 9.
Page 36 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 3 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. Start 1C HPI PUMP. __ IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level.
- 9. Throttle the following as required to 1. __ IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain
- 1HP-26 desired Pzr level.
- 2. __ IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.
Page 37 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 4 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. IAAT LDST level CANNOT be __ GO TO Step 12.
maintained, THEN perform Step 11.
- 11. Perform the following: 1. __ IF both BWST suction valves
- Open 1HP-25.
A. __ Start 1A LPI PUMP.
- Close 1HP-16.
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 12.
- 2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP.
Page 38 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 5 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
- 13. IAAT two Letdown Filters are desired, THEN perform the following:
- Open 1HP-17.
- Open 1HP-18
- 14. IAAT all of the following exist: __ GO TO Step 34.
- Letdown isolated
- LPSW available
- Letdown restoration desired THEN perform Steps 15 - 33. {41}
- 15. Open: 1. __ Notify CR SRO that letdown CANNOT be
- 1CC-8 system.
- 2. __ GO TO Step 34.
- 16. Ensure only one CC pump running.
- 17. Place the non-running CC pump in AUTO.
- 1HP-1 close,
- 1HP-2 THEN GO TO Step 20.
- 19. GO TO Step 22.
NOTE Verification of leakage requires visual observation of East Penetration Room.
- 20. Verify letdown line leak in East __ GO TO Step 22.
Penetration Room has occurred.
- 21. GO TO Step 34.
Page 39 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 6 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. Monitor for unexpected conditions while restoring letdown.
- 23. Verify both letdown coolers to be placed 1. __ IF 1A letdown cooler is to be placed in in service. service, THEN open:
__1HP-1
__1HP-3
- 2. __ IF 1B letdown cooler is to be placed in service, THEN open:
__1HP-2
__1HP-4
- 3. __ GO TO Step 25.
- 24. Open:
- 25. Verify at least one letdown cooler is Perform the following:
aligned. A. __ Notify CR SRO of problem.
B. __ GO TO Step 34.
- 26. Close 1HP-6.
- 27. Close 1HP-7.
- 28. Verify letdown temperature < 125°F. 1. __ Open 1HP-13.
- 2. Close:
__1HP-8
__1HP-9&11
- 3. __ IF any deborating IX is in service, THEN perform the following:
A. __Select 1HP-14 to NORMAL.
B. __Close 1HP-16.
- 4. __ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 40 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 7 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 29. Open 1HP-5.
- 30. Adjust 1HP-7 for 20 gpm letdown.
- 31. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
- 32. Open 1HP-6.
- 33. Adjust 1HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
- 34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
- 35. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A. Obtain SRO concurrence to reduce running HPI pumps.
B. Secure the desired HPI pumps.
C. Place secured HPI pump switch in AUTO, if desired.
- 36. IAAT all the following conditions exist:
- Makeup from BWST NOT required
- LDST level > 55
- All control rods inserted
- Cooldown Plateau NOT being used THEN close:
- 1HP-25 Page 41 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam Page 8 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 37. Verify 1CS-48 (1A BHUT Recirc) has __ GO TO Step 39.
been closed to provide additional makeup flow to LDST.
- 38. WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A. Stop 1A BLEED TRANSFER PUMP.
B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
C. Close 1CS-46.
D. Start 1A BLEED TRANSFER PUMP.
E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure.
F. Stop 1A BLEED TRANSFER PUMP.
- 39. Verify two Letdown Filters in service, __ GO TO Step 41.
AND only one Letdown filter is desired.
- 40. Perform one of the following:
- Place 1HP-17 switch to CLOSE.
- Place 1HP-18 switch to CLOSE.
- 41. WHEN directed by CR SRO, THEN EXIT this enclosure.
- *
- END
- Page 42 of 44
Appendix D Required Operator Actions Form ES-D-2 ILT44 NRC Exam CRITICAL TASKS
- 1. CT-1, Stop all RCPs (Within 2 minutes of LOSCM). page 19 (contingent on LOSCM due to overcooling)
- 3. CT-5, Throttle HPI per Rule 6. page 31 Page 43 of 44
SAFETY: Take a Minute UNIT 0 (OSM)
SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 75% Mode: 1 Mode: 1 Gross MWE: 702 100% Power 100% Power RCS Leakage: .024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: .01 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time SSF Today 0000 7 Days TS 3.10.1 A B C D E Shift Turnover Items (CR SRO)
Primary
- SASS in Manual for I&E Secondary
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
- Holding power at 75% to facilitate work on 1B FDWP.
- 1B FWPT on Handjack
- Voltage Regulator in Manual for maintenance. I&E ready to return it to Auto and reduce VARs to approximately 150 (+ 10) using OP/1/A/1106/001, Encl 4.8 (Changing Generator MVAR) to verify proper operation. SOC is already notified the Voltage Regulator will be swapped to AUTO Reactivity Management (CR SRO)
R2 Reactivity management controls RCS Boron: 86 ppmB Gp 7 Rod Position: 75% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)
Procedure Use and Adherence
Facility: Oconee Scenario No.: 3 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO
________________________ ________________________OATC
________________________ ________________________BOP Initial Conditions:
- Reactor power = 0.02%; below POAH Unit 2: 100%, Unit 3: 100%
Turnover:
- Unit 1 Startup in progress; BOL; not after refueling
- Startup procedure at step 3.36 (OP/1/A/1102/001 Encl 4.7)
- Increase Reactor power to 6 -7%
Event Malfunction Event Event Type* Description No. No.
0a Override Auto start of HPIP on low seal injection flow is blocked 0b Override 1HP-26 failed CLOSED 0c 1 R, OATC, SRO Increase reactor power to 6 -7%
2 Override C: BOP, SRO(TS) Inadvertent ES Channel 7 actuation 3 MPS270,1 C: BOP, SRO High Oil Level on 1A2 RCP 1A HPI pump trips and standby HPI pump fails to auto 4 Override C: BOP, SRO (TS) start 5 Override C: OATC, SRO, PZR Spray Valve (1RC-1) Fails OPEN 6 Override C: OATC, SRO Operating Main FDW Pump trip and ATWS MEL170 M: ALL Blackout Requiring Manual Alignment From CT-4 CT-1 Lockout 7 MEL180 KHU-2 Emergency Lockout 8 MSS330 TDEFWP trips
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 1 Page 1 of 1 Event
Description:
Increase reactor power to 6 - 7%
Time Position Applicant's Actions or Behavior Crew response:
OP/1/A/1102/001 (Controlling Procedure for Unit Startup)
OATC/SRO NOTE:
POAH is normally achieved from 0.05 to 0.15% power on Wide Range Indications.
When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, & SUR will decrease with negative Moderator Temperature Coefficient.
Wide Range indications are used since Source Range NIs saturate.
3.36 Begin reactor power increase to 0.5 - 1.0% at 0.5 DPM SUR.
3.37 WHEN above POAH, begin reactor power increase to 2.5 -3.5%.
3.38 WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215 to 225 PZR Level NOTE:
TAVE error is blocked when on Low Level Limit and TAVE is < setpoint.
Core reactivity effects are minimized with Rx in automatic. (R.M.)
3.39 WHEN at 2.5% - 3.5% Power, perform the following:
- Place REACTOR MASTER to "AUTO".
- Place DIAMOND to "AUTO".
- Ensure TURBINE MASTER Setpoint to 880 - 890 psig.
3.40- 3.42 already completed 3.43 WHILE power change is in progress, monitor the following indications:
- Appropriate ranged Nis
- Neutron error
- RCS Loop T and FDW Flow
- OAC Point O1E2129 and O1E2130 3.44 Begin power increase to 6% - 7% per Encl. 4.16 (CTP Adjustments) (See page 39)
Event is complete when ICS is placed in AUTO and CTP is 6-7% or when directed by the Lead Examiner.
Page 2 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 2 Page 1 of 4 Event
Description:
Inadvertent ES Channel 7 actuation (TS)
Time Position Applicant's Actions or Behavior Plant Response:
- 1A RBS pump will start
- 1BS-1 will open
SRO/OATC Crew Response:
The SRO will initiate AP/1/A/1700/042 Inadvertent ES Actuation 4.1 Verify any of the following have inadvertently actuated:
__ Diverse HPI (not actuated)
__ ES Channel 1 (not actuated)
__ ES Channel 2 (not actuated)
RNO: GO TO step 4.4 4.4 Verify any of the following have inadvertently actuated:
__ ES Channel 5 (not actuated)
__ ES Channel 6 (not actuated)
RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 Encl 5.2 (Letdown Restoration)
- 2. GO TO Step 4.10 4.10 Close 1HP-24 and 1HP-25 NOTE If personnel are available, progression should continue while Encl 5.1 (Required Operator Actions) is in progress.
4.11 Ensure AP/42 Encl 5.1 (Required Operator Actions) is in progress (see page 5) 4.12 Verify any of the following have inadvertently actuated:
__ Diverse LPI
__ ES Channel 3
__ ES Channel 4 RNO: GO TO Step 4.17 This event is complete when the SRO has referred to TS at step 4.25, or as directed by the Lead Examiner.
Page 3 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 2 Page 2 of 4 Event
Description:
Inadvertent ES Channel 7 actuation (TS)
Time Position Applicant's Actions or Behavior AP/42 (continued) 4.17 Verify the Rx is critical CAUTION Do NOT add demin water to counter the boration until RCS boron SRO/OATC concentration stabilizes to prevent a positive reactivity event.
NOTE ICS in Auto means ICS is in control of Tave and Rx power.
4.18 Verify ICS in Auto Examiner Note: Rods will not go outside the desired control band since there is no reactivity event associated with ES-7 actuation.
4.19 Verify control rods are outside the desired control band RNO: GO TO Step 4.21 4.21 Verify any of the following have inadvertently actuated:
__ ES Channel 1
__ Diverse HPI RNO: GO TO Step 4.24 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary 4.25 Initiate logging TS/SLC Entry/Exit, as applicable, IAW Encl 5.4 (TS/SLC Requirements)
EXAMINER NOTE: TS 3.3.7 (Engineered Safeguards Protective System (ESPS) Digital Automatic Actuation Logic Channels) due to the automatic actuation logic being blocked if any ES channel is in MANUAL or ES Voters in OVERRIDE.
Enter TS 3.3.7. The required action is to place the component in ES configuration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The RBS pump will be stopped due to pumping water into the RB. This will require declaring the RBS pump inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and entering TS 3.6.5 Condition A.
4.26 WHEN all of the following exist:
__ Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has been resolved
__ ES Channel or Diverse HPI/LPI reset is desired
__ OSM concurs THEN continue This event is complete when the SRO has referred to TS at step 4.25, or as directed by the Lead Examiner.
Page 4 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 2 Page 3 of 4 Event
Description:
Inadvertent ES Channel 7 actuation (TS)
Time Position Applicant's Actions or Behavior Crew Response:
AP/1/A/1700/042 Enclosure 5.1 Required Operator Actions 1 Initiate announcement of AP entry using the PA system SRO/BOP 2 Verify any of the following have inadvertently actuated:
__ Diverse HPI (not actuated)
__ ES Channel 1 (not actuated)
__ ES Channel 2 3 Open the following:
__ 1HP-20
__ 1HP-21 4 Open the following for operating RCPs:
__ 1HP-228 (1A1)
__ 1HP-226 (1A2)
__ 1HP-232 (1B1)
__ 1HP-230 (1B2) 5 Verify any of the following have inadvertently actuated:
__ ES Channel 7 (not actuated)
__ ES Channel 8 (not actuated) 6 Perform the following on all inadvertently actuated channel(s):
__ Ensure ES CH-7 is in MANUAL
__ Ensure ES CH-8 is in MANUAL 7 Stop the following:
__ 1A RBS PUMP
__ 1B RBS PUMP 8 Close the following:
__ 1BS-1
__ 1BS-2 9 Perform the following:
A. Open the following to restore RB RIAs:
__ 1PR-7
__ 1PR-8
__ 1PR-9
__ 1PR-10 B. From the ENABLE CONTROLS screen on the RIA View Node, perform the following:
- 1. Select OFF for RB RIA sample pump
- 2. Start the RB RIA sample pump This event is complete when the SRO has referred to TS at step 4.25, or as directed by the Lead Examiner.
Page 5 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 2 Page 4 of 4 Event
Description:
Inadvertent ES Channel 7 actuation (TS)
Time Position Applicant's Actions or Behavior AP/42 Encl. 5.1 (Cont.)
- 10. Verify any of the following have inadvertently actuated:
SRO/BOP
__ Diverse HPI
__ ES Channel 1 RNO: GO TO Step 12
- 12. EXIT this enclosure This event is complete when the SRO has referred to TS at step 4.25, or as directed by the Lead Examiner.
Page 6 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 3 Page 1 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position Applicant's Actions or Behavior Plant Response:
Crew Response:
SRO/BOP Refer to Alarm Response Guide for V (RCP 1A2 MTR LOWER OIL POT LEVEL)
- 1) If RCP operating GO TO AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation)
AP/1/A/1700/016, Abnormal RCP Operation 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria),
THEN perform Steps 4.2 - 4.11.
RNO: GO TO Step 4.12 EXAMINER NOTE: In step 4.12, the crew may conservatively decide to secure the RCP because the oil pot level is threatening to go offscale high. If so, they will proceed to step 4.13 and will not end up in Section 4C. This path is on page 8. This path or the path below are acceptable 4.12 IAAT either of the following apply:
- It is desired to secure a RCP THEN perform Steps 4.13 - 4.15.
RNO: GO TO Step 4.16 4.16 Announce AP entry using the PA system.
4.17 Notify OSM to request evaluation by RCP Component Engineer.
4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
Section Failure 4A Seal Failure 4B Abnormal Vibration 4C High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP Temperatures This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 7 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 3 Page 2 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position Applicant's Actions or Behavior AP/1/A/1700/016, Section 4C SRO/BOP 1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria),
THEN perform Steps 2 - 11.
RNO: GO TO Step 12 12 Start trending RCP oil pot levels. (Turn-on Code "unitpump"RCPT3, example 1A2RCPT3)
NOTE
- RCP oil pot level indication range is +1.5 to -1.5 inches.
- RCP motor oil pot temperatures and RCP motor guide bearing temperatures may be used to validate low oil pot level. {4}
13 IAAT oil pot level threatens to go off scale high or low for an operating RCP, THEN perform Steps 14 - 24.
14 Verify MODE 1 or 2.
15 Verify three RCPs will remain operating after affected RCP is tripped.
16 Verify Rx power is 70% as indicated on all NIs.
17 Verify any SG on Low Level Limits.
EXAMINER NOTE: STATALARMS 1SA-07/D-8 (1A2 RCPMP Trip), 1SA-02/A-3 (RC Loop A Flow Low), & 1SA-02/A-5 (RC Total Flow Low) will alarm when the 1A2 RCP is stopped.
18 Stop the affected RCP.
19 GO TO Step 23.
23 Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). NOTE: Just requires monitoring parameters.
24 Make the following notifications:
- Notify OSM to make required notifications of OMP 1-14 (Notifications).
- Notify Rx Engineering and request a power maneuver plan, if needed.
- Notify SOC if load reduction was required.
- Notify Chemistry to take RCS boron samples on a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> frequency.
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 8 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 3 Page 3 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position Applicant's Actions or Behavior SRO/BOP AP/1/A/1700/016, Section 4C (continued) 25 IAAT an RB fire exists, THEN perform Steps 26 - 29.
RNO: GO TO Step 30 30 IAAT either of the following conditions is met:
- a RCP with low oil level has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> , {9}
- a RCP with high oil level has been shut down THEN close the associated RCP motor cooler inlet/outlet valve:
- 1LPSW-11&12 (1B2 RCP) 31 IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart. {8}
32 WHEN conditions permit, THEN EXIT this procedure.
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 9 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 3 Page 4 of 4 Event
Description:
High Oil Level on 1A2 RCP Time Position Applicant's Actions or Behavior AP/1/A/1700/016, (continued)
SRO/BOP 4.13 Verify Rx Power > 70%.
RNO: GO TO Step 4.15 4.15 WHEN Rx Power is 70% ,
THEN GO TO Step 4.2.
4.2 Verify MODE 1 or 2.
4.3 Verify Rx power is 70% a s indica te d on all NIs.
4.4 Verify three RCPs will remain operating after affected RCP is tripped.
4.5 Verify any SG on Low Level Limits.
4.6 Stop the affected RCP.
4.7 GO TO Step 4.26.
4.26 Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power).
4.27 IAAT an RCP has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, {9}
THEN close the associated RCP motor cooler inlet/outlet valves:
This event is complete when actions to secure the 1A2 RCP are completed, or as directed by the Lead Examiner.
Page 10 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 4 Page 1 of 3 Event
Description:
1A HPI pump trips and standby HPI pump fails to auto start (TS)
Time Position Applicant's Actions or Behavior Plant response:
Statalarms:
Board indications:
- RC Makeup Flow = ~0 gpm
- 1A HPI Pump amps low = 0 amps PZR level will begin to decrease and LDST level will begin to increase.
Crew response:
Refer to ARGs: Refer to AP/14 AP/1/A/1700/014, Loss of Normal HPI Makeup and/or RCP Seal Injection SRO/OATC 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:
A. Trip the Rx.
B. Stop all RCPs.
C. Initiate AP/25 (SSF EOP).
3.2 IAAT loss of suction to operating HPI pumps is indicated:
- Motor amps low or cycling
- Discharge pressure low or cycling
- Abnormal LDST level trend THEN GO TO Step 3.3.
RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System.
4.8 Verify any HPI pump operating.
RNO 1. Close 1HP-5
- 2. Place 1HP-120 in HAND and closed
- 3. Place 1HP-31 in HAND and closed
- 5. IF standby HPI pump started, THEN GO TO Step 4.111.
This event is complete when 1HP-31 is placed in AUTO, or as directed by the Lead Examiner.
Page 11 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 4 Page 2 of 3 Event
Description:
1A HPI pump trips and standby HPI pump fails to auto start (TS)
Time Position Applicant's Actions or Behavior AP/14, Loss of Normal HPI Makeup and/or RCP Seal Injection (continued)
OATC/BOP 4.111 Place 1HP-31 in HAND 4.112 Slowly open 1HP-31 until 8 gpm/RCP is achieved.
4.113 Re-establish normal makeup through 1HP120.
4.114 Ensure proper operation of the Component Cooling System.
4.115 Reduce 1HP-7 demand to 0%.
4.116 Close 1HP-6 4.117 Open the following:
1HP-1 1HP-2 1HP-3 1HP-4 BOOTH NOTE: Crew may direct AO to open & rack out the 1A HPIP breaker. (Use Quick Strike to remove fuses) 4.118 Open 1HP-5 4.119 Throttle open 1HP-7 for 20 gpm letdown flow.
4.120 Open 1HP-6 4.121 Adjust 1HP-7 for desired letdown flow.
4.122 Open the following:1HP-228, 1HP-226,1HP-232, 1HP-230 4.123 Open 1HP-21.
4.124 IAAT SEAL INLET HDR FLOW 32 gpm, THEN place 1HP-31 in AUTO 4.125 Monitor RCP seal parameters.
4.126 Maintain RCP seal injection flows as required.
4.127 Log thermal cycle of 1A HPI header.
4.128 WHEN conditions permit, THEN EXIT this procedure.
Note: Crew may enter AP/16 (Abnormal RCP Operation) as a result of high seal return temperatures. Steps are on the next page.
This event is complete when 1HP-31 is placed in AUTO, or as directed by the Lead Examiner.
Page 12 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 4 Page 3 of 3 Event
Description:
1A HPI pump trips and standby HPI pump fails to auto start (TS)
Time Position Applicant's Actions or Behavior AP/16 (Abnormal RCP Operation)
OATC/BOP 4.1 IAAT any RCP meets immediate trip criteria (does not)
RNO: GO TO Step 4.12 4.12 IAAT all of the following apply:
- Any RCP approaching immediate trip criteria of Encl 5.1.
- It is desired to secure a RCP THEN perform Steps 4.13 - 4.15:
RNO: GO TO Step 4.16 4.16 Announce AP entry using the PA system.
4.17 Notify OSM to request evaluation by RCP Component Engineer.
4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:
4D Loss of Seal Return AP/16 (Abnormal RCP Operation) Section 4D
- 1. IAAT any RCP meets immediate trip criteria (does not)
RNO: GO TO Step 12
- 15. Verify either of the following (not met)
RNO GO TO Step 17.
- 17. Verify RCP seal return low flow alarms off.
RNO: Request that RCP Component Engineer provide the following:
- Immediate evaluation
- Additional monitoring requirements EXAMINER CUE: If candidate attempts to monitor the Loose part Monitor, indicate that the noise is normal.
EXAMINER NOTE: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency. Tech Spec 3.5.2 High Pressure Injection
- Condition A
- Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> This event is complete when 1HP-31 is placed in AUTO, or as directed by the Lead Examiner.
Page 13 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 5 Page 1 of 3 Event
Description:
PZR Spray Valve (1RC-1) Fails OPEN Time Position Applicant's Actions or Behavior Booth Cue: Call control room as Secondary Chemist and request position of 1AS-35 (Stm to E Heaters) and steam flow to E heaters. While BOP is at vertical boards, fire Timer 5 to initiate event.
Plant Response:
- RCS pressure will decrease
- 1SA-2/D-3 (RC PRESS HIGH/LOW)
Crew Response:
EXAMINER NOTE: The crew may perform Plant Transient Response (PTR)
Refer to Alarm Response Guide 1SA-2/D-3 (RC PRESS HIGH/LOW) 3.2 Low Alarm 3.2.1 Refer to AP/1/A/1700/044 (Abnormal Pressurizer Pressure Control)
AP/1/A/1700/044 (Abnormal Pressurizer Pressure Control)
SRO/OATC 3. Immediate Manual Actions 3.1 IAAT PORV is open, and RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)),
THEN close 1RC-4 3.2 IAAT RC pressure <2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE EXAMINER NOTE: The crew may perform Immediate Manual Action Step 3.3 from memory prior to the SRO entering AP/44.
3.3 IAAT all the following conditions exist:
__ RC pressure < 2155 psig
__ RC pressure decreasing without a corresponding decrease in PZR level THEN close 1RC-3 EXAMINER NOTE: If the block valve (1RC-3) is not closed, the Reactor will trip on variable low pressure and ES actuation will occur
. EXAMINER NOTE: If they fail to close 1RC-3, then closing 1RC-3 will be a critical task.
This event is complete when 1RC-3 is closed, or as directed by the Lead Examiner.
Page 14 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 5 Page 2 of 3 Event
Description:
PZR Spray Valve (1RC-1) Fails OPEN Time Position Applicant's Actions or Behavior AP/1/A/1700/044 (Abnormal Pressurizer Pressure Control) (continued)
SRO/OATC 4.1 Announce AP entry using the PA system 4.2 GO TO the applicable step per the following table:
Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.18 4.3 Verify 1RC-4 is closed.
RNO: IF PORV is open, AND 1RC-4 has failed to close....
4.4 Verify 1RC-3 is closed NOTE 1RC-3 must NOT be allowed to be closed for 36 minutes at a time to avoid a thermal transient in piping between 1RC-3 and the PZR spray nozzle.
4.5 Position 1RC-3 as required to maintain RC pressure within desired band.
4.6 GO TO Step 4.13 4.13 Verify PZR heaters maintaining RCS pressure within desired band 4.14 Notify SPOC to repair malfunctioning component 4.15 Ensure requirements of following are met: (no TS should apply)
- TS 3.4.9 (Pressurizer)
Examiner note: If unit trips on low RCS pressure, Main FDW pumps will trip and the ATWS will occur.
This event is complete when 1RC-3 is closed, or as directed by the Lead Examiner.
Page 15 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 5 Page 3 of 3 Event
Description:
PZR Spray Valve (1RC-1) Fails OPEN Time Position Applicant's Actions or Behavior AP/1/A/1700/044 (Abnormal Pressurizer Pressure Control) (continued)
SRO/OATC 4.16 WHEN repairs complete, THEN place the following components in desired position for current plant conditions as determined by CR SRO.
- PZR heater bank #1
- PZR heater bank #2
- PZR heater bank #3
- PZR heater bank #4 4.17 WHEN directed by the CR SRO, THEN EXIT this procedure.
This event is complete when 1RC-3 is closed, or as directed by the Lead Examiner.
Page 16 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 6 Page 1 of 3 Event
Description:
Operating Main FDW Pump trip and ATWS Time Position Applicants Actions or Behavior Plant Response:
An automatic RX trip should have occurred due to the Main Feedwater pump trip Crew Response:
The SRO will direct the OATC to perform EOP Immediate Manual Actions The SRO will direct the BOP to perform a Symptoms Check OATC EOP Immediate Manual Actions:
3.1 Depress REACTOR TRIP pushbutton.
3.2 Verify reactor power < 5% FP and decreasing. (Power will not be decreasing)
RNO: GO TO Rule 1 (ATWS/Unanticipated Nuclear Power Production)
EOP Rule 1 (CT-24)
- 1. Verify any Power Range NI 5% FP OATC RNO: IF in MODE 1 or 2 THEN GO TO Step 2
- 2. Initiate manual control rod insertion to the IN LIMIT
- 3. Notify CR SRO to GO TO UNPP tab (see next page)
- 5. Ensure only one of the following operating:
- 1A HPI PUMP
- 1B HPI PUMP
- 6. Start 1C HPI PUMP
RNO IF 1HP-26 will NOT open, Then open 1HP-410
Booth Cue: When contacted to open CRD breakers, FIRE TIMER 14 to Trip CRD breakers (4 minutes timer)
(does not apply)
- 10. EXIT this rule This event is complete when Control Rods insert, or as directed by the Lead Examiner.
Page 17 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 6 Page 2 of 4 Event
Description:
Operating Main FDW Pump trip and ATWS Time Position Applicants Actions or Behavior Crew Response:
- 1. Ensure Rule 1 is in progress or complete
- 2. Verify Main FDW is operating and in AUTO RNO: IF MFDW is operating in MAN, THEN adjust MFDW flow, as necessary, to control RCS temperature
- 3. IAAT Main FDW is NOT operating, THEN perform the following:
A. Trip the turbine-generator B. Start all available EFDW pumps C. Ensure Rule 3 is in progress or complete (See Page 20)
- 4. IAAT all power range Nis are < 5% FP, THEN perform Steps 5-6 RNO: GO TO Step 7
- 5. Depress turbine TRIP pushbutton
- 6. Verify all turbine stop valves closed
- 7. Verify any wide range NI > 1% FP RNO: GO TO Step 16
- 8. Open 1RC-4
- 9. Verify1HP-5 open
- 10. Maximize letdown
- 11. Verify Main FDW available RNO: GO TO Step 13
- 12. Adjust Main FDW flow as necessary to control RCS temperature
- 13. Verify overcooling in progress RNO: GO TO Step 16
- 16. Secure makeup to LDST Examiner Note: Control will drop into the core 4 minutes after the call to de-energize the CRDs.
- 17. WHEN all Wide Range Nis are 1% FP, AND decreasing, THEN continue
- 18. Control RCS temperature using the following methods:
__ Tave 555°F - Adjust SG pressure as necessary to stabilize RCS temperature using either of the following:
- Dispatch two operators to perform Encl 5.24
__ Tave > 555°F - Utilize Rule 7 (SG Feed Control) to control SG feed rate as necessary to maintain cooldown rate within Tech Spec limits during the approach to the SG Level Control Point
This event is complete when Control Rods insert, or as directed by the Lead Examiner.
Page 18 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 6 Page 3 of 4 Event
Description:
Operating Main FDW Pump trip and ATWS Time Position Applicants Actions or Behavior Crew Response:
SRO 20. WHEN RCS pressure < 2300 psig, THEN continue
- 21. Verify PORV closed
- 22. Adjust letdown flow as desired
- 23. Verify RCP seal injection available
- 24. GO TO Subsequent Actions tab EOP Subsequent Actions tab:
4.1 Verify all control rods in Groups 1-7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either of the following:
__ Main FDW overfeeding causing excessive temperature decrease
__ Main FDW underfeeding causing SG level decrease below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, THEN manually control pressure in affected SG using either of the following:
__ TBVs
__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) (PS) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GO TO Step 4.14 4.14 Dispatch operator with Encl 5.29 (MSRV Locations) to verify all MSRVs have reseated 4.15 Verify ES is required RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control) (Page 31)
- 2. GO TO Step 4.17 This event is complete when Control Rods insert, or as directed by the Lead Examiner.
Page 19 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 6 Page 4 of 4 Event
Description:
Operating Main FDW Pump trip and ATWS Time Position Applicants Actions or Behavior SRO/BOP/ EOP Rule 3 OATC
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency)
AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)
- 5. Verify any EFDW pump operating
- 6. GO TO Step 37
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO Step 43
THEN throttle EFDW, as necessary
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (page 25)
- 45. WHEN directed by CR SRO, THEN EXIT this rule Examiner note: HPI should be throttled per Rule 6 (HPI) before the Pzr is solid. If not a CT will be created.
This event is complete when Control Rods insert, or as directed by the Lead Examiner.
Page 20 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 1 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior Examiners note: This event will begin when Control Rods insert.
Plant Response
- Reactor will trip (if not already tripped)
- MFBs will de-energize
- CT-1 Lockout
- KHU-2 Emergency Lockout (Aligned to underground)
Crew Response:
SRO directs OATC to perform Immediate Manual Actions (IMAs):
SRO/OATC
- Depress REACTOR TRIP pushbutton
- Verify Reactor Power < 5% FP and decreasing
- Depress turbine TRIP pushbutton
- Verify all turbine stop valves closed
- Verify RCP seal injection available EXAMINER NOTE: The OATC should determine that RCP Seal Injection and CC are not available and inform the SRO to initiate AP/25. The SRO will then direct an RO to initiate AP/25. When the RO attempts to leave the Control Room, inform him/her that a Unit 2 RO will perform AP/25 actions at the SSF.
SRO directs BOP to perform Symptoms Check:
SRO/BOP
- Power Range NIs < 5% and/or decreasing
- Any SCM 0°F
- Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)
- Uncontrolled Main Steam Line(s) pressure decrease
- Steam Generator Tube Rupture o CSAE Offgas alarms o Process Monitor alarms (RIA-40) o Area monitor alarms (RIA-16/17)
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 21 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 2 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior Crew Response:
SRO will transfer to Subsequent Actions Tab of the EOP after documenting IMAs and will refer to the Parallel Actions Page which will require a transfer to the Blackout Tab due to ALL 4160V switchgear being de-energized.
Blackout Tab SRO/OATC/ EOP Parallel Actions BOP
- IF SSF available, THEN initiate AP/25 (SSF EOP)
- Announce plant conditions using PA system.
- Notify OSM to reference the Emergency Plan and NSD 202 (Reportability).
- 1. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. (page 24)
SRO/BOP
- 2. Verify two ROs available to perform Control Room actions NOTE:
SRO/OATC During performance of Encl 5.38 (Restoration of Power), progression through the Blackout Tab should continue.
- 3. Notify one RO to perform Encl 5.38 (Restoration of Power)
(see page 26)
- 4. Verify both:
- Any SG being fed
- SSF is available
- 5. Verify any MD EFDWP operating using diverse indication.
RNO: Position to OFF:
- 1A MD EFDWP
- 1B MD EFDWP
- 6. Verify either:
- Blackout occurred during Mode 3 and <540 degrees F
- Blackout occurred while in mode 4 with SGs removing decay heat.
RNO: 1. IF SSF is NOT available THEN GO TO Step 7
- 2. Feed and steam available SGs as necessary to stabilize RCS P/T in bands prescribed by Rule 7 (SG Feed Control)
- 3. GO TO step 8.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 22 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 3 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior Blackout Tab (continued)
SRO/OATC NOTE:
Feeding SGs with EFDW is desired over HPI Forced cooling. Step 8 should be performed prior to re-performing Rule 3.
100 gpm could cause overcooling if decay heat levels do NOT exist.
- 8. IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available, THEN perform steps 9 - 11.
RNO: GO TO step 12
- 12. IAAT EFDW from any source is insufficient to maintain stable RCS P/T, THEN notify SSF operator that feeding SGs with SSF ASW is required.
- 13. IAAT power is restored to any of the following:
__ 1TC
__ 1TD
__ 1TE THEN GO TO Step 14 RNO: GO TO Step 19
- 19. Verify Encl 5.38 (Restoration of Power) in progress or complete EXAMINER NOTE: When power is restored using Encl 5.38, return to Blackout Tab here.
- 13. IAAT power is restored to any of the following:
- 1TC
- 1TD
- 1TE THEN GO TO Step 14
- 14. Ensure Step 8 dispositioned appropriately.
- 15. Verify SSF activated.
RNO: GO TO Step 17 NOTE AP/11 (Recovery From Loss of Power) will transition seal injection from SSF to HPI.
- 16. Communicate status of SG feed and seal injection to SSF operator using x-2766, radio, or plant page.
- 17. Initiate AP/11 (Recovery from Loss of Power) (see page 28)
- 18. GO TO Subsequence Actions Tab.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 23 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 4 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ EOP Rule 3 OATC
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency)
AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)
- 5. Verify any EFDW pump operating
- 6. GO TO Step 37
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO Step 43
THEN throttle EFDW, as necessary
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (see next page)
- 45. WHEN directed by CR SRO, THEN EXIT this rule This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 24 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 5 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ Encl 5.9 (Extended EFDW Operation) as directed by Rule 3 OATC
- 1. Monitor EFDW parameters on EFW graphic display.
- 2. IAAT UST level is < 4',
THEN GO TO Step 120
- 8. Perform the following as required to maintain UST level > 7.5':
- Makeup with demin water.
- Place CST pumps in AUTO.
- 9. IAAT all the following exist:
- Rapid cooldown NOT in progress
- EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.
- 10. Verify 1 TD EFDW PUMP operating.
- 11. Start TD EFDWP BEARING OIL COOLING PUMP.
NOTE
- Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open.
- If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.
This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 25 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 6 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ EOP Enclosure 5.38 (Restoration of Power)
OATC
- 1. Verify power has been restored RNO: GO TO Step 3
- 3. Place 1 HP-31 in HAND and reduce demand to 0
- 4. Close 1HP-21
- 5. Verify any of the following energized:
__ MFB1
__ MFB2 RNO: GO TO Step 8
- 8. Verify CT-1 indicates 4160 volts RNO: GO TO Step 18
- 18. Verify both Standby Bus #1 and Standby Bus #2 are de-energized
- 19. Verify both Keowee units operating RNO: 1. Emergency Start Keowee units:
__ KEOWEE EMER START CHANNEL A
__ KEOWEE EMER START CHANNEL B
- 2. IF NO Keowee units are operating, THEN GO TO Step 36
- 20. Verify both Keowee units in Oconee Control (statalarms on):
- UNIT 1 OCONEE CONTROL (2SA-17/E-1)
- UNIT 2 OCONEE CONTROL (2SA-18/E-1).
RNO: Notify Keowee Operator to place both Keowee units Master Transfer switches to remote This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 26 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 7 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ EOP Enclosure 5.38 (continued)
OATC
- 21. Verify both Keowee units operating.
RNO:
- 1. IF UNIT 1 EMER FDR ACB 3 is closed, AND Unit 1 Keowee is NOT operating, THEN open UNIT 1 EMER FDR ACB 3.
- 2. IF UNIT 2 EMER FDR ACB 4 is closed, AND Unit 2 Keowee is NOT operating, THEN open UNIT 2 EMER FDR ACB 4.
EXAMINER NOTE: When power is restored to 1TC, 1TD, or 1TE, IAAT Step 13 (B/O Tab) will apply. Return to the Blackout Tab on page 22 for further actions.
- 22. Ensure one of the following is closed for an operating Keowee unit:
- UNIT 1 EMER FDR ACB 3 (CT-8)
Examiner note: Will fail CT if power not restored when Encl. 5.38 is complete.
- 23. Verify 4160 volt power has been restored to the MFB.
- 24. GO TO Step 35.
- 35. Verify any of the following energized:
- 1TC
- 1TD
- 1TE
- 36. EXIT this enclosure This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 27 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 8 Page 8 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ AP/11 (Recovery From Loss of Power)
OATC 4.1 Announce AP entry using OMP 1-18 placard.
4.2 IAAT all exist:
- 1KI energized
- Pzr level > 80 [180 acc],
- Pzr heaters are desired, THEN position Pzr heaters to AUTO.
4.3 Verify load shed of inverters was performed per Unit 1 EOP Encl (Load Shed of Inverters During SBO).
RNO: GO TO Step 4.9 4.9 Verify load shed has initiated as indicated by either of the following statalarms on:
__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.10 Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).
4.11 Close the following breakers:
__ 1TC INCOMING FDR BUS 1
__ 1TC INCOMING FDR BUS 2
__ 1TD INCOMING FDR BUS 1
__ 1TD INCOMING FDR BUS 2
__ 1TE INCOMING FDR BUS 1
__ 1TE INCOMING FDR BUS 2 4.12 Verify 1SA-15/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) is OFF.
RNO: GO TO Step 4.15 4.15 Verify any Oconee unit receiving power from its normal source (1T, 2T, 3T).
4.16 Place transfer switches in MAN for all Oconee units receiving power from the normal source (1T, 2T, 3T):
- MFB1 AUTO/MAN
- MFB2 AUTO/MAN
- TA AUTO/MAN
- TB AUTO/MAN This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 28 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 7 Page 9 of 9 Event
Description:
Blackout Requiring Manual Alignment From CT-4 Time Position Applicant's Actions or Behavior SRO/BOP/ AP/11 (Continued)
OATC 4.17 Verify load shed was initiated as indicated by either of the following statalarms on:
- 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
RNO: GO TO Step 20 4.20 SimultaAOusly press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
- MFB UNDERVOLTAGE CHANNEL 1 RESET
- MFB UNDERVOLTAGE CHANNEL 2 RESET 4.21 Verify load shed signal reset as indicated by both of the following statalarms off:
- 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)
- 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.22 IAAT electrical loads are added, AND any MFB is energized by:
- CT-4
- CT-5
- Backcharged 1T THEN ensure transformer within limits of the applicable enclosure.
4.23 Verify power is being supplied to U1 Main Feeder Bus through CT-4 underground path.
4.24 Place all CBP control switches to OFF.
4.25 GO TO Step 4.214 This event is complete once the SRO transitions back to Subsequent Actions, or as directed by the Lead Examiner.
Page 29 of 42
Op-Test No.: ILT44 Scenario No.: 3 Event No.: 8 Page 1 of 1 Event
Description:
TDEFWP trips Time Position Applicant's Actions or Behavior Examiners Note: Once power is restored to the MFBs, the TDEFWP will fail. This will prompt the SRO to direct an RO to re-perform Rule 3 to start the MDEFWPs since the switches for them were placed in OFF during the Blackout.
ALL EOP Rule 3
- 1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step 3
- 3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency)
AND any of the following exist:
- Pzr level reaches 375 [340 acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)
- 5. Verify any EFDW pump operating
- 6. GO TO Step 37
- 37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO Step 43
THEN throttle EFDW, as necessary
- 44. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (page 25)
- 45. WHEN directed by CR SRO, THEN EXIT this rule This event is complete when the MD EFDW pumps have been restarted, or as directed by the Lead Examiner.
Page 30 of 42
Page 1 of 8 EXAMINER NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See below.
ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.
- 1. Utilize the following as necessary to maintain __ IF 1HP-26 will NOT open, desired Pzr level: THEN throttle 1HP-410 to maintain
- 1A HPI Pump desired Pzr level.
- 1B HPI Pump
- 1HP-120 setpoint or valve demand
- 2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.
- 3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.
- 4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:
A. Open:
__ 1CS-26
__ 1CS-41 B. Position 1HP-14 to BLEED.
C. Notify SRO.
- 5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.
Page 31 of 42
Page 2 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. IAAT 1C HPI PUMP is required, __ GO TO Step 10.
THEN perform Steps 7 - 9.
- 7. Open: 1. __ IF both BWST suction valves
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 8.
A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.
B. __ IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.
C. __ GO TO Step 9.
Page 32 of 42
Page3 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. Start 1C HPI PUMP. __ IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level.
- 9. Throttle the following as required to 1. __ IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain
- 1HP-26 desired Pzr level.
- 2. __ IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.
Page 33 of 42
Page 4 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. IAAT LDST level CANNOT be __ GO TO Step 12.
maintained, THEN perform Step 11.
- 11. Perform the following: 1. __ IF both BWST suction valves
- Open 1HP-25.
A. __ Start 1A LPI PUMP.
- Close 1HP-16.
B. __ Start 1B LPI PUMP.
C. Open:
__ 1LP-15
__ 1LP-16
__ 1LP-9
__ 1LP-10
__ 1LP-6
__ 1LP-7 D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).
F. __ GO TO Step 12.
- 2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP.
Page 34 of 42
Page 5 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
- 13. IAAT two Letdown Filters are desired, THEN perform the following:
- Open 1HP-17.
- Open 1HP-18
- 14. IAAT all of the following exist: __ GO TO Step 34.
- Letdown isolated
- LPSW available
- Letdown restoration desired THEN perform Steps 15 - 33. {41}
- 15. Open: 1. __ Notify CR SRO that letdown CANNOT be
- 1CC-8 system.
- 2. __ GO TO Step 34.
- 16. Ensure only one CC pump running.
- 17. Place the non-running CC pump in AUTO.
- 1HP-1 close,
- 1HP-2 THEN GO TO Step 20.
- 19. GO TO Step 22.
NOTE Verification of leakage requires visual observation of East Penetration Room.
- 20. Verify letdown line leak in East __ GO TO Step 22.
Penetration Room has occurred.
- 21. GO TO Step 34.
Page 35 of 42
Page 6 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. Monitor for unexpected conditions while restoring letdown.
- 23. Verify both letdown coolers to be placed 1. __ IF 1A letdown cooler is to be placed in in service. service, THEN open:
__1HP-1
__1HP-3
- 2. __ IF 1B letdown cooler is to be placed in service, THEN open:
__1HP-2
__1HP-4
- 3. __ GO TO Step 25.
- 24. Open:
- 25. Verify at least one letdown cooler is Perform the following:
aligned. A. __ Notify CR SRO of problem.
B. __ GO TO Step 34.
- 26. Close 1HP-6.
- 27. Close 1HP-7.
- 28. Verify letdown temperature < 125°F. 1. __ Open 1HP-13.
- 2. Close:
__1HP-8
__1HP-9&11
- 3. __ IF any deborating IX is in service, THEN perform the following:
A. __Select 1HP-14 to NORMAL.
B. __Close 1HP-16.
- 4. __ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Page 36 of 42
Page 7 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 29. Open 1HP-5.
- 30. Adjust 1HP-7 for 20 gpm letdown.
- 31. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.
- 32. Open 1HP-6.
- 33. Adjust 1HP-7 to control desired letdown flow.
NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.
- 34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).
- 35. IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:
A. Obtain SRO concurrence to reduce running HPI pumps.
B. Secure the desired HPI pumps.
C. Place secured HPI pump switch in AUTO, if desired.
- 36. IAAT all the following conditions exist:
- Makeup from BWST NOT required
- LDST level > 55
- All control rods inserted
- Cooldown Plateau NOT being used THEN close:
- 1HP-25 Page 37 of 42
Page 8 of 8 ENCLOSURE 5.5 (cont.)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 37. Verify 1CS-48 (1A BHUT Recirc) has __ GO TO Step 39.
been closed to provide additional makeup flow to LDST.
- 38. WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:
A. Stop 1A BLEED TRANSFER PUMP.
B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).
C. Close 1CS-46.
D. Start 1A BLEED TRANSFER PUMP.
E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure.
F. Stop 1A BLEED TRANSFER PUMP.
- 39. Verify two Letdown Filters in service, __ GO TO Step 41.
AND only one Letdown filter is desired.
- 40. Perform one of the following:
- Place 1HP-17 switch to CLOSE.
- Place 1HP-18 switch to CLOSE.
- 41. WHEN directed by CR SRO, THEN EXIT this enclosure.
- *
- END
- Page 38 of 42
Page 39 of 42 Page 40 of 42 CRITICAL TASKS
- 2. CT-24, Shutdown reactor (Page 17)
- 3. CT-8, Restore Power from CT-4 Standby BUS 1 or 2 Feeder (Page 27)
Page 41 of 42
SAFETY: Take a Minute UNIT 0 (OSM)
SSF Operable: No KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)
Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: 0.02% Mode: 1 Mode: 1 Gross MWE: N/A 100% Power 100% Power RCS Leakage: 0.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)
Component/Train OOS Restoration TS/SLC #
Date/Time Required Date/Time SSF Yesterday 0000 6 Days TS 3.10.1 A B C D E Shift Turnover Items (CR SRO)
Primary
- Tave = 536°F
- Startup procedure at step 3.36 (OP/1/A/1102/001, Enclosure 4.7)
- Increase Reactor power to 6 -7%
- Stop at step 3.44 and wait for a maneuvering plan from reactor engineering
- Unit 2 CRS has oversight during the power increase Secondary
- 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.
- 1AS-35 throttled per Secondary Chemist to provide steam to E heaters for secondary O2 removal.
Reactivity Management (CR SRO)
R1 Reactivity management controls RCS Boron = 1680 ppmb Rod position Gp 7 5% WD established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)
Procedure Use and Adherence Page 42 of 42