ML16116A351

2016 Byron Nuclear Station Initial License Examination Form ES-401-4

ML16116A351
Person / Time
Site:	Byron
Issue date:	03/23/2016
From:	Bielby M E Operations Branch III
To:	Exelon Generation Co
References
Download: ML16116A351 (3)

Text

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection RO T2/G1 Q# 21 063 A4.03 DC Electrical Distribution: Ability to manually operate and/or monitor in the control room: Battery discharge rate. K/A describes an activity that Byron doesn't have instrumentation for: to monitor DC battery discharge rate from the MCR. This is done locally at the DC panel. This was a second question in topic 063. Randomly and systematically selected another K/A from the same category (A4) from another T2/G1 system. Selected 076 A4.01. Verified no overlap with operating exam events. RO T2/G1 Q# 24 073 K5.03 Process Radiation Monitoring System: Knowledge of operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits This K/A lends itself to only LOD 1 type questions for licensed operators; more complex questions would be tasks performed by radiation control personal or technical evaluators and beyond the scope of the operator. Randomly and systematically selected another K/A from the same category (K5) from another T2/G1 System: 005K5.03: Knowledge of the operational implications of the following concepts as they apply to the RHRS: Reactivity effects of RHR fill water. RO T1/G1 Q#43 022 AA2.04 Loss of Reactor Coolant Makeup: Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:

How long Pzr level can be maintained within limits. This K/A was selected for the audit exam. Any question meeting the K/A would be very similar to the audit exam question. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (022): 022AA2.02: Charging pump problems. RO T1/G2 Q# 63 069 AK1.01 Loss of CNMT Integrity: Knowledge of the operational implications of the effect of pressure on leak rate. This K/A is very simple and leads to questions of low difficulty level. Randomly and systematically selected another K/A from the same category (K1) in the same Group and Tier, and related topic: High CNMT Pressure: W/E14 EK1.2.

SRO T2/G1 Q# 78 039 G2.4.8 Main and Reheat Steam: Knowledge of how abnormal operating procedures are used in conjunction with EOPs. No related OAs to this system could be found that would be used with EOPs. Randomly and systematically selected another System from T2/G1 to use the same K/A: 059 Main Feedwater SRO T1/G1 Q# 84 008 AA2.19 Pressurizer Vapor Space Accident: Ability to determine the following as they apply to the PVSA: Pzr spray valve failure, using plant parameters This K/A is similar to one used on the audit exam. Any question meeting the K/A would be very similar to the audit exam question. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (008): 008AA2.20: The effect of an open PORV on code safety, based on observation of plant parameters. SRO T1/G1 Q# 85 011 EA2.05 Large Break LOCA: Ability to determine or interpret the following as they apply to a LB LOCA: Significance of charging pump operation. This K/A is best answered by a question regarding basis of seal injection flow from the charging pumps, during a LOCA; anything else would probably be a pure system question. Another selected K/A, 022G2.2.22, Loss of RC Makeup: Knowledge of LCO is also best tested by a question of that concept. Randomly and systematically selected another K/A from the same category (EA2) in the same Evolution (011): 011EA2.02: Consequences to RHR of not resetting safety injection. SRO T1/G2 Q# 91 036 AA2.03 Fuel Handling Incident: Ability to determine and interpret the following as they apply to Fuel Handling Incidents: Magnitude of potential radioactive release. This K/A would be an effective system JPM, but it would be nothing more than a bookkeeping exercise as a written exam question, which would be LOD 1 and not appropriate to determine SRO abilities. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (036): 036AA2.02 Occurrence of a Fuel Handling Incident SRO T3 Q# 99 2.3.6 Ability to approve release permits This K/A overlaps a SRO JPM to review a release package. Randomly and systematically selected another Generic K/A: 2.4.38 RO T3 Q# 72 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. This K/A is at General Employee knowledge level, hence not suitable to make a licensing decision from. Randomly and systematically selected another Generic K/A: 2.4.1 SRO T3 Q# 92 2.2.40 Ability to apply Technical Specifications for a system. This K/A is very applicable to ROs and difficult to apply as a "generic" K/A not linked to a system. Asking a "basis" question fits the SRO model much better. Randomly and systematically selected another Generic K/A: 2.2.25 ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection RO T2/G1 Q# 21 063 A4.03 DC Electrical Distribution: Ability to manually operate and/or monitor in the control room: Battery discharge rate. K/A describes an activity that Byron doesn't have instrumentation for: to monitor DC battery discharge rate from the MCR. This is done locally at the DC panel. This was a second question in topic 063. Randomly and systematically selected another K/A from the same category (A4) from another T2/G1 system. Selected 076 A4.01. Verified no overlap with operating exam events. RO T2/G1 Q# 24 073 K5.03 Process Radiation Monitoring System: Knowledge of operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits This K/A lends itself to only LOD 1 type questions for licensed operators; more complex questions would be tasks performed by radiation control personal or technical evaluators and beyond the scope of the operator. Randomly and systematically selected another K/A from the same category (K5) from another T2/G1 System: 005K5.03: Knowledge of the operational implications of the following concepts as they apply to the RHRS: Reactivity effects of RHR fill water. RO T1/G1 Q#43 022 AA2.04 Loss of Reactor Coolant Makeup: Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:

How long Pzr level can be maintained within limits. This K/A was selected for the audit exam. Any question meeting the K/A would be very similar to the audit exam question. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (022): 022AA2.02: Charging pump problems. RO T1/G2 Q# 63 069 AK1.01 Loss of CNMT Integrity: Knowledge of the operational implications of the effect of pressure on leak rate. This K/A is very simple and leads to questions of low difficulty level. Randomly and systematically selected another K/A from the same category (K1) in the same Group and Tier, and related topic: High CNMT Pressure: W/E14 EK1.2.

SRO T2/G1 Q# 78 039 G2.4.8 Main and Reheat Steam: Knowledge of how abnormal operating procedures are used in conjunction with EOPs. No related OAs to this system could be found that would be used with EOPs. Randomly and systematically selected another System from T2/G1 to use the same K/A: 059 Main Feedwater SRO T1/G1 Q# 84 008 AA2.19 Pressurizer Vapor Space Accident: Ability to determine the following as they apply to the PVSA: Pzr spray valve failure, using plant parameters This K/A is similar to one used on the audit exam. Any question meeting the K/A would be very similar to the audit exam question. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (008): 008AA2.20: The effect of an open PORV on code safety, based on observation of plant parameters. SRO T1/G1 Q# 85 011 EA2.05 Large Break LOCA: Ability to determine or interpret the following as they apply to a LB LOCA: Significance of charging pump operation. This K/A is best answered by a question regarding basis of seal injection flow from the charging pumps, during a LOCA; anything else would probably be a pure system question. Another selected K/A, 022G2.2.22, Loss of RC Makeup: Knowledge of LCO is also best tested by a question of that concept. Randomly and systematically selected another K/A from the same category (EA2) in the same Evolution (011): 011EA2.02: Consequences to RHR of not resetting safety injection. SRO T1/G2 Q# 91 036 AA2.03 Fuel Handling Incident: Ability to determine and interpret the following as they apply to Fuel Handling Incidents: Magnitude of potential radioactive release. This K/A would be an effective system JPM, but it would be nothing more than a bookkeeping exercise as a written exam question, which would be LOD 1 and not appropriate to determine SRO abilities. Randomly and systematically selected another K/A from the same category (AA2) in the same Evolution (036): 036AA2.02 Occurrence of a Fuel Handling Incident SRO T3 Q# 99 2.3.6 Ability to approve release permits This K/A overlaps a SRO JPM to review a release package. Randomly and systematically selected another Generic K/A: 2.4.38 RO T3 Q# 72 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. This K/A is at General Employee knowledge level, hence not suitable to make a licensing decision from. Randomly and systematically selected another Generic K/A: 2.4.1 SRO T3 Q# 92 2.2.40 Ability to apply Technical Specifications for a system. This K/A is very applicable to ROs and difficult to apply as a "generic" K/A not linked to a system. Asking a "basis" question fits the SRO model much better. Randomly and systematically selected another Generic K/A: 2.2.25