ML20132A266: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 1: Line 1:
#REDIRECT [[IR 05000331/2020001]]
{{Adams
| number = ML20132A266
| issue date = 05/11/2020
| title = Integrated Inspection Report 05000331/2020001
| author name = Dickson B
| author affiliation = NRC/RGN-III/DRP/B2
| addressee name = Curtland D
| addressee affiliation = NextEra Energy Duane Arnold, LLC
| docket = 05000331
| license number = DPR-049
| contact person =
| document report number = IR 2020001
| document type = Inspection Report, Letter
| page count = 14
}}
See also: [[see also::IR 05000331/2020001]]
 
=Text=
{{#Wiki_filter:May 11, 2020
Mr. Dean Curtland
Director of Site Operations
NextEra Energy Duane Arnold, LLC
3277 DAEC Road
Palo, IA 52324-9785
SUBJECT:          DUANE ARNOLD ENERGY CENTER - INTEGRATED INSPECTION REPORT
                  05000331/2020001
Dear Mr. Curtland:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Duane Arnold Energy Center. On April 16, 2020, the NRC inspectors discussed the results of
this inspection with Mr. M. Davis, Licensing Manager, and other members of your staff. The
results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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 Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
                                              Sincerely,
                                              /RA/
                                              Billy C. Dickson, Jr., Chief
                                              Branch 2
                                              Division of Reactor Projects
Docket No. 05000331
License No. DPR-49
Enclosure:
As stated
cc w/ encl: Distribution via LISTSERV
 
 
ML20132A266
                              X    Non-Sensitive                      X Publicly Available
    X SUNSI Review
                                  Sensitive                            Non-Publicly Available
  OFFICE RIII
          BDickson:wc via
  NAME
          email
  DATE    5/11/2020
                                     
                          U.S. NUCLEAR REGULATORY COMMISSION
                                        Inspection Report
Docket Number:        05000331
License Number:        DPR-49
Report Number:        05000331/2020001
Enterprise Identifier: I-2020-001-0046
Licensee:              NextEra Energy Duane Arnold, LLC
Facility:              Duane Arnold Energy Center
Location:              Palo, Iowa
Inspection Dates:      January 01, 2020 to March 31, 2020
Inspectors:            R. Edwards, Senior Health Physicist
                      V. Myers, Senior Health Physicist
                      C. Norton, Senior Resident Inspector
                      T. Ospino, Reactor Engineer
                      J. Rutkowski, Project Engineer
Approved By:          Billy C. Dickson, Jr., Chief
                      Branch 2
                      Division of Reactor Projects
                                                            Enclosure
 
                                          SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated 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.
                                List of Findings and Violations
No findings or violations of more than minor significance were identified.
                                    Additional Tracking Items
None.
                                            2
 
PLANT STATUS
The Unit began the inspection period at rated thermal power. On February 15, 2020, the unit
was down powered to 60 percent power for a control rod sequence exchange. The unit was
returned to full power on February 16, 2020, and remained at or near 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/readingrm/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. From January 1 - March 19, 2020, 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President
of the United States on the public health risks of the coronavirus (COVID-19), resident
inspectors were directed to begin telework and to remotely access licensee information using
available technology. During this time the resident inspectors performed periodic site visits
each week and during that time conducted plant status activities as described in IMC 2515,
Appendix D; and observed risk significant activities when warranted. In addition, resident and
regional baseline inspections were evaluated to determine if all or portion of the objectives and
requirements stated in the IP could be performed remotely. If the inspections could be
performed remotely, they were conducted per the applicable IP. In the cases where it was
determined the objectives and requirements could not be performed remotely, management
elected to postpone and reschedule the inspection to a later date.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
    The inspectors evaluated system configurations during partial walkdowns of the following
    systems/trains:
    (1)    Standby liquid control system on March 10, 2020
                                              3
 
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
    The inspectors evaluated the implementation of the fire protection program by conducting a
    walkdown and performing a review to verify program compliance, equipment functionality,
    material condition, and operational readiness of the following fire areas:
    (1)    Low Level Radioactive Waste Processing and Storage Facility Elevation 757 South
          Fire Zones 21-G and 21-N on March 6, 2020
    (2)    Reactor Building Elevation 786 Fire Zones 3-A and 3-B on March 10, 2020
    (3)    Radwaste Building Fire Zones 13-A, 13-B, and 13-C on March 11, 2020
    (4)    Turbine Building Elevation 757 Fire Zones 8-A, 8-B, 8-D, 8-F and 8-H on
          March 16, 2020
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
    (1)    The inspectors observed and evaluated a reactor plant power evolution and rod
          sequence exchange on February 15, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
    (1)    The inspectors observed and evaluated licensed operator requalification training and
          activities on March 10, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
    The inspectors evaluated the accuracy and completeness of risk assessments for the
    following planned and emergent work activities to ensure configuration changes and
    appropriate work controls were addressed:
    (1)    Emergent work on torus spray and cooling supply header isolation valve on
          January 7, 2020
    (2)    Planned work on the 'A' control rod drive pump speed increaser on February 4, 2020
    (3)    Planned work on the Reactor Core Isolation Cooling (RCIC) system on
          February 24, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
    The inspectors evaluated the licensee's justifications and actions associated with the
    following operability determinations and functionality assessments:
    (1)    Condition Report (CR) 02343529, Kaman equipment not operable on
          February 5, 2020
                                            4
 
    (2)  CR 02343787, Part 21 drywell accident range radiation monitor on February 7, 2020
    (3)  CR 02347414, High Pressure Coolant Injection (HPCI) system room exhaust fan
          outboard belt beginning to fail on March 6, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(1 Sample)
    The inspectors evaluated the following temporary or permanent modifications:
    (1)  'A' and 'B' fuel pool demineralizers flow recording controllers replaced with low
          indicating recorders on February 19, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
    The inspectors evaluated the following post maintenance test activities to verify system
    operability and functionality:
    (1)  Following inboard and outboard torus vent valve seal pressure indicators
          reconfiguration on January 30, 2020
    (2)  Following 'A' control rod drive pump speed changer maintenance on February 4, 2020
    (3)  Following replacement of reactor building door 280 on February 26, 2020
    (4)  Following oil change on the 'B' fuel pool pump on January 22, 2020
    (5)  Following modification to replace 'B' fuel pool demineralizer flow indicating recorder
          with a flow indicating controller on January 22, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01) (8 Samples)
    (1)  In field activities associated with the pressure suppression chamber to reactor
          building vacuum breaker operability test on January 7, 2020
    (2)  In field activities associated with the HPCI system operability test on
          January 14, 2020
    (3)  In field activities associated with the Low Pressure Coolant Injection (LPCI) system
          operability test on January 27, 2020
    (4)  In field activities associated with the fuel pool liner monitoring test on
          January 27, 2020
    (5)  In field activities associated with repositioning torus to reactor building vacuum
          breaker T-seal pressure indicators on January 29, 2020
    (6)  Functional test of turbine stop valve closure input to the reactor protection system and
          recirculation pump trip logic on February 15, 2020
    (7)  In field activities associated with the Standby Liquid Control (SBLC) pump operability
          test on March 10, 2020
    (8)  In field activities associated with the 'B' standby diesel generator operability test
          (fast start) on March 11, 2020
                                              5
 
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)
(1 Sample)
    (1)    The inspectors evaluated the emergency response organization training drill on
          March 4, 2020
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walk Downs and Observations (IP Section 02.01) (1 Sample)
    The inspectors evaluated the following radiation detection instrumentation during plant
    walkdowns:
    (1)    Portable Survey Instruments
              * Ludlum 177, serial number 342940
              * Mirion Telepole II, serial number 228316-027
              * Ludlum 26, serial number HP3508
              * Ludlum 12-4, serial number 326388
              * Ludlum 9-3, serial number 343228
          Source Check Demonstration
              * Ludlum 177, serial number 342940
              * Mirion Telepole II, serial number 228316-027
              * Ludlum 26, serial number HP3508
          Area Radiation Monitors and Continuous Air Monitors
              * RE-9167, reactor building railroad access area
              * RE-9177, clean up phase separator area
              * RE-9156, reactor water clean up pump rooms
              * AMS-4, low level radioactive waste storage and processing facility
              * AMS-4, refuel floor
          Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
              * Argos-5AB, serial number 308
              * Cronos-1, serial number 215
              * Gem 5, serial number 366
Calibration and Testing Program (IP Section 02.02) (1 Partial)
    The inspectors evaluated the calibration and testing of the following radiation detection
    instruments:
    (1)  (Partial)
              * Whole body counter calibration on May 8, 2019
              * AMP 100, serial number 5012-014, calibration on September 13, 2019
              * Argos-5AB, serial number 308, calibration on July 9, 2019
                                            6
 
                *  RE-9156, reactor water clean up pump rooms area monitor, calibration on
                    June 12, 2016
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (1 Sample)
    (1)    Unit 1 (January 1, 2019 to December 31, 2019)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(1 Sample)
    (1)    Unit 1 (January 1, 2019 to December 31, 2019)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
    (1)    Unit 1 (January 1, 2019 to December 31, 2019)
71153 - Followup of Events and Notices of Enforcement Discretion
Reporting (IP Section 03.05) (1 Sample)
    (1)    The inspectors reviewed the circumstances surrounding Event Notification 54528,
            transport of a potentially contaminated person to a medical facility on
            February 18, 2020
INSPECTION RESULTS
  Observation: Licensee Documentation Observation                                        71152
  During the 2019 fourth quarter, while performing reviews associated with baseline inspection
  activities, the inspectors identified several documentation issues. These issues included
  operational logging errors, missing signatures in surveillance test procedures and work
  orders, and inaccurate date and time notations. Although individual performance deficiencies
  associated with these documentation issues were minor, they were numerous, demonstrated
  a lack of attention-to-detail, and made it difficult to track the work performed. During the 2019
  fourth quarter exit, the inspectors informed the licensee that the inspectors would conduct a
  Problem Identification and Resolution (PIR), inspection during the first quarter of 2020 and
  assess Duane Arnold's corrective actions to improve the quality of documentation.
  During the week of January 19, 2020, the inspectors conducted a PIR inspection of the
  documentation associated with the maintenance window on the B control building chiller.
  This work activity was chosen because it was complex and included coordination among
  multiple work groups. The inspectors noted a profound improvement in documentation
  quality over the 2019 fourth quarter that included:
      1. reduced logging errors,
      2. appropriate work and review signatures, and
                                              7
 
      3. improved time and date notations when work was repeated or handed off between
          workers.
  The inspectors concluded the licensee changed behaviors to sustain document quality
  improvements that includes:
      1. call outs at plan-of-the-day meetings,
      2. emphasis on documentation quality during shop briefings, and
      3. nuclear assurance review of documentation quality.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public
disclosure.
    *  On April 16, 2020, the inspectors presented the integrated inspection results to
        Mr. M. Davis, Licensing Manager, and other members of the licensee staff.
    *  On March 19, 2020, the inspectors presented the radiation protection program
        inspection results to Mr. D. Curtland, Director of Site Operations, and other members of
        the licensee staff.
                                              8
 
DOCUMENTS REVIEWED
Inspection Type              Designation      Description or Title                                    Revision or
Procedure                                                                                              Date
71111.05  Fire Plans        PFP-LL-757        Pre-Fire Plan LLRPSF                                    4
                              PFP-RB-786        Pre-Fire Plan Reactor Building Elevation 786            8
                              PFP-RW-757        Pre-Fire Plan Radwaste Building                        2
                              PFP-TB-757        Pre-Fire Plan Turbine Building Elevation 757            6
71111.11Q Miscellaneous                        Reactivity Management Plan Down Power for February 2020 01/22/2020
                                                Control Rod Sequence Exchange
                              SEG 2020B-01E    Evaluated Scenario                                      0
            Procedures        Operating        Reactor Recirculation System                            143
                              Instruction 264
                              Operating        Reactor Manual Control System                          52
                              Instruction 856.1
71111.13  Corrective Action Condition Report  Handswitch has Intermittent Contact for MO2005          01/06/2020
            Documents        (CR) 02340151
            Miscellaneous                      Operations Logs                                        02/24/2020
                                                Operations Logs                                        01/06/2020
                                                Duane Arnold Station Daily Status Report                02/24/2020
                              VALOP-L200-08    Limitorque Valve Operator Inspection and Lubrication    44
            Procedures        MA-AA-100-1011-  Troubleshooting, MO2005 did not Open as Expected HS    01/06/2020
                              FO1              was Taken to Open
            Work Orders      40659928-01      IP209 A-G, Inspect and Oil Change                      0
                              WO 40662001      MO, 2405-0, Elect Lube and Inspect                      0
71111.15  Corrective Action CR 02343529      Kaman Equipment not Operable                            0
            Documents        CR 02343787      Part 21 Drywell Accident Range Radiation Monitor        0
                              CR 02347414      HPCI System Room Exhaust Fan Outboard Belt Beginning    0
                                                to Fail
71111.18  Engineering      EC-287976,        Replace FRC-3511A(B), Fuel Pool F/D IT-206A(B) Effluent 3
            Changes          Replace FRC-      Flow Controllers
                              3511A(B)
            Miscellaneous                      2nd Assistant Logs                                      32
                                                          9
 
71111.18 Miscellaneous    APED-G41-2929-  Fuel Pool Demineralizers Control Panel                  6
                          047, Fuel Pool
                          Demineralizers
                          Control Panel
                          APED-G41-2929-  Fuel Pool Demineralizers Electric Schematic, Filter 'A' 9
                          049 Sheet 1
                          APED-G41-2929-  Fuel Pool Demineralizers Electric Schematic, Filter 'B' 11
                          049 Sheet 2
                          APED-G41-2929-  Fuel Pool Demineralizers Control Panel Wiring          10
                          056
                          APED-G41-2929-  Fuel Pool F/D System, Withdraw Drawing                  2
                          058
                          Bech-M135        P&ID Fuel Pool Demineralizer System                    24
        Procedures        Operating        Fuel Pool Cooling System                                78
                          Instruction 435
        Work Orders      WO 40580523      Replace FRC 3511 by EC 287976                          0
71111.19 Miscellaneous    GMP-Test-54      des Mid/High Range Leak Rate Monitor (LRM) Sec C        1
        Procedures        STP 3.6.1.3-    CAC, PCIS, and ASME Valve Functional Test              4
                          02CAC
                          STP NS700002A    Secondary Containment Test Using SBGT 'A'              7
        Work Orders      40658036-01      STP 3.6.1.3-02CAC, PCIS, and ASME Valve Functional      0
                                            Test
                          40659928-01      IP209 A-G, Inspect and Oil Change                      0
                          40695659-01      PI4300: Reconfigure Orientation                        0
71111.20 Procedures        PCP 2.41        Fuel Pool Liner Monitoring                              3
71111.22 Corrective Action Condition Report Torus Water Temperature Difference Between Recorders at 01/27/2020
        Documents        (CR) 02342593    Maximum Difference
                          CR 02344750      Z19011 Indication During STP 3.3.1.1-19                0
                          CR 02348061      PSV3252B Leaking from Valve Cap                        03/11/2020
        Miscellaneous                      Pictures of PI-4300                                    0
        Procedures        NS490003A        'A' RHR System Leakage Inspection Walkdown              7
                          STP 3.3.1.1-19  Functional Test of TSV Closure Input to RPS and RPT    23
                          STP 3.5.1-02A    A LPCI System Operability Test                        19
                          STP 3.5.1-05    HPCI System Operability Test                            83
                          STP 3.6.1.3-    CAC PCIS and ASME Valve Functional Test                4
                          02CAC
                                                    10
 
                          STP 3.6.1.6-01    Pressure Suppression Chamber to Reactor Building Vacuum 11
                                            Breaker Operability Test
                          STP NS520001      HPCI System Leakage Inspection Walkdown                24
                          WM-AA-1000-F01    Work Activity Risk Evaluation Form                      5
        Work Orders      40654043          Pressure Suppression Chamber Reactor Building Vacuum    11
                                            Breaker Operability Test
                          40655944-01      STP 3.5.1-05 HPCI System Operability Test              0
                          40658036-01      STP 3.6.1.3-02CAC PCIS and ASME Valve Functional Test  0
                          40658042-01      STP 3.5.1-02 LCPI System Operability Test              0
                          40661313          Standby Liquid Control Pump Operability Test            03/10/2020
                          40664416-01      STP 3.8.1-06B 'B' SBDG Operability Test (Fast Start)    03/11/2020
                          40695659-01      P14300: Reconfigure Orientation                        0
71114.06 Corrective Action 02347183          2020 Drill Observations Not Covered by Drill Critique  03/04/2020
        Documents        02347187          2020 Drill Note 5 Information Communication            03/04/2020
                          02347205          2020 Drill Question on Issuing Potassium Iodide        03/04/2020
        Miscellaneous    NOTE-5            Duane Arnold Energy Center Emergency Notification      21
        Procedures        EPIP 3.3          Dose Assessment and Protective Actions                  37
                          EPIP 4.5          Administration of Potassium Iodide                      11
71124.05 Calibration                        Ortec Whole Body Counter                                05/08/2019
        Records                            AMP-100 Serial Number 5012-014                          09/13/2019
                                            Argos-5AB Serial Number 308                            07/09/2019
        Procedures        HPP 3109.87      Operation of the Argos 5AB Personnel Contamination      4
                                            Monitor
        Work Orders      40381701          RE9156: Reactor Water Clean Up Pump Rooms A and B      06/12/2016
71151    Miscellaneous    NG-001L          NRC PI Data Calculation, Review and Approval            07/08/2019
                          NG-001L          NRC PI Data Calculation, Review and Approval            04/16/2019
                          NG-001L          NRC PI Data Calculation, Review and Approval            10/14/2019
        NDE Reports      NG-001L          NRC PI Data Calculation, Review and Approval            01/17/2020
71152    Miscellaneous                      January 12-17, 2020 DAEC Operational Logs              0
        Procedures        Clearance - 3002, AC to DC converter                                      0
                          I/16924B
                          Clearance 3000 -  Control Building Air Conditioning Unit, CB Heating,    0
                          1VAC308B-02      Ventilation, and Air Conditioning (HVAC) Room
                          Clearance 3000 -  Control Building HVAC Chilled Water Pump, North Open    0
                          1VCP030B          Area
                                                      11
 
                        Clearance 3000 -  Control Building HVAC Return Air Fan, CB HVAC Room        0
                        1VRF030B
      Work Orders      40603853-01        1VCP030B: Rebuild Pump                                    0
                        40603853-02        1VCP030B: OPS PMT                                        0
                        40634094-01        I/16924B: Calibrate                                      0
                        40655395-01        1VAC030B: Inspect and Lube Unit                          0
                        40656453-01        1VRF030B: MA, Inspect Unit and Lube BRG                  0
                        406566918-01      PS6933B: Inspect and Calibrate                            0
                        40656919-01        PS6930B: Inspect and Calibrate, High Pressure Safety      0
                                          Switch
                        40671140-01        STP 3.7.5-01-B, 'B' Control Building Chiller Operability  7
                        40671140-02        B2: Swap to 'B' Chiller                                  0
                        40688611-01        1VCH001B: Inspection with ESW Secured                    0
71153 Corrective Action CR 02344843        Medical Emergency                                        02/17/2020
      Documents        CR 02344897        Security Medical Response SEL 20-11                      02/17/2020
      Miscellaneous    Event Notification Transport of Potentially Contaminated Person to a Medical 0
                        (EN) 54528        Facility
                                                    12
}}

Latest revision as of 21:41, 1 August 2020

Integrated Inspection Report 05000331/2020001
ML20132A266
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 05/11/2020
From: Billy Dickson
NRC/RGN-III/DRP/B2
To: Dean Curtland
NextEra Energy Duane Arnold
References
IR 2020001
Download: ML20132A266 (14)


See also: IR 05000331/2020001

Text

May 11, 2020

Mr. Dean Curtland

Director of Site Operations

NextEra Energy Duane Arnold, LLC

3277 DAEC Road

Palo, IA 52324-9785

SUBJECT: DUANE ARNOLD ENERGY CENTER - INTEGRATED INSPECTION REPORT

05000331/2020001

Dear Mr. Curtland:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at Duane Arnold Energy Center. On April 16, 2020, the NRC inspectors discussed the results of

this inspection with Mr. M. Davis, Licensing Manager, and other members of your staff. The

results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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 Title 10 of the Code of Federal Regulations 2.390, Public

Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Billy C. Dickson, Jr., Chief

Branch 2

Division of Reactor Projects

Docket No. 05000331

License No. DPR-49

Enclosure:

As stated

cc w/ encl: Distribution via LISTSERV

ML20132A266

X Non-Sensitive X Publicly Available

X SUNSI Review

Sensitive Non-Publicly Available

OFFICE RIII

BDickson:wc via

NAME

email

DATE 5/11/2020

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 05000331

License Number: DPR-49

Report Number: 05000331/2020001

Enterprise Identifier: I-2020-001-0046

Licensee: NextEra Energy Duane Arnold, LLC

Facility: Duane Arnold Energy Center

Location: Palo, Iowa

Inspection Dates: January 01, 2020 to March 31, 2020

Inspectors: R. Edwards, Senior Health Physicist

V. Myers, Senior Health Physicist

C. Norton, Senior Resident Inspector

T. Ospino, Reactor Engineer

J. Rutkowski, Project Engineer

Approved By: Billy C. Dickson, Jr., Chief

Branch 2

Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees

performance by conducting an integrated 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.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

2

PLANT STATUS

The Unit began the inspection period at rated thermal power. On February 15, 2020, the unit

was down powered to 60 percent power for a control rod sequence exchange. The unit was

returned to full power on February 16, 2020, and remained at or near 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/readingrm/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. From January 1 - March 19, 2020, 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President

of the United States on the public health risks of the coronavirus (COVID-19), resident

inspectors were directed to begin telework and to remotely access licensee information using

available technology. During this time the resident inspectors performed periodic site visits

each week and during that time conducted plant status activities as described in IMC 2515,

Appendix D; and observed risk significant activities when warranted. In addition, resident and

regional baseline inspections were evaluated to determine if all or portion of the objectives and

requirements stated in the IP could be performed remotely. If the inspections could be

performed remotely, they were conducted per the applicable IP. In the cases where it was

determined the objectives and requirements could not be performed remotely, management

elected to postpone and reschedule the inspection to a later date.

REACTOR SAFETY

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) Standby liquid control system on March 10, 2020

3

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a

walkdown and performing a review to verify program compliance, equipment functionality,

material condition, and operational readiness of the following fire areas:

(1) Low Level Radioactive Waste Processing and Storage Facility Elevation 757 South

Fire Zones 21-G and 21-N on March 6, 2020

(2) Reactor Building Elevation 786 Fire Zones 3-A and 3-B on March 10, 2020

(3) Radwaste Building Fire Zones 13-A, 13-B, and 13-C on March 11, 2020

(4) Turbine Building Elevation 757 Fire Zones 8-A, 8-B, 8-D, 8-F and 8-H on

March 16, 2020

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1 Sample)

(1) The inspectors observed and evaluated a reactor plant power evolution and rod

sequence exchange on February 15, 2020

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification training and

activities on March 10, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the

following planned and emergent work activities to ensure configuration changes and

appropriate work controls were addressed:

(1) Emergent work on torus spray and cooling supply header isolation valve on

January 7, 2020

(2) Planned work on the 'A' control rod drive pump speed increaser on February 4, 2020

(3) Planned work on the Reactor Core Isolation Cooling (RCIC) system on

February 24, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the

following operability determinations and functionality assessments:

(1) Condition Report (CR) 02343529, Kaman equipment not operable on

February 5, 2020

4

(2) CR 02343787, Part 21 drywell accident range radiation monitor on February 7, 2020

(3) CR 02347414, High Pressure Coolant Injection (HPCI) system room exhaust fan

outboard belt beginning to fail on March 6, 2020

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) 'A' and 'B' fuel pool demineralizers flow recording controllers replaced with low

indicating recorders on February 19, 2020

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the following post maintenance test activities to verify system

operability and functionality:

(1) Following inboard and outboard torus vent valve seal pressure indicators

reconfiguration on January 30, 2020

(2) Following 'A' control rod drive pump speed changer maintenance on February 4, 2020

(3) Following replacement of reactor building door 280 on February 26, 2020

(4) Following oil change on the 'B' fuel pool pump on January 22, 2020

(5) Following modification to replace 'B' fuel pool demineralizer flow indicating recorder

with a flow indicating controller on January 22, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01) (8 Samples)

(1) In field activities associated with the pressure suppression chamber to reactor

building vacuum breaker operability test on January 7, 2020

(2) In field activities associated with the HPCI system operability test on

January 14, 2020

(3) In field activities associated with the Low Pressure Coolant Injection (LPCI) system

operability test on January 27, 2020

(4) In field activities associated with the fuel pool liner monitoring test on

January 27, 2020

(5) In field activities associated with repositioning torus to reactor building vacuum

breaker T-seal pressure indicators on January 29, 2020

(6) Functional test of turbine stop valve closure input to the reactor protection system and

recirculation pump trip logic on February 15, 2020

(7) In field activities associated with the Standby Liquid Control (SBLC) pump operability

test on March 10, 2020

(8) In field activities associated with the 'B' standby diesel generator operability test

(fast start) on March 11, 2020

5

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1 Sample)

(1) The inspectors evaluated the emergency response organization training drill on

March 4, 2020

RADIATION SAFETY

71124.05 - Radiation Monitoring Instrumentation

Walk Downs and Observations (IP Section 02.01) (1 Sample)

The inspectors evaluated the following radiation detection instrumentation during plant

walkdowns:

(1) Portable Survey Instruments

  • Ludlum 177, serial number 342940
  • Mirion Telepole II, serial number 228316-027
  • Ludlum 26, serial number HP3508
  • Ludlum 12-4, serial number 326388
  • Ludlum 9-3, serial number 343228

Source Check Demonstration

  • Ludlum 177, serial number 342940
  • Mirion Telepole II, serial number 228316-027
  • Ludlum 26, serial number HP3508

Area Radiation Monitors and Continuous Air Monitors

  • RE-9167, reactor building railroad access area
  • RE-9177, clean up phase separator area
  • RE-9156, reactor water clean up pump rooms
  • AMS-4, low level radioactive waste storage and processing facility
  • AMS-4, refuel floor

Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

  • Argos-5AB, serial number 308
  • Cronos-1, serial number 215
  • Gem 5, serial number 366

Calibration and Testing Program (IP Section 02.02) (1 Partial)

The inspectors evaluated the calibration and testing of the following radiation detection

instruments:

(1) (Partial)

  • Whole body counter calibration on May 8, 2019
  • AMP 100, serial number 5012-014, calibration on September 13, 2019
  • Argos-5AB, serial number 308, calibration on July 9, 2019

6

  • RE-9156, reactor water clean up pump rooms area monitor, calibration on

June 12, 2016

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (1 Sample)

(1) Unit 1 (January 1, 2019 to December 31, 2019)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(1 Sample)

(1) Unit 1 (January 1, 2019 to December 31, 2019)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) Unit 1 (January 1, 2019 to December 31, 2019)

71153 - Followup of Events and Notices of Enforcement Discretion

Reporting (IP Section 03.05) (1 Sample)

(1) The inspectors reviewed the circumstances surrounding Event Notification 54528,

transport of a potentially contaminated person to a medical facility on

February 18, 2020

INSPECTION RESULTS

Observation: Licensee Documentation Observation 71152

During the 2019 fourth quarter, while performing reviews associated with baseline inspection

activities, the inspectors identified several documentation issues. These issues included

operational logging errors, missing signatures in surveillance test procedures and work

orders, and inaccurate date and time notations. Although individual performance deficiencies

associated with these documentation issues were minor, they were numerous, demonstrated

a lack of attention-to-detail, and made it difficult to track the work performed. During the 2019

fourth quarter exit, the inspectors informed the licensee that the inspectors would conduct a

Problem Identification and Resolution (PIR), inspection during the first quarter of 2020 and

assess Duane Arnold's corrective actions to improve the quality of documentation.

During the week of January 19, 2020, the inspectors conducted a PIR inspection of the

documentation associated with the maintenance window on the B control building chiller.

This work activity was chosen because it was complex and included coordination among

multiple work groups. The inspectors noted a profound improvement in documentation

quality over the 2019 fourth quarter that included:

1. reduced logging errors,

2. appropriate work and review signatures, and

7

3. improved time and date notations when work was repeated or handed off between

workers.

The inspectors concluded the licensee changed behaviors to sustain document quality

improvements that includes:

1. call outs at plan-of-the-day meetings,

2. emphasis on documentation quality during shop briefings, and

3. nuclear assurance review of documentation quality.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public

disclosure.

  • On April 16, 2020, the inspectors presented the integrated inspection results to

Mr. M. Davis, Licensing Manager, and other members of the licensee staff.

  • On March 19, 2020, the inspectors presented the radiation protection program

inspection results to Mr. D. Curtland, Director of Site Operations, and other members of

the licensee staff.

8

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Fire Plans PFP-LL-757 Pre-Fire Plan LLRPSF 4

PFP-RB-786 Pre-Fire Plan Reactor Building Elevation 786 8

PFP-RW-757 Pre-Fire Plan Radwaste Building 2

PFP-TB-757 Pre-Fire Plan Turbine Building Elevation 757 6

71111.11Q Miscellaneous Reactivity Management Plan Down Power for February 2020 01/22/2020

Control Rod Sequence Exchange

SEG 2020B-01E Evaluated Scenario 0

Procedures Operating Reactor Recirculation System 143

Instruction 264

Operating Reactor Manual Control System 52

Instruction 856.1

71111.13 Corrective Action Condition Report Handswitch has Intermittent Contact for MO2005 01/06/2020

Documents (CR) 02340151

Miscellaneous Operations Logs 02/24/2020

Operations Logs 01/06/2020

Duane Arnold Station Daily Status Report 02/24/2020

VALOP-L200-08 Limitorque Valve Operator Inspection and Lubrication 44

Procedures MA-AA-100-1011- Troubleshooting, MO2005 did not Open as Expected HS 01/06/2020

FO1 was Taken to Open

Work Orders 40659928-01 IP209 A-G, Inspect and Oil Change 0

WO 40662001 MO, 2405-0, Elect Lube and Inspect 0

71111.15 Corrective Action CR 02343529 Kaman Equipment not Operable 0

Documents CR 02343787 Part 21 Drywell Accident Range Radiation Monitor 0

CR 02347414 HPCI System Room Exhaust Fan Outboard Belt Beginning 0

to Fail

71111.18 Engineering EC-287976, Replace FRC-3511A(B), Fuel Pool F/D IT-206A(B) Effluent 3

Changes Replace FRC- Flow Controllers

3511A(B)

Miscellaneous 2nd Assistant Logs 32

9

71111.18 Miscellaneous APED-G41-2929- Fuel Pool Demineralizers Control Panel 6

047, Fuel Pool

Demineralizers

Control Panel

APED-G41-2929- Fuel Pool Demineralizers Electric Schematic, Filter 'A' 9

049 Sheet 1

APED-G41-2929- Fuel Pool Demineralizers Electric Schematic, Filter 'B' 11

049 Sheet 2

APED-G41-2929- Fuel Pool Demineralizers Control Panel Wiring 10

056

APED-G41-2929- Fuel Pool F/D System, Withdraw Drawing 2

058

Bech-M135 P&ID Fuel Pool Demineralizer System 24

Procedures Operating Fuel Pool Cooling System 78

Instruction 435

Work Orders WO 40580523 Replace FRC 3511 by EC 287976 0

71111.19 Miscellaneous GMP-Test-54 des Mid/High Range Leak Rate Monitor (LRM) Sec C 1

Procedures STP 3.6.1.3- CAC, PCIS, and ASME Valve Functional Test 4

02CAC

STP NS700002A Secondary Containment Test Using SBGT 'A' 7

Work Orders 40658036-01 STP 3.6.1.3-02CAC, PCIS, and ASME Valve Functional 0

Test

40659928-01 IP209 A-G, Inspect and Oil Change 0

40695659-01 PI4300: Reconfigure Orientation 0

71111.20 Procedures PCP 2.41 Fuel Pool Liner Monitoring 3

71111.22 Corrective Action Condition Report Torus Water Temperature Difference Between Recorders at 01/27/2020

Documents (CR) 02342593 Maximum Difference

CR 02344750 Z19011 Indication During STP 3.3.1.1-19 0

CR 02348061 PSV3252B Leaking from Valve Cap 03/11/2020

Miscellaneous Pictures of PI-4300 0

Procedures NS490003A 'A' RHR System Leakage Inspection Walkdown 7

STP 3.3.1.1-19 Functional Test of TSV Closure Input to RPS and RPT 23

STP 3.5.1-02A A LPCI System Operability Test 19

STP 3.5.1-05 HPCI System Operability Test 83

STP 3.6.1.3- CAC PCIS and ASME Valve Functional Test 4

02CAC

10

STP 3.6.1.6-01 Pressure Suppression Chamber to Reactor Building Vacuum 11

Breaker Operability Test

STP NS520001 HPCI System Leakage Inspection Walkdown 24

WM-AA-1000-F01 Work Activity Risk Evaluation Form 5

Work Orders 40654043 Pressure Suppression Chamber Reactor Building Vacuum 11

Breaker Operability Test

40655944-01 STP 3.5.1-05 HPCI System Operability Test 0

40658036-01 STP 3.6.1.3-02CAC PCIS and ASME Valve Functional Test 0

40658042-01 STP 3.5.1-02 LCPI System Operability Test 0

40661313 Standby Liquid Control Pump Operability Test 03/10/2020

40664416-01 STP 3.8.1-06B 'B' SBDG Operability Test (Fast Start) 03/11/2020

40695659-01 P14300: Reconfigure Orientation 0

71114.06 Corrective Action 02347183 2020 Drill Observations Not Covered by Drill Critique 03/04/2020

Documents 02347187 2020 Drill Note 5 Information Communication 03/04/2020

02347205 2020 Drill Question on Issuing Potassium Iodide 03/04/2020

Miscellaneous NOTE-5 Duane Arnold Energy Center Emergency Notification 21

Procedures EPIP 3.3 Dose Assessment and Protective Actions 37

EPIP 4.5 Administration of Potassium Iodide 11

71124.05 Calibration Ortec Whole Body Counter 05/08/2019

Records AMP-100 Serial Number 5012-014 09/13/2019

Argos-5AB Serial Number 308 07/09/2019

Procedures HPP 3109.87 Operation of the Argos 5AB Personnel Contamination 4

Monitor

Work Orders 40381701 RE9156: Reactor Water Clean Up Pump Rooms A and B 06/12/2016

71151 Miscellaneous NG-001L NRC PI Data Calculation, Review and Approval 07/08/2019

NG-001L NRC PI Data Calculation, Review and Approval 04/16/2019

NG-001L NRC PI Data Calculation, Review and Approval 10/14/2019

NDE Reports NG-001L NRC PI Data Calculation, Review and Approval 01/17/2020

71152 Miscellaneous January 12-17, 2020 DAEC Operational Logs 0

Procedures Clearance - 3002, AC to DC converter 0

I/16924B

Clearance 3000 - Control Building Air Conditioning Unit, CB Heating, 0

1VAC308B-02 Ventilation, and Air Conditioning (HVAC) Room

Clearance 3000 - Control Building HVAC Chilled Water Pump, North Open 0

1VCP030B Area

11

Clearance 3000 - Control Building HVAC Return Air Fan, CB HVAC Room 0

1VRF030B

Work Orders 40603853-01 1VCP030B: Rebuild Pump 0

40603853-02 1VCP030B: OPS PMT 0

40634094-01 I/16924B: Calibrate 0

40655395-01 1VAC030B: Inspect and Lube Unit 0

40656453-01 1VRF030B: MA, Inspect Unit and Lube BRG 0

406566918-01 PS6933B: Inspect and Calibrate 0

40656919-01 PS6930B: Inspect and Calibrate, High Pressure Safety 0

Switch

40671140-01 STP 3.7.5-01-B, 'B' Control Building Chiller Operability 7

40671140-02 B2: Swap to 'B' Chiller 0

40688611-01 1VCH001B: Inspection with ESW Secured 0

71153 Corrective Action CR 02344843 Medical Emergency 02/17/2020

Documents CR 02344897 Security Medical Response SEL 20-11 02/17/2020

Miscellaneous Event Notification Transport of Potentially Contaminated Person to a Medical 0

(EN) 54528 Facility

12