ML15128A244
| ML15128A244 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/22/2014 |
| From: | Bielby M NRC/RGN-III/DRS/OLB |
| To: | Northern States Power Co |
| Shared Package | |
| ML13093A444 | List: |
| References | |
| Download: ML15128A244 (2) | |
Text
ES-401 Record of Rejected K/As (RO)
Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection Tier 1 Group 1 RO 029 Anticipated Transient Without Scram (ATWS)
EK1.05 This K/A is not applicable because Prairie Island does not have a large PWR coolant system. Randomly selected 029 EK1.03 as a replacement.
Tier 1 Group 1 RO 065 Loss of Instrument Air AK2.01 This K/A value is less than 2.5. All K/A values for AK2 are below 2.5. Randomly selected 065 AK3.03 as a replacement.
Tier 2 Group 1 RO 078 Instrument Air System A2.01 The K/A value is less than 2.5. It is the only K/A under A2. Randomly selected 078 K1.03 as a replacement.
Tier 1 Group 1 RO 015/017 Reactor Coolant Pump (RCP) Malfunctions AK3.05 This K/A concerns shifting Tave to the loop with the highest flow. Prairie Island does not have this ability; therefore this K/A was rejected. Randomly selected 015/017 AK3.02 as a replacement.
Tier 1 Group 2 RO 033 Loss of Intermediate Range Nuclear Instrumentation AK2.02 This K/A is less than 2.5. All K/A values for 033 AK2 are below 2.5. Randomly selected 036 AK2.02 as replacement. New K/A is an AK2 in a new Abnormal Plant Evolution instead of a non AK2 in 033 because the total number for K2s was getting low.
Tier 2 Group 1 RO 008 Component Cooling Water System (CCWS)
K4.03 This K/A is less than 2.5. Randomly selected 008 K4.01 as a replacement.
Tier 2 Group 1 RO 064 Emergency Diesel Generators (ED/G)
K5.01 This K/A is less than 2.5. All K/A values for 064 K5 are below 2.5. Randomly selected 064 K4.11 as a replacement.
Tier 2 Group 1 RO 073 Process Radiation Monitoring (PRM) System K6.02 This K/A is less than 2.5. All K/A values for 073 K6 are below 2.5. Randomly selected 073 K5.01 as a replacement.
Tier 2 Group 2 RO 033 Spent Fuel Pool Cooling System (SFPCS)
K2.01 This K/A is less than 2.5. There is no other K/As in 033 K2. Randomly selected 033 G 2.1.28 as a replacement.
Tier 2 Group 2 RO 079 Station Air System (SAS)
K6.02 This K/A is less than 2.5. All K/A values for 079 K6 are below 2.5. Randomly selected 075 K2.03 as a replacement.
Tier 2 Group 1 RO 076 Service Water System (SWS)
A1.02 Prairie Island has an open loop service water system (cooling water) instead of a closed loop; therefore, this K/A is not applicable to Prairie Island. Randomly selected 076 A2.02 as a replacement.
ES-401 Record of Rejected K/As (SRO)
Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection Tier 1 Group 2 SRO APE 003 Dropped Control Rod 2.1.32 K/A for applying system limits and precautions does not apply to an abnormal procedure for a dropped rod because there are no precautions and limitations in the Rod Control Procedures that lend itself to development of an SRO level question. The topic of dropped rod does not lend itself to SRO questions because the only action is to manually trip the reactor and enter E-0; both are RO knowledge items. Randomly selected APE 036 2.4.4 as a replacement.
Tier 1 Group 2 SRO APE 037 Steam Generator (S/G) Tube Leak AA2.16 Unable to prepare question at the SRO license level for this K/A. This K/A requires the operator to determine the pressure at which to maintain RCS during S/G cooldown with a tube leak. At Prairie Island, Reactor Operators are required to know pressure and temperature limits for cool-downs. Also, at Prairie Island, there are no specific procedures for a RCS cool-down with a tube leak. In regard to RCS pressure control, it would be conducted in the same manner as a normal cool-down. Randomly selected APE 037 AA2.10 as a replacement.
Tier 2 Group 1 SRO 006 Emergency Core Cooling System A2.09 Unable to prepare question at the SRO license level for this K/A. At Prairie Island, the RWST is vented into the Auxiliary Building; therefore, during an accident condition any release from the RWST would be filtered through the Auxiliary Building Special Ventilation (Safeguards System) prior to being released to the atmosphere. Also, at Prairie Island, there are interlocks that prevent radioactive water from entering the RWST during an accident. There are no specific procedures at Prairie Island that would address a radioactive release from the RWST. Randomly selected 006 A2.13 as a replacement.
Tier 2 Group 1 SRO 022 Containment Cooling System 2.4.35 Unable to prepare question at the SRO license level for this K/A. This K/A requires knowledge of local auxiliary operator task during an emergency as it pertains to the Containment Cooling System. This is RO knowledge; therefore, not SRO level. Randomly selected 022 2.2.22 as a replacement.
Tier 2 Group 2 SRO 055 Condenser Air Removal 2.4.30 Unable to prepare question at the SRO license level for this K/A. There is no knowledge or abilities associated with the Condenser Air Removal system that is specific to the SRO position. Randomly selected 015 2.2.12 as a replacement.
Tier 3 SRO Equipment Control 2.2.39 This K/A is knowledge of less than or equal to one hour T.S action statements.
This is RO knowledge; therefore unable to prepare a question at the SRO license level for this K/A. Randomly selected 2.2.5 as a replacement.
Tier 3 SRO Emergency Procedures /
Plan 2.4.49 This K/A concerns immediate operator actions; which is RO knowledge; therefore unable to prepare a question at the SRO license level for this K/A. Randomly selected 2.4.40 as a replacement.