ML13308A616

2013 DAEC Initial License Examination Rejected KAs Form ES-401-4

ML13308A616
Person / Time
Site:	Duane Arnold
Issue date:	04/08/2013
From:	NRC/RGN-III
To:	Duane Arnold
Randal Baker
Shared Package
ML11354A335	List: ML13235A360 ML13308A616 ML13308A636 ML13308A656 ML13308A686
References
Download: ML13308A616 (4)

Text

ES-401 Record of Rejected K/A's Form ES-401-4 DAEC NRC REJECTED KAS ES 401

-4.DOC Tier / Group Randomly Selected KA Reason for Rejection Tier 2, Group 2 272000 / K2.03 replaced with 272000

/ 2.01 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 question, specifically Radiation Monitoring which overlap s with question 22 (UPS and post accident instrumentation)

. Randomly replaced with K2.01, Knowledge of electrical power supplies to the following: Main steamline radiation monitors Tier 3, Category 2.3.14 replaced with 2.3.13 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 radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high

-radiation areas, aligning filters, etc.

Tier 2, Group 2 215003 / K6.01 replaced with 215003

/ K6.06 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 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:

APRM Tier 2, Group 2 215003 / K6.06 replaced with 215003 / K6.02 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 result in any effects during a failure of the APRMs. Could NOT write a question on this K/A

. 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:

24/48 volt D.C. power: Plant

-Specific Tier 1, Group 1 295003 / 2.4.20 replaced with 295003

/ 2.1.20 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 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.

Tier 1, Group 1 295030 / 2.1.32 replaced with 295001 / 2.1.1 Question 54, 295030, Low Suppression Pool Water Level, 2.1.3 2 - Conduct of Operations: Ability to explain and apply all system limits and precautions is double jeopardy with Question 91, both K/As cover suppression pool water level (Question 83 also covers suppression pool level)

. 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 DAEC NRC REJECTED KAS ES 401

-4.DOC Tier 1, Group 1 295038 / 2.4.3 replaced with 2950 18 / 2.1.32 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 this test has several questions covering off

-site releases (53, 64, 87, and 100. Randomly replaced with 295018, Partial or Total Loss of CCW

, 2.1.32, Ability to explain and apply system limits and precautions.

Tier 1, Group 1 295019 / 2.1.25 replaced with

/ 295037, 2.4.6 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 Instrument Air system at the SRO level; could not write an SRO level question. Randomly replaced with 295037, SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknow n, 2.4.6, Knowledge of EOP mitigation strategies.

Tier 1, Group 1 295018 / 2.1.32 replaced with

/ 295003 / 2.4.4 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 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

-level conditions for emergency and abnormal operating procedures.

Tier 2, Group 1 239002 / 2.4.20 replaced with 239002 / 2.418 Question 88, 239002 Safety relief Valves / 2.40

- Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.

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.

Tier 2, Group 2 272000 / K2.01 Replaced with 202001 / K2.03 Question 28, 272000 Radiation Monitoring /

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 DAEC NRC REJECTED KAS ES 401

-4.DOC Tier 1, Group 1 295031 / 2.2.39 Replaced with 295031 / 2.2.12 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.

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

, Tier 2, Group 1 223002 /A2.04 Replaced with 223002 / A2.03 Question 8 7, 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. 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 Tier 2, Group 2 216000 / K6.02 Replaced with 216000 / K6.03 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.

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 DAEC NRC REJECTED KAS ES 401

-4.DOC Tier 2, Group 1 215005 / A2.10 Replaced with 215005 / A2.08 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 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