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{{#Wiki_filter:ES-401 Record of Rejected K/A's Form ES-401-4 | {{#Wiki_filter:ES-401 Record of Rejected K/A's Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection KA Question 28; 272000 Radiation Monitoring, K2.03 - Knowledge of electrical power supplies to the following: Stack gas radiation monitoring system. This is another instrument power supply 272000 / K2.03 question, specifically Radiation Monitoring which overlaps with Tier 2, Group 2 replaced with 272000 question 22 (UPS and post accident instrumentation). Randomly | ||
/ 2.01 replaced with K2.01, Knowledge of electrical power supplies to the following: Main steamline radiation monitors Questions 74 and 96; Both questions have the same K/A, 2.3.14, Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. | |||
Randomly replaced question 96 K/A with 2.3.13, Knowledge of Tier 3, 2.3.14 replaced with radiological safety procedures pertaining to licensed operator Category 2.3.13 duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. | |||
- Knowledge of electrical power supplies to the following: Stack gas radiation monitoring system. This is another instrument power supply question, specifically Radiation Monitoring which | Question 11, the K/A 215003, K6.01; Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Reactor protection system (power supply): Plant-Specific is not 215003 / K6.01 applicable to DAEC. There are no RPS power supplies Tier 2, Group 2 replaced with 215003 associated with the IRMs. Randomly replaced with K6.06, | ||
. | / K6.06 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: APRM Question 11, the K/A 215003, K6.06; Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: APRM. | ||
-radiation areas, aligning filters, etc. | The DAEC RPS logic between the IRMs and APRMs does NOT 215003 / K6.06 result in any effects during a failure of the APRMs. Could NOT Tier 2, Group 2 replaced with 215003 write a question on this K/A. Randomly replaced with K6.02, | ||
/ K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: 24/48 volt D.C. power: Plant-Specific Question 55, the K/A 295003, Partial or Complete Loss of AC / | |||
6, 2.4.20 - Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes 295003 / 2.4.20 cannot be tested because there are no EOP warnings, cautions, Tier 1, Group 1 replaced with 295003 and notes regarding Partial or Complete Loss of AC. Partial or | |||
-Specific is not applicable to DAEC. There are no RPS power supplies associated with the IRMs. Randomly replaced with K6.06, Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: | / 2.1.20 Complete Loss of AC is covered in AOPs. The K/A was randomly replaced with 2.1.20, Ability to interpret and execute procedure steps. | ||
APRM | Question 54, 295030, Low Suppression Pool Water Level, 2.1.32 | ||
. Randomly replaced with K6.02, Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: | - Conduct of Operations: Ability to explain and apply all system limits and precautions is double jeopardy with Question 91, both 295030 / 2.1.32 K/As cover suppression pool water level (Question 83 also Tier 1, Group 1 replaced with 295001 covers suppression pool level). Randomly replaced with 295001, | ||
24/48 volt D.C. power: Plant | / 2.1.1 Partial or Complete Loss of Forced Core Flow Circulation, 2.1.1, Knowledge of conduct of operations requirements. | ||
-Specific | DAEC NRC REJECTED KAS ES 401-4.DOC | ||
- Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes cannot be tested because there are no EOP warnings, cautions, and notes regarding Partial or Complete Loss of AC. Partial or Complete Loss of AC is covered in AOPs. The K/A was randomly replaced with 2.1.20, Ability to interpret and execute procedure steps. | |||
. Randomly replaced with 295001, Partial or Complete Loss of Forced Core Flow Circulation, 2.1.1, Knowledge of conduct of operations requirements. | |||
ES-401 Record of Rejected K/A's Form ES-401-4 | ES-401 Record of Rejected K/A's Form ES-401-4 Question 81, 295038, High Off-Site Release Rate, 2.4.3, Ability to identify post-accident instrumentation, overlaps with question 22 which also covers post accident instrumentation. Additionally 295038 / 2.4.3 this test has several questions covering off-site releases (53, 64, Tier 1, Group 1 replaced with 295018 87, and 100. Randomly replaced with 295018, Partial or Total | ||
/ 2.1.32 Loss of CCW, 2.1.32, Ability to explain and apply system limits and precautions. | |||
-Site Release Rate, 2.4.3, Ability to identify post | Question 80, 295019, Partial or Total Loss of Inst Air, 2.4.3, Ability to interpret reference materials, such as graphs, curves, tables, etc. There are no reference materials associated with the 295019 / 2.1.25 Instrument Air system at the SRO level; could not write an SRO Tier 1, Group 1 replaced with / | ||
-accident instrumentation | level question. Randomly replaced with 295037, SCRAM 295037, 2.4.6 Condition Present and Reactor Power Above APRM Downscale or Unknown, 2.4.6, Knowledge of EOP mitigation strategies. | ||
, overlaps with question 22 which also covers post accident instrumentation. Additionally this test has several questions covering off | Question 81, 295018 Partial or Total Loss of CCW / 8, 2.1.32 - | ||
-site releases (53, 64, 87, and 100. Randomly replaced with 295018, Partial or Total Loss of CCW | Conduct of Operations: Ability to explain and apply system limits and precautions. Could NOT write a valid SRO level question on 295018 / 2.1.32 this K/A. Randomly replaced with 295003, Partial or Complete Tier 1, Group 1 replaced with / Loss of AC / 6, 2.4.4, Emergency Procedures / Plan: Ability to 295003 / 2.4.4 recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. | ||
, 2.1.32, Ability to explain and apply system limits and precautions. | Question 88, 239002 Safety relief Valves / 2.40 - | ||
Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes. | |||
239002 / 2.4.20 There is only one Note or Caution in the EOPs associated Tier 2, Group 1 replaced with with the SRVs. That Note addresses SRV operation with a 239002 / 2.418 low Torus Water Level. That knowledge is RO level knowledge. Could NOT write a valid SRO level question using this K/A. Randomly selected K/A 2.4.18 Knowledge of the specific bases for EOPs. | |||
Question 28, 272000 Radiation Monitoring / K2.01 - | |||
Knowledge of electrical power supplies to the following: | |||
Main steamline radiation monitors. | |||
Ability to explain and apply system limits and precautions. Could NOT write a valid SRO level question on this K/A. Randomly replaced with 295003, Partial or Complete Loss of AC / 6, 2.4.4, Emergency Procedures / Plan: Ability to recognize abnormal indications for system operating parameters that are entry | 272000 / K2.01 There is an oversampling issue on radiation monitoring Tier 2, Group 2 Replaced with questions. Questions 56, 63, 70 and 81 all have K/As 202001 / K2.03 associated with off-site release. There may be more, if all the questions covering radiation monitoring are included; 28, 53, 56, 64, 70, 74, 87, 97, and 100. Randomly selected 202001 / K2.03, Knowledge of electrical power supplies to the following: Recirculation system valves DAEC NRC REJECTED KAS ES 401-4.DOC | ||
-level conditions for emergency and abnormal operating procedures. | |||
There is only one Note or Caution in the EOPs associated with the SRVs. That Note addresses SRV operation with a low Torus Water Level. That knowledge is RO level knowledge. Could NOT write a valid SRO level question using this K/A. Randomly selected K/A 2.4.18 Knowledge of the specific bases for EOPs. | |||
K2.01 - Knowledge of electrical power supplies to the following: | |||
Main steamline radiation monitors | |||
. There is an oversampling issue on radiation monitoring questions. Questions 56, 63, 70 and 81 all have K/As associated with off | |||
-site release. There may be more, if all the questions covering radiation monitoring are included; 28, 53, 56, 64, 70, 74, 87, 97, and 100. Randomly selected 202001 / K2.03, Knowledge of electrical power supplies to the following: Recirculation system valves | |||
ES-401 Record of Rejected K/A's Form ES-401-4 | ES-401 Record of Rejected K/A's Form ES-401-4 Question 79, 295031 Reactor Low Water Level / 2.2.39 - | ||
Equipment Control: Knowledge of less than or equal to one hour technical specification action statements for systems. | |||
295031 / 2.2.39 Tier 1, Group 1 Replaced with Could not write a discriminating SRO level question for this 295031 / 2.2.12 K/A given that one hour Tech Specs are generally considered RO level knowledge. Randomly selected generic K/A, 2.2.12, Knowledge of surveillance procedures, Question 87, 223002, A2.04 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Process radiation monitoring system failures. | |||
Could not write a discriminating SRO level question for this K/A given that one hour Tech Specs are generally considered RO level knowledge. Randomly selected generic K/A, 2.2.12, Knowledge of surveillance procedures | 223002 /A2.04 This question presented a double jeopardy situation for the Tier 2, Group 1 Replaced with 223002 / A2.03 SRO when compared to question number 64. Both questions involved impacts of process radiation monitoring instrumentation on the PCIS. Randomly selected K/A 223002, A2.03, Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Logic Failures Question 32, 216000, K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: D.C. electrical distribution. | ||
216000 / K6.02 Tier 2, Group 2 Replaced with This K/A resulted in an over sampling of topics regarding 216000 / K6.03 DC or loss of DC (see questions 4, 11, 12, 44). Randomly selected K/A 216000, K6.03, Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: Temperature Compensation DAEC NRC REJECTED KAS ES 401-4.DOC | |||
-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Process radiation monitoring system failures. This question presented a double jeopardy situation for the SRO when compared to question number 64. Both questions involved impacts of process radiation monitoring instrumentation on the PCIS. Randomly selected K/A 223002, A2.03, Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT | |||
-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Logic Failures | |||
This K/A resulted in an over sampling of topics regarding DC or loss of DC (see questions 4, 11, 12, 44). Randomly selected K/A 216000, K6.03, Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: Temperature Compensation | |||
ES-401 Record of Rejected K/A's Form ES-401-4 | ES-401 Record of Rejected K/A's Form ES-401-4 Question 86, 215005, A2.10 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Changes in void concentration Could not develop an operationally valid SRO question for this K/A. The only operationally valid question associated 215005 / A2.10 with changes in void concentration that affect the APRMs Tier 2, Group 1 Replaced with 215005 / A2.08 and also require a procedure response would be based on a thermal hydraulic instability event. The response to such an event is RO level knowledge in that the response is an immediate action of the DAEC abnormal procedures. | ||
Randomly selected K/A 215005, A2.08, Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions: Faulty or erratic operation of detectors/systems DAEC NRC REJECTED KAS ES 401-4.DOC}} | |||
- Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Changes in void concentration Could not develop an operationally valid SRO question for this K/A. The only operationally valid question associated with changes in void concentration that affect the APRMs and also require a procedure response would be based on a thermal hydraulic instability event. | |||
The response to such an event is RO level knowledge in that the response is an immediate action of the DAEC abnormal procedures. Randomly selected K/A 215005, A2.08, Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions | |||
: Faulty or erratic operation of detectors/systems}} | |||
Latest revision as of 11:51, 4 November 2019
| ML13308A616 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/08/2013 |
| From: | NRC/RGN-III |
| To: | Duane Arnold |
| Randal Baker | |
| Shared Package | |
| ML11354A335 | List: |
| References | |
| Download: ML13308A616 (4) | |
Text
ES-401 Record of Rejected K/A's Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection KA Question 28; 272000 Radiation Monitoring, K2.03 - Knowledge of electrical power supplies to the following: Stack gas radiation monitoring system. This is another instrument power supply 272000 / K2.03 question, specifically Radiation Monitoring which overlaps with Tier 2, Group 2 replaced with 272000 question 22 (UPS and post accident instrumentation). Randomly
/ 2.01 replaced with K2.01, Knowledge of electrical power supplies to the following: Main steamline radiation monitors Questions 74 and 96; Both questions have the same K/A, 2.3.14, Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
Randomly replaced question 96 K/A with 2.3.13, Knowledge of Tier 3, 2.3.14 replaced with radiological safety procedures pertaining to licensed operator Category 2.3.13 duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Question 11, the K/A 215003, K6.01; Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Reactor protection system (power supply): Plant-Specific is not 215003 / K6.01 applicable to DAEC. There are no RPS power supplies Tier 2, Group 2 replaced with 215003 associated with the IRMs. Randomly replaced with K6.06,
/ K6.06 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: APRM Question 11, the K/A 215003, K6.06; Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: APRM.
The DAEC RPS logic between the IRMs and APRMs does NOT 215003 / K6.06 result in any effects during a failure of the APRMs. Could NOT Tier 2, Group 2 replaced with 215003 write a question on this K/A. Randomly replaced with K6.02,
/ K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: 24/48 volt D.C. power: Plant-Specific Question 55, the K/A 295003, Partial or Complete Loss of AC /
6, 2.4.20 - Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes 295003 / 2.4.20 cannot be tested because there are no EOP warnings, cautions, Tier 1, Group 1 replaced with 295003 and notes regarding Partial or Complete Loss of AC. Partial or
/ 2.1.20 Complete Loss of AC is covered in AOPs. The K/A was randomly replaced with 2.1.20, Ability to interpret and execute procedure steps.
Question 54, 295030, Low Suppression Pool Water Level, 2.1.32
- Conduct of Operations: Ability to explain and apply all system limits and precautions is double jeopardy with Question 91, both 295030 / 2.1.32 K/As cover suppression pool water level (Question 83 also Tier 1, Group 1 replaced with 295001 covers suppression pool level). Randomly replaced with 295001,
/ 2.1.1 Partial or Complete Loss of Forced Core Flow Circulation, 2.1.1, Knowledge of conduct of operations requirements.
DAEC NRC REJECTED KAS ES 401-4.DOC
ES-401 Record of Rejected K/A's Form ES-401-4 Question 81, 295038, High Off-Site Release Rate, 2.4.3, Ability to identify post-accident instrumentation, overlaps with question 22 which also covers post accident instrumentation. Additionally 295038 / 2.4.3 this test has several questions covering off-site releases (53, 64, Tier 1, Group 1 replaced with 295018 87, and 100. Randomly replaced with 295018, Partial or Total
/ 2.1.32 Loss of CCW, 2.1.32, Ability to explain and apply system limits and precautions.
Question 80, 295019, Partial or Total Loss of Inst Air, 2.4.3, Ability to interpret reference materials, such as graphs, curves, tables, etc. There are no reference materials associated with the 295019 / 2.1.25 Instrument Air system at the SRO level; could not write an SRO Tier 1, Group 1 replaced with /
level question. Randomly replaced with 295037, SCRAM 295037, 2.4.6 Condition Present and Reactor Power Above APRM Downscale or Unknown, 2.4.6, Knowledge of EOP mitigation strategies.
Question 81, 295018 Partial or Total Loss of CCW / 8, 2.1.32 -
Conduct of Operations: Ability to explain and apply system limits and precautions. Could NOT write a valid SRO level question on 295018 / 2.1.32 this K/A. Randomly replaced with 295003, Partial or Complete Tier 1, Group 1 replaced with / Loss of AC / 6, 2.4.4, Emergency Procedures / Plan: Ability to 295003 / 2.4.4 recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Question 88, 239002 Safety relief Valves / 2.40 -
Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.
239002 / 2.4.20 There is only one Note or Caution in the EOPs associated Tier 2, Group 1 replaced with with the SRVs. That Note addresses SRV operation with a 239002 / 2.418 low Torus Water Level. That knowledge is RO level knowledge. Could NOT write a valid SRO level question using this K/A. Randomly selected K/A 2.4.18 Knowledge of the specific bases for EOPs.
Question 28, 272000 Radiation Monitoring / K2.01 -
Knowledge of electrical power supplies to the following:
Main steamline radiation monitors.
272000 / K2.01 There is an oversampling issue on radiation monitoring Tier 2, Group 2 Replaced with questions. Questions 56, 63, 70 and 81 all have K/As 202001 / K2.03 associated with off-site release. There may be more, if all the questions covering radiation monitoring are included; 28, 53, 56, 64, 70, 74, 87, 97, and 100. Randomly selected 202001 / K2.03, Knowledge of electrical power supplies to the following: Recirculation system valves DAEC NRC REJECTED KAS ES 401-4.DOC
ES-401 Record of Rejected K/A's Form ES-401-4 Question 79, 295031 Reactor Low Water Level / 2.2.39 -
Equipment Control: Knowledge of less than or equal to one hour technical specification action statements for systems.
295031 / 2.2.39 Tier 1, Group 1 Replaced with Could not write a discriminating SRO level question for this 295031 / 2.2.12 K/A given that one hour Tech Specs are generally considered RO level knowledge. Randomly selected generic K/A, 2.2.12, Knowledge of surveillance procedures, Question 87, 223002, A2.04 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Process radiation monitoring system failures.
223002 /A2.04 This question presented a double jeopardy situation for the Tier 2, Group 1 Replaced with 223002 / A2.03 SRO when compared to question number 64. Both questions involved impacts of process radiation monitoring instrumentation on the PCIS. Randomly selected K/A 223002, A2.03, Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Logic Failures Question 32, 216000, K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: D.C. electrical distribution.
216000 / K6.02 Tier 2, Group 2 Replaced with This K/A resulted in an over sampling of topics regarding 216000 / K6.03 DC or loss of DC (see questions 4, 11, 12, 44). Randomly selected K/A 216000, K6.03, Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: Temperature Compensation DAEC NRC REJECTED KAS ES 401-4.DOC
ES-401 Record of Rejected K/A's Form ES-401-4 Question 86, 215005, A2.10 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Changes in void concentration Could not develop an operationally valid SRO question for this K/A. The only operationally valid question associated 215005 / A2.10 with changes in void concentration that affect the APRMs Tier 2, Group 1 Replaced with 215005 / A2.08 and also require a procedure response would be based on a thermal hydraulic instability event. The response to such an event is RO level knowledge in that the response is an immediate action of the DAEC abnormal procedures.
Randomly selected K/A 215005, A2.08, Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions: Faulty or erratic operation of detectors/systems DAEC NRC REJECTED KAS ES 401-4.DOC