ML16116A351
| ML16116A351 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/23/2016 |
| From: | Bielby M Operations Branch III |
| To: | Exelon Generation Co |
| References | |
| Download: ML16116A351 (3) | |
Text
ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO T2/G1 063 A4.03 DC Electrical Distribution: Ability to manually operate and/or monitor in the control room: Battery discharge rate.
Q# 21 K/A describes an activity that Byron doesnt 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 073 K5.03 Process Radiation Monitoring System: Knowledge of operational implications as they apply to concepts as they apply to the PRM Q# 24 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 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:
Q#43 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 069 AK1.01 Loss of CNMT Integrity: Knowledge of the operational implications of the effect of pressure on leak rate.
Q# 63 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 039 G2.4.8 Main and Reheat Steam: Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Q# 78 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 008 AA2.19 Pressurizer Vapor Space Accident: Ability to determine the following as they apply to the PVSA: Pzr spray valve failure, using Q# 84 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 011 EA2.05 Large Break LOCA: Ability to determine or interpret the following as they apply to a LB LOCA: Significance of charging pump Q# 85 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 036 AA2.03 Fuel Handling Incident: Ability to determine and interpret the following as they apply to Fuel Handling Incidents: Magnitude of Q# 91 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 2.3.6 Ability to approve release permits Q# 99 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 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Q# 72 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 2.2.40 Ability to apply Technical Specifications for a system.
Q# 92 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 / Randomly Reason for Rejection Group Selected K/A RO T2/G1 063 A4.03 DC Electrical Distribution: Ability to manually operate and/or monitor in the control room: Battery discharge rate.
Q# 21 K/A describes an activity that Byron doesnt 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 073 K5.03 Process Radiation Monitoring System: Knowledge of operational implications as they apply to concepts as they apply to the PRM Q# 24 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 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:
Q#43 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 069 AK1.01 Loss of CNMT Integrity: Knowledge of the operational implications of the effect of pressure on leak rate.
Q# 63 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 039 G2.4.8 Main and Reheat Steam: Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Q# 78 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 008 AA2.19 Pressurizer Vapor Space Accident: Ability to determine the following as they apply to the PVSA: Pzr spray valve failure, using Q# 84 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 011 EA2.05 Large Break LOCA: Ability to determine or interpret the following as they apply to a LB LOCA: Significance of charging pump Q# 85 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 036 AA2.03 Fuel Handling Incident: Ability to determine and interpret the following as they apply to Fuel Handling Incidents: Magnitude of Q# 91 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 2.3.6 Ability to approve release permits Q# 99 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 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Q# 72 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 2.2.40 Ability to apply Technical Specifications for a system.
Q# 92 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