IR 05000331/2020001
ML20175A122 | |
Person / Time | |
---|---|
Site: | Duane Arnold ![]() |
Issue date: | 06/22/2020 |
From: | Billy Dickson Division Reactor Projects III |
To: | Dean Curtland NextEra Energy Duane Arnold |
Shared Package | |
ML2017A147 | List: |
References | |
IR 2020001 | |
Download: ML20175A122 (14) | |
Text
une 22, 2020
SUBJECT:
REISSUE - DUANE ARNOLD ENERGY CENTER - INTEGRATED INSPECTION REPORT 05000331/2020001
Dear Mr. Curtland:
The NRC identified that the inspection report sent to you dated May 11, 2020, (ML20132A266)
inadvertently failed to document the completion of an annual inspection sample of the 71152 inspection procedure. As a result, the NRC is reissuing the report in its entirety with the updated subject. None of these changes affected the technical content of the report.
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 by April Nguyen for/
Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Docket No. 05000331 License No. DPR-49
Enclosure:
As stated
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.
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)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Standby liquid control system on March 10, 2020
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01)
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) 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)
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)
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
- (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)
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)
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)
- (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
71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)
- (1) The inspectors evaluated the emergency response organization training drill on March 4,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation Walk Downs and Observations (IP Section 02.01)
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
- RE-9156, reactor water clean up pump rooms area monitor, calibration on June 12,
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) 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)
71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors reviewed the licensees corrective actions associated with inaccurate documentation on February 3, 2020
71153 - Follow-up of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)
- (1) The inspectors reviewed the circumstances surrounding Event Notification 54528, transport of a potentially contaminated person to a medical facility on February 18,
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 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.
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
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
2CAC
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
2CAC
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
2347205 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
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
2