ML22143B009
| ML22143B009 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/21/2018 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | |
| Baker R | |
| Shared Package | |
| ML17214A864 | List: |
| References | |
| Download: ML22143B009 (4) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: Duane Arnold Energy Center Scenario No.: ___1_____ Op-Test No.: 19-1 NRC Examiners: Operators: SRO-U (2), SRO-I (4), RO (5)
Initial Conditions/Turnover:
Reactor Power is 75%
Guarded Equipment: Spent Fuel Cooling Pumps, Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room 1B35, 1B43, Fuel Pool Pump Breakers, 1C136, Fuel Pool Panel Evolutions in progress or planned for upcoming shift
- Alternate EHC Pumps for maintenance later in the shift
- Raise Power with rods IAW the pull sheet to achieve 80% Reactor Power
- Later this shift, Security will be running a force on force drill Plant PRA/PSA Status including CDF/LERF & color
- Green-CDF 1.34 E-6/ ICDP to Yellow equal 1 year
- Green-LERF 3.27 E-7 ILERP to Yellow equal to 1 year 2 Extra Non Licensed Personnel Available in Work Control Event Malf. Event Event No. No. Type* Description 1 N-BOP Shift EHC Pumps N-SRO 2 R-ATC Raise Power With Rods to 80% RTP R-SRO 3 TS-SRO Control Rod 22-07 N2 Leak Tech Spec 3.1.5 Condition A 4 zz03 Design Basis Earthquake, Entry into AOP 901 5 eg08a C-BOP H2 Main Seal Oil Pump fails and the crew will have to start the eg08c C-SRO Emergency H2 Seal Pump ARP 1C08C D-6 do-eg-026 do-eg-027 6 rr06b C-ATC Trip of B Recirc MG Set C-SRO The Crew will enter AOP 255.2 and 264.
TS-SRO Tech Spec 3.4.1, Condition D 7 mc07 M-All Condenser Tube Leak will require the entry into AOP 639, resulting in inserting a manual reactor scram 8 rp05g C-ATC Entry into EOP 1, Transition to EOP ATWS C-SRO Hydraulic ATWS
- Potential to enter Power Level Control Rods will insert via:
- RIP 102.1, Repeated Manual Scram 9 pc14 C-BOP Leak in the torus results in the performance of ED, anticipation will di-ms-076 C-SRO not be available due to a spurious group 1 isolation di-ms-077 di-ms-072 di-ms-074 ms19a ms19b
Appendix D Scenario Outline Form ES-D-1 Facility: Duane Arnold Energy Center Scenario No.: ___2_____ Op-Test No.: 19-1 NRC Examiners: __________________ Operators: SRO-U (2), SRO-I (4), RO (5)
Initial Conditions/Turnover:
Reactor Power is 100%
Guarded Equipment: Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room, 1C136 Fuel Pool Cooling Panel, 1B3507 A Fuel Pool Cooling Pump Breaker, 1B4327 B Fuel Pool Cooling Pump Breaker.
Evolutions in progress or planned for upcoming shift
- Perform Auto Voltage Regulator Wipe per Task Card 154
- Reduce Reactor Power to 95% with Control Rod Insertion for Load Line Adjustment Plant PRA/PSA Status including CDF/LERF & color
- LERF GREEN - 3.92 E-7/ Cumulative Large/Early Release Probability (CLERP) No Limit Rain will be moving into the area later in the shift.
2 Extra Non Licensed Personnel Available in Work Control Event Malf. Event Event No. No. Type* Description 1 N-BOP Perform Auto Voltage Regulator Wipe In Accordance With Task N-SRO Card 154.
2 R-ATC Reduce Rx Power with Rods In Accordance With Load Line R-SRO Adjustment to 95% RTP 3 DI-CS-008 I-BOP A Core Spray pump will receive an inadvertent start signal.
I-SRO TS-SRO Tech Spec 3.5.1 Condition B (3.3.5.1 Also Possible) 4 sl07 TS-SRO Leak on 1T-218 develops and causes 1C05A E-3, SBLC Tank HI/LO Level alarm to come in Tech Spec 3.1.7, Condition B 5 sw37a C-BOP Lightning Strike causes:
an1c06 C-ATC
- Trip of B GSW Pump a(17) C-SRO o Standby Pump Fails to Start AOP 411 sw32 (Possible) stsw01a o High P across Auto Filter ARP Actions
- C RBCCW Pump sw10c o Standby Pump Fails to Start ARP Actions 6 cu05 M-All A leak will develop in the RWCU HX room requiring EOP 3 Entry cu11a
- Scram prior to Temperatures Reaching Max Safe cu12a
- Leak will not be Isolated ms28b
- Defeat 9 will not work to restore ventilation cu07 7 rp05 C-ATC On the reactor scram, there will be an electrical ATWS C-SRO
- ARI will be effective at inserting all but 1 control rod 8 ed08d C-All After all but one of the control rods have inserted, 1A4 will lockout.
The crew will take actions In Accordance With AOP 301 9 DI-AD-015 C-BOP TIP room exceeds a Max Safe Temperature Limit, the crew will DI-AD-017 C-SRO enter ED.
- If the crew attempts to use the EHC Control System, it will fail to control the B/P Valves
Appendix D Scenario Outline Form ES-D-1 Facility: Duane Arnold Energy Center Scenario No.: ___3_____ Op-Test No.: 19-1 NRC Examiners: Operators: SRO-U (2), SRO-I (4), RO (5)
Initial Conditions/Turnover:
Reactor Power is 50%.
1C06B, RFP Aux Lube Oil Pump 1P-2A or 1P-2B Running, will be locked in until the B Feedwater pump is started.
Guarded Equipment: Skimmer Surge Tank Room, Fuel Pool Heat Exchanger Room, 1C136 Fuel Pool Cooling Panel, 1B3507 A Fuel Pool Cooling Pump Breaker, 1B4327 B Fuel Pool Cooling Pump Breaker.
Rain will be moving into the area later in the shift.
Evolutions in progress or planned for upcoming shift
- Perform Daily RWS Flow Verifications
- Raise Power with Recirc to 55%-60% in preparation of putting the B RFP in service Plant PRA/PSA Status including CDF/LERF & color
- LERF GREEN - 3.92 E-7/ Cumulative Large/Early Release Probability (CLERP) No Limit 2 Extra Non Licensed Personnel Available in Work Control Event Malf. Event Event No. No. Type* Description 1 N-BOP Perform Daily RWS Flow Verifications None N-SRO 2 R-ATC Raise Power with Recirc to 55%-60% from an initial power of 50%
None R-SRO 3 C-BOP Breaker 1A312, feeder breaker to 1B09 opens on ground fault.
C-SRO Subsequently, a loss of A side RWS occurs. The crew will start ed08m TS-SRO 1P-117B(D) IAW ARP 1C08A, B-6 and AOP 410 Loss of River Water Supply; Tech Spec 3.8.7, Condition D 3.7.2 Condition A 3
sw21d C-ATC Shortly after the crew enters AOP 903, a lightning strike will result rr37a C-BOP in; rr37b C-SRO
- The Tripping of the D well AOP 408 cu01a/b TS-SRO
- Cleanup Pump Trip TRM 3.3.4 4 A LOCA will develop. The crew will insert a manual scram prior to the DW reaching 2 psig. The crew will enter EOP 1 on the scram, rr15b M-All and when the DW reaches 2 psig, the crew will re-enter EOP 1 and enter EOP 2.
5 On the 2 psig signal; The B CS pump will start and trip .
cs01b C-BOP The A CS pump will fail to automatically start. The A CS pump cs05a C-SRO can be started manually by taking the CS pump HS to the start position. (Critical) 6 C-BOP The HPCI Aux Oil Pump Feeder Breaker will trip on start and hp12 C-SRO prevent HPCI from injecting.
7 On the Turbine Trip, 1A1 will not transfer automatically or manually, to the startup transformer and 1A1 will be lost. The crew will perform the applicable actions of AOP 304.1, Loss of 4160V C-All fw02b Non-Essential Electrical Power.
This will result in a loss of A Condensate and Feed When attempts are made to start B Condensate Pump, the beaker trips on Ground Fault
8 The crew will enter ALC and prepare for an Emergency Depressurization. When RPV level reaches +15, the crew will;
- When RPV pressure lowers to 450 psig, the crew will C-BOP determine that the selected RHR inject valve did not automatically open, and manually open the valve. (Critical)
Maximize injection until the wide range level instruments reach
~90, then throttle injection.