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| {{Adams | | {{Adams |
| | number = ML19345E136 | | | number = ML19252A192 |
| | issue date = 12/11/2019 | | | issue date = 09/06/2019 |
| | title = Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000331/2019013 | | | title = Ltr. 09/06/19 Duane Arnold Energy Center - Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000331/2019013 (DRS-G.Hausman) |
| | author name = Daley R | | | author name = Hausman G |
| | author affiliation = NRC/RGN-III | | | author affiliation = NRC/RGN-III/DRS/EB3 |
| | addressee name = Curtland D | | | addressee name = Curtland D |
| | addressee affiliation = FPL Energy Duane Arnold, LLC | | | addressee affiliation = NextEra Energy Duane Arnold, LLC |
| | docket = 05000331 | | | docket = 05000331 |
| | license number = DPR-049 | | | license number = DPR-049 |
| | contact person = | | | contact person = |
| | document report number = IR 2019013 | | | document report number = IR 2019013 |
| | document type = Inspection Report, Letter | | | document type = Letter |
| | page count = 9 | | | page count = 6 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:December 11, 2019 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| DUANE ARNOLD ENERGY CENTER - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000331/2019013
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| ==Dear Mr. Curtland:==
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| On December 5, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Duane Arnold Energy Center and 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.
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| No findings or violations of more than minor significance were identified during this inspection.
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| 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.
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| Sincerely,
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| /RA/
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| Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
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| Docket No. 05000331 License No. DPR-49
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| ===Enclosure:===
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| As stated
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| ==Inspection Report==
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| Docket Number:
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| 05000331
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| License Number:
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| DPR-49
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| Report Number:
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| 05000331/2019013
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| Enterprise Identifier: I-2019-013-0018
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| Licensee:
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| NextEra Energy Duane Arnold, LLC
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| Facility:
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| Duane Arnold Energy Center
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| Location:
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| Palo, Iowa
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| Inspection Dates:
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| December 2, 2019 to December 5, 2019
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| Inspectors:
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| G. Hausman, Senior Reactor Inspector
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| J. Robbins, Reactor Inspector
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| N. Shah, Project Engineer
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| Approved By:
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| Robert C. Daley, Chief
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| Engineering Branch 3
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| Division of Reactor Safety
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| =SUMMARY=
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| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline 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.
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| ===List of Findings and Violations===
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| No findings or violations of more than minor significance were identified.
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| ===Additional Tracking Items===
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| None.
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| =INSPECTION SCOPES=
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| 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.
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| 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 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.
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| ==REACTOR SAFETY==
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| ===71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)===
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| {{IP sample|IP=IP 71111.17|count=28}}
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| The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from 2015 to 2019.
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| : (1) AR 02175375-01, Power System Stabilizer Removal from Service, January 16, 2017
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| : (2) CA 02102327-01, Placement of Portable Heaters in the Motor Generator Set Room, July 1, 2016
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| : (3) EC 0000281703, Chromalox Replacement Project, Revision 0
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| : (4) EC 0000282458, River Water System Cable Replacement, Revision 0
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| : (5) EC 0000287931, Implementation of Revised Calculations for Loss of Coolant Accident Dose Consequences, Revision 0
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| : (6) EC 0000287997, Residual Heat Removal Discharge Header Pressure Switch Setpoint, Revision 1
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| : (7) EC 0000156026, Replace Existing Reactor Feedwater Pumps (RFP) and Motors with RFP and Motors of Larger Capacity, Revision 43
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| : (8) EC 0000283115, Flow Indication Controller (FIC2309) Replacement Siemens 353 Controller from Design Level A to B, Revision 1
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| : (9) EC 0000283472, Fukushima Spent Fuel Pool Level Instrumentation, Revision 6
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| : (10) EC 0000283785, Replace Obsolete Standby Gas Treatment System Flow Indication Controllers (FIC5828A/B), Revision 2
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| : (11) EC 0000283960, Raise All Level Setpoints for Limit Switch LS3701 to Allow Pump Starts Due to Sticking Level Element Float LE3701 at Lowest Level, Revision 0
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| : (12) EC 0000285459, Connect Diesel Air Compressor to Plant Air System, Revision 0
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| : (13) EC 0000285499, Calculation CAL-E95-015 Calibration Frequency Revised, Revision 1
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| : (14) EC 0000285928, Programmable Logic Controller (PLC1701C) Replacement, Revision 1
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| : (15) EC 0000286670, Compressor Motor (1K001-M) Tripped, Overload Jumper-ed Out (Bypassed), Revision 1
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| : (16) EC 0000287838, Revise Temperature Element (TE4403) Setpoint on Temperature Recorder (TR4400) to Provide Annunciation with Temperature Rise, Revision 0
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| : (17) EC 0000287965, Disable Low Oil Level Alarm XR2 to Prevent Masking Other Alarms, Revision 0
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| : (18) EC 0000288156, Replace Obsolete Control Building Chiller Temperature Controllers (TC6924A/B), Revision 2
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| : (19) EC 0000288815, Diesel Air Compressor Back-Up to Plant Air System, Revision 0
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| : (20) EC 0000289081, Revise CAL-M91-014 To Be in Compliance with ANSI 195-1976, Section 5.4, Revision 1
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| : (21) EC 0000291031, Reconfigure Limit Switch (LS2219) Logic to Remove Automatic Opening of Solenoid Valve (SV2219), Revision 2
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| : (22) EC 0000291104, Replace Level Element (LE-3768) with Longer Length Level Element, Revision 3
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| : (23) Procedure Change Request (PCR 02073808), Annunciator Response Procedure ARP-1C22 Hydrogen/Oxygen Control Panel, Revision 40
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| : (24) Procedure Change Request (PCR 02102503), Abnormal Operating Procedure AOP-903 Severe Weather, Revision 55
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| : (25) Procedure Change Request (PCR 02266292), Operating Instruction OI 878.1 - Source Range Neutron Monitoring System, Revision 21
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| : (26) Procedure Change Request (PCR 02268679), Annunciator Response Procedure ARP-1C22 Hydrogen/Oxygen Control Panel, Revision 42
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| : (27) UFSAR Change Request (UCR#: 2016-007), Revise Discussion Regarding Location of Steam Leak Detection Temperature Elements, Revision 24
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| : (28) UFSAR Change Request (UCR#: 2019-007), Revise Main Steam Line Isolation Valve Position Indication Description, August 22,
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| ==INSPECTION RESULTS==
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| No findings were identified.
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| ==EXIT MEETINGS AND DEBRIEFS==
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| The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
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| * On December 5, 2019, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Dean Curtland and other members of the licensee staff.
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| =DOCUMENTS REVIEWED=
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| Inspection
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| Procedure
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| Type
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| Designation
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| Description or Title
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| Revision or
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| Date
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| 71111.17T Calculations
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| CAL-E98-004
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| Setpoint Calculation High Reactor Vessel Level, HPCI,
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| RCIC, Feedwater, and Turbine Trip in Remote Shutdown -
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| LS4540
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| CAL-MC-138
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| Diesel Oil Storage Tank Level Switch
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| CAL-R17-002
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| Dose Rate Evaluation of Reactor Vessel Water Levels
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| During Refueling for EAL Thresholds
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| Corrective Action
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| Documents
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| AR 01988025
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| NRC CGD [Commercial Grade Dedication] Inspection Issue
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| of Third Party Dedication
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| 06/22/2015
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| AR 02100600
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| NRC Questions on Use of [Recurring-Use Temporary
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| Modification] RTM-04-OI151
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| 2/03/2016
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| AR 02102327
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| 2016 50.59: Eval of Portable Heaters During Severe
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| Weather
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| 08/08/2016
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| AR 02102503
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| AOP 903 - Severe Weather
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| 01/14/2016
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| AR 02102754
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| 2016 50.59: Water Temperature Input to Mark I Analysis
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| 2/22/2016
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| AR 02103084
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| 2016 50.59: Inspection Identified Inadequate 50.59
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| Screening
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| 01/26/2016
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| AR 02115464
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| RCIC Room Steam Leak Detection Not Consistent with CLB
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| [Current Licensing Basis]
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| 10/02/2016
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| AR 02138974
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| T.S. Bases Change Request: B3.3.6.1
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| 2/14/2016
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| AR 02138981
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| UFSAR Change Request: Chapter 7
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| 10/12/2016
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| AR 02139054
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| Evaluate Process Utilized to Move STP 3.5.1-03A/B to
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| Online
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| 09/23/2016
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| AR 02175375
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| Power System Stabilizer 50.59
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| 01/18/2017
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| AR 02332637
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| 2019 NRC 50.59/Mod Pre-Inspection Identified Items
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| 10/24/2019
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| AR-LIC 2138981
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| DAEC UFSAR Chapter 7
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| 06/20/2016
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| PCR 02073808
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| Annunciator Response Procedure ARP-1C22
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| Hydrogen/Oxygen Control Panel
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| PCR 02090816
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| Bases-ATWS (Anticipated Transient Without Scram)
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| PCR 02102503
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| AOP 903 Severe Weather, Revision 55
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| 01/14/2016
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| PCR 02225747
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| AOP 302.1 - Loss of 125 Vdc Power
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| PCR 02259266
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| Biennial Review - ATWS - RPV Control,
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| PCR 02266292
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| OI 878.1 - Source Range Neutron Monitoring System
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| Inspection
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| Procedure
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| Type
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| Designation
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| Description or Title
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| Revision or
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| Date
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| PCR 02268679
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| Annunciator Response Procedure ARP 1C22 -
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| Hydrogen/Oxygen Control Panel
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| PCR 02307806
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| AOP 302.1 - Loss of 125 Vdc Power
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| Corrective Action
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| Documents
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| Resulting from
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| Inspection
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| AR 02337533
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| 50.59 Screening for EC 290224
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| 2/05/2019
| |
| Engineering
| |
| Changes
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| CA 02102327-01
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| Placement of Portable Heaters in the MG [Motor Generator]
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| Set Room
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| 07/01/2016
| |
| EC 0000156026
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| Replace Existing Reactor Feedwater Pumps (RFP) and
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| Motors with RFP and Motors of Larger Capacity
| |
| EC 0000283115
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| FIC2309 Replacement Siemens 353 Controller from Design
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| Level A to B
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| EC 0000283472
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| Fukushima Spent Fuel Pool Level Instrumentation
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| EC 0000283785
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| SBGT 1V-SGT-1A\\B Flow Ind Controller Replacement
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| Siemens 353 Controller from Design Level A to B
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| FIC5828A/B
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| EC 0000283960
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| Raise All Level Setpoint for LS3701 to Allow Pump Starts
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| Due to Sticking LE3701 Float at Lowest Level
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| EC 0000285459
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| Connect Diesel Air Compressor to Plant Air System
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| EC 0000285499
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| CAL-E95-015 Calibration Frequency Revision
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| EC 0000285928
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| PLC 1701C Replacement
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| EC 0000286670
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| 1K001-M Compressor Motor Overload Trip Jumper-ed Out
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| (Bypassed)
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| EC 0000287838
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| Revise TE4403 Setpoint on TR4400 to Provide Annunciation
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| with Temperature Rise
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| EC 0000287965
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| Disable XR2 Low Oil Level Alarm to Prevent Masking Other
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| Alarms
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| EC 0000287997
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| RHR [Residual Heat Removal] Discharge Header Pressure
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| Switch Setpoint
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| EC 0000288156
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| TC6924A/B Control Building Chiller Temperature Controller
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| Siemens 353 Controller from Design Level A to B
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| EC 0000288815
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| Diesel Air Compressor Back-Up to Plant Air System
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| EC 0000289081
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| Revise CAL-M91-014 To Be in Compliance with
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| | |
| Inspection
| |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| ANSI 195-1976, Section 5.4
| |
| EC 0000291031
| |
| Reconfigure LS2219 Logic to Remove Automatic Opening of
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| SV2219
| |
| EC 0000291104
| |
| Replace LE-3768 with Longer Length Level Element
| |
| Engineering
| |
| Evaluations
| |
| ACE 01949946
| |
| 2016 50.59: Eval of Portable Heaters During Severe
| |
| Weather
| |
| 2/16/2016
| |
| EC 0000281703
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| Chromalox Replacement Project
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| EC 0000282458
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| RWS Cable Replacement
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| EC 0000287931
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| Implementation of Revised Calculations for LOCA Dose
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| Consequences
| |
| Miscellaneous
| |
| IP 71111.17T
| |
| Evaluations of Changes, Tests, and Experiments
| |
| 01/01/2017
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| NEI 96-07
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| Guidelines for 10 CFR 50.59 Implementation
| |
| UCR #: 2016-007
| |
| Revise Discussion Regarding Location of Steam Leak
| |
| Detection Temperature Elements
| |
| UCR #: 2019-007
| |
| Revise MSIV [Main Steam Line Isolation Valve] Position
| |
| Indication Description
| |
| 08/22/2019
| |
| Procedures
| |
| EN-AA-203-1100
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| Engineering Evaluations
| |
| EN-AA-203-1201
| |
| CFR Applicability and 5059 Screen Reviews
| |
| EN-AA-203-1202
| |
| CFR 5059 Evaluation
| |
| EN-AA-205-1102
| |
| Temporary Configuration Changes
| |
| Self-Assessments AR 02276319
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| 50.59/Modification Pre-Inspection Assessment
| |
| 2/02/2019
| |
| through
| |
| 2/06/2019
| |
| PDA 19-001
| |
| Duane Arnold Nuclear Assessment Report - Engineering
| |
| 03/28/2019
| |
| }} | | }} |
