IR 05000331/2019013
| ML19345E136 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/11/2019 |
| From: | Robert Daley NRC/RGN-III |
| To: | Dean Curtland Duane Arnold |
| References | |
| IR 2019013 | |
| Download: ML19345E136 (9) | |
Text
December 11, 2019
SUBJECT:
DUANE ARNOLD ENERGY CENTER - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000331/2019013
Dear Mr. Curtland:
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.
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/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 05000331 License No. DPR-49
Enclosure:
As stated
Inspection Report
Docket Number:
05000331
License Number:
Report Number:
Enterprise Identifier: I-2019-013-0018
Licensee:
NextEra Energy Duane Arnold, LLC
Facility:
Duane Arnold Energy Center
Location:
Palo, Iowa
Inspection Dates:
December 2, 2019 to December 5, 2019
Inspectors:
G. Hausman, Senior Reactor Inspector
J. Robbins, Reactor Inspector
N. Shah, Project Engineer
Approved By:
Robert C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
SUMMARY
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.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from 2015 to 2019.
- (1) AR 02175375-01, Power System Stabilizer Removal from Service, January 16, 2017
- (2) CA 02102327-01, Placement of Portable Heaters in the Motor Generator Set Room, July 1, 2016
- (3) EC 0000281703, Chromalox Replacement Project, Revision 0
- (4) EC 0000282458, River Water System Cable Replacement, Revision 0
- (5) EC 0000287931, Implementation of Revised Calculations for Loss of Coolant Accident Dose Consequences, Revision 0
- (6) EC 0000287997, Residual Heat Removal Discharge Header Pressure Switch Setpoint, Revision 1
- (7) EC 0000156026, Replace Existing Reactor Feedwater Pumps (RFP) and Motors with RFP and Motors of Larger Capacity, Revision 43
- (8) EC 0000283115, Flow Indication Controller (FIC2309) Replacement Siemens 353 Controller from Design Level A to B, Revision 1
- (9) EC 0000283472, Fukushima Spent Fuel Pool Level Instrumentation, Revision 6
- (10) EC 0000283785, Replace Obsolete Standby Gas Treatment System Flow Indication Controllers (FIC5828A/B), Revision 2
- (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
- (12) EC 0000285459, Connect Diesel Air Compressor to Plant Air System, Revision 0
- (13) EC 0000285499, Calculation CAL-E95-015 Calibration Frequency Revised, Revision 1
- (14) EC 0000285928, Programmable Logic Controller (PLC1701C) Replacement, Revision 1
- (15) EC 0000286670, Compressor Motor (1K001-M) Tripped, Overload Jumper-ed Out (Bypassed), Revision 1
- (16) EC 0000287838, Revise Temperature Element (TE4403) Setpoint on Temperature Recorder (TR4400) to Provide Annunciation with Temperature Rise, Revision 0
- (17) EC 0000287965, Disable Low Oil Level Alarm XR2 to Prevent Masking Other Alarms, Revision 0
- (18) EC 0000288156, Replace Obsolete Control Building Chiller Temperature Controllers (TC6924A/B), Revision 2
- (19) EC 0000288815, Diesel Air Compressor Back-Up to Plant Air System, Revision 0
- (20) EC 0000289081, Revise CAL-M91-014 To Be in Compliance with ANSI 195-1976, Section 5.4, Revision 1
- (21) EC 0000291031, Reconfigure Limit Switch (LS2219) Logic to Remove Automatic Opening of Solenoid Valve (SV2219), Revision 2
- (22) EC 0000291104, Replace Level Element (LE-3768) with Longer Length Level Element, Revision 3
- (23) Procedure Change Request (PCR 02073808), Annunciator Response Procedure ARP-1C22 Hydrogen/Oxygen Control Panel, Revision 40
- (24) Procedure Change Request (PCR 02102503), Abnormal Operating Procedure AOP-903 Severe Weather, Revision 55
- (25) Procedure Change Request (PCR 02266292), Operating Instruction OI 878.1 - Source Range Neutron Monitoring System, Revision 21
- (26) Procedure Change Request (PCR 02268679), Annunciator Response Procedure ARP-1C22 Hydrogen/Oxygen Control Panel, Revision 42
- (27) UFSAR Change Request (UCR#: 2016-007), Revise Discussion Regarding Location of Steam Leak Detection Temperature Elements, Revision 24
- (28) UFSAR Change Request (UCR#: 2019-007), Revise Main Steam Line Isolation Valve Position Indication Description, August 22,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
- 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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.17T Calculations
CAL-E98-004
Setpoint Calculation High Reactor Vessel Level, HPCI,
RCIC, Feedwater, and Turbine Trip in Remote Shutdown -
LS4540
CAL-MC-138
Diesel Oil Storage Tank Level Switch
CAL-R17-002
Dose Rate Evaluation of Reactor Vessel Water Levels
During Refueling for EAL Thresholds
Corrective Action
Documents
NRC CGD [Commercial Grade Dedication] Inspection Issue
of Third Party Dedication
06/22/2015
NRC Questions on Use of [Recurring-Use Temporary
Modification] RTM-04-OI151
2/03/2016
2016 50.59: Eval of Portable Heaters During Severe
Weather
08/08/2016
AOP 903 - Severe Weather
01/14/2016
2016 50.59: Water Temperature Input to Mark I Analysis
2/22/2016
2016 50.59: Inspection Identified Inadequate 50.59
Screening
01/26/2016
RCIC Room Steam Leak Detection Not Consistent with CLB
[Current Licensing Basis]
10/02/2016
T.S. Bases Change Request: B3.3.6.1
2/14/2016
UFSAR Change Request: Chapter 7
10/12/2016
Evaluate Process Utilized to Move STP 3.5.1-03A/B to
Online
09/23/2016
Power System Stabilizer 50.59
01/18/2017
2019 NRC 50.59/Mod Pre-Inspection Identified Items
10/24/2019
AR-LIC 2138981
06/20/2016
PCR 02073808
Annunciator Response Procedure ARP-1C22
Hydrogen/Oxygen Control Panel
PCR 02090816
Bases-ATWS (Anticipated Transient Without Scram)
PCR 02102503
AOP 903 Severe Weather, Revision 55
01/14/2016
PCR 02225747
AOP 302.1 - Loss of 125 Vdc Power
PCR 02259266
Biennial Review - ATWS - RPV Control,
PCR 02266292
OI 878.1 - Source Range Neutron Monitoring System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PCR 02268679
Annunciator Response Procedure ARP 1C22 -
Hydrogen/Oxygen Control Panel
PCR 02307806
AOP 302.1 - Loss of 125 Vdc Power
Corrective Action
Documents
Resulting from
Inspection
50.59 Screening for EC 290224
2/05/2019
Engineering
Changes
CA 02102327-01
Placement of Portable Heaters in the MG [Motor Generator]
Set Room
07/01/2016
Replace Existing Reactor Feedwater Pumps (RFP) and
Motors with RFP and Motors of Larger Capacity
FIC2309 Replacement Siemens 353 Controller from Design
Level A to B
Fukushima Spent Fuel Pool Level Instrumentation
SBGT 1V-SGT-1A\\B Flow Ind Controller Replacement
Siemens 353 Controller from Design Level A to B
FIC5828A/B
Raise All Level Setpoint for LS3701 to Allow Pump Starts
Due to Sticking LE3701 Float at Lowest Level
Connect Diesel Air Compressor to Plant Air System
CAL-E95-015 Calibration Frequency Revision
PLC 1701C Replacement
1K001-M Compressor Motor Overload Trip Jumper-ed Out
(Bypassed)
Revise TE4403 Setpoint on TR4400 to Provide Annunciation
with Temperature Rise
Disable XR2 Low Oil Level Alarm to Prevent Masking Other
Alarms
RHR [Residual Heat Removal] Discharge Header Pressure
Switch Setpoint
TC6924A/B Control Building Chiller Temperature Controller
Siemens 353 Controller from Design Level A to B
Diesel Air Compressor Back-Up to Plant Air System
Revise CAL-M91-014 To Be in Compliance with
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ANSI 195-1976, Section 5.4
Reconfigure LS2219 Logic to Remove Automatic Opening of
SV2219
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
Chromalox Replacement Project
RWS Cable Replacement
Implementation of Revised Calculations for LOCA Dose
Consequences
Miscellaneous
Evaluations of Changes, Tests, and Experiments
01/01/2017
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
Engineering Evaluations
CFR Applicability and 5059 Screen Reviews
CFR 5059 Evaluation
Temporary Configuration Changes
Self-Assessments AR 02276319
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