ML22186A108
| ML22186A108 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/12/2018 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | FirstEnergy Nuclear Operating Co |
| Baker R | |
| Shared Package | |
| ML17068A442 | List: |
| References | |
| Download: ML22186A108 (1) | |
Text
NUREG-1021, Revision 11 FENOC Facsimile Revision 0 ES-401 Record of Rejected K/As Form ES-401-4 Facility: Davis Besse Nuclear Power Station Date of Exam 2/5/2018 to 2/16/2018 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 011EK3.03 KA requires knowledge of the reason for starting AFW pump during a large break LOCA. AFW is not required for heat removal during a large break LOCA.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 011EK3.05.
EK3 - Knowledge of the reasons for the following responses as they apply to the Large Break LOCA:
EK3.05 Injection into Cold Leg.
RO - 4.0 SRO - 4.1 1/1 027 AA1.04 KA requires knowledge of PZR Emergency Only heaters which are not installed at Davis Besse.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 027AA1.01.
AA1 - Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunction:
AA1.01 PZR heaters, sprays, and PORVs.
RO - 4.0 SRO - 3.9 1/1 029 EK3.07 KA requires knowledge of using the local turbine trip lever during an ATWS. This is not addressed at Davis Besse during an ATWS.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 029EK3.06.
EK3 - Knowledge of the reasons for the following responses as they apply to the ATWS:
EK3.06 Verifying a main turbine trip; methods.
RO - 4.2 SRO - 4.3 Replacement KA is also not applicable to B&W EOPs as Davis Besse does not trip the turbine as a part of the response to an ATWS. The operators will continue with the step to verify Turbine trip only after the Reactor has been shut down.
9/20/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 029EK3.12 EK3 - Knowledge of the reasons for the following responses as they apply to the ATWS:
EK3.12 Actions contained in EOP for ATWS.
RO - 4.4 SRO - 4.7 1/2 051 G2.4.9 KA requires knowledge of the impact of a Loss of Condenser Vacuum during an accident (LOCA or loss of DHR). In either instance, you use AVVs which are independent of condenser vacuum.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 051G2.4.31.
APE-051: Loss of Condenser Vacuum:
G2.4.31 Knowledge of annunciator alarms, indications, or response procedures.
RO - 4.2 SRO - 4.1 2/2 033 A1.02 KA requires ability to monitor/predict changes in the spent fuel pool cooling due to radiation monitoring system input. There are no Radiation Monitor inputs to the spent fuel pool cooling system that will prevent it from exceeding design limits.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 033A1.01.
033A1 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including:
A1.01 Spent fuel pool water level.
RO - 2.7 SRO - 3.3 2/2 055 A3.03 KA requires ability to monitor automatic diversion of CARS exhaust. There is no automatic function associated with CARS exhaust.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 041A3.02.
041A3 - Ability to monitor automatic operation of the SDS, including:
A3.02 RCS pressure, RCS temperature, and reactor power.
RO - 3.3 SRO - 3.4 2/2 086 G2.4.2 KA requires knowledge of Fire protection AUTOMATIC actions that will lead to EOP entry. There are no fire protection functions that actuate to trip the reactor / turbine / open breakers resulting in EOP entry.
8/25/17 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with G2.4.34.
086: Fire Protection System:
G2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.