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| issue date = 03/06/2015
| issue date = 03/06/2015
| title = 2015 Point Beach Nuclear Plant Initial License Examination Form ES-401-4
| title = 2015 Point Beach Nuclear Plant Initial License Examination Form ES-401-4
| author name = McNeil D R
| author name = Mcneil D
| author affiliation = NRC/RGN-III/DRS/OLB
| author affiliation = NRC/RGN-III/DRS/OLB
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:ES-401 Record of Rejected K/As Form ES-401-4   Tier / Group Randomly Selected K/A Reason for Rejection RO Tier 1 / Group 1 APE 022AK1.04 Loss of Reactor Coolant Makeup Reason for changing from manual to automatic control of charging flow valve controller
{{#Wiki_filter:ES-401                           Record of Rejected K/As                     Form ES-401-4 Randomly Tier /
: PBNP does not have a Charging Flow V alve Controller which has an automatic feature. Reselected 022AK1.03 RO Tier 1 /
Selected                              Reason for Rejection Group K/A RO Tier 1 / APE       Loss of Reactor Coolant Makeup Group 1    022AK1.04  Reason for changing from manual to automatic control of charging flow valve controller: PBNP does not have a Charging Flow Valve Controller which has an automatic feature. Reselected 022AK1.03 RO Tier 1 / EPE       Steam Generator Tube Rupture (SGTR): Reflux boiling: Reflux boiling is not Group 1    038EK1.04  used as a mitigation strategy for SGTR at PBNP: Reselected 038EK1.01 RO Tier 1 / APE       Loss of Main Feedwater (MFW): No K2.* K/A with an RO Importance Rating Group 1    054K2.*    2.5: Reselected 054G2.2.36 RO Tier 1 / EPE       Loss of Offsite and Onsite Power (Station Blackout): No K2.* K/A with an RO Group 1    055EK2.*  Importance Rating  2.5: Reselected 055G2.4.8 RO Tier 1 / W/E04EA2. LOCA Outside Containment: Facility conditions and selection of appropriate Group 1    1          procedures during abnormal and emergency operations: Determined to be an SRO level question due to selection of procedures while within the EOP network: Reselected W/E04EA2.2 RO Tier 1 / APE       Accidental Liquid Radioactive-Waste Release: The calculation of offsite Group 2    059AK1.05  doses due to a release from the power plant: This is not an RO responsibility/job at PBNP: Reselected 059AK1.01 RO Tier 1 / W/E13EA2. Steam Generator Overpressure: Facility conditions and selection of Group 2    1          appropriate procedures during abnormal and emergency operations: This is not an RO responsibility at PBNP due to being a Yellow Critical Safety Function Path: Reselected W/E13EA2.2 RO Tier 2 / SYS       Pressurizer Pressure Control System (PZR PCS): PRT temperature and Group 1    010A3.01  pressure during PORV testing: No PORV testing is performed at PBNP which causes a temperature change in the PRT: Reselected 010A3.02 RO Tier 2 / SYS       Instrument Air System (IAS): No K5.* K/A with an RO Importance Rating Group 1    078K5.*    2.5: Reselected 078K1.04, see explanation below (061K1.*)
Group 1 EPE 038EK1.04 Steam Generator Tube Rupture (SGTR)
RO Tier 2 / SYS       Auxiliary / Emergency Feedwater (AFW) System: Was not used due to no Group 1    061K1.*    078K5.* K/A with an RO Importance Rating  2.5, randomly selected the available K/As within 078 (Instrument Air) which had a K/A  2.5, and then randomly exchanged it with an already selected K/A (i.e., 061K1.*):
: Reflux boiling: Reflux boiling is not used as a mitigation strategy for SGTR at PBNP
Reselected 061K5.05 RO Tier 2 / SYS103K5.* Containment System: No K5.* K/A with an RO Importance Rating 2.5:
: Reselected 038EK1.01 RO Tier 1 /
Group 1                Reselected 103K3.01, see explanation below (073K3.*)
Group 1 APE 054K2.* Loss of Main Feedwater (MFW)
RO Tier 2 / SYS       Process Radiation (PRM) System: Was not used due to no 103K5.* K/A with Group 1    073K3.*    an RO Importance Rating  2.5, randomly selected the available K/As within 103 (Containment) which had a K/A  2.5, and then exchanged it with an already selected K/A (i.e., 073K3.*): Reselected 073K5.01 RO Tier 2 / SYS       Service Water System (SWS): Conditions initiating automatic closure of Group 1    076K4.01  closed cooling water auxiliary building header supply and return valves: The Auxiliary Building at PBNP does not have header supply and return valves with an automatic closure: Reselected 076K4.06
: No K2.* K/A with an RO Importance Rating : Reselected 054G2.2.36 RO Tier 1 /
Group 1 EPE 055EK2.* Loss of Offsite and Onsite Power (Station Blackout)
: No K2.* K/A with an RO : Reselected 055G2.4.8 RO Tier 1 /
Group 1 W/E04EA2.1 LOCA Outside Containment
: Facility conditions and selection of appropriate procedures during abnormal and emergency operations
: Determined to be an SRO level question due to selection of procedures while within the EOP network: Reselected W/E04EA2.2 RO Tier 1 /
Group 2 APE 059AK1.05 Accidental Liquid Radioactive
-Waste Release
: The calculation of offsite doses due to a release from the power plant
: This is not an RO responsibility/job at PBNP
: Reselected 059AK1.01 RO Tier 1 /
Group 2 W/E13EA2.
1 Steam Generator Overpressure
: Facility conditions and selection of appropriate procedures during abnormal and emergency operations: This is not an RO responsibility at PBNP due to being a "Yellow" Critical Safety Function Path: Reselected W/E13EA2.2 RO Tier 2 /
Group 1 SYS 010A3.01 Pressurizer Pressure Control System (PZR PCS)
: PRT temperature and pressure during PORV testing
: No PORV testing is performed at PBNP which causes a temperature change in the PRT
: Reselected 010A3.02 RO Tier 2 /
Group 1 SYS 078K5.* Instrument Air System (IAS)
: No K5.* K/A 2.5: Reselected 078K1.04, see explanation below (061K1.*)
RO Tier 2 /
Group 1 SYS 061K1.* Auxiliary / Emergency Feedwater (AFW) System
: Was not used due to no he randomly exchanged it with an already selected K/A (i.e., 061K1.*)
Reselected 061K5.05 RO Tier 2 /
Group 1 SYS103K5.*
Containment System
: No K5.* K/A with an RO Importance Rating
Reselected 103K3.01, see explanation below (073K3.*)
RO Tier 2 /
Group 1 SYS 073K3.* Process Radiation (PRM) System
: Was not used due to no 103K5.* K/A with 103 (Calready selected K/A (i.e., 073K3.*)
: Reselected 073K5.01 RO Tier 2 /
Group 1 SYS 076K4.01 Service Water System (SWS)
: Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves
: The Auxiliary Building at PBNP does not have header supply and return valves with an automatic closure
: Reselected 076K4.06


Tier / Group Randomly Selected K/A Reason for Rejection RO Tier 2 /
Randomly Tier /
Group 1 SYS 076K4.06 Service Water System (SWS)
Selected                              Reason for Rejection Group K/A RO Tier 2 / SYS       Service Water System (SWS): Service water train separation: Train Group 1    076K4.06  separation is only achieved by Service Water Pump power supplies at PBNP:
: Service water train separation
Reselected 076K4.02 RO Tier 2 / SYS       Containment Purge System (CPS): Containment evacuation signal: Unable Group 2    029A4.04  to construct a question with the required level of difficulty: Reselected 029A4.01 RO Tier 2 / SYS       Containment Purge System (CPS): Containment purge flow rate: Purge flow Group 2    029A4.01  rate of the Containment Purge System is not monitored: No further A4.* K/A exist with an RO Importance Rating 2.5, selected 029A3.01 due to A3 not being sampled within Tier 2/Group2 RO Tier 2 / SYS       Steam Dump System (SDS) and Turbine Bypass Control: S/G level: Unable Group 2    041K1.02  to construct a question with the required level of difficulty: Reselected 041K1.05 SRO Tier   APE       Loss of Component Cooling Water (CCW): (multi-unit license) Ability to 1/          026G2.2.4  explain the variations in control board/control room layouts, systems, Group 1                instrumentation, and procedural actions between units at a facility: No differences between the units which leveraged as a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 026G2.2.38 SRO Tier   APE       Steam Line Rupture: Conditions requiring a reactor trip: Unable to write a 1/          040AA2.02  question to the requirements of an SRO level question (meeting the Group 1                requirements of 10CFR55.43(b)): Reselected 040AA2.04 SRO Tier   APE       Fuel Handling Incidents: Ability to interpret reference materials, such as 1/          036G2.1.25 graphs, curves, tables, etc: Unable to write a question to the requirements of Group 2                an SRO level question (meeting the requirements of 10CFR55.43(b)):
: Train separation is only achieved by Service Water Pump power supplies at PBNP
Reselected 036G2.1.31 SRO Tier   APE       Fuel Handling Incidents: Ability to locate control room switches, controls, and 1/          036G2.1.31 indications, and to determine that they correctly reflect the desired plant Group 2                lineup.: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 036G2.1.23 SRO Tier   SYS        Pressurizer Relief Tank/Quench Tank System (PRTS): Bubble formation in 2/          007A2.06  PZR: Unable to write a question to the requirements of an SRO level Group 1                question (meeting the requirements of 10CFR55.43(b)): Reselected 007A2.07 SRO Tier   SYS       Pressurizer Relief Tank/Quench Tank System (PRTS): Recirculating quench 2/          007A2.07  tank: There are no procedures at PBNP which accomplish this task. Unable Group 1                to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 007A2.01 SRO Tier   SYS       Pressurizer Level Control System (PZR LCS): Ability to locate control room 2/          011G2.1.31 switches, controls, and indications, and to determine that they correctly reflect Group 2                the desired plant lineup: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)):
Reselected 076K4.02 RO Tier 2 /
Reselected 011G2.1.32
Group 2 SYS 029A4.04 Containment Purge System (CPS)
: Containment evacuation signal
: Unable to construct a question with the required level of difficulty: Reselected 029A4.01 RO Tier 2 /
Group 2 SYS 029A4.01 Containment Purge System (CPS)
: Containment purge flow rate
: Purge flow rate of the Containment Purge System is not monitored
: No further A4.* K/A  029A3.01 due to A3 not being sampled within Tier 2/Group2 RO Tier 2 /
Group 2 SYS 041K1.02 Steam Dump System (SDS) and Turbine Bypass Control
: S/G level: Unable to construct a question with the required level of difficulty
: Reselected 041K1.05 SRO Tier 1 / Group 1 APE 026G2.2.4 Loss of Component Cooling Water (CCW)
: (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility
: No differences between the units which leveraged as a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
: Reselected 026G2.2.38 SRO Tier 1 / Group 1 APE 040AA2.02 Steam Line Rupture
: Conditions requiring a reactor trip
: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
: Reselected 040AA2.04 SRO Tier 1 / Group 2 APE 036G2.1.25 Fuel Handling Incidents
: Ability to interpret reference materials, such as graphs, curves, tables, etc
: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
Reselected 036G2.1.31 SRO Tier 1 / Group 2 APE 036G2.1.31 Fuel Handling Incidents
: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
: Reselected 036G2.1.23 SRO Tier 2 / Group 1 SY S 007A2.06 Pressurizer Relief Tank/Quench Tank System (PRTS)
: Bubble formation in PZR: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
: Reselected 007A2.07 SRO Tier 2 / Group 1 SYS 007A2.07 Pressurizer Relief Tank/Quench Tank System (PRTS)
: Recirculating quench tank: There are no procedures at PBNP which accomplish this task. Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
: Reselected 007A2.01 SRO Tier 2 / Group 2 SYS 011G2.1.31 Pressurizer Level Control System (PZR LCS)
: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup
: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b))
Reselected 011G2.1.32


Tier / Group Randomly Selected K/A Reason for Rejection RO Tier 2 /
Randomly Tier /
Group 2 SYS 022G2.2.4 Containment Spray System (CSS)
Selected                              Reason for Rejection Group K/A RO Tier 2 / SYS       Containment Spray System (CSS): (multi-unit license) Ability to explain the Group 2    022G2.2.4  variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility: Unable to write a question to meet this K/A due to no major differences between units for this system:
: (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility
Reselected 022G2.2.39 RO Tier 2 / SYS       Instrument Air System (IAS): Cooling water to compressor: Unable to write a Group 1    078K1.04  question to meet this K/A due only one station air compressor has cooling water supplied to it, and there is a question focused on this in the test already (SRO Tier 1/Group 1, 065A204 - Typical conditions which could cause a compressor trip (e.g., high temperature): Reselected 078K1.05 Loss of Intermediate Range Nuclear Instrumentation: Ability to determine RO Tier 1 / APE        and interpret the following as they apply to the Loss of Intermediate Range Group 2    033AA2.12 Nuclear Instrumentation: Maximum allowable channel disagreement.:
: Unable to write a question to meet this K/A due to no major differences between units for this system
Submitted question was determined to not be discriminatorily valid. Unable to write a replacement question that meets this KA and that has discrimination validity. Discussed with Chief Examiner and obtained approval to redraw:
Reselected 022G2.2.39 RO Tier 2 /
Reselected 033AA2.01}}
Group 1 SYS 078K1.0 4 Instrument Air System (IAS)
: Cooling water to compressor
: Unable to write a question to meet this K/A due only one station air compressor has cooling water supplied to it, and there is a question focused on this in the test already (SRO Tier 1/Group 1, 065A204 - Typical conditions which could cause a compressor trip (e.g., high temperature)
: Reselected 078K1.05 RO Tier 1 / Group 2 APE 033AA2.12 Loss of Intermediate Range Nuclear Instrumentation
: Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Maximum allowable channel disagreement.
Submitted question was determined to not be discriminatorily valid. Unable to write a replacement question that meets this KA and that has discrimination validity. Discussed with Chief Examiner and obtained approval to redraw: Reselected 033AA2.01}}

Latest revision as of 15:02, 31 October 2019

2015 Point Beach Nuclear Plant Initial License Examination Form ES-401-4
ML15083A062
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/06/2015
From: Mcneil D
NRC/RGN-III/DRS/OLB
To:
Florida Power & Light Energy Point Beach
References
Download: ML15083A062 (3)


Text

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Tier /

Selected Reason for Rejection Group K/A RO Tier 1 / APE Loss of Reactor Coolant Makeup Group 1 022AK1.04 Reason for changing from manual to automatic control of charging flow valve controller: PBNP does not have a Charging Flow Valve Controller which has an automatic feature. Reselected 022AK1.03 RO Tier 1 / EPE Steam Generator Tube Rupture (SGTR): Reflux boiling: Reflux boiling is not Group 1 038EK1.04 used as a mitigation strategy for SGTR at PBNP: Reselected 038EK1.01 RO Tier 1 / APE Loss of Main Feedwater (MFW): No K2.* K/A with an RO Importance Rating Group 1 054K2.* 2.5: Reselected 054G2.2.36 RO Tier 1 / EPE Loss of Offsite and Onsite Power (Station Blackout): No K2.* K/A with an RO Group 1 055EK2.* Importance Rating 2.5: Reselected 055G2.4.8 RO Tier 1 / W/E04EA2. LOCA Outside Containment: Facility conditions and selection of appropriate Group 1 1 procedures during abnormal and emergency operations: Determined to be an SRO level question due to selection of procedures while within the EOP network: Reselected W/E04EA2.2 RO Tier 1 / APE Accidental Liquid Radioactive-Waste Release: The calculation of offsite Group 2 059AK1.05 doses due to a release from the power plant: This is not an RO responsibility/job at PBNP: Reselected 059AK1.01 RO Tier 1 / W/E13EA2. Steam Generator Overpressure: Facility conditions and selection of Group 2 1 appropriate procedures during abnormal and emergency operations: This is not an RO responsibility at PBNP due to being a Yellow Critical Safety Function Path: Reselected W/E13EA2.2 RO Tier 2 / SYS Pressurizer Pressure Control System (PZR PCS): PRT temperature and Group 1 010A3.01 pressure during PORV testing: No PORV testing is performed at PBNP which causes a temperature change in the PRT: Reselected 010A3.02 RO Tier 2 / SYS Instrument Air System (IAS): No K5.* K/A with an RO Importance Rating Group 1 078K5.* 2.5: Reselected 078K1.04, see explanation below (061K1.*)

RO Tier 2 / SYS Auxiliary / Emergency Feedwater (AFW) System: Was not used due to no Group 1 061K1.* 078K5.* K/A with an RO Importance Rating 2.5, randomly selected the available K/As within 078 (Instrument Air) which had a K/A 2.5, and then randomly exchanged it with an already selected K/A (i.e., 061K1.*):

Reselected 061K5.05 RO Tier 2 / SYS103K5.* Containment System: No K5.* K/A with an RO Importance Rating 2.5:

Group 1 Reselected 103K3.01, see explanation below (073K3.*)

RO Tier 2 / SYS Process Radiation (PRM) System: Was not used due to no 103K5.* K/A with Group 1 073K3.* an RO Importance Rating 2.5, randomly selected the available K/As within 103 (Containment) which had a K/A 2.5, and then exchanged it with an already selected K/A (i.e., 073K3.*): Reselected 073K5.01 RO Tier 2 / SYS Service Water System (SWS): Conditions initiating automatic closure of Group 1 076K4.01 closed cooling water auxiliary building header supply and return valves: The Auxiliary Building at PBNP does not have header supply and return valves with an automatic closure: Reselected 076K4.06

Randomly Tier /

Selected Reason for Rejection Group K/A RO Tier 2 / SYS Service Water System (SWS): Service water train separation: Train Group 1 076K4.06 separation is only achieved by Service Water Pump power supplies at PBNP:

Reselected 076K4.02 RO Tier 2 / SYS Containment Purge System (CPS): Containment evacuation signal: Unable Group 2 029A4.04 to construct a question with the required level of difficulty: Reselected 029A4.01 RO Tier 2 / SYS Containment Purge System (CPS): Containment purge flow rate: Purge flow Group 2 029A4.01 rate of the Containment Purge System is not monitored: No further A4.* K/A exist with an RO Importance Rating 2.5, selected 029A3.01 due to A3 not being sampled within Tier 2/Group2 RO Tier 2 / SYS Steam Dump System (SDS) and Turbine Bypass Control: S/G level: Unable Group 2 041K1.02 to construct a question with the required level of difficulty: Reselected 041K1.05 SRO Tier APE Loss of Component Cooling Water (CCW): (multi-unit license) Ability to 1/ 026G2.2.4 explain the variations in control board/control room layouts, systems, Group 1 instrumentation, and procedural actions between units at a facility: No differences between the units which leveraged as a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 026G2.2.38 SRO Tier APE Steam Line Rupture: Conditions requiring a reactor trip: Unable to write a 1/ 040AA2.02 question to the requirements of an SRO level question (meeting the Group 1 requirements of 10CFR55.43(b)): Reselected 040AA2.04 SRO Tier APE Fuel Handling Incidents: Ability to interpret reference materials, such as 1/ 036G2.1.25 graphs, curves, tables, etc: Unable to write a question to the requirements of Group 2 an SRO level question (meeting the requirements of 10CFR55.43(b)):

Reselected 036G2.1.31 SRO Tier APE Fuel Handling Incidents: Ability to locate control room switches, controls, and 1/ 036G2.1.31 indications, and to determine that they correctly reflect the desired plant Group 2 lineup.: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 036G2.1.23 SRO Tier SYS Pressurizer Relief Tank/Quench Tank System (PRTS): Bubble formation in 2/ 007A2.06 PZR: Unable to write a question to the requirements of an SRO level Group 1 question (meeting the requirements of 10CFR55.43(b)): Reselected 007A2.07 SRO Tier SYS Pressurizer Relief Tank/Quench Tank System (PRTS): Recirculating quench 2/ 007A2.07 tank: There are no procedures at PBNP which accomplish this task. Unable Group 1 to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)): Reselected 007A2.01 SRO Tier SYS Pressurizer Level Control System (PZR LCS): Ability to locate control room 2/ 011G2.1.31 switches, controls, and indications, and to determine that they correctly reflect Group 2 the desired plant lineup: Unable to write a question to the requirements of an SRO level question (meeting the requirements of 10CFR55.43(b)):

Reselected 011G2.1.32

Randomly Tier /

Selected Reason for Rejection Group K/A RO Tier 2 / SYS Containment Spray System (CSS): (multi-unit license) Ability to explain the Group 2 022G2.2.4 variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility: Unable to write a question to meet this K/A due to no major differences between units for this system:

Reselected 022G2.2.39 RO Tier 2 / SYS Instrument Air System (IAS): Cooling water to compressor: Unable to write a Group 1 078K1.04 question to meet this K/A due only one station air compressor has cooling water supplied to it, and there is a question focused on this in the test already (SRO Tier 1/Group 1, 065A204 - Typical conditions which could cause a compressor trip (e.g., high temperature): Reselected 078K1.05 Loss of Intermediate Range Nuclear Instrumentation: Ability to determine RO Tier 1 / APE and interpret the following as they apply to the Loss of Intermediate Range Group 2 033AA2.12 Nuclear Instrumentation: Maximum allowable channel disagreement.:

Submitted question was determined to not be discriminatorily valid. Unable to write a replacement question that meets this KA and that has discrimination validity. Discussed with Chief Examiner and obtained approval to redraw:

Reselected 033AA2.01