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=Text=
=Text=
{{#Wiki_filter:UNITED STATES May 4, 2018
{{#Wiki_filter:May 4, 2018


==SUBJECT:==
==SUBJECT:==
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Sincerely,
Sincerely,
/RA/
/RA/  
Karla Stoedter, Chief Branch 1 Division of Reactor Projects Docket No. 50-331 License No. DPR-49
 
Karla Stoedter, Chief Branch 1 Division of Reactor Projects  
 
Docket No. 50-331 License No. DPR-49  


===Enclosure:===
===Enclosure:===
Inspection Report 05000331/2018001
Inspection Report 05000331/2018001  


REGION III==
REGION III==
Docket Number: 50-331 License Number: DPR-49 Report Numbers: 05000331/2018001 Enterprise Identifier: I-2018-001-0035 Licensee: NextEra Energy Duane Arnold, LLC Facility: Duane Arnold Energy Center Location: Palo, IA Dates: January 1 through March 31, 2018 Inspectors: C. Norton, Senior Resident Inspector J. Steffes, Resident Inspector R. Stone, Acting Resident Inspector A. Dunlap, Senior Reactor Inspector T. Nakanishi, Reliability and Risk Analyst J. Neurauter, Senior Reactor Inspector T. Ospino, Reactor Engineer Approved by: K. Stoedter, Chief Branch 1 Division of Reactor Projects Enclosure
Docket Number:
50-331 License Number:
DPR-49 Report Numbers:
05000331/2018001 Enterprise Identifier: I-2018-001-0035 Licensee:
NextEra Energy Duane Arnold, LLC Facility:
Duane Arnold Energy Center Location:
Palo, IA Dates:
January 1 through March 31, 2018 Inspectors:
C. Norton, Senior Resident Inspector J. Steffes, Resident Inspector R. Stone, Acting Resident Inspector A. Dunlap, Senior Reactor Inspector T. Nakanishi, Reliability and Risk Analyst J. Neurauter, Senior Reactor Inspector T. Ospino, Reactor Engineer  
 
Approved by:
K. Stoedter, Chief Branch 1 Division of Reactor Projects


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated quarterly inspection at Duane Arnold Energy Center in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated quarterly inspection at Duane Arnold Energy Center in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.


List of Findings and Violations No findings or violations were identified.
===List of Findings and Violations===
No findings or violations were identified.


Additional Tracking Items Type     Issue Number                 Title                       Report           Status Section URI     05000331/2018001-01         Failure to Perform           71111.15        Open Nondestructive Examination of Main Steam Isolation Valve 4415 Following Machining of Valve Bore
===Additional Tracking Items===
Type Issue Number Title Report Section Status URI 05000331/2018001-01 Failure to Perform Nondestructive Examination of Main Steam Isolation Valve 4415 Following Machining of Valve Bore 71111.15 Open


TABLE OF CONTENTS
TABLE OF CONTENTS
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==INSPECTION RESULTS==
==INSPECTION RESULTS==
.............................................................................................................. 8
.............................................................................................................. 8  


===71111.15Operability Determinations and Functionality Assessments....................................... 8 PLANT STATUS Duane Arnold Energy Center began the inspection period at rated thermal power. On March 17, 2018, the licensee lowered thermal power to 74 percent of rated to perform a control rod sequence exchange. The unit was returned to steady state rated thermal power on March 19, 2018. With the exception of minor power reductions of less than 2 percent for surveillance testing and control rod line adjustments, the unit remained at rated thermal power for the remainder of the inspection period.
===71111.15Operability Determinations and Functionality Assessments....................................... 8 PLANT STATUS  
 
Duane Arnold Energy Center began the inspection period at rated thermal power. On March 17, 2018, the licensee lowered thermal power to 74 percent of rated to perform a control rod sequence exchange. The unit was returned to steady state rated thermal power on March 19, 2018. With the exception of minor power reductions of less than 2 percent for surveillance testing and control rod line adjustments, the unit remained at rated thermal power for the remainder of the inspection period.


==INSPECTION SCOPES==
==INSPECTION SCOPES==
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==REACTOR SAFETY==
==REACTOR SAFETY==
71111.01Adverse Weather Protection Seasonal Extreme Weather ===
71111.01Adverse Weather Protection Seasonal Extreme Weather===
{{IP sample|IP=IP 71111.15|count=1}}
{{IP sample|IP=IP 71111.15|count=1}}
The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 3, January 4, January 5, January 17, and February 6, 2108.
The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 3, January 4, January 5, January 17, and February 6, 2108.


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The inspectors evaluated readiness to cope with external flooding on March 27, 2018.
The inspectors evaluated readiness to cope with external flooding on March 27, 2018.


===71111.04Equipment Alignment Partial Walkdown ===
===71111.04Equipment Alignment Partial Walkdown===
{{IP sample|IP=IP 71111.04|count=1}}
{{IP sample|IP=IP 71111.04|count=1}}
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
: (1) Control Rod Drive (CRD) system on March 2, 2018.
: (1) Control Rod Drive (CRD) system on March 2, 2018.
Line 84: Line 104:
The inspectors evaluated system configurations during a complete walkdown of the Standby Liquid Control System on March 29, 2018.
The inspectors evaluated system configurations during a complete walkdown of the Standby Liquid Control System on March 29, 2018.


===71111.05AQFire Protection Annual/Quarterly Quarterly Inspection ===
===71111.05AQFire Protection Annual/Quarterly  
 
Quarterly Inspection===
{{IP sample|IP=IP 71111.05|count=6}}
{{IP sample|IP=IP 71111.05|count=6}}
The inspectors evaluated fire protection program implementation in the following selected areas:
The inspectors evaluated fire protection program implementation in the following selected areas:
: (1) Reactor Building 786 Level on February 3, 2018;
: (1) Reactor Building 786 Level on February 3, 2018;
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: (6) Reactor Building 716 Level (Zones 1-AN, 1-AS, 1-C and 1-G) on March 20, 2018.
: (6) Reactor Building 716 Level (Zones 1-AN, 1-AS, 1-C and 1-G) on March 20, 2018.


===71111.07Heat Sink Performance Heat Sink (Triennial) ===
===71111.07Heat Sink Performance Heat Sink (Triennial)===
{{IP sample|IP=IP 71111.07|count=3}}
{{IP sample|IP=IP 71111.07|count=3}}
The inspectors evaluated heat exchanger/heat sink performance on the following components:
The inspectors evaluated heat exchanger/heat sink performance on the following components:
: (1) Residual Heat Removal (RHR) Pump Seal Coolers (1E220A, B, C, D), Section 02.02b;
: (1) Residual Heat Removal (RHR) Pump Seal Coolers (1E220A, B, C, D), Section 02.02b;
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: (3) Heat Sink, Section 02.02d, Specifically Sections 02.02d.2 and 02.02d.4 were completed.
: (3) Heat Sink, Section 02.02d, Specifically Sections 02.02d.2 and 02.02d.4 were completed.


===71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification ===
===71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification===
{{IP sample|IP=IP 71111.11|count=1}}
{{IP sample|IP=IP 71111.11|count=1}}
The inspectors observed and evaluated a licensed operator evaluated scenario on


===January 27, 2018.
The inspectors observed and evaluated a licensed operator evaluated scenario on January 27, 2018.


Operator Performance (1 Sample)===
===Operator Performance (1 Sample)===
The inspectors observed and evaluated a control rod sequence exchange on March 17-18, 2018.
The inspectors observed and evaluated a control rod sequence exchange on March 17-18, 2018.


===71111.12Maintenance Effectiveness Routine Maintenance Effectiveness ===
===71111.12Maintenance Effectiveness  
 
Routine Maintenance Effectiveness===
{{IP sample|IP=IP 71111.12|count=2}}
{{IP sample|IP=IP 71111.12|count=2}}
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
: (1) MO 1902, B torus cooling isolation valve actuator disassembly and movement on January 27, 2018; and
: (1) MO 1902, B torus cooling isolation valve actuator disassembly and movement on January 27, 2018; and
: (2) B standby diesel generator critical maintenance management starting air emergent issue on March 27, 2018.
: (2) B standby diesel generator critical maintenance management starting air emergent issue on March 27, 2018.


===71111.13Maintenance Risk Assessments and Emergent Work Control ===
===71111.13Maintenance Risk Assessments and Emergent Work Control===
{{IP sample|IP=IP 71111.13|count=4}}
{{IP sample|IP=IP 71111.13|count=4}}
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
: (1) B Standby Gas Treatment (SBGT) System Efficiency Test on January 27, 2018;
: (1) B Standby Gas Treatment (SBGT) System Efficiency Test on January 27, 2018;
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: (4) Phoenix Risk calculation for B standby diesel generator critical maintenance management window on March 25, 2018.
: (4) Phoenix Risk calculation for B standby diesel generator critical maintenance management window on March 25, 2018.


===71111.15Operability Determinations and Functionality Assessments ===
===71111.15Operability Determinations and Functionality Assessments===
{{IP sample|IP=IP 71111.15|count=8}}
{{IP sample|IP=IP 71111.15|count=8}}
The inspectors evaluated the following operability determinations and functionality assessments:
The inspectors evaluated the following operability determinations and functionality assessments:
: (1) Condition Report (CR) 02243010; SBGT System Inlet Relief Damper on January 6, 2018;
: (1) Condition Report (CR) 02243010; SBGT System Inlet Relief Damper on January 6, 2018;
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Exhaust Fan Failure on February 17, 2018.
Exhaust Fan Failure on February 17, 2018.


===71111.18Plant Modifications ===
===71111.18Plant Modifications===
{{IP sample|IP=IP 71111.18|count=2}}
{{IP sample|IP=IP 71111.18|count=2}}
The inspectors evaluated the following temporary or permanent modifications:
The inspectors evaluated the following temporary or permanent modifications:
: (1) Reactor Protection System test box use for main steam isolation valve logic testing; and
: (1) Reactor Protection System test box use for main steam isolation valve logic testing; and
: (2) Reactor Protection System test box use for turbine stop valve logic testing.
: (2) Reactor Protection System test box use for turbine stop valve logic testing.


===71111.19Post Maintenance Testing ===
===71111.19Post Maintenance Testing===
{{IP sample|IP=IP 71111.19|count=6}}
{{IP sample|IP=IP 71111.19|count=6}}
The inspectors evaluated the following post maintenance tests:
The inspectors evaluated the following post maintenance tests:
: (1) Motor operated valve (MO) 1902, RHR (Drywell Spray) Actuator Maintenance, on February 3, 2018;
: (1) Motor operated valve (MO) 1902, RHR (Drywell Spray) Actuator Maintenance, on February 3, 2018;
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: (6) Post Maintenance Testing during Surveillance Test Procedure (STP) 3.5.1-02, Low-Pressure Coolant Injection Operability, on February 17, 2018.
: (6) Post Maintenance Testing during Surveillance Test Procedure (STP) 3.5.1-02, Low-Pressure Coolant Injection Operability, on February 17, 2018.


===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:
===71111.22Surveillance Testing  
Routine ===
 
The inspectors evaluated the following surveillance tests:
Routine===
{{IP sample|IP=IP 71111.22|count=5}}
{{IP sample|IP=IP 71111.22|count=5}}
: (1) B RHRSW Operability Test; NS160002B, on February 17, 2018;
: (1) B RHRSW Operability Test; NS160002B, on February 17, 2018;
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: (3) STP 3.3.1.1-17; MSIV Functional Test, on March 17, 2018;
: (3) STP 3.3.1.1-17; MSIV Functional Test, on March 17, 2018;
: (4) STP 3.3.1.1-13; Turbine Control Valve End of Cycle Recirculation Pump Trip Logic And RPS Instrument Functional Test, on March 18, 2018; and
: (4) STP 3.3.1.1-13; Turbine Control Valve End of Cycle Recirculation Pump Trip Logic And RPS Instrument Functional Test, on March 18, 2018; and
: (5) STP 3.1.7-01; Standby Liquid Control (SBLC) Pump Operability Test, on
: (5) STP 3.1.7-01; Standby Liquid Control (SBLC) Pump Operability Test, on March 26, 2018.


===March 26, 2018.
===In-service (2 Samples)===
 
In-service (2 Samples)===
: (1) STP 3.5.1-02B; B Low Pressure Coolant Injection (LPCI) System Operability Test, on February 17, 2018; and
: (1) STP 3.5.1-02B; B Low Pressure Coolant Injection (LPCI) System Operability Test, on February 17, 2018; and
: (2) Main Turbine Stop and Combined Intermediate Valves Test, on March 17, 2018.
: (2) Main Turbine Stop and Combined Intermediate Valves Test, on March 17, 2018.
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: (1) STP 3.6.4-01B; Secondary Containment Isolation Damper Closing Time Test Channel B, on February 24, 2018.
: (1) STP 3.6.4-01B; Secondary Containment Isolation Damper Closing Time Test Channel B, on February 24, 2018.


===71114.06Drill Evaluation Emergency Planning Drill ===
===71114.06Drill Evaluation  
 
Emergency Planning Drill===
{{IP sample|IP=IP 71114.06|count=1}}
{{IP sample|IP=IP 71114.06|count=1}}
The inspectors evaluated licensed operator emergency planning performance during requalification training, on January 27,
The inspectors evaluated licensed operator emergency planning performance during requalification training, on January 27,


==OTHER ACTIVITIES - BASELINE==
==OTHER ACTIVITIES - BASELINE==
===71151Performance Indicator Verification===
{{IP sample|IP=IP 71151|count=3}}


===71151Performance Indicator Verification ===
{{IP sample|IP=IP 71151|count=3}}
The inspectors verified licensee performance indicators submittals listed below:
The inspectors verified licensee performance indicators submittals listed below:
: (1) IE01: Unplanned Scrams per 7000 Critical Hours-1 Sample; January 1, 2017 through December 31, 2017;
: (1) IE01: Unplanned Scrams per 7000 Critical Hours-1 Sample; January 1, 2017 through December 31, 2017;
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: (3) IE04: Unplanned Scrams with Complications (USwC) -1 Sample; January 1, 2017 through December 31, 2017.
: (3) IE04: Unplanned Scrams with Complications (USwC) -1 Sample; January 1, 2017 through December 31, 2017.


===71153Follow-Up of Events and Notices of Enforcement Discretion Events ===
===71153Follow-Up of Events and Notices of Enforcement Discretion Events===
{{IP sample|IP=IP 71153|count=1}}
{{IP sample|IP=IP 71153|count=1}}
: (1) B channel half SCRAM on January 13,
: (1) B channel half SCRAM on January 13,


==INSPECTION RESULTS==
==INSPECTION RESULTS==
71111.15Operability Determinations and Functionality Assessments Unresolved Item       Failure to Perform a Nondestructive Examination     71111.15 (Open)          (NDE) of Main Steam Line Isolation Valve (MSIV)     Operability CV 4415 Following Machining of Valve Bore           Determinations and URI 05000331/2018-01                                 Functional Assessments
71111.15Operability Determinations and Functionality Assessments  
 
Unresolved Item (Open)
Failure to Perform a Nondestructive Examination (NDE) of Main Steam Line Isolation Valve (MSIV)
CV 4415 Following Machining of Valve Bore URI 05000331/2018-01 71111.15 Operability Determinations and Functional Assessments  


=====Description:=====
=====Description:=====
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Corrective Action Reference: CR 02251009; Missed NDE During Rebuild Of MSIV CV4415.
Corrective Action Reference: CR 02251009; Missed NDE During Rebuild Of MSIV CV4415.


71153Follow-Up of Events and Notices of Enforcement Discretion Observation - B Channel Half SCRAM                                     71153Follow-Up of Events and Notices of Enforcement Discretion On January 10, 2018, the inspectors evaluated the licensees response to a B Channel half SCRAM condition. The half SCRAM was caused by the failure of Average Power Range Monitor (APRM) B. The inspectors determined the operators appropriately implemented pertinent procedures and Technical Specification requirements which allowed the operators to bypass APRM B and reset the half SCRAM.
71153Follow-Up of Events and Notices of Enforcement Discretion  
 
Observation - B Channel Half SCRAM 71153Follow-Up of Events and Notices of Enforcement Discretion On January 10, 2018, the inspectors evaluated the licensees response to a B Channel half SCRAM condition. The half SCRAM was caused by the failure of Average Power Range Monitor (APRM) B. The inspectors determined the operators appropriately implemented pertinent procedures and Technical Specification requirements which allowed the operators to bypass APRM B and reset the half SCRAM.


The licensee performed simple troubleshooting and determined the power supply for APRM B had failed. The power supply had recently been replaced. The inspectors determined the licensee had replaced the power supply in accordance with NextEra procedures and that the APRM power supply failure was not within the licensees ability to foresee and prevent. The licensee entered this minor issue into their corrective action program as CR 02243984; E/S 265 No Voltage Output.
The licensee performed simple troubleshooting and determined the power supply for APRM B had failed. The power supply had recently been replaced. The inspectors determined the licensee had replaced the power supply in accordance with NextEra procedures and that the APRM power supply failure was not within the licensees ability to foresee and prevent. The licensee entered this minor issue into their corrective action program as CR 02243984; E/S 265 No Voltage Output.
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=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


71111.01Adverse Weather Protection
71111.01Adverse Weather Protection  
- Operations Shift Manager (OSM) Logs - January 3, 2018
- Operations Shift Manager (OSM) Logs - January 3, 2018  
- OSM Logs - January 4, 2018
- OSM Logs - January 4, 2018  
- OSM Logs - January 5, 2018
- OSM Logs - January 5, 2018  
- OSM Logs - January 17, 2018
- OSM Logs - January 17, 2018  
- OSM Logs - February 6, 2018
- OSM Logs - February 6, 2018  
- Abnormal Operating Procedure (AOP) 903; Adverse Weather; Revision 59
- Abnormal Operating Procedure (AOP) 903; Adverse Weather; Revision 59  
- AOP 902; Flood; Revision 62
- AOP 902; Flood; Revision 62
71111.04Equipment Alignment
71111.04Equipment Alignment  
- Operating Instruction (OI) 255A2; CRD System; Revision 7
- Operating Instruction (OI) 255A2; CRD System; Revision 7  
- OI 255A3; CRD System HCU; Revision 3
- OI 255A3; CRD System HCU; Revision 3  
- P&ID of Standby Liquid Control (SLBC) System; BECH-M126; Revision 26
- P&ID of Standby Liquid Control (SLBC) System; BECH-M126; Revision 26  
 
- OI 153A2; SLBC System Valve Lineup; Revision 6
- OI 153A2; SLBC System Valve Lineup; Revision 6
71111.05AQFire Protection Annual/Quarterly
71111.05AQFire Protection Annual/Quarterly  
- Pre-Fire Plan (PFP) -LL-757; PFP-LLRPSF; Revision 3
- Pre-Fire Plan (PFP) -LL-757; PFP-LLRPSF; Revision 3  
- PFP-CB-757; Pre-Fire Plan Control Building El. 757; Revision 4
- PFP-CB-757; Pre-Fire Plan Control Building El. 757; Revision 4  
- PFP-TB-757; Pre-Fire Plan Turbine Building El. 757; Revision 4
- PFP-TB-757; Pre-Fire Plan Turbine Building El. 757; Revision 4  
- PFP-RB-786; Pre-Fire Plan Reactor Building El. 786; Revision 6
- PFP-RB-786; Pre-Fire Plan Reactor Building El. 786; Revision 6  
- PFP-RB-716; Pre-Fire Plan Reactor Building El. 716; Revision 3
- PFP-RB-716; Pre-Fire Plan Reactor Building El. 716; Revision 3  
- PFP-RW-757; Pre-Fire Plan Radwaste Building; Revision 0
- PFP-RW-757; Pre-Fire Plan Radwaste Building; Revision 0
71111.07Heat Sink Performance
71111.07Heat Sink Performance  
- 2016 Bathymetric Survey and Channel Stability Analysis; December 28, 2016
- 2016 Bathymetric Survey and Channel Stability Analysis; December 28, 2016  
- 2017 Summer Bathymetric Survey and Channel Stability Analysis; September 5, 2017
- 2017 Summer Bathymetric Survey and Channel Stability Analysis; September 5, 2017  
- Borg-Warner Bulletin 1861; Light Weight High Pressure Heat Exchangers for Mechanical Seal
- Borg-Warner Bulletin 1861; Light Weight High Pressure Heat Exchangers for Mechanical Seal
Injection Cooling and Sample Cooling; March 1986
Injection Cooling and Sample Cooling; March 1986  
- CAL-M06-012; Required Water Depth at River Water Intake; Revision 0
- CAL-M06-012; Required Water Depth at River Water Intake; Revision 0  
- CAL-M93-078; Emergency Service Water (ESW) RHRSW Pit Pumpdown Times; Revision 1
- CAL-M93-078; Emergency Service Water (ESW) RHRSW Pit Pumpdown Times; Revision 1  
- CAL-M05-027; Emergency Diesel Generator Heat Exchanger Heat Transfer Calculation;
- CAL-M05-027; Emergency Diesel Generator Heat Exchanger Heat Transfer Calculation;
Revision 4
Revision 4  
- CAL-M10-010; RHR Pump Seal Water Cooler Performance; Revision 0
- CAL-M10-010; RHR Pump Seal Water Cooler Performance; Revision 0  
- EC 285373; Equivalent Design Package: Fabricate Replacement Dollar Plates;
- EC 285373; Equivalent Design Package: Fabricate Replacement Dollar Plates;
February 15, 2016
February 15, 2016  
- FPLE 102-DAEC-01; Curtis-Wright Report: DAEC Final Eddy Current Inspection Report for
- FPLE 102-DAEC-01; Curtis-Wright Report: DAEC Final Eddy Current Inspection Report for
EDG 1E053A; October 20, 2015
EDG 1E053A; October 20, 2015  
- AOP 410; Loss of River Water Supply; Revision 30
- AOP 410; Loss of River Water Supply; Revision 30  
- GENERA-F010-01; Procedure: Mechanical Inspection; Revision 70
- GENERA-F010-01; Procedure: Mechanical Inspection; Revision 70  
- I.LI-R979-01; Rickly Hydrological Co., Model R114-B-56-E Sounding Reel; Revision 2
- I.LI-R979-01; Rickly Hydrological Co., Model R114-B-56-E Sounding Reel; Revision 2  
- M015-145; Data Sheet for Emergency Diesel Generator Lube Oil Cooler; Revision 2
- M015-145; Data Sheet for Emergency Diesel Generator Lube Oil Cooler; Revision 2  
- M015-146; Data Sheet for Emergency Diesel Generator Jacket Water Cooler; Revision 2
- M015-146; Data Sheet for Emergency Diesel Generator Jacket Water Cooler; Revision 2  
- M015-147; Data Sheet for Emergency Diesel Generator Inter Cooler Water Cooler;
- M015-147; Data Sheet for Emergency Diesel Generator Inter Cooler Water Cooler;
Revision 2
Revision 2  
- NG-OO6C; Sand/Silt Levels, Bryozoa Growth, Concrete and Piping Inspection Stilling Basin,
- NG-OO6C; Sand/Silt Levels, Bryozoa Growth, Concrete and Piping Inspection Stilling Basin,
RHRSW & ESW Pits in the Pumphouse; Revision 3
RHRSW & ESW Pits in the Pumphouse; Revision 3  
- NS540002A; Surveillance Test Procedure: A Emergency Service Water Operability Test;
- NS540002A; Surveillance Test Procedure: A Emergency Service Water Operability Test;
Revision 40
Revision 40  
- NS540003A; Surveillance Test Procedure: A Emergency Service Water Operability Test and
- NS540003A; Surveillance Test Procedure: A Emergency Service Water Operability Test and
Comprehensive Pump Test; Revision 29
Comprehensive Pump Test; Revision 29  
- NS540003B; Surveillance Test Procedure: B Emergency Service Water Operability Test and
- NS540003B; Surveillance Test Procedure: B Emergency Service Water Operability Test and
Comprehensive Pump Test; Revision 29
Comprehensive Pump Test; Revision 29  
- OI 515; RHRSW/ESW Systems Chlorination Dechlorination; Revision 128
- OI 515; RHRSW/ESW Systems Chlorination Dechlorination; Revision 128  
- PCP FORM 334; RHRSW/ESW Sample Point; Revision 4
- PCP FORM 334; RHRSW/ESW Sample Point; Revision 4  
- PCP 9.5; Chlorination/Halogenation Of Circulating Water, GSW, and RHRSW/ESW;
- PCP 9.5; Chlorination/Halogenation Of Circulating Water, GSW, and RHRSW/ESW;
Revision 45
Revision 45  
- PCP 1.75; Open Cooling Water Strategic Chemistry; Revision 0
- PCP 1.75; Open Cooling Water Strategic Chemistry; Revision 0  
- STP NS100106; High Sand Bed Elevation/Low River Water Depth; Revision 0
- STP NS100106; High Sand Bed Elevation/Low River Water Depth; Revision 0  
- STP 3.7.2-02; River Water Depth; Revision 11
- STP 3.7.2-02; River Water Depth; Revision 11  
- STP 3.0.0-01; Instrument Checks; Revision 163
- STP 3.0.0-01; Instrument Checks; Revision 163  
- CR 02140289; LLI-01 Unable to be Completed as Written; June 24, 2016
- CR 02140289; LLI-01 Unable to be Completed as Written; June 24, 2016  
 
- CR 02235027; Self-Assessment for 2018 Triennial NRC Ultimate Heat Sink Inspection;
- CR 02235027; Self-Assessment for 2018 Triennial NRC Ultimate Heat Sink Inspection;
January 18, 2018
January 18, 2018  
- CR 02254445; 2018 NRC UHS Eddy Current Exam Prog Manual Has Inconsistency;
- CR 02254445; 2018 NRC UHS Eddy Current Exam Prog Manual Has Inconsistency;
March 15, 2018
March 15, 2018  
- CR 02254389; 2018 NRC RHR Pump Seal Water Cooler Performance Calculation;
- CR 02254389; 2018 NRC RHR Pump Seal Water Cooler Performance Calculation;
March 15, 2018
March 15, 2018  
- CR 2025781; B Core Spray, 2A205 Conduit Inspection Results; February 16, 2015
- CR 2025781; B Core Spray, 2A205 Conduit Inspection Results; February 16, 2015  
- CR 2040615; Change Out B SBDG Jacket Water at Next Opportunity; April 15, 2015
- CR 2040615; Change Out B SBDG Jacket Water at Next Opportunity; April 15, 2015  
- CR 2085932; A EDG CMM 2015: Heat Exchanger End Plate Inspections; October 26, 2015
- CR 2085932; A EDG CMM 2015: Heat Exchanger End Plate Inspections; October 26, 2015  
- CR 2174232; Develop Contingency Work Order for 1E053A Floating Head Adjustment;
- CR 2174232; Develop Contingency Work Order for 1E053A Floating Head Adjustment;
January 19, 2017
January 19, 2017  
- CR 2242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers; May 8, 2018
- CR 2242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers; May 8, 2018  
- CR 2242946; STP NS540003A: A SW Operability Valve Adjustments; January 4, 2018
- CR 2242946; STP NS540003A: A SW Operability Valve Adjustments; January 4, 2018  
- CR 2244850; 2018 UHS SA: Improper Documentation of Incomplete STP Step;
- CR 2244850; 2018 UHS SA: Improper Documentation of Incomplete STP Step;
February 16, 2018
February 16, 2018  
- CE 0344500; Evaluate the ESW/RHRSW/RWS Pumps per the NRC Bulletin 88-04
- CE 0344500; Evaluate the ESW/RHRSW/RWS Pumps per the NRC Bulletin 88-04
Requirements
Requirements  
- WO 40507744; B Forebay Results; June 14, 2017
- WO 40507744; B Forebay Results; June 14, 2017  
- WO 40507755; B RWS Pit Dive Results; June 15, 2017
- WO 40507755; B RWS Pit Dive Results; June 15, 2017  
- WO 40507747; A RWS Pit Results; July 26, 2017
- WO 40507747; A RWS Pit Results; July 26, 2017  
- WO 40507756; B RWS Pit Results; August 15, 2017
- WO 40507756; B RWS Pit Results; August 15, 2017  
- WO 40507748; A RWS Pit Results; August 23, 2017
- WO 40507748; A RWS Pit Results; August 23, 2017  
- WO 40507742; A RWS Forebay Dive Results; September 6, 2017
- WO 40507742; A RWS Forebay Dive Results; September 6, 2017  
- WO 40507752; Stilling Basin Results; August 17, 2017
- WO 40507752; Stilling Basin Results; August 17, 2017  
- WO 40428150; Stilling Basin Dive Results; August 18, 2016
- WO 40428150; Stilling Basin Dive Results; August 18, 2016  
- WO 40496903; Perform Walkdown Inspections - Intake structure; August 23, 2017
- WO 40496903; Perform Walkdown Inspections - Intake structure; August 23, 2017  
- WO 40508978; Maintenance Rule Structural Monitoring - Pump House; October 24, 2016
- WO 40508978; Maintenance Rule Structural Monitoring - Pump House; October 24, 2016  
- WO 40396442; LI 2900 Calibration; June 23, 2016
- WO 40396442; LI 2900 Calibration; June 23, 2016  
- WO 40498996; LI 2901 Calibration; November 9, 2016
- WO 40498996; LI 2901 Calibration; November 9, 2016  
- WO 40256007; TE2900 Calibration; July 31, 2013
- WO 40256007; TE2900 Calibration; July 31, 2013  
- WO 40221618-01; 1G031/ENG: 2-Year Mechanical Inspection; September 24, 2013
- WO 40221618-01; 1G031/ENG: 2-Year Mechanical Inspection; September 24, 2013  
- WO 40354514-01; 1G031/ENG: 2-Year Mechanical Inspection; October 30, 2015
- WO 40354514-01; 1G031/ENG: 2-Year Mechanical Inspection; October 30, 2015  
- WO 40506630-23; 1G031/ENG: 2-Year Mechanical Inspection; November 20, 2017
- WO 40506630-23; 1G031/ENG: 2-Year Mechanical Inspection; November 20, 2017  
- WO 40269622-01; 1E220A: Disassemble Clean and Inspect and Reassemble;
- WO 40269622-01; 1E220A: Disassemble Clean and Inspect and Reassemble;
August 5, 2014
August 5, 2014  
- WO 40414694-01; 1E220A: Disassemble Clean and Inspect and Reassemble;
- WO 40414694-01; 1E220A: Disassemble Clean and Inspect and Reassemble;
December 21, 2016
December 21, 2016  
- WO 40284683-01; 1E220B: Disassemble Clean and Inspect and Reassemble;
- WO 40284683-01; 1E220B: Disassemble Clean and Inspect and Reassemble;
August 12, 2014
August 12, 2014  
- WO 40435570-01; 1E220B: Disassemble Clean and Inspect and Reassemble;
- WO 40435570-01; 1E220B: Disassemble Clean and Inspect and Reassemble;
December 27, 2016
December 27, 2016  
- WO 40273309-01; 1E220C: Disassemble Clean and Inspect and Reassemble;
- WO 40273309-01; 1E220C: Disassemble Clean and Inspect and Reassemble;
August 5, 2014
August 5, 2014  
- WO 40418930-01; 1E220C: Disassemble Clean and Inspect and Reassemble;
- WO 40418930-01; 1E220C: Disassemble Clean and Inspect and Reassemble;
December 27, 2016
December 27, 2016  
- WO 40285529-01; 1E220D: Disassemble Clean and Inspect and Reassemble;
- WO 40285529-01; 1E220D: Disassemble Clean and Inspect and Reassemble;
February 10, 2015
February 10, 2015  
- WO 40435573-01; 1E220D: Disassemble Clean and Inspect and Reassemble;
- WO 40435573-01; 1E220D: Disassemble Clean and Inspect and Reassemble;
March 29, 2017
March 29, 2017  
- WO 40507044-01; Surveillance Test Procedure NS540002-A: A Emergency Service Water
- WO 40507044-01; Surveillance Test Procedure NS540002-A: A Emergency Service Water
Operability Test; September 28, 2017
Operability Test; September 28, 2017  
 
- WO 40388742-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
- WO 40388742-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
Operability Test; January 4, 2016
Operability Test; January 4, 2016  
- WO 40396676-01; Measure 1E220A(C) RHR Pump Seal Cooler Flow Rates; August 9, 2016
- WO 40396676-01; Measure 1E220A(C) RHR Pump Seal Cooler Flow Rates; August 9, 2016  
- WO 40507044-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
- WO 40507044-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
Operability Test; September 28, 2017
Operability Test; September 28, 2017  
- WO 40519333-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
- WO 40519333-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water
Operability Test; January 11, 2018
Operability Test; January 11, 2018  
- WO 40243946-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water
- WO 40243946-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water
Operability Test; February 5, 2014
Operability Test; February 5, 2014  
- WO 40439017-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water
- WO 40439017-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water
Operability Test; July 14, 2016
Operability Test; July 14, 2016
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
71111.11Licensed Operator Requalification Program and Licensed Operator Performance  
- PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0
- PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0  
- Reactivity Management Plan; Downpower from March 2018 Control Rod Sequence Exchange;
- Reactivity Management Plan; Downpower from March 2018 Control Rod Sequence Exchange;
Revision Date: March 13, 2018
Revision Date: March 13, 2018  
- OP-020; Area Inspections; Revision 27
- OP-020; Area Inspections; Revision 27
71111.12Maintenance Effectiveness
71111.12Maintenance Effectiveness  
- WO 40518134 01; MO 1902-O: Overhaul Limitorque Operator
- WO 40518134 01; MO 1902-O: Overhaul Limitorque Operator  
- CR 02256369; Tubing Failure to V32-0109
- CR 02256369; Tubing Failure to V32-0109
71111.13Maintenance Risk Assessments and Emergent Work Control
71111.13Maintenance Risk Assessments and Emergent Work Control  
- STP 3.6.4.3-03B; B SBGT System HEPA & Charcoal Filter Efficiency Tests; Revision 15
- STP 3.6.4.3-03B; B SBGT System HEPA & Charcoal Filter Efficiency Tests; Revision 15  
- Duane Arnold Daily Status Report - March 12, 2018;
- Duane Arnold Daily Status Report - March 12, 2018;  
- Duane Arnold Daily Status Report - March 15, 2018;
- Duane Arnold Daily Status Report - March 15, 2018;  
- WM-AA-203-1006; Critical Maintenance Management; Revision 8
- WM-AA-203-1006; Critical Maintenance Management; Revision 8  
- WPG-2 On-Line Risk Management Guideline; Revision 70
- WPG-2 On-Line Risk Management Guideline; Revision 70
71111.15Operability Determinations and Functionality Assessments
71111.15Operability Determinations and Functionality Assessments  
- CR 02243010; SBGT Inlet Relief Damper has no Maintenance or Testing
- CR 02243010; SBGT Inlet Relief Damper has no Maintenance or Testing  
- CR 02242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers
- CR 02242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers  
- CR 02242192; A Chiller Trip Upon Start From Low Oil Temperature
- CR 02242192; A Chiller Trip Upon Start From Low Oil Temperature  
- CR 02242997; 1C06A (C-2), Low Disch Pressure , Activated on Pump Start
- CR 02242997; 1C06A (C-2), Low Disch Pressure, Activated on Pump Start  
- CR 02244854; Valve Could not be Closed While Shutting Down Torus Cooling
- CR 02244854; Valve Could not be Closed While Shutting Down Torus Cooling  
- CR 02251009; [Missed Non-Destructive Examination] NDE During Rebuild of MSIV; CV4415
- CR 02251009; [Missed Non-Destructive Examination] NDE During Rebuild of MSIV; CV4415  
- General Electric Spec. No. 22A1295 AD
- General Electric Spec. No. 22A1295 AD  
- General Electric Spec. No. 21A9230; Revision 2
- General Electric Spec. No. 21A9230; Revision 2  
- Power Piping; USAS B31.1.0-1967
- Power Piping; USAS B31.1.0-1967  
- APED-B-21-2793-073; MSIV Drawing
- APED-B-21-2793-073; MSIV Drawing  
- APED-B-21-2793-074; MSIV Parts List
- APED-B-21-2793-074; MSIV Parts List  
- CR 02256369; B Standby Diesel Generator Tubing Failure to V32-0109
- CR 02256369; B Standby Diesel Generator Tubing Failure to V32-0109  
- ASME 2007 Section XI, Division 1, IWA-4410; Welding, Brazing, Metal Removal, Fabrication,
- ASME 2007 Section XI, Division 1, IWA-4410; Welding, Brazing, Metal Removal, Fabrication,
And Installation
And Installation  
- CR 02249636; 1VEF081 A LLRPSF Exhaust Fan Failure
- CR 02249636; 1VEF081 A LLRPSF Exhaust Fan Failure
71111.18Plant Modifications
71111.18Plant Modifications  
- STP 3.3.1.1-19; Functional Test of TSV Closure Input to RPS and RPT; Revision 22
 
- STP 3.3.1.1-17; MSIV Functional Test; Revision 12
- STP 3.3.1.1-19; Functional Test of TSV Closure Input to RPS and RPT; Revision 22  
- CR 02248146; Potential Loss of RPS Trip Capability During MSIV Testing
- STP 3.3.1.1-17; MSIV Functional Test; Revision 12  
- CR 02248121; Potential Loss of RPS Trip Capability During TSV Testing
- CR 02248146; Potential Loss of RPS Trip Capability During MSIV Testing  
- CR 02248121; Potential Loss of RPS Trip Capability During TSV Testing  
- DAEC UFSAR 7.2; Reactor Protection System
- DAEC UFSAR 7.2; Reactor Protection System
71111.19Post Maintenance Testing
71111.19Post Maintenance Testing  
- WO 40518134-05; Post Maintenance Test (PMT) MO 1902; B RHR Loop Inboard Drywell
- WO 40518134-05; Post Maintenance Test (PMT) MO 1902; B RHR Loop Inboard Drywell
Spray Limitorque Operator
Spray Limitorque Operator  
- STP 3.5.1-02B; LPCI System Operability Test; Revision 19
- STP 3.5.1-02B; LPCI System Operability Test; Revision 19  
- CR 02242916; Upcoming Reactor Core Isolation Coolant (RCIC) Remote Shutdown Controller
- CR 02242916; Upcoming Reactor Core Isolation Coolant (RCIC) Remote Shutdown Controller
PMT Insufficient
PMT Insufficient  
- WO 40535567-01; A-CRD Pump (Conduit 1A106)
- WO 40535567-01; A-CRD Pump (Conduit 1A106)  
- WO 40461291-01; 4160V CRD Pump Overcurrent Relay
- WO 40461291-01; 4160V CRD Pump Overcurrent Relay  
- WO 40526456-01; CRD Hyd Pump Motor
- WO 40526456-01; CRD Hyd Pump Motor  
- WO 40531843-01; 1P209A-G: Inspect and Change Oil
- WO 40531843-01; 1P209A-G: Inspect and Change Oil  
- WO 40577090; RTS Task B RHR/RHRSW RTS
- WO 40577090; RTS Task B RHR/RHRSW RTS  
- WO 40581586; RCIC Return to Service Testing
- WO 40581586; RCIC Return to Service Testing  
- STP 3.3.3.1-09 RHRB; B RHR Valve Position Indicator Verification-Operating; Revision 6
- STP 3.3.3.1-09 RHRB; B RHR Valve Position Indicator Verification-Operating; Revision 6  
- NS160002B; B RHRSW Operability Test; Revision 14
- NS160002B; B RHRSW Operability Test; Revision 14  
- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19
- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19  
- STP NS490003B; B RHR System Leakage Walkdown; Revision 4
- STP NS490003B; B RHR System Leakage Walkdown; Revision 4  
- CR 02242916; Upcoming RCIC Remote Shutdown PMT Insufficient
- CR 02242916; Upcoming RCIC Remote Shutdown PMT Insufficient
71111.22Surveillance Testing
71111.22Surveillance Testing  
- NS49003B; B RHR System Leakage Inspection Walkdown; Revision 4
- NS49003B; B RHR System Leakage Inspection Walkdown; Revision 4  
- NS160002B; B RHRSW Operability Test; Revision 14
- NS160002B; B RHRSW Operability Test; Revision 14  
- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19
- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19  
- STP 3.6.4.2-01B; Secondary Containment Isolation Damper Closing Time Test Channel B;
- STP 3.6.4.2-01B; Secondary Containment Isolation Damper Closing Time Test Channel B;
Revision 11
Revision 11  
- CR 0225057; IV-AD-51B Failed Closing Time Requirement
- CR 0225057; IV-AD-51B Failed Closing Time Requirement  
- STP NS930002; Main Turbine Stop and Combined Intermediate Valves Test; Revision 12
- STP NS930002; Main Turbine Stop and Combined Intermediate Valves Test; Revision 12  
- STP 3.3.1.1-17; MSIV Functional Test; Revision 12
- STP 3.3.1.1-17; MSIV Functional Test; Revision 12  
- STP 3.3.1.1-13; Turbine Control Valve EOC RPT Logic And RPS Instrument Functional Test;
- STP 3.3.1.1-13; Turbine Control Valve EOC RPT Logic And RPS Instrument Functional Test;
Revision 15
Revision 15  
- STP 3.1.7-01; SBLC Pump Operability Test; Revision 43
- STP 3.1.7-01; SBLC Pump Operability Test; Revision 43
71114.06Drill Evaluation
71114.06Drill Evaluation  
-   PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0
-
71151Performance Indicator Verification
PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0
- NG-002L; INPO Reportable Losses Monthly Summary; Revision 2
71151Performance Indicator Verification  
- NG-002L; INPO Reportable Losses Monthly Summary; Revision 2  
- Operations Shift Manager Logs: January 1, 2017 through December 31, 2017
- Operations Shift Manager Logs: January 1, 2017 through December 31, 2017
71152Problem Identification and Resolution
71152Problem Identification and Resolution  
- OP-AA-100-1000; Conduct Of Operations; Revision 24
 
- MM-AA-100-1002 Scaffold Installation, Modification and Removal Requests; Revision 8
-
- CR 02254212; Scaffold Inspection Documentation
OP-AA-100-1000; Conduct Of Operations; Revision 24  
- WO 40509538-05; Scaffold Inspection Documentation
-
- Scaffold Work Plan; RCIC Outboard Torus Suction Valve Operator
MM-AA-100-1002 Scaffold Installation, Modification and Removal Requests; Revision 8  
- Scaffold Work Plan; RCIC Steam Exhaust to Torus Stop-Check
-
- Scaffold Work Plan; V87-0001, 0002 & 0003
CR 02254212; Scaffold Inspection Documentation  
- Scaffold Work Plan; 1VAC017B-M
-
- Scaffold Work Plan; Conduit 2A202; Torus Basement, North Wall
WO 40509538-05; Scaffold Inspection Documentation  
71153Follow-Up of Events and Notices of Enforcement Discretion
-
- OI 878.3; Local Power Range Monitoring System; Revision 42
Scaffold Work Plan; RCIC Outboard Torus Suction Valve Operator  
- TS 3.3.1.1 A
-
- TS 3.3.1.1 B
Scaffold Work Plan; RCIC Steam Exhaust to Torus Stop-Check  
- TRM 3.2.2
-
- ER-AA-122-1001; Printed Circuit Board Life Cycle Management Plan; Revision 2
Scaffold Work Plan; V87-0001, 0002 & 0003  
- CR 02243984; E-S9265 No Voltage Output
-
- OSM Logs; January 10, 2018 at 1259 through January 10, 2018 at 1406
Scaffold Work Plan; 1VAC017B-M  
-
Scaffold Work Plan; Conduit 2A202; Torus Basement, North Wall
71153Follow-Up of Events and Notices of Enforcement Discretion  
-
OI 878.3; Local Power Range Monitoring System; Revision 42  
-
TS 3.3.1.1 A  
-
TS 3.3.1.1 B  
-
TRM 3.2.2  
-
ER-AA-122-1001; Printed Circuit Board Life Cycle Management Plan; Revision 2  
-
CR 02243984; E-S9265 No Voltage Output  
-
OSM Logs; January 10, 2018 at 1259 through January 10, 2018 at 1406  
 
UNITED STATES
UNITED STATES
NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION
Line 458: Line 520:
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Withholding.
Sincerely,
Sincerely,  
                                                  /RA/
/RA/  
 
Karla Stoedter, Chief
Karla Stoedter, Chief
Branch 1
Branch 1
Division of Reactor Projects
Division of Reactor Projects  
 
Docket No. 50-331
Docket No. 50-331
License No. DPR-49
License No. DPR-49
Enclosure:
Enclosure:
Inspection Report 05000331/2018001
Inspection Report 05000331/2018001
cc: Distribution via ListServ
cc: Distribution via ListServ  
 
Letter to Dean Curtland from Karla Stoedter dated May 4, 2018
Letter to Dean Curtland from Karla Stoedter dated May 4, 2018
SUBJECT: DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION
SUBJECT: DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION
REPORT 05000331/2018001
REPORT 05000331/2018001  


}}
}}

Latest revision as of 22:53, 5 January 2025

NRC Integrated Inspection Report 05000331/2018001
ML18124A232
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 05/04/2018
From: Karla Stoedter
NRC/RGN-III/DRP/B1
To: Dean Curtland
NextEra Energy Duane Arnold
References
IR 2018001
Preceding documents:
Download: ML18124A232 (16)
v • d • e


Text

May 4, 2018

SUBJECT:

DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION REPORT 05000331/2018001

Dear Mr. Curtland:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Duane Arnold Energy Center. On April 4, 2018, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

Based on the results of this inspection, no findings or violations were identified.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Karla Stoedter, Chief Branch 1 Division of Reactor Projects

Docket No. 50-331 License No. DPR-49

Enclosure:

Inspection Report 05000331/2018001

REGION III==

Docket Number:

50-331 License Number:

DPR-49 Report Numbers:

05000331/2018001 Enterprise Identifier: I-2018-001-0035 Licensee:

NextEra Energy Duane Arnold, LLC Facility:

Duane Arnold Energy Center Location:

Palo, IA Dates:

January 1 through March 31, 2018 Inspectors:

C. Norton, Senior Resident Inspector J. Steffes, Resident Inspector R. Stone, Acting Resident Inspector A. Dunlap, Senior Reactor Inspector T. Nakanishi, Reliability and Risk Analyst J. Neurauter, Senior Reactor Inspector T. Ospino, Reactor Engineer

Approved by:

K. Stoedter, Chief Branch 1 Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated quarterly inspection at Duane Arnold Energy Center in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.

List of Findings and Violations

No findings or violations were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000331/2018001-01 Failure to Perform Nondestructive Examination of Main Steam Isolation Valve 4415 Following Machining of Valve Bore 71111.15 Open

TABLE OF CONTENTS

PLANT STATUS

INSPECTION SCOPES

.............................................................................................................

REACTOR SAFETY

..................................................................................................................

OTHER ACTIVITIES - BASELINE

...........................................................................................

INSPECTION RESULTS

.............................................................................................................. 8

===71111.15Operability Determinations and Functionality Assessments....................................... 8 PLANT STATUS

Duane Arnold Energy Center began the inspection period at rated thermal power. On March 17, 2018, the licensee lowered thermal power to 74 percent of rated to perform a control rod sequence exchange. The unit was returned to steady state rated thermal power on March 19, 2018. With the exception of minor power reductions of less than 2 percent for surveillance testing and control rod line adjustments, the unit remained at rated thermal power for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515 Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.01Adverse Weather Protection Seasonal Extreme Weather===

Main article: IP 71111.15

The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 3, January 4, January 5, January 17, and February 6, 2108.

External Flooding (1 Sample)

The inspectors evaluated readiness to cope with external flooding on March 27, 2018.

71111.04Equipment Alignment Partial Walkdown

Main article: IP 71111.04

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Control Rod Drive (CRD) system on March 2, 2018.

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the Standby Liquid Control System on March 29, 2018.

===71111.05AQFire Protection Annual/Quarterly

Quarterly Inspection===

Main article: IP 71111.05

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Reactor Building 786 Level on February 3, 2018;
(2) Low Level Radwaste Processing and Storage Facility Zones 21-A through 21-E, 21-N, 21-P, 21-Q, 21-R, 21-T, 21-U) & Radioactive Release (Zone 21-E) on January 27, 2018;
(3) Control Building 757 Level on January 20, 2018;
(4) Turbine Building 757 Level on February 3, 2018;
(5) Machine Shop Building and Radwaste Building on February 24, 2018; and
(6) Reactor Building 716 Level (Zones 1-AN, 1-AS, 1-C and 1-G) on March 20, 2018.

71111.07Heat Sink Performance Heat Sink (Triennial)

Main article: IP 71111.07

The inspectors evaluated heat exchanger/heat sink performance on the following components:

(1) Residual Heat Removal (RHR) Pump Seal Coolers (1E220A, B, C, D), Section 02.02b;
(2) Emergency Diesel Generator Heat Exchanger (1E053A), Section 02.02b; and
(3) Heat Sink, Section 02.02d, Specifically Sections 02.02d.2 and 02.02d.4 were completed.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

Main article: IP 71111.11

The inspectors observed and evaluated a licensed operator evaluated scenario on January 27, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated a control rod sequence exchange on March 17-18, 2018.

===71111.12Maintenance Effectiveness

Routine Maintenance Effectiveness===

Main article: IP 71111.12

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) MO 1902, B torus cooling isolation valve actuator disassembly and movement on January 27, 2018; and
(2) B standby diesel generator critical maintenance management starting air emergent issue on March 27, 2018.

71111.13Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) B Standby Gas Treatment (SBGT) System Efficiency Test on January 27, 2018;
(2) Switchyard work; first instance, on March 12, 2018;
(3) Switchyard work; second instance, on March 15, 2018; and
(4) Phoenix Risk calculation for B standby diesel generator critical maintenance management window on March 25, 2018.

71111.15Operability Determinations and Functionality Assessments

Main article: IP 71111.15

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Condition Report (CR) 02243010; SBGT System Inlet Relief Damper on January 6, 2018;
(2) CR 02242936; Unable to verify flow through RHR Pump Seal Water Coolers on January 13, 2018;
(3) CR 02242192; A Chiller Trip Upon Start from Low Oil Temperature on February 10, 2018;
(4) CR 02242997; Low Discharge Pressure when starting B Emergency Service Water Pump on February 10, 2018;
(5) CR 02244854; Torus Cooling Isolation Valve Failed to Close on January 20, 2018;
(6) CR 02252009; Missed Nondestructive Examination During Rebuild of Main Steam Isolation Valve (MSIV), CV4415 on February 24-March 3, 2018;
(7) CR 02256369; B Standby Diesel Generator Tubing Failure to V32-0109 on March 27-28, 2018; and
(8) CR 02249636; 1VEF081 A LLRPSF [low level radwaste storage and processing facility]

Exhaust Fan Failure on February 17, 2018.

71111.18Plant Modifications

Main article: IP 71111.18

The inspectors evaluated the following temporary or permanent modifications:

(1) Reactor Protection System test box use for main steam isolation valve logic testing; and
(2) Reactor Protection System test box use for turbine stop valve logic testing.

71111.19Post Maintenance Testing

Main article: IP 71111.19

The inspectors evaluated the following post maintenance tests:

(1) Motor operated valve (MO) 1902, RHR (Drywell Spray) Actuator Maintenance, on February 3, 2018;
(2) Replace Battery in RCIC [reactor core isolation cooling] RSP [remote shutdown panel]

hand controller on February 10, 2018;

(3) A CRD Pump Maintenance on February 10, 2018;
(4) B Residual Heat Removal Service Water (RHRSW) Post Maintenance Testing on February 17, 2018;
(5) B RHR Valve Cycling Post Maintenance Testing on February 17, 2018; and
(6) Post Maintenance Testing during Surveillance Test Procedure (STP) 3.5.1-02, Low-Pressure Coolant Injection Operability, on February 17, 2018.

===71111.22Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine===

Main article: IP 71111.22
(1) B RHRSW Operability Test; NS160002B, on February 17, 2018;
(2) B RHRSW Leakage Inspection Walkdown; NS49003B, on February 17, 2018;
(3) STP 3.3.1.1-17; MSIV Functional Test, on March 17, 2018;
(4) STP 3.3.1.1-13; Turbine Control Valve End of Cycle Recirculation Pump Trip Logic And RPS Instrument Functional Test, on March 18, 2018; and
(5) STP 3.1.7-01; Standby Liquid Control (SBLC) Pump Operability Test, on March 26, 2018.

In-service (2 Samples)

(1) STP 3.5.1-02B; B Low Pressure Coolant Injection (LPCI) System Operability Test, on February 17, 2018; and
(2) Main Turbine Stop and Combined Intermediate Valves Test, on March 17, 2018.

Containment Isolation Valve (1 Sample)

(1) STP 3.6.4-01B; Secondary Containment Isolation Damper Closing Time Test Channel B, on February 24, 2018.

===71114.06Drill Evaluation

Emergency Planning Drill===

Main article: IP 71114.06

The inspectors evaluated licensed operator emergency planning performance during requalification training, on January 27,

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

Main article: IP 71151

The inspectors verified licensee performance indicators submittals listed below:

(1) IE01: Unplanned Scrams per 7000 Critical Hours-1 Sample; January 1, 2017 through December 31, 2017;
(2) IE03: Unplanned Power Changes per 7000 Critical Hours-1 Sample; January 1, 2017 through December 31, 2017; and
(3) IE04: Unplanned Scrams with Complications (USwC) -1 Sample; January 1, 2017 through December 31, 2017.

71153Follow-Up of Events and Notices of Enforcement Discretion Events

Main article: IP 71153
(1) B channel half SCRAM on January 13,

INSPECTION RESULTS

71111.15Operability Determinations and Functionality Assessments

Unresolved Item (Open)

Failure to Perform a Nondestructive Examination (NDE) of Main Steam Line Isolation Valve (MSIV)

CV 4415 Following Machining of Valve Bore URI 05000331/2018-01 71111.15 Operability Determinations and Functional Assessments

Description:

On February 28, 2018, while the licensee was planning contingency work order packages for possible MSIV repairs during the upcoming refuel outage (RFO) 26, a self-revealing failure to perform an NDE of MSIV CV 4415 during RFO 25 was identified.

During RFO 25, inboard MSIV CV 4415 failed local leak rate testing. The valve was disassembled; the valve bore was machined, and the valve was reassembled. Subsequently, the valve passed local leak rate testing. However, the licensee failed to perform post-machining NDE of the valve bore as required by plant design.

The MSIV was purchased and installed in accordance with USAS B 31.1.0. The General Requirements of USAS B31.1.0, Part 107, Valves, states that

(a) Valves complying with the standards and specifications listed in Table 126.1 may be used within the specified pressure-temperature ratings,
(b) Valves not complying with Paragraph
(a) above shall be of a design, or equal to the design, which the manufacturer recommends for the service as stipulated in Paragraph 102.2.2. Purchase Specification General Electric Spec. No. 21A9230, Revision 2, requires in Part 6.2.4, Castings for pressure-containing parts shall be 100 percent examined by radiography and all accessible surfaces, including machined surfaces, shall be examined by either liquid penetrant or magnetic particle methods following heat treatment.

Re-examination of repaired areas shall be by the above techniques following heat treatment.

Contrary to the above, the licensee failed to perform either liquid penetrant or magnetic particle testing following machining of the valve bore.

The inspectors determined that the failure to perform design required NDE was a performance deficiency. However, the inspectors cannot assess whether the performance deficiency is more than minor until they review the NDE results.

Planned Closure Actions: The inspectors will review the results of the NDE after it is performed during RFO 26 and determine the significance of the violation.

Licensee Action: The licensee will perform an NDE of the MSIV bore during RFO 26.

Corrective Action Reference: CR 02251009; Missed NDE During Rebuild Of MSIV CV4415.

71153Follow-Up of Events and Notices of Enforcement Discretion

Observation - B Channel Half SCRAM 71153Follow-Up of Events and Notices of Enforcement Discretion On January 10, 2018, the inspectors evaluated the licensees response to a B Channel half SCRAM condition. The half SCRAM was caused by the failure of Average Power Range Monitor (APRM) B. The inspectors determined the operators appropriately implemented pertinent procedures and Technical Specification requirements which allowed the operators to bypass APRM B and reset the half SCRAM.

The licensee performed simple troubleshooting and determined the power supply for APRM B had failed. The power supply had recently been replaced. The inspectors determined the licensee had replaced the power supply in accordance with NextEra procedures and that the APRM power supply failure was not within the licensees ability to foresee and prevent. The licensee entered this minor issue into their corrective action program as CR 02243984; E/S 265 No Voltage Output.

The inspectors discussed the corrective actions and associated evaluations with licensee personnel.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.

  • On March 16, 2018, the inspectors presented the ultimate heat sink triennial inspection results to Mr. M. Davis, Licensing Manager, and other members of the licensee staff.
  • On April 4, 2018, the inspectors presented the quarterly integrated inspection results to Mr. D. Curtland, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- Operations Shift Manager (OSM) Logs - January 3, 2018

- OSM Logs - January 4, 2018

- OSM Logs - January 5, 2018

- OSM Logs - January 17, 2018

- OSM Logs - February 6, 2018

- Abnormal Operating Procedure (AOP) 903; Adverse Weather; Revision 59

- AOP 902; Flood; Revision 62

71111.04Equipment Alignment

- Operating Instruction (OI) 255A2; CRD System; Revision 7

- OI 255A3; CRD System HCU; Revision 3

- P&ID of Standby Liquid Control (SLBC) System; BECH-M126; Revision 26

- OI 153A2; SLBC System Valve Lineup; Revision 6

71111.05AQFire Protection Annual/Quarterly

- Pre-Fire Plan (PFP) -LL-757; PFP-LLRPSF; Revision 3

- PFP-CB-757; Pre-Fire Plan Control Building El. 757; Revision 4

- PFP-TB-757; Pre-Fire Plan Turbine Building El. 757; Revision 4

- PFP-RB-786; Pre-Fire Plan Reactor Building El. 786; Revision 6

- PFP-RB-716; Pre-Fire Plan Reactor Building El. 716; Revision 3

- PFP-RW-757; Pre-Fire Plan Radwaste Building; Revision 0

71111.07Heat Sink Performance

- 2016 Bathymetric Survey and Channel Stability Analysis; December 28, 2016

- 2017 Summer Bathymetric Survey and Channel Stability Analysis; September 5, 2017

- Borg-Warner Bulletin 1861; Light Weight High Pressure Heat Exchangers for Mechanical Seal

Injection Cooling and Sample Cooling; March 1986

- CAL-M06-012; Required Water Depth at River Water Intake; Revision 0

- CAL-M93-078; Emergency Service Water (ESW) RHRSW Pit Pumpdown Times; Revision 1

- CAL-M05-027; Emergency Diesel Generator Heat Exchanger Heat Transfer Calculation;

Revision 4

- CAL-M10-010; RHR Pump Seal Water Cooler Performance; Revision 0

- EC 285373; Equivalent Design Package: Fabricate Replacement Dollar Plates;

February 15, 2016

- FPLE 102-DAEC-01; Curtis-Wright Report: DAEC Final Eddy Current Inspection Report for

EDG 1E053A; October 20, 2015

- AOP 410; Loss of River Water Supply; Revision 30

- GENERA-F010-01; Procedure: Mechanical Inspection; Revision 70

- I.LI-R979-01; Rickly Hydrological Co., Model R114-B-56-E Sounding Reel; Revision 2

- M015-145; Data Sheet for Emergency Diesel Generator Lube Oil Cooler; Revision 2

- M015-146; Data Sheet for Emergency Diesel Generator Jacket Water Cooler; Revision 2

- M015-147; Data Sheet for Emergency Diesel Generator Inter Cooler Water Cooler;

Revision 2

- NG-OO6C; Sand/Silt Levels, Bryozoa Growth, Concrete and Piping Inspection Stilling Basin,

RHRSW & ESW Pits in the Pumphouse; Revision 3

- NS540002A; Surveillance Test Procedure: A Emergency Service Water Operability Test;

Revision 40

- NS540003A; Surveillance Test Procedure: A Emergency Service Water Operability Test and

Comprehensive Pump Test; Revision 29

- NS540003B; Surveillance Test Procedure: B Emergency Service Water Operability Test and

Comprehensive Pump Test; Revision 29

- OI 515; RHRSW/ESW Systems Chlorination Dechlorination; Revision 128

- PCP FORM 334; RHRSW/ESW Sample Point; Revision 4

- PCP 9.5; Chlorination/Halogenation Of Circulating Water, GSW, and RHRSW/ESW;

Revision 45

- PCP 1.75; Open Cooling Water Strategic Chemistry; Revision 0

- STP NS100106; High Sand Bed Elevation/Low River Water Depth; Revision 0

- STP 3.7.2-02; River Water Depth; Revision 11

- STP 3.0.0-01; Instrument Checks; Revision 163

- CR 02140289; LLI-01 Unable to be Completed as Written; June 24, 2016

- CR 02235027; Self-Assessment for 2018 Triennial NRC Ultimate Heat Sink Inspection;

January 18, 2018

- CR 02254445; 2018 NRC UHS Eddy Current Exam Prog Manual Has Inconsistency;

March 15, 2018

- CR 02254389; 2018 NRC RHR Pump Seal Water Cooler Performance Calculation;

March 15, 2018

- CR 2025781; B Core Spray, 2A205 Conduit Inspection Results; February 16, 2015

- CR 2040615; Change Out B SBDG Jacket Water at Next Opportunity; April 15, 2015

- CR 2085932; A EDG CMM 2015: Heat Exchanger End Plate Inspections; October 26, 2015

- CR 2174232; Develop Contingency Work Order for 1E053A Floating Head Adjustment;

January 19, 2017

- CR 2242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers; May 8, 2018

- CR 2242946; STP NS540003A: A SW Operability Valve Adjustments; January 4, 2018

- CR 2244850; 2018 UHS SA: Improper Documentation of Incomplete STP Step;

February 16, 2018

- CE 0344500; Evaluate the ESW/RHRSW/RWS Pumps per the NRC Bulletin 88-04

Requirements

- WO 40507744; B Forebay Results; June 14, 2017

- WO 40507755; B RWS Pit Dive Results; June 15, 2017

- WO 40507747; A RWS Pit Results; July 26, 2017

- WO 40507756; B RWS Pit Results; August 15, 2017

- WO 40507748; A RWS Pit Results; August 23, 2017

- WO 40507742; A RWS Forebay Dive Results; September 6, 2017

- WO 40507752; Stilling Basin Results; August 17, 2017

- WO 40428150; Stilling Basin Dive Results; August 18, 2016

- WO 40496903; Perform Walkdown Inspections - Intake structure; August 23, 2017

- WO 40508978; Maintenance Rule Structural Monitoring - Pump House; October 24, 2016

- WO 40396442; LI 2900 Calibration; June 23, 2016

- WO 40498996; LI 2901 Calibration; November 9, 2016

- WO 40256007; TE2900 Calibration; July 31, 2013

- WO 40221618-01; 1G031/ENG: 2-Year Mechanical Inspection; September 24, 2013

- WO 40354514-01; 1G031/ENG: 2-Year Mechanical Inspection; October 30, 2015

- WO 40506630-23; 1G031/ENG: 2-Year Mechanical Inspection; November 20, 2017

- WO 40269622-01; 1E220A: Disassemble Clean and Inspect and Reassemble;

August 5, 2014

- WO 40414694-01; 1E220A: Disassemble Clean and Inspect and Reassemble;

December 21, 2016

- WO 40284683-01; 1E220B: Disassemble Clean and Inspect and Reassemble;

August 12, 2014

- WO 40435570-01; 1E220B: Disassemble Clean and Inspect and Reassemble;

December 27, 2016

- WO 40273309-01; 1E220C: Disassemble Clean and Inspect and Reassemble;

August 5, 2014

- WO 40418930-01; 1E220C: Disassemble Clean and Inspect and Reassemble;

December 27, 2016

- WO 40285529-01; 1E220D: Disassemble Clean and Inspect and Reassemble;

February 10, 2015

- WO 40435573-01; 1E220D: Disassemble Clean and Inspect and Reassemble;

March 29, 2017

- WO 40507044-01; Surveillance Test Procedure NS540002-A: A Emergency Service Water

Operability Test; September 28, 2017

- WO 40388742-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water

Operability Test; January 4, 2016

- WO 40396676-01; Measure 1E220A(C) RHR Pump Seal Cooler Flow Rates; August 9, 2016

- WO 40507044-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water

Operability Test; September 28, 2017

- WO 40519333-01; Surveillance Test Procedure NS540003-A: A Emergency Service Water

Operability Test; January 11, 2018

- WO 40243946-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water

Operability Test; February 5, 2014

- WO 40439017-01; Surveillance Test Procedure NS540003-B: B Emergency Service Water

Operability Test; July 14, 2016

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0

- Reactivity Management Plan; Downpower from March 2018 Control Rod Sequence Exchange;

Revision Date: March 13, 2018

- OP-020; Area Inspections; Revision 27

71111.12Maintenance Effectiveness

- WO 40518134 01; MO 1902-O: Overhaul Limitorque Operator

- CR 02256369; Tubing Failure to V32-0109

71111.13Maintenance Risk Assessments and Emergent Work Control

- STP 3.6.4.3-03B; B SBGT System HEPA & Charcoal Filter Efficiency Tests; Revision 15

- Duane Arnold Daily Status Report - March 12, 2018;

- Duane Arnold Daily Status Report - March 15, 2018;

- WM-AA-203-1006; Critical Maintenance Management; Revision 8

- WPG-2 On-Line Risk Management Guideline; Revision 70

71111.15Operability Determinations and Functionality Assessments

- CR 02243010; SBGT Inlet Relief Damper has no Maintenance or Testing

- CR 02242936; Unable to Verify Flow Through RHR Pump Seal Water Coolers

- CR 02242192; A Chiller Trip Upon Start From Low Oil Temperature

- CR 02242997; 1C06A (C-2), Low Disch Pressure, Activated on Pump Start

- CR 02244854; Valve Could not be Closed While Shutting Down Torus Cooling

- CR 02251009; [Missed Non-Destructive Examination] NDE During Rebuild of MSIV; CV4415

- General Electric Spec. No. 22A1295 AD

- General Electric Spec. No. 21A9230; Revision 2

- Power Piping; USAS B31.1.0-1967

- APED-B-21-2793-073; MSIV Drawing

- APED-B-21-2793-074; MSIV Parts List

- CR 02256369; B Standby Diesel Generator Tubing Failure to V32-0109

- ASME 2007 Section XI, Division 1, IWA-4410; Welding, Brazing, Metal Removal, Fabrication,

And Installation

- CR 02249636; 1VEF081 A LLRPSF Exhaust Fan Failure

71111.18Plant Modifications

- STP 3.3.1.1-19; Functional Test of TSV Closure Input to RPS and RPT; Revision 22

- STP 3.3.1.1-17; MSIV Functional Test; Revision 12

- CR 02248146; Potential Loss of RPS Trip Capability During MSIV Testing

- CR 02248121; Potential Loss of RPS Trip Capability During TSV Testing

- DAEC UFSAR 7.2; Reactor Protection System

71111.19Post Maintenance Testing

- WO 40518134-05; Post Maintenance Test (PMT) MO 1902; B RHR Loop Inboard Drywell

Spray Limitorque Operator

- STP 3.5.1-02B; LPCI System Operability Test; Revision 19

- CR 02242916; Upcoming Reactor Core Isolation Coolant (RCIC) Remote Shutdown Controller

PMT Insufficient

- WO 40535567-01; A-CRD Pump (Conduit 1A106)

- WO 40461291-01; 4160V CRD Pump Overcurrent Relay

- WO 40526456-01; CRD Hyd Pump Motor

- WO 40531843-01; 1P209A-G: Inspect and Change Oil

- WO 40577090; RTS Task B RHR/RHRSW RTS

- WO 40581586; RCIC Return to Service Testing

- STP 3.3.3.1-09 RHRB; B RHR Valve Position Indicator Verification-Operating; Revision 6

- NS160002B; B RHRSW Operability Test; Revision 14

- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19

- STP NS490003B; B RHR System Leakage Walkdown; Revision 4

- CR 02242916; Upcoming RCIC Remote Shutdown PMT Insufficient

71111.22Surveillance Testing

- NS49003B; B RHR System Leakage Inspection Walkdown; Revision 4

- NS160002B; B RHRSW Operability Test; Revision 14

- STP 3.5.1-02B; B LPCI System Operability Tests; Revision 19

- STP 3.6.4.2-01B; Secondary Containment Isolation Damper Closing Time Test Channel B;

Revision 11

- CR 0225057; IV-AD-51B Failed Closing Time Requirement

- STP NS930002; Main Turbine Stop and Combined Intermediate Valves Test; Revision 12

- STP 3.3.1.1-17; MSIV Functional Test; Revision 12

- STP 3.3.1.1-13; Turbine Control Valve EOC RPT Logic And RPS Instrument Functional Test;

Revision 15

- STP 3.1.7-01; SBLC Pump Operability Test; Revision 43

71114.06Drill Evaluation

-

PDA OPS ESG 2018A-01E; Evaluated Scenario; Revision 0

71151Performance Indicator Verification

- NG-002L; INPO Reportable Losses Monthly Summary; Revision 2

- Operations Shift Manager Logs: January 1, 2017 through December 31, 2017

71152Problem Identification and Resolution

-

OP-AA-100-1000; Conduct Of Operations; Revision 24

-

MM-AA-100-1002 Scaffold Installation, Modification and Removal Requests; Revision 8

-

CR 02254212; Scaffold Inspection Documentation

-

WO 40509538-05; Scaffold Inspection Documentation

-

Scaffold Work Plan; RCIC Outboard Torus Suction Valve Operator

-

Scaffold Work Plan; RCIC Steam Exhaust to Torus Stop-Check

-

Scaffold Work Plan; V87-0001, 0002 & 0003

-

Scaffold Work Plan; 1VAC017B-M

-

Scaffold Work Plan; Conduit 2A202; Torus Basement, North Wall

71153Follow-Up of Events and Notices of Enforcement Discretion

-

OI 878.3; Local Power Range Monitoring System; Revision 42

-

TS 3.3.1.1 A

-

TS 3.3.1.1 B

-

TRM 3.2.2

-

ER-AA-122-1001; Printed Circuit Board Life Cycle Management Plan; Revision 2

-

CR 02243984; E-S9265 No Voltage Output

-

OSM Logs; January 10, 2018 at 1259 through January 10, 2018 at 1406

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, ILLINOIS 60532-4352

May 4, 2018

Mr. Dean Curtland

Director of Site Operations

NextEra Energy Duane Arnold, LLC

277 DAEC Road

Palo, IA 52324-9785

SUBJECT: DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION

REPORT 05000331/2018001

Dear Mr. Curtland:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated

inspection at your Duane Arnold Energy Center. On April 4, 2018, the NRC inspectors

discussed the results of this inspection with you and other members of your staff. The results of

this inspection are documented in the enclosed report.

Based on the results of this inspection, no findings or violations were identified.

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document

Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for

Withholding.

Sincerely,

/RA/

Karla Stoedter, Chief

Branch 1

Division of Reactor Projects

Docket No. 50-331

License No. DPR-49

Enclosure:

Inspection Report 05000331/2018001

cc: Distribution via ListServ

Letter to Dean Curtland from Karla Stoedter dated May 4, 2018

SUBJECT: DUANE ARNOLD ENERGY CENTERNRC INTEGRATED INSPECTION

REPORT 05000331/2018001

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