ML20072P266
| ML20072P266 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/27/2020 |
| From: | Gregory Roach FirstEnergy Nuclear Operating Co |
| To: | NRC/RGN-III/DRS/OLB |
| Roach G | |
| Shared Package | |
| ML19121A156 | List: |
| References | |
| Download: ML20072P266 (2) | |
Text
NUREG-1021, Revision 11 ES-401 Record of Rejected K/As Form ES-401-4 Facility: Davis Besse Nuclear Power Station Date of Exam 2/3/2020 to 2/14/2020 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 027 AK1.01 RO KA requires knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Definition of saturation temperature - unable to write a discriminatory question to this KA.
7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 027AK1.02 AK1 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions:
AK1.02 Expansion of liquids as temperature increases RO - 2.8 SRO - 3.1 1/2 005 AK2.03 RO KA requires knowledge of the interrelations between the inoperable stuck control rod and the Metroscope. Davis Besse does not use a Metroscope.
7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 005AK2.01 AK2 Knowledge of the interrelations between the Inoperable / Stuck Control Rod and the following:
AK2.01 Controllers and Positioners RO - 2.5 SRO - 2.5 1/2 028 AK3.02 RO KA requires knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Relationships between PZR pressure increase and reactor makeup/letdown imbalance - unable to write a discriminatory question to this KA.
9/18/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with AK1.01 AK1 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Level Control Malfunctions:
AK1.01 PZR reference leak abnormalities RO - 2.8* SRO -
3.1*
2/1 022 A4.03 RO KA requires ability to manually operate/or monitor in the CTRM dampers in the Containment Cooling System. The only dampers in the Containment Cooling System are local manual dampers that are not monitored or operated by Operators 7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 022A4.01 A4 - Ability to manually operate and/or monitor in the control room A4.01 CCS Fans RO - 3.6 SRO - 3.6 2/1 073 G2.4.49 RO KA requires the ability to perform without reference to procedures those actions that require immediate operation of system components and controls in the Process Radiation Monitoring System There are no immediate actions related to the PRM system.
7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 064G2.4.49 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls 2.4.49 Generic RO - 4.6 SRO - 4.4
NUREG-1021, Revision 11 2/1 076 K4.01 RO KA requires knowledge SWS design features and/or interlocks which provide for conditions initiating closure of closed cooling water auxiliary building header supply and return valves. there are no closed cooling water auxiliary building header supply and return valves affected by service water design or interlocks at DB.
7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 076K4.06 K4 - Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:
K4.06 Service water train separation RO - 2.8 SRO - 3.2 2/1 022 A2.06 SRO KA requires the ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS pump. No CCS Pumps at DB 7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 013A2.06 A2 - Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.06 Inadvertent ESFAS actuation RO - 3.7 SRO - 4.0 2/2 011 A2.12 SRO KA requires the ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Operation of auxiliary spray. The auxiliary spray at DB is not associated with Pressurizer level Control but is used to cooldown the Pressurizer 7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with A2.06 A2 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.06 Inadvertent PZR spray actuation RO - 3.7 SRO - 3.9 3
2.4.21 SRO KA requires knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactive release control, etc - Unable to write a generic SRO level discriminatory question to this KA 7/10/19 - FOLLOWING DISCUSSION WITH CHIEF EXAMINER: Replaced with 2.4.13 2.4.13 - Knowledge of Crew roles and responsibilities during EOP usage 2.4.13 Generic RO - 4.0 SRO - 4.6