ML15128A244

2014 Prairie Island Nuclear Generating Plant Initial License Examination Form ES-401-4

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: ML15126A237 ML15126A466 ML15127A185 ML15128A227 ML15128A244 ML15128A250 ML15128A259 ML15128A292
References
Download: ML15128A244 (2)

Text

ES-401 Record of Rejected K/As (RO) Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A Tier 1 029 This K/A is not applicable because Prairie Island does not have a large PWR Group 1 Anticipated Transient coolant system. Randomly selected 029 EK1.03 as a replacement.

RO Without Scram (ATWS)

EK1.05 Tier 1 065 This K/A value is less than 2.5. All K/A values for AK2 are below 2.5. Randomly Group 1 Loss of Instrument Air selected 065 AK3.03 as a replacement.

RO AK2.01 Tier 2 078 The K/A value is less than 2.5. It is the only K/A under A2. Randomly selected Group 1 Instrument Air System 078 K1.03 as a replacement.

RO A2.01 Tier 1 015/017 This K/A concerns shifting Tave to the loop with the highest flow. Prairie Island Group 1 Reactor Coolant Pump does not have this ability; therefore this K/A was rejected. Randomly selected RO (RCP) Malfunctions 015/017 AK3.02 as a replacement.

AK3.05 Tier 1 033 This K/A is less than 2.5. All K/A values for 033 AK2 are below 2.5. Randomly Group 2 Loss of Intermediate Range selected 036 AK2.02 as replacement. New K/A is an AK2 in a new Abnormal RO Nuclear Instrumentation Plant Evolution instead of a non AK2 in 033 because the total number for K2s AK2.02 was getting low.

Tier 2 008 This K/A is less than 2.5. Randomly selected 008 K4.01 as a replacement.

Group 1 Component Cooling Water RO System (CCWS)

K4.03 Tier 2 064 This K/A is less than 2.5. All K/A values for 064 K5 are below 2.5. Randomly Group 1 Emergency Diesel selected 064 K4.11 as a replacement.

RO Generators (ED/G)

K5.01 Tier 2 073 This K/A is less than 2.5. All K/A values for 073 K6 are below 2.5. Randomly Group 1 Process Radiation selected 073 K5.01 as a replacement.

RO Monitoring (PRM) System K6.02 Tier 2 033 This K/A is less than 2.5. There is no other K/As in 033 K2. Randomly selected Group 2 Spent Fuel Pool Cooling 033 G 2.1.28 as a replacement.

RO System (SFPCS)

K2.01 Tier 2 079 This K/A is less than 2.5. All K/A values for 079 K6 are below 2.5. Randomly Group 2 Station Air System (SAS) selected 075 K2.03 as a replacement.

RO K6.02 Tier 2 076 Prairie Island has an open loop service water system (cooling water) instead of a Group 1 Service Water System closed loop; therefore, this K/A is not applicable to Prairie Island. Randomly RO (SWS) selected 076 A2.02 as a replacement.

A1.02

ES-401 Record of Rejected K/As (SRO) Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A Tier 1 APE 003 K/A for applying system limits and precautions does not apply to an abnormal Group 2 Dropped Control Rod procedure for a dropped rod because there are no precautions and limitations in SRO 2.1.32 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 APE 037 Unable to prepare question at the SRO license level for this K/A. This K/A Group 2 Steam Generator (S/G) Tube requires the operator to determine the pressure at which to maintain RCS during SRO Leak S/G cooldown with a tube leak. At Prairie Island, Reactor Operators are required AA2.16 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 2 006 Unable to prepare question at the SRO license level for this K/A. At Prairie Group 1 Emergency Core Cooling Island, the RWST is vented into the Auxiliary Building; therefore, during an SRO System accident condition any release from the RWST would be filtered through the A2.09 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 2 022 Unable to prepare question at the SRO license level for this K/A. This K/A Group 1 Containment Cooling requires knowledge of local auxiliary operator task during an emergency as it SRO System pertains to the Containment Cooling System. This is RO knowledge; therefore, 2.4.35 not SRO level. Randomly selected 022 2.2.22 as a replacement.

Tier 2 055 Unable to prepare question at the SRO license level for this K/A. There is no Group 2 Condenser Air Removal knowledge or abilities associated with the Condenser Air Removal system that is SRO 2.4.30 specific to the SRO position. Randomly selected 015 2.2.12 as a replacement.

Tier 3 Equipment Control This K/A is knowledge of less than or equal to one hour T.S action statements.

SRO 2.2.39 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 Emergency Procedures / This K/A concerns immediate operator actions; which is RO knowledge; therefore SRO Plan unable to prepare a question at the SRO license level for this K/A. Randomly 2.4.49 selected 2.4.40 as a replacement.