ML21144A323
| ML21144A323 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/13/2021 |
| From: | Gregory Roach Operations Branch III |
| To: | NRC/RGN-III/DRS/OLB |
| Roach G | |
| Shared Package | |
| ML20136A301 | List: |
| References | |
| Download: ML21144A323 (3) | |
Text
ILT 19-1 NRC Exam Scenario 2 Rev. 0 ILT 19-1 NRC Exam Scenario 2 Rev 0 Post OSV.docx Page 2 of 21 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 2 Operating Test No.: 2021-301 Examiners: ____________________________
Operators: ____________________
Initial Conditions:
Mode 1 Rx Power at RTP.
Weather conditions are calm and clear.
MC Pump A (0MC01PA) is OOS for maintenance. Not expected back this shift.
Turnover:
- On the previous shift, the Drywell was vented per CPS 3316.01 Containment Combustible Gas Control (HG) to support performance of CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.
First Priority - Perform CPS 9064.01 Drywell Post-LOCA Vacuum Breaker Verification Test.
- Maintain power at RTP throughout the shift.
Critical Tasks:
- [CT-1] Inserts control rods to lower power below 65% to exit MELLLA within 10 minutes of tripping B Reactor Recirculation pump.
- [CT-2] Enters and executes EOP-3 Emergency RPV Depressurization within 15 minutes of 2 or more of the following areas exceeding max safe temperature values of EOP-8 Table T Area Temperature Limits:
Point 14 1TR-CM326 (Upper Recorder) - Aux Bldg Below MS Tunnel > 200°F Point 18 1TR-CM326 (Upper Recorder) - Aux Bldg Steam Tunnel > 200°F Point 15 or 16 1TR-CM327 (Lower Recorder) - Aux Bldg MSIV Room A or B > 200°F Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-BOP Drywell Vacuum Breaker Test 2
YP_XMFTB_4102 I-BOP TS-SRO (NEW) Spurious HPCS auto initiation 3
SA01B1SA1CFO SA01B0SA1CFTC C-BOP
- 1 SA Compressor trips with failure of Standby Compressor to Auto Start 4
RRB_HORZ_MALF 21.7 MILS RRB_VERT_MALF 21.1 MILS C-ATC TS-SRO (NEW) RR Pump B high vibration 5
N/A R-ATC Reduce power to <65% with Control Rods 6
YP_XMFTB_4965 ROD0437TFIA4 ROD5221TFIA4 C-ATC (NEW) RR Pump A trip 7
YPXMALSE_256 0.08%
M-All (NEW) Low Power ATWS / Unisolable MSL D Leak /
Multiple area temps > Max Safe / EOP-3 Blowdown 8
YAFWHVFP_9 0%
C-All (NEW) FRV 1FW004 Fails Shut (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NEW - Not used on the previous two (2) NRC exams.
ILT 19-1 NRC Exam Scenario 3 Rev. 0 ILT 19-1 NRC Exam Scenario 3 Rev 0 Post OSV.docx Page 2 of 18 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 3 Operating Test No.: 2021-301 Examiners: ____________________________
Operators: ____________________
Initial Conditions:
Mode 1 at ~10% power.
Thunderstorms are expected in the area within the next hour.
CY Pump B (0CY01PB) is OOS for maintenance. Not expected back this shift.
Turnover:
CPS 3002.01 Heatup and Pressurization is complete.
CPS 3004.01 Turbine Startup and Generator Synchronization is in progress. Section 5.0 Prerequisites are complete.
Steps 8.1.1 and 8.1.5 are in progress. Steps 8.1.2 - 8.1.4 are complete.
Main Turbine Chest Warming has just been completed.
Control rods - On Step 15. Gang 7E, Rod 40-17 is at position 18.
Priorities for the shift are as follows:
RHR A is currently being flushed as directed by CPS 3312.03 Shutdown Cooling (SDC) & Fuel Pool Cooling And Assist (FP&A) by operating RHR A in Pool to Pool mode per CPS 3312.01 Residual Heat Removal (RHR).
First Priority - Secure RHR A operation in Pool To Pool mode per CPS 3312.01 Residual Heat Removal (RHR).
Continue with power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. The RE has requested single rod, single notch rod motion.
After reaching 15% power, perform Turbine Roll IAW Step 8.1.8 of CPS 3004.01.
Critical Tasks:
[CT-1] PC-3.1, SCRAMs the reactor before suppression pool level lowers to less than 15 1.
[CT-2] PC-3.3, Enters EOP-3 prior to suppression pool level reaching 151 and performs an emergency depressurization. If the suppression pool level lowers to less than 151 after the announcement is made to enter EOP-3, but before the blowdown is initiated, then this critical task is considered to be met.
Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-BOP (NEW) Secure RHR A Operation in Pool To Pool Mode 2
NA R-ATC Raise power with rods to 15%
3 ROD4017TFIA5 C-ATC TS-SRO Uncoupled Rod 4
YP_XMFTB_4992 A04_A28_S23=2 C-BOP (NEW) Trip of MSOP / ESOP fails to auto start 5
YFCUCTPW_1 C-ATC A Reactor Water Cleanup Filter Demin Trip 6
A05_A02_A0204_1_TVM; A05_A02_A09DS08_1 I-BOP TS-SRO (NEW) RCIC failure to auto-isolate on an isolation signal 7
YPXMALSE_665 100%
YPXMALSE_666 100%
A05_A02_A09S38_2=ON A05_A02_A16DS60_1=OFF A05_A02_A16DS61_1=OFF M-All Suppression Pool leak into the LPCS Room / RHR A Pump Room / 1E21F001 LPCS Suppr Pool Suction Valve fails to close 8
A05_A02_A13S60B_1 A05_A02_A13S62B_1 C-All Manual ADS Initiation Logic failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NEW - Not used on the previous two (2) NRC exams.
ILT 19-1 NRC Exam Scenario 4 Rev. 0 ILT 19-1 NRC Exam Scenario 4 Rev 0 Post OSV.docx Page 2 of 22 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 4 Operating Test No.: 2021-301 Examiners: ____________________________
Operators: ____________________
Initial Conditions:
Mode 1 at 56% power.
Weather conditions are calm and clear.
MC Pump A (0MC01PA) is OOS for maintenance. Not expected back this shift.
Turnover:
Priorities for the shift are as follows:
- First Priority - Continue performing HPCS Pump Operability IAW CPS 9051.01 HPCS Pump & HPCS Water Leg Pump Operability starting at step 8.2.7. An extra equipment operator is briefed, staged and ready to support the surveillance.
- Continue with power ascension to 62% IAW CPS 3005.01 Unit Power Changes using rods.
CPS 3005.01 is complete through Step 8.1.10.
Control rods - Step 26 is current / Gang 10C @ position 08.
LCOs in effect HPCS is inop per ITS LCO 3.5.1 (day 2 of SOW) (entered at 0500 on the previous day).
ORM 2.5.2 Action 3.5.2 due to HPCS MOV TEST PREP switch being in TEST (entered at 0500 on the previous shift).
Critical Tasks:
[CT-1] TCA-10 BOP/ATC starts Standby Liquid Control Pumps to shutdown the reactor within 120 seconds of the time at which the ATWS trip setpoint is reached (RPV pressure of 1127 psig).
[CT-2] Inhibits ADS within 105 seconds of RPV level reaching Level 1 (-145.5 Wide Range).
[CT-3] Terminates and prevents injection from LPCS and LPCI before RPV level reaches Level 1 (-145.5 Wide Range) and pressure lowers below 472psig.
[CT-4] Initiates RCIC injection prior to RPV level reaching -160 (TAF).
[CT-5] If RPV level < TAF and no systems are injecting, initiate ADS per EOP-3 within 17.5 minutes of RPV level reaching -
160 (TAF).
Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-BOP (NEW) Perform CPS 9051.01 HPCS Pump Operability 2
YP_XMFTB_4104 C-BOP (NEW) Failure of HPCS Pump Discharge valve (1E22-F301) 3 N/A R-ATC Raise Power with rods to 62%
4 ROD0429TFIA3 C-ATC TS-SRO Rod drifts outward 5
A04_A18_A02_4 Manual A04_A18_A02_7 Press I-BOP (NEW) EHC Temperature Controller Failure 6
A11_A05_S40_2 ON A11_A02_07_4_TVM 2 A_11_A08_DS30_1 OFF TS-SRO (NEW) Loss of Control Power to Suppression Pool Dump Valve (1SM001A) 7 YAFWPPLB_16 C-ATC (NEW) TDRFP B High Bearing Temperature 8
YP_XMFTB_5001/3/4 GROUP_1_ISOL_MALF M-All (NEW) Inadvertent Group 1 Isolation / Partial ATWS 9
YP_XMFTB_4094 YP_XMFTP_4959 C-All Trip of MDRFP / RCIC fails to auto start (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NEW - Not used on the previous two (2) NRC exams.