ML20056C646
| ML20056C646 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/16/2019 |
| From: | Joseph Demarshall NRC Region 1 |
| To: | Exelon Generation Co, NRC/RGN-III/DRS/OLB |
| Demarshall J | |
| Shared Package | |
| ML17214A840 | List: |
| References | |
| 50-454/19-01, 50-455/19-01 50-454/OL-19, 50-455/OL-19 | |
| Download: ML20056C646 (2) | |
Text
ES-401 Record of Rejected K/As Form ES-401-4 Page 1 of 2 Tier / Group Randomly Selected K/A Reason for Rejection Tier 2 / Group 2
015 K1.04 RO Q58 NRC was unable to develop an operationally valid and discriminating RO level question to test the selected K/A (Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: ESF). Nuclear Instrumentation does not cause or block an ESF signal at Byron Station.
3/8/19 - CHIEF EXAMINER randomly re-selected K/A K1.02:
Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: Vital ac systems. (IR 3.4)
Tier 2 / Group 1
013 K4.04 RO Q40 Oversampling concern within T2G1 relative to Auxiliary/Emergency Feedwater System (Qs 40, 47, & 48), requiring K/A re-selection.
4/29/19 - CHIEF EXAMINER randomly re-selected K/A K4.12 for Q40:
Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following:
Safety injection block. (IR 3.7)
Tier 2 / Group 1
059 A2.07 RO Q46 Overlap/balance of coverage concern between K/A A2.07 (Q46) and K/A AA2.02 (Q78) on the topic of Main Feedwater Pump trips, requiring K/A re-selection.
4/30/19 - CHIEF EXAMINER randomly re-selected K/A A2.05 for Q46:
Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction or discharge line. (IR 3.1)
Tier 2 / Group 1
076 K2.08 RO Q53 NRC was unable to develop an operationally valid RO level question to test the selected K/A (Knowledge of bus power supplies to the following: ESF-actuated MOVs). The only ESF actuated MOVs in the Service Water system are normally in their safeguards position.
5/6/19 - CHIEF EXAMINER randomly re-selected K/A K2.01 for Q53:
Knowledge of bus power supplies to the following: Service water. (IR 2.7)
Tier 1 / Group 1
W/E11 EK3.4 RO Q17 NRC was unable to develop an operationally valid RO level question to test the selected K/A (Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation): RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated).
5/22/19 - CHIEF EXAMINER randomly re-selected K/A EK3.2 for Q17:
Loss of Emergency Coolant Recirculation - Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation). (IR 3.5)
Tier 3 G2.1.43 SRO Q95 NRC was unable to develop an operationally valid and discriminating SRO level question that would test and maintain a plant-wide generic focus for the selected Tier 3 K/A (Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.).
5/23/19 - CHIEF EXAMINER randomly re-selected K/A G2.1.37 for Q95:
Knowledge of procedures, guidelines, or limitations associated with reactivity management. (IR 4.6)
Tier 1 / Group 2
037 G2.4.20 SRO Q83 NRC was unable to develop an operationally valid and discriminating SRO level question to test the randomly selected combination of Abnormal Plant Evolution (APE) #037, Steam Generator (S/G) Tube Leak and K/A topic G2.4.20 (Knowledge of the operational implications of EOP warnings, cautions, and notes). The Steam Generator Tube Leak event is not dealt with in EOPs at Westinghouse plants.
6/13/19 - CHIEF EXAMINER randomly re-selected K/A AA2.12 for Q83:
Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: Flow rate of leak. (IR 4.1)
Tier 1 / Group 1
062 G2.4.8 RO Q13 NRC was unable to develop an operationally valid and discriminating RO level question to test the randomly selected combination of Abnormal Plant Evolution (APE) #062, Loss of Nuclear Service Water and K/A topic G2.4.8 (Knowledge of how abnormal operating procedures are used in conjunction with EOPs).
ES-401 Record of Rejected K/As Form ES-401-4 Page 2 of 2 6/14/19 - CHIEF EXAMINER randomly re-selected APE 026 (Loss of Component Cooling Water) from the Tier 1/Group 1 EPEs/APEs that were open/available on both the RO or SRO outlines, to maintain balance of coverage. Generic K/A G2.4.8 was retained for Q13.
Tier 1 / Group 1
015 AK2.10 RO Q3 NRC was unable to develop an operationally valid and discriminating RO level question to test the limited number (i.e., 3) of APE 015 AK2 Knowledge Items with Importance Ratings 2.5.
6/27/19 - CHIEF EXAMINER randomly re-selected EPE 011 (Large Break LOCA) from the Tier 1/Group 1 EPEs/APEs that were open/available on both the RO or SRO outlines, to maintain balance of coverage. CHIEF EXAMINER then randomly re-selected EK2.02 for Q3 to maintain outline category balance:
Knowledge of the interrelations between the Large Break LOCA and the following:
Pumps. (IR 2.6)
Tier 1 / Group 1
054 AA2.02 SRO Q78 NRC was unable to develop an operationally valid and discriminating SRO level question to test (1) the selected K/A (Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Differentiation between loss of all MFW and trip of one MFW pump), and (2) the remaining APE 054 AA2 Ability Items.
6/28/19 - CHIEF EXAMINER randomly re-selected APE 015 (Reactor Coolant Pump Malfunctions) from the Tier 1/Group 1 EPEs/APEs that were open/available on both the RO or SRO outlines, to maintain balance of coverage. CHIEF EXAMINER then randomly re-selected AA2.08 for Q78 to maintain outline category balance:
Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.
(IR 3.5)
Tier 2 / Group 2
029 K3.01 RO Q59 Overlap/balance of coverage concern between Plant System 029, K/A K3.01 (Q59) and Plant System 103, K/A G2.1.32 (Q90), on the topic of Containment Purge, requiring Plant System re-selection.
7/10/19 - CHIEF EXAMINER randomly re-selected Plant System 002 (Reactor Coolant) from the Tier 2/Group 2 Plant Systems that were open/available on both the RO or SRO outlines, to maintain balance of coverage. CHIEF EXAMINER then randomly re-selected K3.03 for Q59 to maintain outline category balance:
Knowledge of the effect that a loss or malfunction of the RCS will have on the following:
Containment.
(IR 4.2)